directory of certificates of compliance for radioactive

NUREG-0383Volume 2Revision 19

Directory ofCertificates of Compliance forRadioactive Materials Packages

Certificates of Compliance

Manuscript Completed: October 1996Date Published: October 1996

Spent Fuel Project OfficeOffice of Nuclear Material Safety and SafeguardsU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

*****

DISTRIBUTION OF THIS DOCUMENT IS UNLIMITED

DISCLAIMER

Portions of this document may be illegiblein electronic image products. Images areproduced from the best available originaldocument

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of theUnited States Government Neither the United States Government nor any agencythereof, nor any of their employees, makes any warranty, express or implied, orassumes any legal liability or responsibility for the accuracy, completeness, or use-fulness of any information, apparatus, product, or process disclosed, or representsthat its use would not infringe privately owned rights. Reference herein to any spe-cific commercial product, process, or service by trade name, trademark, manufac-turer, or otherwise does not necessarily constitute or imply its endorsement, recom-mendation, or favoring by the United States Government or any agency thereof.The views and opinions of authors expressed herein do not necessarily state orreflect those of the United States Government or any agency thereof.

FOREWORD

The purpose of this directory is to make available a convenient source ofinformation on packagings approved by the U.S. Nuclear Regulatory Commission.To assist in identifying packaging, an index by Model Number and correspondingCertificate of Compliance Number is included at the front of Volumes 1 and 2.An alphabetical listing by user name is included in the back of Volume 3 forapproved Quality Assurance programs. The reports include a listing of allusers of each package design and approved Quality Assurance programs prior tothe publication date of the directory.

Comments to make future revisions of this directory more useful are invitedand should be directed to the Spent Fuel Project Office, U.S. NuclearRegulatory Commission.

m

U.S. NUCLEAR REGULATORY COMMISSIONINDEX OF CERTIFICATES BY MODEL NUMBER

10/01/1996

MODEL #

A-0109

ABB-2901

AI 500 SU

ANF-250

AP-101

ATR

A1W-3 CB/TS DC

A1W-3 HD/SB SDC

A1W-3 PUSC

B-3

BCL-2

BCL-3

BCL-4

BETTIS WASTE

BMI-1

BS-33-180

BU-7

BUSS R-l

BW-2901

C-1

C-8

CGN 25/35 RCDP

CI-20WC-2

CI-20WC-2A

CNS 1-13C

CERTIFICATE #

6280

9274

9006

9217

9071

9099

9789

9790

9787

6058

9068

9067

5950-

6142

5957

6722

9019

9511

9251

9036

9128

9794

9098

9098

9081

MODEL #

CNS 1-13C II

CNS 1-13G

CNS 10-160B

CNS 14-170 III

CNS 14-195-H

CNS 21-300

CNS 3-55

CNS 4-85

CNS 6-75

CNS 6-80-2

CNS 6-80-2A

CNS 8-120A

CNS 8-120B

CNSI 14-215H A

DHTF

DIG CB-TS

D2G POWER UNIT

E-MEH-00-00004

FL 10-1

FPD-100

FSV-1

FSV-3

GE-100

GE-21PF-1

GE-500

CERTIFICATE $

9152

9216

9204

9249

9094

9096

5805

6244

9108

9111

9111

6601

9168

9176

9203

9792

6441

9011

9009

9057

6346

6347

5926

4909

9049


10/01/1996

MODEL #

GE-8500

HFBR UNIR CONT

HN-100 SERIES 3

HN-190-1

HN-190-2

HN-194S

IF-300

INNER HFIR UN

IR-100

IR-50

LCG-25A

LCG-25B

LCG-25C"

LL-60-150

LN 10-135A

LN 14-170 1

LN 14-170H

LN 14-170L

LN 14-170M

LN 14-195H

LN 14-195L

LN 6-80H

LN 6-80L

LN 7-100

M-130

CERTIFICATE #

6697

9853

9151

9086

9224

9089

9001

5797

9157

9156

4888

4888

4888

6568

9177

9151

9159

9159

9159

9176

9176

9179

9179

9178

6003

MODEL #

M-140

M-160

MCC-3

MCC-4 -

MCC-5

MO-1

MODEL B

MODEL 1 S-6213

MODEL 2 S-6213

MW-3000

N-55

NAC-LWT

NAC-STC

NAC-1

NATICK IRRADI

NCI-21PF-1

NFS-URANYL NIT.

NLI-1/2

NLI-10/24

NNFD 5X22

NNFD-10

NONE SPECIFIED

NPI-20WC-6

NPI-20WC-6 MKII

NRBK-41

CERTIFICATE #

9793

9781

9239

9239

9239

9069

6206

9186

9186

9030

9070

9225

9235

9183

5362

9234

5059

9010

9023

9250

6357

6406

9102

9215

9221

VI


10/01/1996

MODEL #

NUPAC 10/140

NUPAC 14/19OH

NUPAC 14/190L

NUPAC 14/190M

NUPAC 14/210H

NUPAC 14/210L

NUPAC 14D-2.0

NUPAC 50-1.5L

NUPAC 50-2.5L

NUPAC 50-3.0L

NUPAC 50-4.0L

NUPAC 6/100H

NUPAC 6/100L

NUPAC 7/100

OP-100

ORNL TRU CALIF

OUTER HFIR UN

PADUCAH TIGER

PAS-1

PAT-1

PAT-2

PWR-2 CORE BAR.

RA-2

RA-3

RCC

CERTIFICATE #

9177

9159

9159

9159

9176

9176

9079

9145

9145

9145

9145

9179

9179

9178

9185

5740

5797

6553

9184

0361

9150

9791

4986

4986

5450

MODEL #

RCC-1

RCC-3

RCC-4

SENTINEL-100F

SENTINEL-25A

SENTINEL-25B

SENTINEL-25C

SENTINEL-25C3

SENTINEL-25D

SENTINEL-25E

SENTINEL-25F

SENTINEL-8

SNAP-21

SP-1

SP-2

SPEC 2-T

SPEC-150

ST

S2C REC. COMPT.

S3G CBDCA

S3W REC. COMPT.

S4W REC. COMPT.

S5W POWER UNIT

S5W REC. COMPT.

S5W REFUEL.SRCE

CERTIFICATE fl

5450

5450

5450

5862

4888

4888

4888

4888

4888

4888

4888

9030

5830

9248

9248

9056

9263

9246

9788

9786

9788

9788

5580

9788

5757

V1X

MODEL #


10/01/1996

CERTIFICATE #

T-2

T-3

TN-BRP

TN-FSV

TN-RAM

TN-REG

TN-8

TN-8L

TN-9

TRIGA-I

TRIGA-II

TROJAN PRESSUR.

TROJAN STEAM

TRUPACT-II

UC-609

UNC-2600

UNC-2901

URIPS-8A

URIPS-8B

UX-30

WAPD-40

YNPS RPV

YNPS STEAM GEN.

10-135B

10-142

5607

9132

9202

9253

9233

9206

9015

9015

9016

9034

9037

9260

9259

9218

9932

5086

6294

6786

6786

9196

5874

9262

9256

9210

9208

MODEL #

10-142A

100

10 0A

110G-A

125-B

14-215

1500

181361 •

181375

2.7 NEW FUEL

20

20A

200

200A

2000

235R001

3-82B

3206B

3218

3227B

4.5 TON CF

40G-A

420

50

50A

CERTIFICATE #

9073

9127

9127

9247

9200

9222

5939

5796

5796

5894

9126

9126

9127

9127

9228

6386

6574

9167

9167

9167

6642

9254

9245

9126

9126

Vlll


10/01/1996

MODEL #

51032-1

51032-2

589

5979

5984

6400

650

650L

660

660A

660AE

660B

660BE

660E

6717-B

676

676A

676AE

676B

676BE

676E

680

680A

680AE

680B

CERTIFICATE #

6581

9252

9139

5979

5984

6400

9032

9269

9033

9033

9033

9033

903-3

9033

6717

9029

9029

9029

9029

9029

9029

9035

9035

9035

9035

MODEL #

680BE

680E

684

684A

684AE

684B

684BE

684E

702

715

741

741A

741AE

741B

741BE

741E

770

771

814A

820

850

855

864

865

920

CERTIFICATE #

9035

9035

9028

9028

9028

9028

9028

9028

6613

9039

9027

9027

9027

9027

9027

9027

9148

9107

5149

9137

9147

9165

9166

9187

9143

xx


10/01/1996

MODEL # CERTIFICATE # I MODEL # CERTIFICATE #

927A1 6078

927C1 6078

934 9243

^

NRC FORM 618(8-85I10 CFR 71

U.S. NUCLEAR REGULATORY COMMISSIONCERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIALS PACKAGES1.B.CERTIFICATE NUMBER

0361b. REVISION NUMBER

6c. PACKAGE IDENTIFICATION NUMBER

USA/0361/B(U)F-85d. PAGE NUMBER

1e. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packaging_and contents described in item 5 below, meets theapplicablesafetystandardsset forth inTitle 10, Code

of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."

b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEiDESlGN OR APPLICATIONa. ISSUED TO IName end Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

U.S. Nuclear RegulatoryCommission

Washington, DC 20555

NUREG-0361; Safety Analysis Report for thePlutonium Air Transportable Package Model

..Jlo.r PAT-1, as supplemented.

c. DOCKET NUMBER 7 1 7*0361

A, CONDITIONS , «.v ,'rThis certificate is conditional upon fulfilling tha:requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging $JH

(1) Modef%.:

Des.ofiption

A sta'inlessL

are sealed*:.the*

^ ) (MijStee^6;6n;tafinmenr~vessel^Cdesignated TJtel) surrounded by aalp af^êciwopdTp.ye^pack-;('designated AQsl). The contentsMhiin a&jtaihlei'sj steel^'product xan (designated PC-1)ontaanmentovessel >. K > >

iisi'1PiThe AQ-'l ovepp ackuiss a w^t|^rew'ajg&cj'nnder^âpproximately 42-1/2inches\Tong by 24-i/2 OT^Ms(\puJsideS|iameter^the walls of the overpackconsist^£approximately^8j i^ftes ofîgrain op/nted redwood encasedwithin doiijne»%stainless steel drums. The erTds of the drums are doublyclosed. A "cQp'per heat conducting elemenj and an aluminum loaddistributer are encased within theijr-edwood.

The TB-1 containment vessel is'lipproximately 8-1/2 inches outsidelength by 6-3/4 inches outside diameter. The minimum wall thicknessof the vessel is approximately 1/2 inch. The interior cavity of thevessel is a right circular cylinder, 4-1/4 inches diameter, withhemispherical ends. The vessel is closed by 12, 1/2-inch diameterbolts and doubly sealed with a copper gasket and knife edges and anelastomer O-ring.

\I\

Ii

I\Iiiiiii

NRC FORM 618A CONDITIONS (continued)

Page 2 - Certificate No. 0361 - Revision No. 6 - Docket No. 71-0361

U.S. NUCLEAR REGULATORY COMMISSION

f

(iiiiiIf

IE

t

E

i

6.

7.

8.

(a)

(b)

Packaging (continued)

(2) Description (continued)

The weight of the package is approximately 500 pounds. The weight ofthe TB-1 containment vessel, when loaded with 4.4 pounds of contentsis approximately 41.7 pounds.

(3) Drawings and Specifications

The Model No. PAT-T packaging is fabricated in accordance with thedrawings and specificatiS|is M pfCion 9.0 of the Safety AnalysisReport, NUREG-036T€as|^u^pleynTeo^iC/s/ue B of Drawing Nos. 1004,1009, 1013, * """

Contents

(1) Type and

(2)

Pluton%un oxiplutonTum oxideproducts, in any,

<Maximum quancontents

id form. Thet s daughter

1 permissible

(i) M a x i m u m ^ » i t b ^ i | | | | c | | ^ e mat iM, plala maximum 16 grams' " r pol\^4nylchloride bagging

of th^bontents may not

( i i ) Maximd feDO grams totaiAi^ffioactive ma^jfci , plus: maximum onegram of«fefter, maximum 200 grams of m&&l canning material (inaddition to the^PC-1 product can^Jrawing No. 1024), maximum 64grams of alumiilmr fMJ J^no&&/d:ffm (in addition to the topspacer, Drawing No/foiUfC mlBeimum 175 grams of glass and maximum35 grams polyethylene or polyvinylchloride bagging material. Themaximum decay heat load of the contents may not exceed 25 watts.

(c) Transport Index for Criticality Control

Minimum transport index to be shown onlabel for nuclear crit icality control: 0.4

The PC-1 product can (Drawing No. 1024) and the top spacer (Drawing No. 1015)need not be used when the contents include 20 curies or less of plutonium.

Prior to first use, each packaging shall meet the acceptance tests and standardsspecified in Subsection 8.1 and Section 9.0 of the Safety Analysis Report.

Prior to each shipment, the package shall meet the tests and criteria specifiedin Subsection 8.2 of the Safety Analysis Report.

^

NRC FORM 618A(6-83)

CONDITIONS (continued)



9. The package shall be prepared for shipment and operated in accordance with theprocedures specified in Section 7.0 of the Safety Analysis Report.

10. The systems and components of each packaging shall meet the periodic tests andcriteria specified in Subsection 8.3 of the Safety Analysis Report.

11. Repair and maintenance of the packaging shall be in accordance with Sections 8.0and 9.0 of the Safety Analysis Report.

12. The packaging shall be designed, procured, fabricated, accepted, operated,maintained, and repaired in accordance with a quality assurance plan approved bythe Nuclear Regulatory Commission |&>r |3 | | £

13. Through special arrangemer^wfth the carrier, the^^^per shall ensure observanceof the following operatiâl controls for each shipmetit^Bf plutonium by air:

(a) The package(sâwst be stowed aboard aircraft on thlocation that rs possible for cargo of i t i #cargo may beSsfcowi^-jfft of the package(s)

(b) The packagers) mustthe aircroffP. The tirestraint^gainst theto the deckôf the a.iDownward, Pff5g.

(c) Cargo which bearstransportedf%oard

.in deck in the aft-mostt. No other type

-down t<j»t?he main deck ofle of p r i d i n g package

ately relative•ward, 1. 5g;

labels may not be

ExplosiExplosivExplosive *•/§*SpontaneouslyÔfibusti bl eDangerous When WetOrganic Peroxide

mmableFlammableOxidize*

This restriction does not apply to hazardous material cargo labeled solelyas:

Radioactive IRadioactive IIRadioactive IIIMagnetized Materials

PoisonPoison GasIrritantEtiologic Agent

14. The package authorized by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12.

15. The package authorized by this certificate is hereby approved for transportationof plutonium by air.

16. Expiration date: September 30, 1998.

'£M9AJaWMSU9UaU&M9M«y9MeU&J«V^^

^

NRC FORM 618A(6-83)

U.S. NUCLEAR REGULATORY COMMISSIONCONDITIONS (continued)


REFERENCES

Safety Analysis Report for the Plutonium Air Transportable Package Model Number PAT-1,NUREG-0361, June 1978.

Sandia Laboratories application dated February 20, 1980.Supplements dated: July 27, 1990 and July 20, 1993.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Date: 3

William D.^T^vers, DirectorSpent Fuel Prej^fet OfficeOffice of Nucleaâterial Safety

and Safeguards'3^

»^-«««»M«>«M«^fflâ««i^M«M«^«^«^«v«y«y«âua5âi^B^«5^^

^NBC FORM 618(M5)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.B.CERT1FICATE NUMBER b. REVISION NUMBER


USA/4888/B( )d. PAGE NUMBER


PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code


applicable regulatory agencies, Including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE .DESIGN OR APPLICATION 'a. ISSUED TO INmeand Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Department of the Air ForceTechnical Operations Division/CC6000 Patrol RoadMcClellan AFB, CA 95652-1709

Teledyne Energy Systems applicationsdated April 26, 1985 and August 19, 1986,as supplemented.

c. DOCKET NUMBER 71-48884. CONDITIONS .,,

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model No.:r Sentinel |inel |?5|^;L,eG-25A; Sent inel^B, LCG-25B;^e l ^ ^ tCG-g l ^Sen t i ne i f 25C3 , -25D, -25E,

(2) Description, f. I.

The packages, are j)j^rmain housings *"The approximatefollows:

and -25F

components include theelectrical connectors.

varioUs Model Nos. are as

Model No.

Sentinel-25A, LCG-25ASentinel-25B, LCG-25BSentinel-25C, LCG-25CSentinel-25C3Sentinel-25DSentinel-25ESentinel-25F

i metis ions

25 ODi-A,, 25:;0D<'•"-; 24x0D

24 OD25 OD25 OD24 OD

(inches) ,

X.25 '^ '''"X-'- Sx 32x 32x 27x 34x 32

Weiaht Hbs.1

3000330020001300330042001400

^

NRC FORM 618A(643)

jJ|t

t

t

t

t

f

it

i(

t£i



(a) Packaging (Continued)

(3) Drawings

The packagings are constructed in accordance with the following Drawing Nos:

E

Model No.

All Models

Sentinel-25A, LCG-2.5A

*-•«;•--„ V

Drawing Nos.

Isotopes, Inc. Drawing Nos.:001-20000, Rev. E001-20001, Rev. F001-20002, Ref. F

>001-200,03, Sht. 1, Rev. Ba 001-80003/

Martin Company/Orawing Nos.:N0013100, R e v f A•-"<N0013108, Rev. D >.001-40000, Rev^'A >

". \'' ,'/' '-' c"Isotopes^2|nc". Drawing Nos.:

ropi-idoaopRev. B ; ;" ' " ~"""' }Rev. C ,;-.0dl-70025.,:Sht. 1, Rev; DO0K70O33,<Shts. 1 & '1-, Rev. APQ1^0d3| f

Sentinel-25C, LCG-25C

Sentinel-25C3

. j - - •

Isotopes, Inc.^Drawing Nos.:001-70024, R§y> C001-70025, Slit. 1, Rev. D

A OOlr-70033, Shts. 1 & 2, Rev. A;• ; 001-70036

001-80005

Martin Company Drawing Nos.:001-40004, Rev. A001-70010001-70012, Rev. B001-80004

Isotopes, Inc. Drawing Nos.:001C10000, Sht. 1 Rev. D, & Sht. 3001-70009, Rev. D

Isotopes, Inc. Drawing Nos.:001C10000 Shts. 1 & 2, Rev. D001-70009, Rev. D001-70057, Rev. D001-70060, Rev. C001-40019, Rev. B

(W3) COND.T.ONS (continued)U S ' N U C L E A R R E G U L A T O R Y COMMISS.ON


Sentinel-25D

Sentinel-25E

Sentinel-25F

-.\?:

Martin Company Drawing No.001-80004

Isotopes, Inc. Drawing Nos.:001D10000 Shts. 1 & 2, Rev. C001-70036001-70033 Shts. 1 & 2, Rev. A001-70025 Sht. 1, Rev. D001-70024, Rev. C001-40015, Rev. C001-40006, Rev. B

Isotopes, Inc. Drawing Nos.:OOlIIOOtJO^Shts. 1 & 2, Rev. E, & Sht. 3001-70039/ Rev. C001-70025, Sht. 1, Rev. D & Sht. 2001-70024, Rev. C,001-40017, Shts. 1 & 2, Rev. D001-40006, Rev.B

Isotopes,.Inc. Drawing Nos.:-001F1000O4>:$hts. 1 & 2, Rev. H*~001-70p.iQ, Rev. C001-70060i 'Rev. C-00177000%* Rev. DpOl0S2SrR A

,;4,(b) Contents : -;; •':

(1) Type and form of material

!t *As:mpdifjed'by Figure 1 ofi-,-./th;e!--'Aj)rn-2'6, 1985, application.

6.

(i) Strontium 90 titanate doubly encapsulated in a Hastelloy orUniloy fuel capsule w_hich meet the requirements of special formradioactive material; or

(ii) Model No. Sentinel-25F may have, strontium fluoride doublyencapsulated in Hastelloy or Uniloy fuel capsule, with a HastelloyC-276 liner which meets the requirements of special formradioactive material.

(2) The maximum quantity of material per package

125,000 curies

A barrier (permitting the free circulation of air) must be provided withsufficient separation distance to ensure that the requirement of §71.43(g) will bemet.

&^&^^Jt\H/&!if&&^

^

£C F 0 R H „ „ CONDITIONS (continued, ^ N U C L E A R R E G U L A T 0 R Y COMMISSION


1. Eye-bolts shall be removed or covered during transportation to prevent their use astie-down devices of packages.

8. In addition to the requirements of Subpart G of 10 CFR Part 71, each package shallbe operated, prepared for shipment and maintained in accordance with the followingOperating Procedures and Maintenance Programs:

Model No. Operating Procedures Maintenance Program

Sentinel-25A, LCG-25A Appendix E of TES-3206, Appendix F of TES-3206,as revised as revised

Sentinel-25B, LCG-25B AppendJxgjE of^T|Sj-3209., Appendix F of TES-3209,asêps'iefr b u 'w c*4f J ff as. revised

Sentinel-25C, LCG-25C,jyAppendix E of TES-3210, l Appendix F of TES-3210,-,J as revised asyevised

Sentinel-25C3 ^f..,. Appendix E of TES-3211, ^<-#pf[erfdix F of TES-3211,"-; ~- .'as. revised ,~>t V a s revised

Sentinel-25D ^ ' ^peiid'ix E pf-;IE-S-3242^/ Appendix F of TES-3212,%p|||)d'tx E pf-;IE-S-3242.^$'' Append Fasscev;iled >">^ " ? i >:?&"?~ as rev-tsed

Sentinel-25E ^ x App^jk^ i f^ t -ES-^z i^ ;^ ..Appendf*; F of TES-3213,\:|Oas'i^yêiB. .,^ J^^^ >„itjte revi-sed

Sentinel-25F v ' " ^ ^ h a p | e r ^ j 1 1 - ^ ^ ^ 3 2 1 ) 2 , '/I^ChaptetlX of TES-3202,revised

:;'^Ch4p|efî|I<;b|iÊSc3202, .7|^Chaptefe<« ^•.a 'rjBvis'eclK $ t '. \\ d r*" t r-J^ a s rev-i-'

9. The packages authorized by tiiiis;> cer^tf^'cirt'e. arejliereby approved for use under thegeneral license provisions of 10 CFR 171^12. Vf<?' _,. H'

10. Expiration date: December 31, 1996. H .,

;:;>- -REFERENCES, "SA.'.•' • - ' i V-

• •: ' . ^ V'-

Teledyne Energy Systems applications dated April 26, 1985; and August 19, 1986.

Teledyne supplements dated: November 3, 1986; September 17 and December 2, 1991.

Department of the Air Force supplement dated: November 12, 1993.


Cass R. Chappell, Se6tion LeaderCask Certification SectionStorage and Transport Systems BranchDivision of Industrial and

Medical Nuclear Safety, NMSS

'"•: .» $"1993Date:

^»"»^»^»"«^«»^^^

NBC FORM 618(W6I10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES

1.a.CERTIFICATE NUMBER



USA/4909/AFd. PAGE NUMBER


2. PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safetystandards set forth in Title 10. Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

General Electric CompanyP.O. Box 780Wilmington, NC 28401

General Electric Company application datedJanuary 26, 1994.

. DOCKET NUMBER 71-4909

A. CONDITIONS ^. \~^ . ' 'This certificate is conditional upon fulfilling.therequirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1)

(2)

Model Nofr*GE-21PF-;

Description

Overpackffor

(3)

m'hjBxafluoniiide (UF6) cyl inders,'^••'••"ted .ofetwo stainless steel

f i l l e d ; with wood blocks andth ick . The foam is in

1, an^Supplement K/TL-729. A

shells, JRe, anni&ajfire-resistant phenlaccordance Wth USkpstepped and^gasjceted hor^zotMffSpiri^ p£ff|ts the tjpp/haif of the overpack tobe removed from|t|ie base. Tn£fp.cjcj£age "Wl'Tves" .a^'secured with fourteen,3/4-inch bolt/nU^/washer assemblies. The overpacB is approximately 43-5/8inches OD by 95-l/g inches long. Maximum grrfs^weight of the package is8,600 pounds. VfL A

Drawings ^^

The packaging is constructed in accordance with General Electric CompanyDrawing No. 769E237 - Sheet Nos. 1 and 2, Rev. 4. In addition, the length ofthe 8" x 2.5" tie-down support channel may be from 43 to 55 inches long andvent holes in the exterior shell may be sealed with plastic plugs.

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NRC FORM 618A(6-83)

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(b) Contents


Uranium hexafluoride enriched in the U-235 isotope.

(2) Maximum quantity of material per package

(i) Model No. 30A cylinder: 4,950 pounds UF6 enriched to not more than 5w/o in the U-235 isotope.

(ii) Model No. 30B cylindw/o in the U-235 v0

(c) Transport Index for C^G^afity Control

Minimum transportlabel for nuclear c

6. In addition to

enriched to not more than 5

(b) Each packa^fjig miSections 7.2 and

(c) The packagevshallthe Operating^fxoced

to be shown onality control:

(a) Prior to efcfi shipmentgaskets mu f1 be replaywhichever.occurs fA)

(d) The loaded cyliftM^must be shiftfeWithout a valprotector must be^replaced in accordance with n(the cylinder is removed from the overpack.

(e)

inserted. These^ f every 12 months,

Program of

accordance with

Jjbrotector. The valve1 handling practice when

Prior to each shipment, the sfainUiss sPteel components of the packaging mustbe visually inspected. Packagings in which stainless steel components showpitting, corrosion, cracking, or pinholes are not authorized for transport.

(a) For packagings which are not seal welded, the joints between the inner andouter shells (ends) and the side (end) panel moldings must be siliconesealed. The inner and outer overpack gaskets must cover side (end) panelmolding joints (unless seal welded). Except for joints covered by a glueddown gasket, visually inspect all silicone sealed joints and maintain in goodrepair prior to each shipment or outside storage (loaded or empty).

(b) All body seams and joints for the inner and outer shells (ends) and the side(end) panel moldings must be continuous welds. Welding must be by a fusionprocess in accordance with the American Welding Society Code or AmericanSociety of Mechanical Engineers' Code.

10

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NRC FORM B13A(S-B3I




8.

(

[[c

<:

The 30-inch diameter UF6 cylinders must be fabricated, inspected, tested andmaintained in accordance with American National Standard N14.1 (1990 version).Cylinders must be fabricated in accordance with Section VIII, Division I, of theASME (American Society of Mechanical Engineers) Boiler and Pressure Vessel Codeand be ASME Code stamped.

At least once every five years, each packaging must be inspected to verify thepresence and condition of the insulation. The inspection shall consist ofinserting a probe through each vent hole in both the lid and base to confirm thepresence and rigidity of the insulation. For packagings which require drying, theinspection must be performed after drying.

'Shackles I W i M / b e used for tying down the

Supplement dated O ^ b e r 2 6 0 9 9 4

10. Shackles are for liftingpackage during transport*^

11. The package authorizedjby this certificate is hereby apprciyed for use under thegeneral license provisions of 10 CFR §71.12. <?g\

12. Expiration date^^RovemBev^O. 1999. ^ ^ <&=*

General Electric Companyif / ^

REGULATORY COMMISSION

\ . ^

Date:

William D. Traver^DirectorSpent Fuel Proaect>Office

^/Qff:i<g oMOc^fear Material Safety^ T and! Safeguards

1 1

**B**<&*<n**jn*&B*&^^

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KRC FORM 618(MS)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESl.CERTIFICATE NUMBER

4986

b. REVISION NUMBER

33

c. PACKAGE IDENTIFICATION NUMBER

USAMQSfi/AF

d. PAGE NUMBER e. TOTAL NUMBER PAGES

42. PREAMBLE

a. This certificate is issued to certify that the packaging_and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."

applicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


General Electric Company application datedMarch 17, 1992, as supplemented.

c. DOCKET NUMBER

4. CONDIT IONS < * > • " ' '"This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model NosJ RA-2

(2) Description

A fuel asVemblrectangul aj£a metal fnner cd"fi$aTri

T-d

ng; container.' PackVgings are rightpiiter" cont/ainer of wooden construction andy&ushioni/og material.

cf\18 \ncf\is by 179 inches long andA b i iitioned/within a Modet,#ofyR^3 wojoflen outejr^cbntainer approximately 30

by Sl^wches by 207 incHe'sj-iong. CushionirTg is provided between theand outef'/dBhtainers bv Dhenolic imoreartaWd honevcomb and ethafoam. or

The metal ^$$w coriiis positioned?inches _ ' ^ înner and outefVîtainers by phenolic impregu'atecfhoneycomb and ethafoam, orequivalent. Closure js; accomplished by bolts^latches, or equivalent. Apressure re l ief (breal(fer.)~/Valv,e is^proêd on the inner container, and isset for 0.5 psi differenti-aJ. ^ffie^tataT'weight of the packaging and contentsis 2,800 pounds.

(3) Drawings

The packagings are constructed in accordance with the following GeneralElectric Company Drawing Nos.:

769E229, Revision 7, Model RA-3 Outer Container769E231, Revision 5, Model RA-3 Inner Container769E232, Revision 5, Model RA-2 Inner Container

(4) Product Container

Five-inch, Schedule 40, stainless steel pipe fitted with screw type or flangeclosure. Container shall be vented in the event it contains materials whichdecompose at less than 1475°F.

12tMiueu

NRC FORM 618A(6-83)




5.(b) Contents


(i) Unirradiated U02 fuel rods with a maximum U-235 enrichment of 6.5% byweight. Rods are clad with Zircaloy, Incaloy, Inconel or stainless steelsuch that the ratio of clad to fuel cross sectional area is at least0.26, and have a maximum fuel pellet outside diameter of 0.508 inch.Each rod must have a maximum length of 174 inches. The clad rods must bebundled (contained) in the product container described in 5(a)(4).

( i i ) Unirradiated U02 fuel assemblies. Each fuel assembly is made up ofeither 60 or 62 rods jyn tara 8 p | 8uS£ttat;e array with maximum fuel cross-sectional area of 25. square inbnesMnl^maximum fuel length of 150inches. The ma^mpiTfu-235 enrichment isCs^ft percent by weight, and themaximum averagg/enrichment is 5.0 percent "By Sfeight. The maximum pelletdiameter, m njjmum clad thickness, water rod specifications, and poisonrod speci£j£ations are in accordance with SectWL^. 1, Appendix 8-H, ofthe supplements dated June 27 and

( i i i ) UnirradMed Uifull amttpartiacrossFsectional

The maxmaximum5 avera?

rod so$pfthe supplemet"

(iv) Unirrafull ancross-seinches.

kedrtia

rojjal areaiximum U-235

assemble is made up of 74iare arr%*rith maximum fuelid a maxiweffij fuel length of 150,0 percenfcBy weight, and the

/eight ^JThe maximum pellet•i«S?ions, and poison

>n 6 ^ Appendix 8-1, of'1995.«

assemojsy is made up of 920 j ^ l ^ s q u a r e ^ r a y with maximum fuelnc1re!|fand a^ximum fuel length of 150

ent is 5.5fc@cent by weight, and themaximum averaw=enrichment is 5.0 percent b|NWeight. The maximum pelletdiameter, minimum clad thickness, watejcjrod specifications, and poisonrod specifications ^*i-nj|ccqrda^^-w^h Section 6.1, Appendix 8-J, ofthe supplements datedr Junls27]^d iProvember 1, 1995.


Total quantity of radioactive material within a package may not exceed a TypeA quantity.

(i) For the contents described in 5(b)(l)(i):

Two (2) fuel bundles.

(A bundle is defined as an arrangement of rods which are either containedwithin a product container or strapped together.)

(ii) For the contents described in 5(b)(l)(ii), 5(b)(l)(iii), and 5(b)(l)(iv):

Two (2) fuel assemblies.

13

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NRCFOHM618A(W33)

CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION

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5.(c) Transport Index for Criticality Control

Minimum transport index to be shown onlabel for nuclear criticality control:

10.

11.

12.

0.4

Each fuel assembly must be unsheathed or must be enclosed,™ an unsealed,polyethylene sheath which may not extend beyond the ends of the fuel assembly.The ends of the sheath may not be folded or taped in any manner that wouldprevent the flow of liquids into or out of the sheathed fuel assembly.

For contents described in 5(b)(l)(ii), 5(b)(l)(iii), and 5(b)(l)(iv), polyethyleneholders with a maximum effective thickness of 0.151 inches (0.3835 cm) may beplaced surrounding the fuel assemb$5 u|^6â/laximum of 0.13 grams H20 hydrogenequivalent per cubic centime^rpVeraged o er tl e? assembly. The effective holderthickness is the linearyavWê of the maximum anc&nj&fiiDum thickness.

b)(l)(iv), polyethylenessemblies up to a

ensfmeter averaged over1 '•*•' polyethylene

For contents describe^n 5(b)(l)(ii), 5(b)(l)(iii), andishipping shims may S&inserted between rods within the fimaximum of 0.10 grams- HLQhydrogen equivalent per cujjithe assembly. ThS^hipp^g^ghims may be usedholders.

product |6ifttainer specified innt greatet^than 3.2%, clad

r mol*!? locations) with a•^total^reaking strength of'ds. ^

ifwlsen adjacent rodsst be jna^ntained by the

ral m e t r i c dunnage with a

eans the highest enrichmdâveraged over any axial

For contents described in5(a)(4), except^|or U0? furods must be bimcfled (bmaximum cross sectionthe strapping mfll$ be

For contents destfFig>edwithin the bundleHteproduct container Wjmelting point greaf

Maximum average enrichzone of the assembly.

In addition to the requirements of^bplmt (Fof 10 CFR Part 71, each packagingmust meet the Acceptance Tests and Maintenance Program of Chapter 6 of theapplication, and the package must be prepared for shipment and operated inaccordance with the Operating Procedures of Chapter 6 of the application.


14. Expiration date: October 31, 1997.

14lmy&^J*M»^^

«wt»fts?«yrei'«#reftaw}fti«reftgft»ft<^

NRC FORM 818A(6-83)



REFERENCES

General Electric Company application dated March 17, 1992.

General Electric Company supplements dated: April 16, October 5, and November 18, 1992;March 18, 1993; and June 27, and November 1 and 3, 1995.


William D. Travers, DirecjbrSpent Fuel Project Office/^Office of Nuclear Material

and Safeguards

Date:

15

NRC FORM 618(3-96)10CFR71

CERTIFICATE OF COMPLIANCEFOR RADIOACTIVE MATERIALS PACKAGES


1. a. CERTIFICATE NUMBER





2

i. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10,Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."

b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported. *

a. ISSUED TO (Name and Address)

Nuclear Fuel Services,P. 0. Box 337, MS 123Erwin, TN 37650

Inc.b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Nuclear Fueldated March

c. DOCKET NUMBER

Services27, 1981,

71-5059

Inc., applicationas supplemented.

4. CONDITIONS

This certificate is conditional upon fulfilling the requirements, of KT.CFR Part 71, as'applicable.and the conditions specified below.

(a) Packaging . i ^ r

(1) Model 'No^vJlFS Uranyl Nitrate Tank^

(2) Description^^X..'~, -4^

Bulk Hquidp^liffteclyfcirgp iirik§0i 1 er. The 3,800 gallon tanktrailer ds 6^^1Twel,dedycon,strui:ii^n of type:304L stainless steel

(3) ^awing|grnxmrniis,(b)

The; tanklir^er $&;icblnkltrtfdted in acWrdance-with DOTSpeed f i cafi^TM^; i;U sM^Jt-f \f £ f

Contents".''.'/^ ' '''<-'e'*ji$§& *''•''•;>• •^'•'/

(1) Type and/fqrm of material -;.\ -•-'-'

Uranyl nitrate, indi.lute acid/solution. The maximum U-235enrichment in the uranium must not exceed 5% by weight. The U-235content of the solution must not exceed 10 grams per liter.

The total uranium content must not exceed 357 grams per liter(1.5M). The U02(N03)2-6H20 content must not exceed 50 weightpercent. The HNO3 concentration will be normally 0.4M. Thefreezing temperature of any of the solutions must be less than32*F.

16

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fcNRC FORM 618A(3-96)



5. (b) Contents (continued)


Not more than 45,600 pounds net weight of uranyl nitrate acid solution.Total quantity of radioactive material within a package may not exceed aType A quantity.


Minimum transport index to be shown onlabel for nuclear criticality control: 100

6.

7.

The solution must be at a temperature of 68*F. or,above at the time of packaging.

Prior to delivery to a carrier for transport, for U-235 enrichments greater than4% by weight, the shipper must ensure that at no point along the proposed shippingroute that the ambient temperature will be less than 32*F. In the event freezingweather is encountered, Jthe administrative procedures and controls as specified inNuclear Fuel Services, inc.,,application dated March 27, 1981, must be compliedwith for all U-235 enrichments. 1. '

8. In addition to the requirements, of Subpart G of~10. CFR Part 71:

(a) Each package must.be kcceytance tested and: maintained in accordance withSection 8,0 of the>%pl%&£on ?, as supplemented././

ach package,shaft;be';;pp'erat^dand! prepared for shipment in accordanceith the OperatinglP.rgcedur'e's' ,iri*Section,7.O^of the application, as

(b) Eachwithsupplemented?.

9. The package authorized.by this ceftftffi'bj&e-is'-Kefeby approved for use under thegeneral license provisions of 10 CFRf'§7l.l2. f

10. Expiration date: August^31,1996.,

'REFERENCES

Nuclear Fuel Services, Inc., application dated March 27, 1981.

Supplements dated: August 6, 1986, and July 18, 1991.


Date: H

William D. Trayers, DirectorSpent Fuel Project OfficeOffice of Nuclear .Material Safety

and Safeguards

17

NRC FORM 618(H6>10 CFB 71


FOR RADIOACTIVE MATERIALS PACKAGES1. a. CERTIFICATE NUMBER



USA/508fi/RrU)Fd. PAGE NUMBER

1

e. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Babcock and WilcoxP.O. Box 785Lynchburg, VA 24505-0785

Babcock and Wilcox Company applicationdated November 29, 1993.

'c. DOCKET NUMBER

4. CONDITIONSuunui i IUM3 ^ Sis$ "" V;' i\This certificate is conditional upon fulfillingvth»requirernents of 10 CFR Part 71, as applicable, and the. copa'jtions specified below.

(a) Packaging^

(1) Mo^el No.:

(2)

The inne2 - 0 " ^hi

formeiLby ......approximately rpiates^by.angle irons

st^e^piox wilfi? inside dimensions ofong. ThfeprJvner container is supported in a

JM^gaiJge^teel d»uftr by an insertable cagejyj^8" thicjpfteel plates, spaced

a4f)|fpnel forfel through the center of theter dontainesr\closure is made with a

14-gauge^|rum lid with 12-gauge bolt Tpcking ring with drop forged lugs,one of whidn isj;hreaded, having a 5/8^diameter bolt.

(3) Drawing

(b)

The packaging is constructed in accordance with Thomas Gutman ConsultantDrawing No. B-2600-2, Sheets 1 through 6, Rev. 3.

Contents


Unirradiated, uranium-zirconium, Naval fuel elements. The uranium maybe enriched to any degree in the U-235 isotope.


Up to 8.9 kilograms of U-235 per package. The ratio of the weight ofU-235 to the weight of U-235 plus zirconium shall not exceed 0.074.The net weight of the contents shall not exceed 265 pounds.

18

^

CONDITIONS (continued)NRCFORMB18A(643)




Minimum transport index to be shown onlabel for nuclear criticality control: 1.4

6. In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) The package must be prepared for shipment and operated in accordancewith Chapter 7 of the application.

(b) The package must be acceptance tested and maintained in accordance withChapter 8 of the application.

7.

8.

The package authorized by-thts cSjUji.the general license pro$i!Ph>W? of 1

Expiration date:v\lsfiiuary 31, 1999.

a is hereby approved for use underjJ/12.

Babcock and

Supplements Datetl? Septemb

Date:

REFERENCES

ated November

RY COMMISSION

s, Direct Offfar Majfcjhsfal Safety

afeguards

19MU&M*bi*U*SM!U*M*K*l*M*U9*M**9U*^^





5149

b. REVISION NUMBER

9


USA/5149/B( )Fd. PAGE NUMBER


22. PREAMBLE



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Babcock & Wilcox CompanyP.O. Box 785Lynchburg, VA 24505

Babcock & Wilcox Company applicationdated September 20, 1979, as supplemented.

c. DOCKET NUMBER 71-5149

4. CONDITIONS ,. ^"-) X. ) j f j ,;-;%This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as'applicabie/and the conditions specified below.

5.

6.

7.

V- ,-yfi

(a) Packaging \\1;

(1) Model N o S -8.14A

(2) Description % & C x

{•"•\

Steel "cbntainer Meserifred^tnJBabco"ck0 Wi 1 cox Company'sappl ica t ion Hat«sCxa«'tomhov<'?n I 1 Q'7Q:&(&£ v =;

(b) Contents

Unirradiated "ftfeltgC

(2) Maximum quantity of mate|^i||VpB^:pa'cl<age

One fuel cluscter containing U-235 with inserted poison fixture asspecified in Babcock & Wilcox Company'.s application datedSeptember 20, 1979. /-. .A.. V ^ v



The package authorized by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12.'

Use of packaging fabricated after August 31, 1986, is not authorized.

20

J3ZW ffTSLiMl DM. SZitl )itc

NRC FORM 618A(3-96)




(a) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures in the application supplement dated May 18, 1990.

(b) The package shall be maintained in accordance with the Maintenance Programin the application supplement dated May 18, 1990.

9. Expiration date: June 30, 2000.

REFERENCE

Babcock & Wilcox application dated September ;20, ,1979.

Supplements dated: May 18, 19,9t\, pd-'ftpYil 27,*" 199'5'.--,'' .

,1. ;;/ FOR THE U.S. NUCLEAR-REGULATORY COMMISSION

Date:

vv..

WXtf/ Spirit |, DirectorOffice:""'

212&J&J£U£L2SU3U£L2£USJf{7K7W23L&W7Vy£L2£i7f^

^

NRC FORM 618(8-85)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1. a.CERTIFICATE NUMBER


4


HSA/S3fi?/R( )


PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the appiicabiesafety standards set forth inTitie 10, Code




U.S. Department of AgricultureAgricultural Research ServiceRadiological Safety Staff6303 Ivy LaneGreenbelt, MD 20770

U.S. Department of Agriculture applicationOctober 17, 1980, as supplemented.

71-5362e. DOCKET NUMBER

4. CONDITIONS ^, • I' '''''''J- >>This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1)

(2)

{(

Model Noif J Nati cic-|%adi ator

Description s^v^O £^W %

holder (drawerbottom

46,!6p^with.;9-l/2" shielding ondM^k insert assembly 20" 0D by

^ k d hy

the^sk and the entirefd

9.52" ID b ^ U 2 . 1 2 ^ s ' % t a l « l | \ t K ' e ^ p f i b f ^ entireassembly is"held in platfe w£ihfm>Uthlc!^fsteel l.fd/secured with twelve, 1"bolts. A cassk^Jrain line i l ^se j iWwi th" ! pipr-#ug. A 39" 0D laminatedplywood pTug ffT,% the space between the top^ofVthe cask and the overpack.Plywood wil l be positipned around the circumference of the irradiator forsupport. The cask weighs,. 16,000 lbs. <"{

(3) Drawings

The packaging is constructed in accordance with Lockheed Nuclear ProductsDrawing Nos. 442-2093, Rev. 0, 442-2094, Rev. 0, 442-2096, Rev. 0; 442-2098,Rev. 0; 442-3002, Rev. 0; and U.S. Army Natick Research and DevelopmentLaboratories Drawing No. FE-81-16, Rev. 0.

22

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NRC FORM 618A(6-03)

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5. (b) Contents



Cesium-137 sources meeting requirements for special form radioactivematerial.

Maximum quantity of material per package

250,000 Ci.

(2)

In addition to the requiremejitS^ûbî^lgof 10 CFR p a r t 71> e a c n Pa c k a9e s n a 1 1

be maintained, operated andê'pared for shipment/in^ccordance with the operatingprocedures and maintenaiibe^program in supplement d ^ d ^ a y 21, 1992.

The package authori^crby this certificate is hereby appj pved for use under thegeneral license prWpsions of 10 CFR §71.12.

8. Expiration date:

.S. Department ofjAgricult

Supplements dated: Ôctobe

LATORY COMMISSION

0Cass R.KChange!1, Section Leader

FEB 1 4 1995

ratification SectionStorage and Transport Systems BranchDivision of Industrial and


Date

23

^


FOR RADIOACTIVE MATERIALS PACKAGES1.a.CERTIFICATE NUMBER




_Le. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafetystandardsset forth inTitlelO, Code

of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material." •


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATIONa ISSUED TO {Name and Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Westinghouse Electric CorporationP.O. Box 355Pittsburgh, PA 15230

^\ >

Westinghouse Electric Corporationapplication dated December 20, 1985,assupplemented.

> "c. DOCKET NUMBER (//71-54504. CONDITIONS

^requiThis certificate is conditional upon fulfillingJhe^requirements of 10 CFR Part 71, as applicable, and ths/cop<l|tions specified below.

(a) Packaging

(1)

(2)

Model NdW: RCC

Descri ptron

Steel ui,e=l el eladjusta^Te fusteel outer corequiredworlbs.,

(3) Drawings

ng^of/a stfcoggback andV ^Mc^mounted to a 14-gauge

f NeuMcinfabsor^gf plates areI- G^WweightsJ'or the RCC is 6,300a1tdrfcrC-4 is 8^00 lbs.

The packagings $r$ constructed in accordanceWestinghouse Electri(Corporation Drawipa Nos

For the RCC packaging:For the RCC-1 packaging:For the RCC-3 packaging:For the RCC-4 packaging:

the following

002RCCL102RCCL302RCCL402through 3, Rev. 2.

Sheets 1 through 3,Sheets 1 through 3,

Rev.Rev.

2.2.

Sheets 1 through 3, Rev. 2.Sheet 1, Rev. 3; Sheets 2

(4)

(5)

Fuel rod container reinforced 13-gauge steel box constructed in accordancewith Westinghouse Electric Corporation Drawing No. C5650D55, Rev. 7.

Dimensions and placement of neutron absorber plates in accordance withunnumbered drawing attached to Westinghouse Letter # LA 89-19 dated2/14/89.

24

NRC FORM 618A(6-83)




,,5.(b) Contents


(i) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuelelements. Two neutron absorber plates consisting of 0.19" thick,full length stainless steel containing 1.3% minimum boron or 0.19"thick OFHC copper are required between fuel elements of the followingspecifications:

Type

Pellet diameter(nom), in

Rod diameter(nom), in

Maximum fuellength, in

Maximum rods/element

Maximum cross £*=*»section,(nom), in sq'

Maximum U-235/|-«element, kg

Maximum U-235enrichment, w/o

15x15Zr

ad?

14x14ZrClad

?367 0.3670.400-0.422 0.422

14x14SST

15x15SSTClad

17x17ZrClad

16x16ZrClad

14x14ZrClad

0.308-0.322 0.322

.360-374

4.0 3.85

(ii) Uranium dioxide as Zircaloy clad unirradiated fuel elements containedwithin the Model |^> BC£-4 Dack^n^^. Two neutron absorber platesconsisting of 0.19"< th^R Tpfbdiftsteel are required between fuelelements of the following specifications:

Type

Pellet diameter, inRod diameter, inMaximum fuel length, inMaximum rods/elementMaximum cross section (nom) in sqMaximum U-235/element, kgMaximum U-235 enrichment, w/o

17x17Zr Clad

0.308 - 0.3220.360 - 0.374

1682648.419.33.55

25

NRC FORM 618A(6-83)

CONDITIONS (continued)U.S. NUCLEAR REGULATORY COMMISSION


5.(b) (1) Type and form of material (continued)

( i i i ) Uranium dioxide as Zircaloy clad unirradiated fuel elements. Twoneutron absorber plates consisting of carbon steel, 0.035 inches inthickness, with a cermet GcU), coating affixed to each side providinga total of 0.054 g-Gd,03/cnTfor both sides of the plate, area uui.ai ui U . U J I y aupu?/LIM IUI UUI.II oiuco ui uue piai,^, ui c

required between fuel elements of the following specifications:

Type



Maximum fuellength, in

Maximum rods/element

Maximum crosssection,(nom), in sq

Maximum U-235/(element, kg


Type



Maximum fuellength, inRods/elementMaximum crosssection, (nom),in sq

Maximum U-235/element, kg


14x14ZrClad

0.344-0.3670.400^0.4221

15x15ZrClad

14x14SSTClad

15x15SSTClad

17x17ZrClad

17x17ZrClad

16x16ZrClad

5.0

141.8208

8.5

17.8

3.95

16x16ZrClad

0.325

0.382

150

236

7.98

21.1

5.0

26

NRC FORM 618A CONDITIONS (continued)U.S. NUCLEAR REGULATORY COMMISSION


5.(b) (1) Continued

t

i

t

i

(iv)

(v)

Uranium dioxide as Zircaloy clad unirradiated fuel elementscontaining a minimum of 48 IFBA rods and 25 Instrument/Guide tubesper specification and loading pattern described in Westinghousedrawing SKA-89044, Sheet 1, Rev. 2. Two neutron absorber platesconsisting of carbon steel, 0.035 inches in thickness, with 4 mils ofGd2O3 (0.02 gm-Gd203/cm

2) affixed to each side of the plate arerequired between fuel elements of the following specifications:

Type

Pellet di(noi

Rod diameter

urn fuelength, in

xele

aximum(nom)

Maximumele

Minir

17 xZr Cl

0.308

0.360

168

264

8.4

22.5

48108

17ad

(144"L)

4.85

Uraniunf#j$<ide as ZircaHi^/fe^a unirradiat^fuel elements. Twoneutron aoldjjber plates consisting of ca^^n steel 0.035 inches inthickness, wiji 4 mils of Gd203 (0.02gtn-Gd203/cm2) affixed to eachside of the plate^se^equiyea^twe^. fuel elements of the followingspecification: *

Type


Rod diameter (nom), inMaximum fuel length, inMaximum rods/elementMaximum cross section (nom), in sqMaximum U-235/element, kgMaximum U-235 enrichment, w/o

17 x 17Zr Clad

0.3080.3601682648.422.5 (144"L)4.85

27

^

^NRC FORM 618A(6-83)




SSTClad

ZrClad

ZrClad

ZrClad

ZrClad

Zrclad

0.344-0.3670.400-0.422

0.308-0.3220.360-0.374

t

iIiiiE

t

i

cE

E

E

it

iiti

i

5.(b) (1) Continued

(vi) Uranium dioxide as Zircaloy or stainless steel clad unirradiated fuel rodsof the following specifications:

Type


Rod diameter,in

Fuel length (max)in

U-235 enrichment(max), w/oNote (1)Note (2)Note (3)

Notes:

(1) Twofneutron ablenjfh stain!e

iefe OFHC

(2) Twthi

(3) Two ne#rronsteel a^fjrequired

0.19-ininimum)

he rod bo

0.325

0.382

150

4.2

thick, fullon or 0.19-inch

^ i ^ , 0.035 inch ingm -G&03/cm2) affixed to

the 1»ad boxes.99$S*nch thick carbon

(vii) Unirradiated, urariiym dioxide, zircaloy cl>ad fuel elements, with annularpellets at the top and l§|fctcêndsofj|he<ittive fuel length. Two neutronabsorber plates consisting o^â^^h"fêel , 0.035 inches in thickness, witha cermet Gd2O3 coating affixed to each side providing a total of 0.054 g-Gd203/cm2 for both sides of the plate, are required between fuel elements.The fuel assemblies shall be held in place by at least 7 clamping framearms. Specifications for the fuel elements are as follows:

Type 14x14 14x14 CE-1

Pellet diameter (nom), in 0.3444 0.3765Annular pel let inner diameter (nom), in 0.172 0.183Rod diameter (nom), in 0.4000 0.4400Maximum active fuel length (nom), in 144 136.25Solid pellet stack length, in 132 122.65Annular pellet stack length at the top and

bottom ends of the active fuel length, in 6 6.8Rods/element 179 176Maximum cross section, (nom), in sq 7.8 8.110Maximum U-235/element, kg 18.1 18.6Maximum U-235 enrichment, w/o 5.0 4.8

28

&?&r?wwK^^

NRC FORM 618A(6-83)




(b) (2) Maximum quantity of material per package

(i) For the contents described in 5(b)(l)(i), 5(b)(l)(ii),5(b)(l)(iii), 5(b)(l)(iv), and 5(b)(l)(vii):

Two fuel elements

(ii) For the contents described in 5(b)(l)(v):

One fuel element

(iii) For the contents described in 5(b)(l)(vi):

itaoUfncf $ot more than 80 kilogramsTwo innerU-235

(c) Transport Index jpr Criticality Control

Minimum transport index to be shown on1 abel for nG&l ea^Tt^-iii cal i ty control:

Closelyo-metal

Fuel rods mustequivalent metaj!1must be fitted (Wj th a miniinoncombustible portion ofmust assure th^t«the rcrasmetal square " *""

ainer oirto more than anloaded fu&] rod containersd blocksôf which the

hich flay are securedan etSSvalent metal-ta-

Each fuel assembl?y^mustê^^hea*fle|iP(Si^|i|^%be erWMfsed in*=an unsealed,polyethylene s h e b l f ^ w h i a O T 3 % 0 ^ M ^ d | ^ ^ d ^ J s f ends o&Jhe fuel assembly.The ends of the shjeafth mu%/lrW*\be fmma^Tt^M^n any fanner that wouldprevent the flow ofefiquids into* ort^f'^dfxPe-^îthed jPugT assembly.

VAlternatively, the fuH^t^sembly may be'enclosed in ajJ^Ybngated plastic bag orsheath along its full lefnglh. At the bottom enclof the fuel assembly, the bagwill be cut off or folded bac^ô assure th»Ltb|Centire cross section of thelower end of the assembly is urobsl^cipf. $Stien folding is used, the portion ofthe sheath that is folded back will be cinched with tape near its end to hold itin place, and the length will be such that when the assembly is loaded in thepackaging, the folded sheath will be clamped in place in at least two gridlocations. The top end of the bag may be gathered together and taped closed.However, the top end then will be slit on all four sides. The slits will runperpendicular to the axis of the assembly and will extend the inner distancebetween the top nozzle pads and spring clamps (approximately 60% of the length ofeach side). The slits will be made in a plane near that formed by the top of thepads and clamps.

Use of packaging fabricated after February 28, 1986, is not authorized.

The gross weight must not exceed 6,300 pounds for the RCC packaging, 7,200 poundsfor the RCC-1 and RCC-3 packagings, and 8,400 pounds for the RCC-4 packaging.

29

^ ^ £

NRC FORM 618A(W3) CONDITIONS (continued)




(a) The package must be maintained in accordance with the maintenanceprocedures submitted with Westinghouse supplements dated June 20, September16, and September 19, 1991.

(b) The package must be prepared for shipment and operated in accordance withthe operating procedures submitted with Westinghouse supplements dated June20, September 16, and September 19, 1991.


12. Expiration date: Septembert30,p$b. *» C

REFERENCES

Westinghouse E lec t r i c Corgg^a'tion appl icat ion dated December 2 ^ 1 9 8 5 .

1986; J a n u a r y ^ | e % r u a r ^ l 4 , April 18,>, April 17, jJti»|?p, September 16, September

27, 19941*

Supplements dated: Apwj L 2October 5, and Novembe/p3O,19, and September 24,%291;

Department of Energy J*PPlement

.EAR/REGULAESY COMMISSION

J I/////,

Date:

Trj | | fs , Director

^ % N u c l e a r Mat^al Safetyand Safeguards \

30

NBC FORM 618IM6)

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.8.CERTIFICATE NUMBER





2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicablesafety standards set forth in Title 10, Code

of Federal Regulations, Part 71, "Packaging and Transportation of "Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJ3ESIGN OR APPLICATIONa. ISSUED TO Warns and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

U.S Department of EnergyDivision of Naval ReactorsWashington, DC 20585

A X

Safety Analysis Report for S5W Power Unitshipping container dated August 9, 1968,

ras amended.

> "c. DOCKET NUMBER 7,5580

4. CONDITIONS <K W ^ l <,This certificate Is conditional upon fulfillingahftrequirements of 10 CFR Part 71, as applicable, and the/conditions specified below.

5.

(a) Packaging

(1) Model

(2) Description

The $5W <P6yer ^ ^ h ^ ^ p f & e n t a A n e j ^ ^ p ^ ' is/a'contalner and supportassembly designeâd.^hip^d sifohe rKffipâji;%g^tor power units. The PUSCis comprised e s s i ^ M f y dgthre'ejM3$r asseMffes: ( ^ the outer frame, (2)the i n n e r V r | m e , ^ a | s t e y g ^ Dur+ns shipment, theshipping c b W a i n e r M f T O t M » | R O f f l e » ^ & e in Cgprizontal position.Two trunnion/êlded to ahe^ fd1 |^c t^ ;oMof the sjMpping container supportthe lower end^pj the contaiFeW|incB*Tso'!;pJiivide/Jfte>

imeans whereby thecontainer can Wk j ta ted from thfe^horizontal (^hjjiping) attitude to thevertical (loading^fnloading) attitude in t h e ^ i e r frame. The trunnionsturn in trunnion bases^hich are boltedjta t h r inner frame. The inner frameand shipping container\areTsiipp.dKted}-by'4>fte outer frame and pedestal through80 elastic shock mounts, each (Mwhrcn is secured to both the inner frame andouter frame.

Approximate dimensions of the three major assemblies of the PUSC are:shipping container: 95 inches diameter by 234 inches; Inner Frame: 109inches width by 52 inches height by 269 inches length; Outer Frame: 121inches width by 56 inches height by 236 inches length. Maximum weight of theloaded PUSC is approximately 127,900 lbs.

(3) Drawings

The packaging is constructed in accordance with Westinghouse ElectricCorporation Drawing Nos. 936F963, Rev. 3 and 936F964, Rev. 2.

3 1

^^^g^S^X^S^r»^I*t

I

t

c

it

i

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i

t

ttii

i

iii

i

i

NRC FORM 618A(6-83)




(b) Contents


Unirradiated fuel assemblies of the following type,

(i) S5W Core 4 power unit with control rods installed and secured inplace by holddown mechanism.

(ii) S3G Core 3 power unit with control rods installed and secured inplace by holddown mechanism.

(iii) DMC Power Unit w|thOpn"S^'^.r/Sa"s*instaned and secured in place byholddown mech#i|#^^ ^ %JA"

1)(ii), or

(2) Maximum quan^i^ of material per package

One fuel ^sembly as described in 5(b)(l)(i),5(b)l)(viT>:

(c) Transport I

Minimum transport indlabel for BflSlear cri

Expiration Dater Dec

Safety Analysis Report ¥bruS5WAugust 9, 1968; AddendumNpck>WAPD-OP(Rf

Naval Reactors Supplements dl&?fc March 2, 1992 (G#92-03

iner, W/8hM)P(R)SA-820 datedV 1 9 8 7 .

NUCLEAR REGULATORY COMMISSION

Date:

William D. Trayers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

32

» ^ ^

argrw w \tr t*r \*nNRC FORM 618(3-96)10CFR71




5607

b. REVISION NUMBER

9


USA/5607/B( )F

d. PAGE NUMBER

1


3

3

i

2. PREAMBLE




U.S. Department of EnergyWashington, DC 20585

T-2 Shipping Package, Safety AnalysisReport, Draft: April 1980,as supplemented.

c. DOCKET NUMBER 7 1 - 5 6 0 7

333

3

4. CONDITIONS


(a) Packaging / •

(1) Model No.,: T-2.

(2) Description

Packaging for irrMi|ted; reactor fuel/anat'components_consisting of a leadencased in steel c^sk|; removable con$a|nffent vessel insert and shippingc a s e . " 1 • .••,.< ~~K'z-•,'"• "'" "'* ':-T:'*£''

The cask isshielding in , ,diameter by 10"0n'nches.long/rThe:.'Tead shielding ts:.8.0 inches thickalong a 45 1* nch'Rentier:'"iec^prt-/i(;educe^0;f4.2 inche? at each 36-inch endsection. -The containmient//ye^sex;l( is positioned within the cask. Caskclosure is accomplished byt'0gasj:eted and bolted/"steel plug. The cask isenclosed in the. shipping case-which is 36 inched in diameter by 133inches long welde'd to a 4-foot by 6-foot steel pallet. The maximumweight of the packaging is 18,400 pounds. '

s a^double%a1/led; stjefel;' ct^culTar||:y-Xinder with thickenedin the^enter^portipyj;) TJre cen|fal:>cavity^s 6.065 inches in

(3) Drawings

(i) The shipping case is constructed in accordance with DuPont DrawingNos.: W716539, Rev. 0; 180191, Rev. 1; 180192, Rev. 0; 180193, Rev.1; 180194, Rev. 0; 180197, Rev. 0; W716538, Rev. 0; 180195, Rev. 0;180196, Rev. 0; and 180089, Rev. 0.

(ii) The cask is constructed in accordance with General Electric DrawingNos.: 919D755, Rev. 0; 135C5202, Rev.0; 153F966, Rev. 0; and106D3721, Rev. 0; or it is constructed in accordance with DuPontDrawing Nos.: W239534, Rev. 2"; 147214, Rev. 15; 147215, Rev. 2*;and 147216, Rev. 1.

* As provided in the April 12, 1983, supplement

i

i

33

nNRC FORM 6 1 8 A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)


£ 5.(a) (3) Drawings (Continued)

(iii) The ANL insert is constructed in accordance with Argonne NationalLaboratory Drawing Nos.: W0147-0227-DD, Rev 7; W0147-0228-DD, Rev.6; W0147-0229-DC, Rev. 6; W0147-0231-DD, Rev. 3; W0147-0234-DC,Rev. 4; and W0147-0312-DE, Rev. 2.

(iv) The TREAT Vessel insert is constructed in accordance withWestinghouse Hanford Company Drawing Nos.: H-3-39082, Sheets 1through 4 and 6, Rev. 0, and Sheet 5, Rev. 1; H-3-36134, Sheet 1,Rev. 3 and Sheet 2, Rev. 2; and H-3-36823, Sheet 1, Rev. 1 andSheets 2 through 4, Rev. 0.

(b) Contents

(1) Type and form of material •' ' • •• 's . :-' -5 (i) Irradiated clad fuel in the form of solid;metal, oxides, nitrides,g and carbides of uranium, plutonium, or mixed uranium-plutoniumg contain.ejd within the ANL insert or TREAT Vessel insert. The clad£ fuel may>€ontain small quantities of^Narôr-NaK. The minimumg cooling time Bust be no less than/ISO,days. •

z (ii) Irradiated :cf§iaV;fuel pins of lir arfium/dioxide enriched to up to 3.0* w/o in U-23||c:o:htained.witfiin^th^^NL insert or\TREAT vessel" insert. .Average exposure of fueJ'inVt to exceed 18 megawatt days* per ki X.6g.P;am;/* J h e ^ of Na or

( i i i ) I r r a d i a t X d j r ^ the,container shown in

NaK. Theiminimum/.cb6lîhg. tijjie^lnust,îe!;no' less than 90 days.iK. Theiminimum/cbtiTirig. tiriie\4nust,beV.h'c.<•- 'N^ : X - ' • ' , , - , -f;'-'/ji " ' , : • ; , ! * W \ . " - >V:.\'/.'"-r

Tadi aferf?rSar.tnr: homrihnpnt!?;; hpl H Wit;h*i r

Drawing?S (2) Maximum quantity of

S Internal decay heat not to exceed 208 wattsvind:

8 (i) For the material"descrlbed^.in^5(b).(l)(i), fissile material not toS exceed 1.71 kg.S (ii) For the material described in 5(b)(l)(ii), fissile material (U-235)

not to exceed 300 grams.S (c) Transport Index for Criticality ControlSS For the contents described in 5(b)(l)(i)S and 5(b)(l)(ii), and limited in 5(b)(2)(i)8 and 5(b)(2)(ii):S Minimum transport index to be shown on3 label for nuclear criticality control: 0.4

34

Sic SK :5c MK atf ate JSETMK tc W W w Ht ^ ^tc

NRC FORM 618A(3-96)



6. The contents must be shipped dry. When loaded underwater, the package must bedried using Consumer Power Company's procedure, "T-2 Cask Liner Assembly DryingProcedure," Proc. No. EE&T-C12, Rev. 1, 11/12/81.

7. The ANL Insert and TREAT Vessel insert must be leak tested prior to first useand annually thereafter in accordance with the procedures specified in ArgonneNational Laboratories Document No. W0195-0054-ES-00.

8. Prior to each shipment, the package must be leak tested in accordance withprocedures specified in Appendix A to HFEF/N OMM 6202, Rev. 2, March 17, 1981.

9. In addition to the requirements of Subpart G of 10 CFR Part 71 and the otherconditions of this certificate:

(a) The package shall;be operated and prepared for shipment in accordancewith the Operating Procedures in Chapter 7 of the application, assupplemented; ajid

(b) The package must be maintained in accordance with the Maintenance Programof Chapter 8 of the. application, as supplemented.

10. The package authorized by this certificate is hereby approved for use under thegeneral license provisions .of 10 CFR"§71.12. C S V

11. Expiration date: May 3i£§L99&.... s V 4 -

^ 0 ! ' : C w REFERENCES^.' -,?•'-/

DuPont Safety Analysis Report, Draft^pril 1980. V

Department of Energy supplements'dated^Nijruary 11;- April 8 and 20, 1982; April 12,1983; February 26, 1992;, and •--•--••-•-•••""'•••"«w "

FOR THE U.S. NUCLEAR-REGULATORY COMMISSION

Date:

William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

35

TSJSsjsj&j^kWsWs WJSJSJSJSJ^PJWKWS m*-, m^isjsj&j^j^jiRJSJSJSu









3

2. PREAMBLE





b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Safety Analysis Report for Packaging (SARP) ofthe Oak Ridge National Laboratory TRU CaliforniumShipping Container, August 7, 1981, Rev. ofReport No. 0RNL-5409/R1, as supplemented.

71-5740c. DOCKET NUMBER

4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable; and the conditions specified below.

(a) Packaging -

(1) Model No.: ORNL TRU Californium Shipping Container ,

(2) Description ,x „ //

A 304L stainless ste^eincased.concrete shipping cask. "The outer shellconsists of two, l/2xijic|i thick, 66-inch diameter hemispherical heads joinedby a 6-inch cylindrical "Section*.,. The cyl tncfri cal cavity has a1-inch thick stai.nles^tstreeT wall and is /Synches in diameter x 6 inches long.Shielding consist^'pf 30 tfches; of. Blackburn Limonite concrete having adensity of approximately 1;7.5-1 b/ft3L-. 'Upper and-tower levelball valves'locatedy'at'the end of. concrete filled plugs define, isolate, andseal the cavity. ?Both" of these plugs have/0-ring seals, are bolted in placeand are protected witha'. gasket|'d;cqyer'plate. Fusible plugs are located inthe cover plates and the '-shell*i^vfflv ",.' ;,-.-j

The top ball valve and plug may be replaced by other plugs for multiple sourceshipments. Sources- are contained in special form inner containers.

The cask is mounted onto? a .l-,Tnch. thick steel base plate by eight steel 2-1/2inch NPS Schedule 40 pipe struts. The cask is transported on a specialt rai ler . The package gross weight is 23,500 pounds.

36

n w wwaz a? wwwaraTaz az wwwwwwwai: az wwaz azwaz agwae arwww az az www wag a? acNRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


5. (a)(3) Drawing

The package and special trailer are constructed in accordance with Oak RidgeNational Laboratory (ORNL) Drawing Nos.:M-11230-EN-001-D Rev. 4M-11230-EN-002-D Rev. 0M-11230-EN-003-D Rev. 0M-11230-EN-004-D Rev. 2M-11230-EN-005-D Rev. 0M-11230-EN-006-D Rev. 0M-11230-EN-007-D Rev. 0M-11230-EN-008-D Rev. 1M-11230-EN-012-E Rev. 4M-11230-EN-014-E Rev. 3M-11230-EN-017-D Rev. 3 .M-11230-EN-018-E Rev. 0(Appendix A, August .7," 1981 revision of 0RNL-5409/R1, as supplemented.)

(b) Contents

(1) Type and. form of .material ./•-.-

The contents consist of isotopes of Amejpic'ium (Am), Curium (Cm),Berkelium (Bk), Californium (Cfj, Ein|tî)iium (Es), and Fermium (Fm) asa solid (metal, rbxide, oxysulfate, ofî0 salt), contained in capsule(s)that meet the,.requirements of special?.•Krm radioactive material.

(2) Maximum quantity pfiifaterijal per<package,//;v/:

For the contents,described in 5(b)(l):, -

Three (3);grams and the^ftîmumiMefrnai heat njbt'to exceed 5 watts.

6. The contents describedrjn 5(b)(l) mustJbe shipped inâ.êal welded special forminner container as described in section 5.2.1 of tHeâpplication.

7. In addition to the requirements" oflSubpart ~G of 10 CFR Part 71:

(i) Each packaging must be maintained in accordance with the supplement datedMay 10, 1991; and

(ii) The package must be prepared for shipment and operated in accordance with thesupplement dated May 10, 1991.

8. A minimum of two lifting ribs shall be used to lift the package.

9. The package authorized by this certificate is hereby approved for use undergeneral license provisions of 10 CFR §71.12.

10. Expiration date: July 31, 2001.

37w^w^wswj^wjcjgej&we.we.we.we^w^w^^jjyej^

ssrNRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)

Page 3 - Certificate No. 5740 - Revision No. 5 - Docket No. 71-57405M

M

M

REFERENCES

Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRUCalifornium Shipping Container, August 7, 1981, revision of Report No. 0RNL-5409/R1.

Supplements dated: April 4, 1986; March 26, April 23, and May 10, 1991; June 4, 1992;and May 13, 1996.

3FOR THE U.S. NUCLEAR REGULATORY COMMISSION

:«

William D. Trayers, DirectorSpent Fuel Project OfficeOffice of Nuclear. Material Safety

•'.:- and Safeguards-^v

a Date:3

3 • > i ' ^ ; v ; . 4 . . ' , v ^ s i ; ; ! ! ! ; j : ; : ; : t ; ^ " V>?^'/~ -»•- £

v -~i \,; v\

38

NRC FORM 618(3-96)10 CFR 71




5757

b. REVISION NUMBER

6


USA/5757/B( )F

d. PAGE NUMBER

1


22. PREAMBLE




U.S. Department of EnergyDivision of Naval ReactorsWashington, DC 20585


Safety Analysis Report for S5W RefuelingSource shipping container dated February 14, 1968

c. DOCKETNUMBER 7 1 - 5 7 5 74. CONDITIONS -. < . '

This certificate is conditional upon fulfilling the requirementsof 10 CFR Part 71, as applicable; and the conditions specified below.

5.

(a) Packaging >. ' ->

(1) Model No.: ;S5W Refueling Source

(2) Description ''v;-:••,.„ ., ;-; .

The S5W Refueling*;Spurce, shipppg contajfteij consists of two structures,one nested within5t1ie?.btKer,"having an^yejjall envelope of 5 feet,5 inches diameter$£9 feet,>?5-5/8 inchreMlength. The outer structure,the shipping c.6ntaffferr?; is, a-nngof p;dl^thylene 11-1/2 inches thickwith an 0D ofi^êef^îwhes and lengtfivof;approximately 5 feet2 inches:i The p'dl et'Ry|;§rie is tanked;^n a/l/Z/inch thick carbon steelshe! 1. The inherils^fucturey the repl acement>and instal 1 ation container,fits into'the cfvityôf/ithe outer:structured This.assembly consists of a6-1/2 incb/OD/7s[^/^',fnch^;3-qn^statff%s centraljtube, which isplugged at-both ends by, maeh>|\>^ stainless steel forging. Three cavitiesare machined;/in the bottomed plug to contain the neutron sourceassemblies. A'jacket of leacf^'6 inches thick,, encircles the central tubeand this innermost layer of shielding to attenuate the gamma radiation.A wall of polyethylene, 8-1/2 inches thick, surrounds the lead shield andis canned with a 1/2-inch thick carbon.steel plate. Gross weight isapproximately 19,000 pounds.

(3) Drawings

The packaging is constructed in accordance with Westinghouse ElectricCorporation Drawing Nos. 905D318, Rev. C; 905D315, Rev. F; and 905D285,Rev. A.

39

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5.(b) Contents


(i) Radium-Beryllium special form radioactive material neutron source.These sources may be either new or irradiated and have surface

3

3

sj

M

M

3^ contamination as a result of previous use.3M

3M

33

(i i) Plutonium 238-Beryllium special form radioactive material neutronsource. These sources may be either new or irradiated and havesurface contamination as a result of previous use.


(i) One, two, or thpee^jieUtrbfr sburce's/;a.s described in 5(b)(l)(i) andlimited tp-a total content of notvm6re,-than 940 curies, with radiumlimited<tp-riot more than 2.5 curies (gfnsj and total emission rateof 3.8/x-lO n/sec. These sources are limjted to a combined surfacecontamination of not more than an A2 quantity.of radioactivematerial;.:^. ^^ ''/--•,

(ii) One, two, bi|*tniregN neutron sources^s^escribed in 5(b)(l)(ii) andlimited to a^ptancontenfcof nbtltnpli than 92.5;curies and totallimited to a%p1fcal\conjtenfcof rfi%i$0 than 92^5;curies and totalemission rat^b.|;li48 x)1lO9/n/secg Jr&ese sources are limited to a

d ^ | t i i ^ t ? h tit fcombined sur%c'econtami^tion ?pf?^t? more than an A2 quantity of• r a d i o a c t i ' v . e i-'--£B---^--" •'• —••"•:->- ••• '•-••--

(c) Transport Index

Minimum transport in^x-tjB^bfcfs^wn^pn/'V^^ r 'label for nuclear- critfcai;i;ty"coWr5bl';:vv

A> : v'r;'" / 0.4

9. The package authorized by this ce$#f-lc)ite is hereby,approved for use under thegeneral license provisions of 10 CFRV§'71.12. -

10. Expiration date: December 3*1, 1997., -

REFERENCES

Safety Analysis Report for S5W Refueling Source Shipping Container, WAPD-OP(R)S-2473dated February 14, 1968.

Supplements: Bettis Atomic Power Laboratory letter WAPD-OP(R)C-474 datedDecember 22, 1975; and Naval Reactors letter G#92-03738, dated October 15, 1992.


William D. Trav^rs, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and SafeguardsDate: ^ _ " i " l l l '

W6fi®R&KS?ifWi/6ttF&FW®tt^

NRC FORM 618(M6)10 CFR 71



1.«.CERTIFICATE NUMBER



USA/5796/B(U)d. PAGE NUMBER


22. PREAMBLE

a. This certificate Is Issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Codeof Federal Regulations, Part 71 , "Packaging and Transportation of Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJ3ESIGN OR APPLICATIONa. ISSUED TO (Ntmo and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Advanced Medical Systems Inc.121 North Eagle StreetGeneva, OH 44041

Advanced Medical Systems, Inc. applicationdated June 26, 1992, as supplemented.

Ci.e. DOCKET NUMBER /1 'T57,96

4. CONDITIONSThis certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and tha'conditions specified below.

(a) Packaging tf> C*

(1) Model Nos.^?181375

(2) Description

5 1 N tK-C*

Overpacksrthat p;rpy de15i.n1pNaqt and thermal^rj&ectyi o/i forSteletherapy headassembliesf^br solu£!6f exii'Rjingeâ^s^^ o~verpacks covered with16 guage steel p'aq:e|(s)/iîWiôreH^jsieQ^fstr^Jc^nd an53^s are weldedtogether an%spacie^1;6^4imi^thi;;open^ betêpHhemô less than 6inches. Sk'ui\runne'KS;fa .e' pQ>Q<i to^|WcilA.wce fo r k - l i f t usage. Dimensionsof the Modeii'Nq. 181375:t|re"""4^t^39Wt5%#41 l lH wi'iR} a maximum grossweight of SJ^pounds. fDimeHsf6ti%v f theffjodel No -181361 are 39"L x34.25"W x 44.5'"^with a maximMm^gf sj "weight of 4 .000 pounds.

(3) Drawing /

(i) The Model No. 181375 packaging4sfconstructed in accordance with AdvancedMedical Systems, Inc. Drawing NosT. as specified in Section 1.3.1 (p 1-11)of the application.

(ii) The Model No. 181361 packaging is constructed in accordance with AdvancedMedical Systems, Inc. Drawing Nos. as specified in Section 1.3.2 (p 1-12)of the application.

4 1

glMftfflli T ™• TBfTFMMSZB hT ill



5. (b) Contents(1) Type and form of material

(i) Cobalt 60 sealed sources that meet the requirements of specialform radioactive material; or

(ii) Cesium 137 in the form of cesium chloride encapsulated in sealedsources that meet the requirements of special form radioactivematerial.


(i) 13,680 curies of cobalt 60 with a radioactive decay heat load notto exceed 200 --•"— >'•** ---

(ii) 2,200 qurie/ôf cesium 137 with 1a'4^diqactive decay heat load notto ex.ceVd/17 watts. « A

X 'i {( a

6. In addition to theJfceq'uirements of Subpart G of 10 CFR Part\71:(a) The packages^musirvHe^ppêrated and prepared fq^hipment^-in accordance with

the Operating^Procedafte'sNjf Chapter 7 of ^hesM'piication..,

(b) Each packag"ing must m je%%hi Accep^tarfcelT^^nd Maintenance program ofI Chapter 8jjo;f the appl|;e:at|fori. ^ J^ \WktM jjf.

7. Use of packagiB'g-JfabriG4ifed^^^Âugyjs.t._3L^^6f:> \&k$. authorized.

8. The packages authorize^gbyijth-is'e^^fijcatlegre her.^^^pproved for use under the

9. Expiration date: \3uly "W/tM&s xêfs^x. ^&s?

Advanced Medical Systems, Inc.âppjjfation dated Junex.26, 1992.

Supplements dated: August 13 and Oc'tober f5Vfl992\


Charles E. MacDonald, ChiefTransportation BranchDivision of Safeguards

\% ^L and Transportation, NMSSDate:

42

2«^«MSMa^SVaia«^ffl^»yS^¥^¥^«jayffiU»i*!ft^¥^^^

•V»YY»VY*YY»VY»Y7»YY»YY»VY»YY»YY»VY»Y7»YY»VY»YY»v

NRC FORM 618

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESLaXEflTIFICATE NUMBER



USA/5797/B(U)Fd. PAGE NUMBER


2. PREAMBLEa. This certificate Is Issued to certify that the packagingand contents described in Item 5 below, meets theappiicablesafety standards set forth inTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEUESIGN OR APPLICATIONa, ISSUED TO Warns end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


U.S. Department of Energyapplication dated May 30, 1991,as i?supp,l emented.

' "a. DOCKET NUMBER " 7 1 ^ 5 X 9 7

CONDITIONS « \ $ " J < i V /This certificate Is conditional upon fulfill!ng.thS,requlrements of 10 CFR Part 71, as applicable, and the/conditions specified below.

(a) Packaging

(1) Model

(2)

lement Shipping Container, andElement §h§lpping Container

FIR Unvpcadiated'i" * Ufii^t/d

Description,

Paddingfor the Hicirctfjar cy{attached tosteemtiel lrings.'TThe plywoothick poxyfethylene foai

•#j!nch high/^Douglas f i r plywoodwhich is lined with 1-inch

The packaging^for the inner HFIR fuel element has overall dimensions of25 inches OD bycavity, and a

igh,, a D0f7/8-inch diameter by 30-1/4-inch deep

The packaging for the outer HFIR fuel element has overall dimensions of31.5 inches 0D x 45.75 inches high, a 17-3/8-inch diameter by 31-1/8-inchdeep cavity, and a 1,050 pound gross weight.

(3) Drawings

(i)

(ii)

The packaging for the inner HFIR fuel is constructed in accordancewith Martin Marietta Energy Systems, Inc., Drawing Nos.M-20978-EL-003E, Rev. C, and M-20978-EL-008E, Rev.B.

The packaging for the outer HFIR fuel is constructed in accordancewith Martin Marietta Energy Systems, Inc., Drawing Nos.M-20978-EL-002E, Rev. C, and M-20978-EL-008E, Rev.B.

43

\l&?JK>J

ffi

t

•t

c

ttt*Ittiii

Ittt•

r

t

NRC FORM 618A(6-83)




(b)

(1)

Contents

Type and form of material

Uranium as U308-Al cermet, enriched up to 95% in the U-235 isotope, and cladin aluminum, 10-mils thick, and:

( i ) For the packaging described in 5(a)(3)(i), the contents are describedin ORNL/TM-9220, "Specifications for High Flux Isotope Reactor FuelElements HFIR-FE-3," and in the following Oak Ridge NationalLaboratory Drawing Nos: E-42118, Rev. M; E-42112, Rev. H; D-42113,Rev. G; E-42114, Rev. H; and E-42117, Rev. H.

(ii) For the packag$nd^deTs^riIbld1'°iM^|^)(ii) the contents are describedin 0RNL/Tfc9g2Of "Specifications T"o$»|W||h Flux Isotope Reactor FuelElements l-pil-FE-3," and in the fol 1 owflng>Oak Ridge NationalLabora«tf$y Drawing Nos: E-42126, Rev. J; Ef'42120, Rev. H; D-42121,Rev. j^TO-42122, Rev. H; and E-42125, V ^

(2) Maximum q|ranti

(i)

(ii)

(c) Transport"

Minimum transportlabel for nu&rt

material per package

n than 2.63 kg of

than 6.88 kg of

6. The l id l i f t ing atlffdhjnents must belbj'bciced as showqSystems, Inc. , Drawiftgyfto. M-20978-EL-009E, Rev. 21the attachments during transport .

}Martin Marietta Energyprevent inadvertent use of

7. In addition to the requirements

(a)

arFG of 10 CFR Part 71:

Each package shall be maintained in accordance with the Maintenance Programin Chapter 8 of the application;

(b) Each package shall be operated and prepared for shipment in accordance withthe Operating Procedures in Chapter 7 of the application; and

(c) The fuel element shall meet the fabrication inspection requirements ofORNL/TM-9220, "Specifications for High Flux Isotope Reactor Fuel ElementsHFIR-FE-3."

8. Use of packaging fabricated after December 31, 1976, is not authorized.

44

^NRC FORM 818A(6^3)






REFERENCES

U.S. Department of Energy Application dated May 30, 1991.

Supplement dated: February 26, 1992, and April 2, 1993.

PTS.SNUCLEAR REGULATORY COMMISSION

Date:

(

William D. Trayers,Spent Fuel ^Office of

and Safeg

^^^

NRC FORM 618

10 era 71


FOR RADIOACTIVE MATERIALS PACKAGES1.8. Cl NUMBER b. REVISION NUMBER

16C. PACKAGE IDENTIFICATION NUMBER

USA/5805/B(d. PAGE NUMBER

10. TOTAL NUMBER PAGES




rt

a. ISSUED TO (Name end Address}

Chem-Nuclear Systems, Inc.140 Stoneridge DriveColumbia, SC 29210


Chem-Nuclear Systems, Inc. applicationdated February 25, 1994.


4. CONDITIONS .. _ •;This cettificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model No. :>-;.CNS 3-55 J § i - \ ---- . . ' ?£/

(2) Description; 'f>^( { : •/. -•; •':"'

The packagers a>s|ie;el-^^|a>>-.l.ef|d--shMde1^ca§lc,with crushable impactl innters. The basôaski%is;teei; :cyl inder 13'3j-3/4 inches long by 50-1/2inches in dêter^jpnaxîOin.-cavityNtfi inens^ôf 36 inches in diameter by116 inches Ions rediicefeto;1%:inches ^>the. sh-ield ring attached to the l i dcover. Shielding i ^ ro^ l i a^g^ch fes -^nGhemica l - l ead in the sides andclosure base plate arid 5-1/4 iiêsîriAth<<|!osed end. "'

The outside steei|encasement isHiVde up of two, 1/2-inch plates on the sidesand three plates totaling 2-5/8 inches on the end. The containment vessel isa 1/4-mch thick cylinder:with a 1/2-inch end plate. The shells are weldedtogether with the lead shielding, poured to f i l l the annular and end spaces.

The removable, flanged and recessed base plate weldment consists of 3/8-inchand 1-1/4-inch outside plates and a 5/8-inch inside plate. The space betweenthe plates is lead-f i l led.

The base plate is secured to the cask body by means of twelve, 1-1/2-inchhigh strength bolts and nuts and sealed with two silicone 0-rings.

The cavity is penetrated by a vent l ine at the closed end and a drain linethrough the base plate. The vent l ine is sealed by a gasketed and shieldedplug. The drain line is sealed with a 25 psig re l ie f valve.

4 6

I

i

{i



.(a) Packaging (continued)


Cask appendages include two, 8-inch lifting trunnions and two, 4-inchremovable tilting trunnions on the cask side.

Removable impact limiters are provided at the cask ends and at the two, 8-inch trunnions. The former consist of a series of 6-inch diameter closed endtubes. Each impact limiter has tubes approximately 6 inches long around theend periphery. The closure end impact limiter has 12 tubes, six about 6inches long and six about 2 inches long, around the sides. The closed endimpact limiter has six tubes about 6 inches long around the sides. Agusseted tube acts as the trunnion impact limiter.

The cask is secured horizontally to a skid which is mounted to the transportvehicle for shipment. An optional sunshade is provided.

The gross weight of the package, excluding the skid and sunshade isapproximately 70,000 pounds. The skid weighs about 4,200 pounds.

(3) Drawings

The packaging is constructed in accordance with Chem-Nuclear Systems, Inc.Drawing Nos.: HOD 100, Rev. 12; C-lll-D-0001, Rev. 0; and C-lll-E-0002,Rev. 1; and ATCOR Drawing Nos.: MOD 139.-1, Rev. K; MOD 140, Rev. C; MOD 124,Rev. D; 0999-D-07, Rev. G; and 0999-C-08, Rev. G.- An optional sunshade isconstructed in accordance with Chem-Nuclear Systems, Inc. Drawing No.C-110-D-5001, Rev. 1.;

(b) Contents


Depleted Antimony-Beryllium (Sb-Be) neutron sources and irradiated metalcomponents packaged in secondary containers.


Package internal decay heat load not to exceed 250 watts. The source strengthof depleted neutron sources not to exceed 2.3 curies of Antimony-124.

(a) Both the inner cask cavity and the secondary container must be free of waterwhen the package is delivered to a carrier for transport.

(b) Except for close fitting items, shoring must be placed between contents,secondary container and cask cavity to minimize secondary impacts due toaccident sequence.

(c) The maximum gross weight of the contents, secondary container and shoring islimited to 9,220 pounds.

47

6.

^



7. Prior to each shipment, the silicone 0-ring seals (base plate and vent plug) mustbe inspected, the seals must be replaced with new seals if inspection shows anydefects or e^ery six (6) months, whichever occurs first.

8. Prior to delivery of the package to a carrier for transport, the packagecontainment cavity shall be leak tested. The sensitivity of the test shall be atleast 1 x 10 atm-cm/sec (STP). In addition, the packaging containment cavityshall be leak tested at least once every twelve (12) months. The sensitivity ofthe test shall be at least 1 x 10 atm-cm3/sec (STP).

9. The package shall be prepared for shipment and operated in accordance with the£ Operating Procedures of Section 7.0 of the application.i

i

i

10. Each packaging must meet the Acceptance Tests and Maintenance Program ofSection 8.0 of the application.

11. The package authorized by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12. Fabrication of additional packagingsafter December 31, 1983 is not authorized.

12. Expiration date: March 31, 1999.

• • : REFERENCES .-'•*'

Chem-Nuclear Systems,-Inc. application djated, February 25, 1994.

FOR THE ;U,S... NUCL-FAR REGULATORY COMMISSION

Cass R. Chappell, Section LeaderCask Certification Section

"'" Storage and Transport Systems BranchDivision of Industrial andMedical Nuclear Safety, NMSS

APR 0 5.1984Date

48

^


FOR RADIOACTIVE MATERIALS PACKAGES'.CERTIFICATE NUMBER





£.. PREAMBLEa. This certificate is issued to certify that the packaging_and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



3, THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Department of the NavyNaval Support Force AntarticaFPO San Francisco, CA 96601

Minnesota Mining and Manufacturing Companyapplication dated June 28, 1968, as supplemented

kc. DOCKET NUMBER '~ ' d - , 5 8 3 0

4. CONDITIONS v-^vThis certificate is conditional upon fulfilling.tnerrequirements of 10 CFR Part 71, as applicable, and the conditions specified below.

' "^ A ,^/ *

(a) Packaging^

(1) Model

(2) Description t\fl

A thermoelectrapackaged^n a^Sby 68 iVchesBerylco-UVsthermoel ets.tr1 j c mdclul e1,900

(3) Drawings

The SNAP-21 isManufacturing Company Draviin3M Report No. MMM-3691-33.

by,30;.inches longeJenclosujpe 52 inches in diameter

jhe£g'enerato;r^consist o f an outersJpeldingsCthermal insulation;

weight of the package is

V-WJI-UHI.^C with Minnesota Mining andlo.^B-SK-37-4014 and Drawings included in

(b) Contents


Strontium 90 titanate pellets doubly encapsulated by a thin innerliner and a 0.2-inch thick Haste!loy C primary containment capsule which meetsthe requirements of special form radioactive material.

(2) Maximum quantity of material per package 33,000 ci.

4 9

NRC FORM 618A(6-83)


tt

tE

t

•t

E

ii



(a) The package must be prepared for shipment, operated and maintained inaccordance with Minnesota Mining and Manufacturing Company Report No. MMM 3691-42, "SNAP-21 Program, Phase II, Deep Sea Radioisotope-Fueled ThermoelectricGenerator Power Supply System, Shipping and Handling Manual."

7. The package authorized by this certificate is hereby approved for use underthe general license provisions of 10 CFR §71.12.

8. Expiration date: Noyen)b>r

Minnesota Mining andmnufacturing Company application^Department of Navy^applWrvts dated June 8 and "September 20, 1 9 9 5 ^

ne 28, 1968.to, and


Date: U \ I \t\s

fi«WiSgig^^^^

KRC FORM 618IMS)10 CFH 71


FOR RADIOACTIVE MATERIALS PACKAGES1.B.CER IMBER b. REVISION NUMBERIUBE c. PACKAGE IDENTI d. PAGE NUMBER1MB 8. TOTAL NUMBEB PAGES



b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, Including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DESIGN OR APPLICATIONa. ISSUED TO Warns and Address! ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Department of the Air ForceHQ ATAC/SEG1030 S. Highway A1APatrick AFB, FL 32925-3002

• V

Teledyne Energy Systems application datedJune 26, 1985, as supplemented.

5 V DOCKET NUMBER

4. CONDITIONS < \ ^ Vf ^This cenificate is conditional upon fulfilling-ihe^requirements of 10 CFR Part 71, as applicable, and th<j conditions specified below.

5.

(a) Packaging

(1) Model No>& Sentinel*A

(2) Descnpt^ ^ | 1 | g |T . . '*$•'$£</••,. • t s W J iThe nar.kaae.. a tiiraKmneiipnfTfcrr-1

2The package-, a *%^ê|ect#ijc[ aeneMi|^r is J]p»^nche§pn height with a basediameter af^24.5"^|^s- j j^^ iud)n ,9 j^^M^n9/f^ and^weighs approximately2,600 pounds - Theî^Q^rieWt'S^TO&lbde^^^^ffgsten biological shield (10.705" X

um^?061) outej^-protective housing._ wf the aluminum housing provide the

13.837" 0D)vw.hich is wit}hinFour 6061-T6*<mo\inting paa's ashipping palleiâttachment p

(3) Drawings

uc> . ^ , ^ W ^

The packaging is constructed'ii^ccqrlance with the following Isotopes, Inc.Drawing Nos.:

010F10000 Sheets 1-3 (Rev. C), Generator Assembly Sentinel 100F010-20000 Sheets 1-2 (Rev. B), Fuel Capsule Assembly010-70003 (Rev. A) Shield Body010-70004 Shield Plug001-90064 Sheets 1-2 (Rev. A), Shipping Crate Sentinel RTG001-90039 Sheets 1-2 (Rev. J), Sheet 3 (Rev. H), and Sheet 4, Pallet Assembly

NFtC FOHM 618A(6-83)




5. (b) Contents


Strontium-90 titanate doubly encapsulated in a stainless steel liner andHastelloy or Uniloy HC capsule which meets the requirements of specialform radioactive material.


370,000 curies.

6. Fabrication of additional packfgpg's i^r

7. In addition to the reqifinelents of Subpart G of 10<C$R*B$rt 71:

(a) The package sffa£r be prepared for shipment and operated in accordancewith the Oper§Ein£ Procedures in the supplementâêidÂugust 30, 1985.

(b) The packageTraust be^%Uined in accordaj ""**"»• "•- "--•-in the sugpi-iment df^Ôgyst ^ , J | "

8. The package authorized bygeneral license^provisi

Expiration datet^9.

Teledyne Energy SystemjMappli

the Maintenance Program

approved=#or use under the

Teledyne supplements dated^? August 30,

Department of the Air Force supplements dated: November 1>2, 1993; and August 15, 1995.

: KMTII^NUCLEAR REGULATORY COMMISSION

Date:OCT 0 3 1995

JWilliam D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

52

H"gggg

**

:wii()ifwafittwata<w w wjifacwatatc









3

2. PREAMBLE


b, This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.

gg

ggggggggggggg•a

*


Department of EnergyDivision of Naval ReactorsWashington, DC 20585


Safety Analysis for Radioactive MaterialShipping Cask No. WAPD-40 datedDecember 1984, as supplemented.

c. DOCKET NUMBER71-5874

4. CONDITIONS , " -, ,„ - . - .

This certificate is conditional upon fulfilling the requirements of 10..CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No.:VWAPD-40 ~>.

(2) Description <i.>;>; ---<."; </~

The WAPD-40 shipp\rt| xontainej^ris ,a cy]indf;ical, staqnless steel clad,lead shielded, shipping" container, used^fo^sjiip irradiated fuel and non-fuel test specimens^:ph^contêr hia,sfaj)|outer Typ|-304 stainless steelshell 172-inchijlhicfeand ari'Triher TypeÔ^stainless^teel shell 1/4-inchthick, With 9V87|I ine^slofril.e.ad.vbetêgn;^ overall size ofthe container;î1{c;lu/f^ in diameter by158 inches in %ng:t(w ^6ss:|wei;ghtÛncludfng"skid)-bf the container isapproximately 2'8'jijOO.O pptinfds;'y;Th'e!;he||.4;em<qval capacity is approximately2000 BTU/hbur. T^'GyltindW^liînner chyity is 2,-rinbhes in diameter and135 inchesîh,length. Îm&mcont^ners..'aVe required for all shipments.Stainless steel, clad, lead'ispeljded endvplugs.-bolt into each end. One-half-inch thick^plates are bolted over the ,end;piugs to provide a totalend plug.flange .thickness of 1.0 inch for puncture resistance. Metallic,pressure-filled 0-rihgs between the endplugs and the container seal thepackage. The cask may be- wrapped ;in pdlyvinyl chloride when shipped in aclosed truck. A special holddown cradle is used during truck shipments.This cradle weighs approximately 5,000 pounds. ;

(3) Drawings

The WAPD-40 cask is fabricated in accordance with Westinghouse ElectricDrawing Nos. 936F577, Rev. 11, and 936F578, Sheet 1, Rev. 9, and Sheet 2,Rev. 4.

53

37. As needed, shoring must be used to limit movement of contents under accident

* conditions of transport^

m

H

8. The lifting trunnions must be covered during J;r$risport to preclude their use astie-down devices. ^ ^'t^.' '>•'*-'-.'• ''^-§'

9. The contents of the- cbntainj6r>miist be"limited^so that;the maximum measured gammadose rate (above backgrovjndj "ofi the( side ot: the icisio for normal conditions doesnot exceed the value-defined by..Cs

f (lOOO-NJ/F. . < :".•-;>-• >"'/''V'..,. . '.V:.v•-../.' ;'

where Cs = themaximumpefmissibleVgamma dose rate on the side of the cask inmrem/hour for normal!jc6nd;i$ibns. \-

NA = 0.0 mrem/hour for shipments of irradiated structural materials and37.0 mrem/hour for shipments of irradiated fuel.

F = factor obtained'directly from Table 1 or Table 2 (attached).

For non-fuel whose principal isotope is not included in Table 1, an F factormust be determined based on calculated ratios of the limiting accident radiationlevels to the normal condition radiation levels for each of the principalisotopes.

For U-233 with approximately 30,000 hours of effective full power operation andgreater that 17,520 hours of decay, the F factors in Table 2 for U-235 areconservative and may be used.

The maximum measured neutron level dose rate on the side of the cask must notexceed 10.7 mrem/hour for normal conditions.

NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


5.(b) Contents


Byproduct and special nuclear material contained within inner productcontainers. The contents must be dry and unmoderated (H to X atomic ratioless than 2). £

£(2) Maximum quantity of material per package L

The fissile content of the cask must be limited to a maximum of 350equivalent grams of U-235. The number of equivalent grams of U-235 isdetermined by the equation: 1.0 x grams U-235 + 1.4 x grams U-233 + 1.6 xgrams plutonium.

(c) Transport Index for Critical ity Control '..


6. Maximum decay heat per package must not exceed 2,000 BTU/hr.

ySL7^WW2SU&J&J£USJ£USU£L2£L2&J3U£J£L3^^

rwat w at a? at at w w MK at at w ag a? at.NRCFORM618A(3-96)



9. (continued)

For mixed shipments of fuel and irradiated non-fuel, the more limiting Cs valuemust be employed.

If Cs is below the maximum measurable level of the gamma instrument, othermethods (e.g., thermal luminescent detectors, source strength calculations) mustbe employed to estimate the expected level for comparison with Cs.

10. The acceptance tests and maintenance program must be in accordance with Chapter8.0 to WAPD-RE0(C)-270, Rev. 3.

11. The packaging must be leak tested within one year prior to use to a minimumsensitivity of 1 x 10 std-cm3/sec.

12. Prior to each shipment, the.package must be leak tested after assembly to aminimum sensitivity of 1 x 10"3 std-cnr/sec.

13. The WAPD-40 shipping container may be covered with a wrapping of polyvinylchloride (PVC) during shipment provided that the internal heat load of theshipment does not exceed 2000 BTU/hr and the shipment is made in a closed truck.The applicable requirements of Condition No. 9 above must be satisfied prior towrapping. V


\ '; '"/•//'[':. REFERENCES

Safety Analysis for Radioactive Material Shipping Cask No. NRBK-40 dated December 1984(WAPD-RE0(C)-270 through R f ^ )

Naval Reactors supplements dated: July:3v 1985 (S#85-1328), Hay 6, 1987 (S#87-2721),and November 18, 1991 (S#92-02,620). '.



and Safeguards

Date

Attachments: 1. Table 12. Table 2

55

J^2K/^/^IR^2ILgL3Uiy3Eyil2?5^fl^^

Attachment toUSA/5874/B( )F Rev. 7

Isotope

Manganese-56

Cobalt-60

Iron

Energy(MeV)

0.471.812.11

1.171.33

1.095

Table 1

F Factors1 For Use in Formula Cs = (1000-NA)/F

For Irradiated Structural Material Shipments by

Principal Isotope

and

1.292

Yield(K/decay)

0.990.290.15

1.01.0

0.560.44

Factor

174

1492

1875

'The F Factor is a constant for each isotope because the energy spectrum of theemitted gamma radiation of each isotope does not change as a function of time.

56

Attachment toUSA/5874/B( )F Rev. 7

in

Table 2

F Factors For Use in Formula Cs = (1OOO-NA)/F

For Irradiated U-235 Fuel Shipments

EffectiveHours FullPowerOperation

100

500

1000

5000

10,000

15,000

20,000

25,000

30,000

40,000

50,000

720

339

338

338

332

317

310

306

302

300

295

292

1440

339

338

337

317

300

294

290

286

285

282

279

2160

330

325

318

283

271

269

268

268

267

266

265

Hours4320

219

219

219

230

242

249

254

256

257

258

259

Decav6480

200

203

206

228

243

253

257

260

263

264

264

8760

194

198

203

229

248

258

265

267

270

271

111

17.520

192

198

206

250

278

292

300

305

308

310

311

43.800

208

237

268

382

427

445

457

464

466

472

472

87.600

698

648

629

606

607

610

612

617

624

637

651

NRC FORM 618(3-96)10 CFR 71



I. a. CERTIFICATE NUMBER

5894

b. REVISION NUMBER




3

2. PREAMBLE




U.S Department of EnergyDivision of Naval ReactorsWashington, DC 20585


Safety Analysis Report for 2.7 New FuelShipping Container dated July 15, 1968,as supplemented.

c. DOCKET NUMBER 71-58944 . C O N D I T I O N S ,, -. •• ;• . .'." . - ;


5.

(a) Packaging

(1)

(2)

Model No. :^2.7 New Fuelc </

Description %§vK -. V^kr ''"'"The Model No. 2.7|j|et£xFuêl c ^ a i . n e f wa;s|c§;signed ih ?ship and store newand unirradiated ^Wlcbr'e R2^fuel mo(duie,s|Âdaptersfare used to permitadditional shi'pmen$|t*f^^ R2, aijd/SIC Type I fuelmodulesY The^gntl^lrâlsembly con^| tsôf Jtyo majfr components, aninner ,aintaini|i|j/h^^ an .outer container whichsupports the^|in4fe^c^fei%B^Ji;!i|h'fefsi;e!el g0er"container is approximately24.5 ir^tRes wvd |>|by)c24./5f^n^hesMh,i h;iand 4-28înches"::Tong. The crosssection ,6f:,the^6pt'£)f^cb|^ the /S;teel shell thickness is0.1875 fhcÂSTMÂi' 83^ G R . ^ | f ^ e ; outer s'hel 1 iS;»Xurrounded by aframeworkvb%>steel stiffen,e^â|i.dpra-il;Si' The inner container isconstructed from Type 304 t-RE.S'^l'ates, "0.1875f"inch thick and is 7.76inches squareâtid 99 inches long. Bolted closure is provided for eachcontainer. The'gross weight of the package ranges from approximately1,500 to 2,000 pounds: -.

(3) Drawing

The packaging is constructed in accordance with Westinghouse ElectricCorporation Drawing No. 924J152, Rev. 16.

i58

NRCFORM618A(3-96)



5.(b) Contents


Unirradiated fuel assemblies of the following type:

(i) S5W Core R2 standard module or corner module;

(ii) S5W Core R3 standard module or corner module;

(iii) A1W Core R2 standard cluster or half cluster;

(iv) SIC Core Type I standard cluster;

(v) SIC Core Type I fuel subassembly;

(vi) S5W Core 2 standard module or corner module;

(vii) A!W.Core~,R2 subassembly.

(2) Maximum, quantity-of material per package /

(i) One fuel assembly'as described -i&5(-b)(l)(i),. 5(b)(l)(11),or

(ii) Two fuelrassemblies as describedlih 5(b)(l)(v).

(iii) Four fuel assembl i;es as described in 5(b) (1) (vi i).

(c) Transport Index for Critical ity Control ';"-"""•

Minimum transport .index to be sHp^n.onlabel for nuclear criticality control:

(1) For the contents described in 5(b)(l)(i),

(2)

(3)

()()(), ()()(), ()()(),

and 5(b)(l)(vi), and limited in 5(B)(2)(i)and 5(b)(2)(ii):

For the contents described in 5(b)(l)(iii)and limited in 5(b)(2)(i):

For the contents described in 5(b)(1)(vii)and limited in 5(b)(2)(iii):

100

5.0

31.3


59

fWWWWWWWWWWWWWWWWJ^WWatWWWWMK

NRC FORM 618A(3-96)


£

M

£

g

8£g

sft


REFERENCES

Safety Analysis Report 2.7 New Fuel Shipping Container, WAPD-0P(R)S-2650 datedJuly 15, 1968.

Supplements: Bettis Atomic Power Laboratory letters WAPD-0P-(R)S-2800 datedSeptember 3, 1968, WAPD-OP(R)C-3425 dated August 14, 1969; and Department of Energyletters G#6291 dated July 13, 1979, and G#92-03424 dated March 20, 1992.

FOR THE U.-S, NUCLEAR REGULATORY COMMISSION

Date:

Wi 11 i am ,-D .^Travers, Di rectort-Spent Fuel^Project Office\ Off i c;e ocf Nucl ear Materi al Safety

and'ScCfe^uards /

..'' ^ '\ \

60

J£J£^^

r a? ra W wwwwatz w w aTWSEWW





5926

b. REVISION NUMBER

16


USA/5926/Bf )F

d. PAGE NUMBER

1


32. PREAMBLE




General Electric CompanyP.O. Box 460, Vallecitos RoadPleasanton, CA 94566

General Electric Company applicationdated November 19, 1987, as supplemented.


4. CONDITIONS

This certificate is conditional upon fulfilling the requirements^/10, CFR Part 71, as applicable/and the conditions specified below.

(a) Packaging •

(1) Model No.: :GE-J00

(2) Description 5P^

A steel encasedifeafd/sliielj-led shippin^fc'ask. The<;,cask is double-walledsteel circular qyji.i|der, ZQ7,^-in,cH|aîeter by 26-7/8 inch high witha central cayjjtyTtpptoximately 7?5/S~i!fe;h diameter^ By 10 inches high.Approximately'5-f/8V4fiches,-of-ji ea1J;\^#ourid,>the central cavity. Thecask is equipped,$&$%<cav'ity :<l^Mnin;#trfd' 1 i ^ " 9 device. Closureis accompli§heH;b'yâ g?ketedr#d;-,boltedrste'el lead filled plug. Foradditional shi.eTdingâdjlitunistienô,ûranium [Liners may be inserted inthe cask'cavityv?f--The1hax:i|iujnWe i ^ packaging is 4,800 pounds.

(3) Drawings 'W;/. :"i'-->l:>')iA> 'v / ,

The packaging<;is constructed in accordance with General Electric CompanyDrawing Nos. 129D4727, Rev. ,5; 129D.4729, Rev. 5; 129D4730, Rev. 4;and 129D4731, Rev." 1. l > \/> '/, *"

6 13K?K?VJSkM?WWUgJ&JSU3U£U3USL23U&JSUEJSk^^

W.raWWWWWWWWW

«

£

NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION96)


5. (b) Contents


(i) Byproduct and irradiated special nuclear material in the form offuel rods, or plates, fuel assemblies, or meeting the requirementsof special form radioactive material; or

(ii) Solid nonfissile irradiated metal hardware and reactor controlrods (blades).


Radioactive decay heat not to exceed 400 watts and 500 grams U-235equivalent mass fissile materials (Ur235 equivalent mass equals U-235mass plus 1.66 times U-233 mass plus 1.66 times Pu mass).

Plutonium jri excess of twenty (20) curies per package must be in the formof metal/:metal alloy or reactor elements,

(c) Transport Index Tor:Criticality Control . •;,'•""',':-:/

For the contents deslfri-bed' in 5v(t){l).(i):'•%''•' •''

Minimum transport iriaex^to'be sho.vyii on•' ''fyJf./>label for.Nuclearcnêality control-:';'- v?fV , ~5.6

6. Shoring shall be proîd^d, $6* minimize. imoyemfenV of; contents'during accidentconditions of transport.-if-; * '"''', :.<- ••;-,-r ''" f/'''-'"v'

1. At the time of d^tivery;JSjfot-^ carri.eryfor transport, thepackage contents sh"all be dry and/tftelpîle material unmoderated (H to X atomicratio less than 2)., ., V. \ v


(a) The package must be maintained .in, accordance with the maintenance proceduressubmitted with GE application dated January 18, 1993.

Z (b) The package must be prepared for shipment and operated in accordance withthe operating procedures submitted with GE application dated January 18, 1993.


10. Expiration date: February 28, 1998. j*

62^ ^

sgggg

g

g

ggggggggggggggg•3M

M

i

NRC FORM 618A(3-96)


I


REFERENCES

General Electric Company application dated January 18, 1993.

Supplements dated: March 3, 1993.


Date: /S

William D. Travers,/ DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

• " - " * • • ' "

63

T^T^T^T^T^WP^

NRC FORM 618(8-86)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESX CERTIFICATE NUMBER


27


USA/5939/B( )Fd. PAGE NUMBER 8. TOTAL NUMBER PAGES




a. ISSUED TO (Name end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

General Electric CompanyP.O. Box 460, Vallecitos RoadPleasanton, CA 94566

General Electric Company applicationdated November 19, 1992, as supplemented.

DOCKET NUMBER 74^-59394. CONDITIONSCONDITIONS <, %J ^<^j/ ^

This certificate is conditional upon fulfilling4h$requirements of 10 CFR Part 71, as applicable, and the, coodjtions specified below.

(a) Packaging

(1) Mo^djTNo.:

(2) Description

siell ciinches hiimg|s higf§incles^ byApproximate.., . .is equipped withaccompfMhed by a

Thjagcask is double-walledrj .-irjcfp diameter by 48 1/2tately^ inch diameter by 25

., im 30 tip inches to 17 1/27 inche|3f the cask.

the^CMtral cavity. The cask"mîg device. Closure is•itnefand # ^ g

r•*••£# j - a - ^ ^ ^ m bolted steel^1>ead-filled plug. Aprotectivyfaicket consisting of an uprwhVcircular cylinder with openbottom and 4C protruding box section dialetrically across the top andvertically downiiheîde^tta^heiô a square pallet. Dimensions ofthe protective jacke*far|îppjpQximately 60 7/8 inches high by 50 incheswide across the box section. The outer cylindrical diameter is 36 1/2inches and the pallet is 59 1/2 inches square. The maximum weight ofthe packaging is approximately 15,500 pounds.

Drawings

(i) The packaging is constructed in accordance with General ElectricCompany Drawing Nos. 129D4748, Rev. 7; 129D4749, Rev. 5: and129D4750, Rev. 9.

An optional canister insert is constructed in accordance with thefollowing Chem-Nuclear Systems, Incorporated Drawing Nos.:

C-110-D-48019-001, Rev. D; and C-110-A-48019-002, Rev. C.

64

Certificate No. 5939 - Revision No. 27 - Docket No. 71-5939

COND.T.ONS (continued) U S " N U C L E A R «EGULATORY COMMISSION

- Certificate No. 5939 - Revision No. 27 - Docket No. 71-5939

6. For the contents described in 5(b)(l)(ii): The 90SrF2 capsules must be inaccordance with Vitro Drawing Nos. H-2-66759, Rev. 0; and H-2-66758, Rev. 0. The"XsCl capsules must be in accordance with Vitro Drawing Nos. H-2-66760, Rev. 0;and H-2-66761, Rev. 0. After fabrication, the 90SrF? and

13XsCl capsules must beleak tested using a method having sufficient sensitivity to detect a leak rate of10"* atm cc/sec. Any capsule with a detectable leak may not be delivered to acarrier for transport.

7. For the contents described in 5(b)(l)(v): The 137CsCl capsules must be containedin the canister insert described in item 5(a)(3)(11), above. The CsCl capsulesmust be constructed and tested in accordance with Section 1.2.3 of the Chem-Nuclear Systems, Incorporated supplement d&ted March 1, 1993. The canisterinsert must be operated, tested*, afl m|^fatfu|djriji accordance with Chapters 7 and8 of the Chem-Nuclear SystenC IncOrporatel srappleitent dated March 1, 1993. Theshipment period must be^rol^llted within 30 days fVKfwyig the placement of thecanister lid on the caarsêr insert.

8. In addition to the^ljuirements of Subpart G of 10 CFR

(a) The packageaccordance yapplication!,^

(b) The silicortfStrubber l idi iD hipreceding ajj£h shi

gaskets m u s O e iinspection yhowsappropriate seal an

(c) The packagingâlleach shipment,\apd afby filling the eajfjccavity to

T • Mm _ _ _

ared for shipment,Package Asse

ressure to notance is indicated by

Jd, arr^fmaintained inassembly* sections of the

12-month period3e rubber lidbe replaced if

iled with»

12-mon±rrêriod precedingubble Jelpt shall be performed-inchêpth with water,

2.5 issWand holding for atno cqrftinuous generation of

reducing the cavleast 5 minutesbubbles.

*r ^ «4t "«* •9. The package authorized by this cerfTfi<Me fs hereby approved for use under the

general license provision of 10 CFR §71.12.

10. Expiration date: December 31, 1997.

66

-*^'*"*"*"*"*"*^-*"*"^ i*"*"'»"*Â^-*-v^^

NRC FORM 618A(6-83)



REFERENCES

General Electric Company application dated November 19, 1992.

Chem-Nuclear Systems, Incorporated supplement dated March 1, 1993.


WilTiamHf. Waifer*, DirectorSpent Fuel Pro^eO OfficeOffice of Nuclear Material Safety

and Safeguards f**)

Dated: Z

67

NRC FORM 618(3-96)10 CFR 71



1. a. CERTIFICATE NUMBER b. REVISION NUMBER

7


USA/5950/Bf

d. PAGE NUMBER

1


32. PREAMBLE



M

M

3aSgg

. ISSUED TO (Name and Address)

Battelle Columbus Laboratories505 King AvenueColumbus, OH 43201


Battelle Columbus Laboratories applicationdated August 21, 1981, as supplemented.

c. DOCKET NUMBER 71-59504. CONDITIONS n ' ^ <"^

This certificate is conditional upon fulfilling the requirements of 10CFR Part 71, as applicable!and the conditions specified below.

(a) Packaging

(1) Model No.:

(2) Description" v. J'

Steel Incased l e a ^ f ^ T d e d ^ j ^ ^ i n c ^ a i ^ ^ e . The package is providedwith recessed plug%t^e/iid and gaskete^10bolted closure, lifting andtie-dowfi> devices artd^elief^VaXvi, yerif#1ne, and drain linepenetrations. oGont iifmerit for theCco^tents is Drovided by an inner can

weightY4

<>\Lead*,shielding, in

(3) Drawing

Loade'd weight, 1b?'?

64^:8^

^ 6 . 1^ 8.413,200 (Incl. 270-lb skid)

The packaging is constructed in accordance with Battelle MemorialInstitute Drawing No. BCL4-01, Sheet 1 and 2, Rev. D.

The inner can assembly is constructed in accordance with BattelleMemorial Institute Drawing No. BCL4-49, Rev. C.

jgK^S^.7

68

NRCFORM618A(3-96)



5.(b) Contents


Byproduct material, source material, and special nuclear material insolid metal or oxide form, which is packaged within the inner canassembly specified in Item 5(a)(3), or which meets the requirements ofspecial form radioactive material.


Not to exceed 400 watts decay heat, and

(i) Fissile material not toyexceed 650 grams U-235 equivalent mass.

(ii) Fissile mafer.iaT not to exceed 2,0.00 grams U-235 equivalent mass.

Transport Index for^Criticality Control

Minimum transport index to be shown on ..-label for nuclear criticality control:

(c)

6.

7.

8.

For contents, described W5(B)(l)/-fcrand limited in 5(b)(2)(?f)M; •' ';?'•':

For contents described inl-and limited in --"-"•-

""> *'•'?

0.4

--•••*•-'4;* 5#* -/<'••* 100:£The U-235 equiyalent;,jffas s%mus 4be 'detre)f;iRined byf£n& foil owing method:

U-235 equjvalen^jha^/6qu'^T^lt^35Ms^x'pTus 1.75 times U-233 mass plus1.6 times Pu mass. \\ P>';;$M;.. .,"'.''• ':~:-':

At the time of delivery of the loaded package to a carrier for transport, thepackage contents must^be (1) dry (contents of inner can assembly must notdecompose up to a temperature of 750 °F) and-/the fissile material unmoderated(H to X atomic ratio less'than 2) and (2); sb limited that the dose rate willnot exceed 10 millirem per hour atthree (3) feet from the external surface ofthe package.

The maximum gross weight of the cavity contents must not exceed 180 pounds(inner can assembly, radioactive material, etc.).

ii

i

69 i

W?1^{7¥\7W7K7V{?^2BJ&JK7K7¥{23U&tt

•

The following item in the thermal acceptance tests (8.1.6) is changed asfol1ows:




(a) Each package must meet all of the acceptance and periodic tests specifiedin Section 8.0 of the application.

(4) The acceptance criteria must be that the maximum measuretemperature of any portion of the cask must not exceed thetemperatures indicated in Figure 3.3 of this application by morethan 25 °F. In this comparison, solar heating and ambienttemperature differences between Figure 3.3 and the test data mustbe taken into account. •

(b) Each package shall ..be operated and prepared for shipment in accordancewith Section 7.0 of the application.

10. The following item in the Test Procedure (8.1.3), Section 8.0 of theapplication is chancjed as follows: ^.

g. Remove pressurizatton line and insert plug;-in pressure port according tothe loading procedure. Use;Teflon tape"or other compatible sealant inthe threads. :

11. The package authorized byithis certificate's thereby approved for use under theThe package authorized byithis certificate's^hereby approved for usegeneral license proyjsions.bf 10 CFR §71; 12oKf/ ,//

12. Expiration date: August 31, 1996s.

,; H REFERENCES'- : .i :-•

Battelle Columbus Laboratories application dated August 21: 1981.

Supplement dated July 26, 1991. :


and Safeguards

Date:


d S f d

70

•

S«

sH




1, a. CERTIFICATE NUMBER

5957

b. REVISION NUMBER

24


USA/5957/B( )FA PAGE NUMBER


82. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10,

Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."



Department of EnergyWashington, D.C. 20585

Department of Energy application datedApril 18, 1995, as supplemented.


4 . C O N D I T I O N S . '- • • --•-This certificate is conditional upon fulfilling the requirements'of 10CFR Part 71, as applicable/and the conditions specified below.

H

H

H

5.

(a) Packaging

(1) Model Nd::: ..BMI-1

(2) Description - ^

A steel-encasedd-êa^shielded shippingf^sk. The basic cask body is acylinder 33.37 c^chies/in diameter\ByS7jp37 inches high formed by twoconcentric s,taihiiM^/steetr>shells whfs^rannular region is filled withlead." Theôêra/^nph thick (%e;l>|h^s;a^0.12-inch thick plate spotweldec( to W,<,;p.rov^ gap.rinsulator. The innershell is ^^'ijich/s^ns.ide'idjameter by|/;5.Canchesr;inside length. Thecaski.id is fa^statnlesg"»steeTw^ldment/having 7.7^'inches of leadshielding. tâj'jba^^-itl-^.^cuêdHi^'.the cask;by twelve steel studswhich are; welded 1tov.thej^|kô1dy'.^'fh;e- cask is\provided with a drainline with needle val'Ve %0'0$:&s pressure gaugeV and a pressure reliefvalve, the. total cask wHi:gti#' including maximum contents of 1,800 lbs,is 23,660 lbs... , . ; , ''

(3) Drawings

The cask is constructed in accordance with the following BattelleMemorial Institute (BMI) Drawing Nos.: 43-6704-0001, Rev. B; and41-4409-0003, Rev. B.

71



5. (a) Packaging (continued)

(4) Product Containers

The various authorized product containers are constructed in accordancewith the following Drawing Nos.:

(i) Inner can assembly as shown in BMI Drawing No. 00-000-421,Rev. C.

(ii) Basket Assembly as shown in BMI Drawing Nos. BCL-000-500, Rev. A;BCL-000-501, Rev. A; and 0048, Rev. A.

(iii) Fermi Fuel Element copper<casting assembly as shown in BMIDrawing,NovK5928^5d049D,'iRev/.?to May 12, 1966.

B(iv) BaslcetJAssembly as shown in BMI Drawing No. 1020, Rev. B (or with

alternate spacer shown in CI Drawing',No. 334D2193) or GA Drawing*Nj>; 9590001, Rev. A. Failed fuel assemblies must be seal welded

.; Xri' aluminum or stainless steel tubesywf,i;h\wall and end cap^thicknesses of at least 0.015 ,in'eni

(v) - .; Basket Aêmbly defiDed by ;BMfdrawing NoCBCL-000-500, Rev. A,„.. as modif^dlby;5 BMI .Drawing No;s;#uO-000-236/,

r Rev. C, and:?;, BCL-000|5l2>;êv.(BÎ )'-fg%. -•-

Carbide Corporation Drawing

( v i i i ) Basicet,Assembly as^siiown in University of Missouri ResearchReactbr' (MURR) Drawing No. 2234,"Sheets 1 through 5, Revision 0.

( ix ) HFBR assembly basket;>and"Spacer plate as shown in BrookhavenNational Laboratory Drawing Nos.: BNL 93-001, Sheets 1, 2, and3, Rev. 2, and BNL 93-002, Sheet 1 , Rev. 2.

(x) Basket assembly as shown in General Electr ic CompanyDrawing No. 183C8253, Rev. 1.

(b) Contents


(i) Intact irradiated MTR- or BRR-type fuel assemblies containing notmore than 200 grams U-235 per assembly prior to irradiation.Uranium may be enriched to a maximum 93.5 w/o in the U-235isotope. Active fuel length shall be approximately 25 inches.

72

,NBC FORM 618A(3-96)



5. (b) Contents (Continued)

(1) Type and form of material (Continued)

(ii) Intact irradiated Enrico Fermi Core. A fuel assembly containingnot more than 4.77 kgs U-235 prior to irradiation. Uranium maybe enriched to 25.6 w/o in the U-235 isotope.

(iii) Greater than Type A quantity of radioactive material which mayinclude uranium enriched in the U-235 isotope, U-233, plutonium,as metal, oxides, or compounds which are thermally stable up to600°F. Plutonium in excess of twenty (20) curies per packagemust be in the form of metal, metal alloy, or reactor elements.

(iv) Greater than, Type A quantity of byproduct material meeting therequirements of special form radioactive material.

(v) Greater than Type A quantity of byproduct material in normal formas metal, oxides, or compounds which are thermally stable up to600•VF. . . ;

(vi) . Irradiated Triga Type fuel assemblies described in Section 6.6 ofthe application (pp.. 6.-23 through 6-27).

(vii) Irradiate^. 38DR fuel elements O.v56-inch OD by 18.7 inches long byO.Olbv.iricii; wall thickness of-"Ha"stelloy-N. The fuel material isUZrH :fi|lly;6nVtched in -235.; .,./.

(viit).Intact, irradiate CP-5 fuel assemblies containing not more than176 aframs;U^23.5 per assembly^prior to irradiation. Uranium may, be enrichednto a^niaximum 93-w/q..in the U-235 isotope. Activefuel length shalrtbe-28;5 inches.

(ix) Solid nonfissile irradiated hardware.which may containencapsulated fission monitors.

(x) Irradiated uranium oxide waste enriched in the U-235 isotope upto a nominal 93 w/o which is thermally stable up to 800°F.

(xi)

(xii)

Irradiated uranium enriched in the U-235 isotope meeting therequirements of special form radioactive material.

Intact irradiated MURR fuel assemblies containing not more than775 grams of U-235 per assembly prior to irradiation. Uraniummay be enriched to a maximum 93.5 w/o in the U-235 isotope.Active fuel length shall be 24 inches.

73

sNRC FORM 6 1 8 A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)

J Page 4 - Certificate No. 5957 - Revision No. 24 - Docket No. 71-5957



(xiii) Intact irradiated MITR-II fuel assemblies containing not morethan a nominal 510 grams of U-235 per assembly prior toirradiation. Uranium may be enriched to a maximum 93.5 w/o inthe U-235 isotope. Active fuel length shall be approximately 24inches.

(xiv) Intact irradiated High Flux Beam Reactor (HFBR) fuel assembliescontaining not more than a nominal 351 grams of U-235 perassembly prior to irradiation. Uranium may be enriched to amaximum of 93.5 ;w/o in?the .U-235 isotope. Active fuel lengthshall be nominal 24!'inches. -\.n.,

(xv) Intact irradiated MTR-type fuel assemblies containing not moretljari; 240 grams U-235 per assembly prior to irradiation. Uraniummay be enriched to a maximum 93.5 w/o; ih.the U-235 isotope.

, Actiye^fuel length shall be approximately 25 inches.

(xvi)v Irradtate^MTR-type fuel se^lpfej'containing not more than 176grams U^235>;per fvue:l s.ectidn--pfis-fbr to irradiation. Uranium may

surface of-the cask and:

g ^!fp v H / $ 0 a ybe enriened^to a maximum 93v5::ig£o in the U-235 isotope. Activefuel leftj|;h|per fuel ,secti]pn|s^ll be approximately 11 inches.The ?fiteT|ascs.§mbly sfratl \be>S(eC;tlJoned only in the non-fuel beariregion); oitjêâssembly # !4s#" ^ Aregion);

bearing

(2) Maximum quafif$.ty£bf material; per^:âckag¥w-

The minimum c;obi4Qg^ti^ rod is 90 days,maximum;decay heat%ene:t

5î^R'er^pa,Qkage noijtp exceed 1.5 kw, and thet l d t t t 6 / ? ^ i 10 / h ^ f f h l

maximum;decay heat%ene :tî^Rer^pa,Qkage noijtp exceed 1.5 kw, andexternal/dose rate not t6/?excêci 10 -mrem/hr^-feet from the externalsurface o f t h e cask andf *x' ' >:

(i) For the contents described ;HK'5(b)(l)(i):

Twenty-four (24)* fifei assemblies as contained in productcontainers specified in 5(a)(4)(ii) or 12 fuel assemblies ascontained in product containers specified in 5(a)(4)(v).

(ii) For the contents described in 5(b)(1)(ii):

One (1) fuel assembly as contained in product container specifiedin 5(a)(4)(i11).

(iii) For the contents described in 5(b)(l)(iii):

480 grams U-233 or 480 grams Pu-239 or 800 grams U-235 ascontained in product container specified in 5(a)(4)(i).

74

asmas

NRCFORM618A(3-96)




(2) Maximum quantity of material per package (Continued)

(iv) For the contents described in 5(b)(1)(iv):

Gamma sources securely confined in the cask cavity to precludesecondary impacts during accident conditions of transport.Thermal heat generation rate is limited to 200 watts.

(v) For the contents described in 5(b)(l)(v):

Contained in,product; containers specified in 5(a)(4)(i) andlimited to'ÔO- thermal 'watts> ;! -

(vi) For-the contents described in 5(b)(l,).(vi):

•Thirty-eight (38) fuel assemblies as contained in product.^containers specified in 5(a)(4)(iy,),./ Fuel assemblies with an/ ^ n i trialênrichment (U-235 in U.).;af'Jg'reat.er than 70 w/o U-235 arei/.flimite^ciô'19 assemblies per**'p0Sfxzt container. Shipments of; ., less thanl:Jl?,'assembl-ies, with ,(1^235 enrichment greater than 70., w/o mayr;be':(combined";with assfembi|3es of 70 w/o U-235 or less

;', provided^ x/38 + y//19/ < rj'^ggno. assy's < 70 w/o U-235, y =

(vii'-)-' For~|be,.conti^ts descn i):

el' elements;.per can and six sealed cans perx,,., -In; 5(a-y^jf^vi). Each>of the six cans may

*cdntain' up t.Q 81^9:^^235, ami'158 g hydrogen. The cask islimited to 4.908f#snp|235. '• -''.•

(viii) For thecontents described in 5(b)(l)(viii):

Twel ve (12) •• fuei-'assembi ies\'•':•

(ix) For the contents described in 5(b)(l)(ix):

Thermal heat generation rate is limited to 200 watts.

For the contents described in 5(b)(l)(x):(x)

Twenty-four (24) containers each limited to 352 grams U-235 ascontained in product containers specified in 5(a)(4)(vii). Thedecay heat per container is limited to 20 watts. The containersmust be leak tested in accordance with Union Carbide Corporationletter dated November 17, 1980.

75 jj

'jan. an «7 w SK Mai: waBcaz w WWaTaTazag a? araTaTaTaoK a? aTai? w a£ az a* a? ataif ataca? attWatMaKWWWgtan




(2) Maximum quantity of material per package (Continued)

(xi) For the contents described in 5(b)( l ) (x i ) :

Twenty-four (24) capsules each limited to 100 grams U-235.

(x i i ) For the contents described in 5(b) ( l ) (x i i ) :

Eight (8) fuel assemblies as contained in the product containerspecified in 5(a)(4)(v i i i ) . The maximum burnup is 150MWD/Assemblyran,d: ;the;.pijvi.mum..cooling time of each fuel assemblyis 150 dayi.f>Th^ma:ximum*raiii:at-ion source term is 400,000curies.

( x i i i ) Rqr the contents described in 5(b)( l ) , (x i i i ) :

, - . „ . . . . ..(8) fuel assemblies, contaijjedîftlthe product container;JspecYfied-Jn 5(a)(4)(v i i i ) . T^maximufn4ecay heat per package

H (xiv) For the^tqnjents desbribed. fni53jp)(l)(xiv);:

Twenty ^Q^^tfel/as's'eTmSWe^ô'jâined, in two baskets separated by, ;- a spHer V|f^^â^-=-s|>eoi-^%dî^3(^)fC4,) (ix)C Each shipment must

con^Tn^twent^^^^ burnup is..approximately l30|M'wp/assjgibly,â'nd^the minimum cooling time is

(xv) ;Eo> the content^dfeM^Wed/in 5(b) (1) (M):

Twelve (12) fuel Vssimblies contain^dîn product containerspecified in 5(a)(4)(v). .^>

(xvi) For the contWjs-described in""5(b)(l)(xvi):

Forty (40) fuel sections contained in the product containerspecified in 5(a)(4)(x). When a shipment contains less than themaximum number of fuel sections (40), empty fuel section basketspaces must be provided with an aluminum or steel spacer in theform of an open-ended pipe with a minimum outer diameter of 2.5inches and a minimum wall thickness of 0.125 inches. The spacermust be of sufficient length to replace the absent fuel sections.

21 ,

jitfir

NRC FORM 618A(3-96)




Minimum transport index to be shown on labelfor nuclear criticality control:

(1) For the contents described in 5(b)(l)(iii) and5(b)(l)(xv), and limited in 5(b)(2)(iii) and5(b)(2)(xv):

(2) For the contents described in 5(b)(l)(i), 5(b)(l)(ii),5(b)(l)(i) 5(b)(l)(ii) 5(b)(l)(iii) 5(b)(l)()

9.

10.

11.

0.4

( ) ( ) ( ) ( ) ) ( ) ( )5(b)(l)(xiv), and 5(b)(l)(xvi), and limited in5(b)(2)(i) 5(b)t2)(ii)5(b)(2)(i) 5(b)(2)(()()(),()()() ()()() ()(

5(b)(2)(xiii), 5(b)(2)(xiv), and 5(b)(2)(xvi): 100

For Item 5(b)(l)(iii), mixtures of fissile material are authorized, providedthe following equation is satisfied:

< 1, where-480 480. 800

X = Grams U-233;^t4wbe; shippedY = Grams Pu-23jlKto ,be shipped1 =•; Grams UT235 to "bj^shipped

• • • ; ' ; / ! ''•?'"?/'"'.'• • • ; " • ' • / \ - > ) . . /

Except for the cpntMts described in S(b)(l)'/Ciij-, 5(b)(l)(iv) and5(b)(l)(xii); andvlirti*ed,i;n 5(b)(2)(ii), 5{b,)(2)(iv) "and 5(b)(2)cask must be. shipped dry^

they

If the cask contents ofl5(b|p(it),^5{b)(l)(iv) <pr 5(b)(l)(xii) are shippedwet, the licensee, must confirm tftat the pressure relief valve is operable(set pressure - 75;psig). When needed, sufficient antifreeze in the caskmust be used to prevent^damage of any component of the package by freezing.

Loading and unloading oper.atioHs.of the contents described in 5(b)(l)(iii)and limited in 5(b)(2)(iii) must preclude contact of water with the contents.

When the contents of 5(b)(l)(vi) are loaded wet, the optional 0.5-inchdiameter drain hole must be present in the primary basket lower plate toassure proper draining of the basket.

The presence and effectiveness of the Bora! poison plate in the BasketAssemblies as shown in BMI Drawing Nos. BCL-000-500, Rev, A; 0048, Rev. A;and 00-000-236, Rev. C, must be verified by neutron measurements prior tofirst use and records maintained of such verification. Verification of thepresence of the Boral must be made in each subsequent use.

77



^ 12. Contents 5(b)(1)(i) and 5(b)(l)(x) may be mixed provided the sum of the~ product containers and fuel assemblies does not exceed 24.

13. Axial movement of fuel assemblies must be limited so that the active fuelregion will remain correctly positioned with respect to the poisoned sectionof the basket. Removable spacers may be used in each section of the basketto limit axial movement of the assemblies.

14. Contents must be securely confined in the cask cavity to minimize movement.

15. Prior to each use, adequacy of containment vessel must be demonstrated byperformance of the leak test described in Section 7.1.1.1 of the application.

16. Gaskets and seals (cask and fuel canister) must be replaced at least every 12months or earlier if visible degradation occurs.

17. For contents described in 5(b)(l)(iii) and limited in 5(b)(2)(iii), the massof fissile material contained in reactor fuel must.be based on the mass priorto irradiation. . ,.

18. In addition to the;requirements of Subpart-G;;pf 10 CFR Part 71:

(a) The package shal\l\jbe prepared .for- sh/pment and operated in accordancewith the Operating: Procedures /of Chafpt|| 7 of the-" application.

(b) The packaging mustt.meet the Accept.aftc^>Tests, and Maintenance Program ofChapter 8-.of" the^ application * >~T^-T ;/./-

19. The package authorized, by]Shis certificate fefiereby approved for use underthe general liceHsefpYwiîb^sôî'O^'ER^fyl.^. . /.'--•

n'ration d a t e ! Ma'rr.h 31.. PQhi.C'Ai^.-, < , •"<-•20. Expiration date: March 31, ;20i?l>; i ::. ,;

. > - ' • • ' ~ ' ' x ; / - '

REFERENCES :>

Department of Energy applicat4on;,<i,ated:- ApMl 18, 1995.

Department of Energy supplement dated: November 20, 1995.


s Date: 4William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

78

NRC FORM 618

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.B.CERTIFI IBER b. REVISION NUMBER c.PACKAG!E IDENTIFICATION NU

lJSA/5979/B(MBER

)d. PAGE NUMBER e. TOTAL NUMBER PAGES

'REAMBLEa. This certificate is Issued to certify that the packaging_and contents described in Item 5 below, meets theapplicable safety standards set forth inTitie 10. Code




Alpha-Omega Services, Inc.9156 Rose StreetBell flower, CA 90706

Alpha-Omega Services, Inc. applicationdated June 1980, as supplemented.

* c. DOCKET NUMBER1,F5979

4. CONDITIONS ^ \^> ^ 7 <xThis certificate is conditional upon fulfilllngdthe-jrequirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging e , <&^ <?Q

(1) M o d ^ o . : 5979^v ,--#^" /U

(2) Despription

A Ssh-ipping/fc^nta^6grNfi(n^t%Wther'aDviGo'balt sources. Configurationj ' appr^imately 38" x 50"*J • i i l -, 0.125" outer

Transverseus&fo'f a forik^lift and l i f t ing

lugsVa*=e pro^m^meMmfmm^^s. Thg>fnner shield vesselis essentially a 24" o^|f#efv>Oead5f/i1led, barrel-shapedconfigW^ion. Three*™jfeftep^ c^n'drical <£fug inserts and boltedend capsqirovide f 1 eximloxyHo accommodatip^slveral sizes and shapesof sources^yGross weight is approximate.1 r5,000 lbs.

strips-lugs^r-e

(3) Drawings

te;}

The packaging is constructed in accordance with Alpha-OmegaServices, Inc. Drawing Nos.: 0090, Rev. 0; 0091, Rev. 0;0092, Rev. 1; and 0093, Rev. 0.

79

A^ftg^re^fS^K'ra^^afrft^^

I

t

t

t

{

't

t

i

i

t

ci

*iii

'f'I

iiit

t

ii

NRC FORM 618A(6-83)

i

i

t




5. (b) Contents


Cobalt 60 or cesium 137 as sealed sources which meet therequirements of special form radioactive material.


13,000 curies Co-60 or 3,000 curies Cs-137, with decay heatload not to exceed 200 watts.

6.

7.

8.

Lifting eyes shall be coy£attachments. C

The shield vesj

to prevent use as tie-down

osures shall be equipped wTyr*gaskets.

hall be securedBolts used t|p§ecure the shield vessel closure cap1against loosetringby vibration during transpor

9. In addition Tto

a) Each^package msupplement dat

b) The!*packaOpening

10. The packaqe^uthunder the general

11. Expiration

Alpha-Omega Services, Inc.

ements of Subp

tne^Jaintet 2a. 1990:

10 CFRJgart 71:

spection/Pfcogram of the

ice with the20, 1990.

roved for use

1980.

Supplement dated: April 12, 1983, May 22 and August 20, 1990, and January 30,and November 16, 1995.


Date

William D. Travers,'DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand Safeguards

80

M^ £





5984

b. REVISION NUMBER

6


USA/5984/B( )<L PAGE NUMBER


2. PREAMBLE




J. L. Shepherd and Associates1010 Arroyo AvenueSan Fernando, CA 91340-8095


J. L. Shepherd and Associates applicationdated September 12, 1974, as supplemented.

c. DOCKET NUMBER 7 1 ~ 5 9 8 4

4. CONDITIONS _ .This certificate is conditional upon fulfilling the requirements'of 10;GFR Part 71, "as applicable, and the conditions specified below.

5.

(a) Packaging

(1)

(2)

Model No.: 5984^

Description ^

A protective overplpjgiihich ^ ^ i d e s M j n p a ^ resistance, and thermal

fitting.steeloverpatkare app'roximi^ high, and the plywood

(3)

The overpack is;^c6nstructed in accordance with J. L. Shepherd andAssociates Drawirig Nosf. A-0068-2C-1 dated March 8, 1969; and A-0068-2Cdated April 26, 1995. v" ;;: . , - \ r ' V

The inner shielded containers are constructed in accordance with J. L.Shepherd and Associates Drawing Nos. A-0068-1B, Rev. 2, or A-0068-1B-B,dated April 26, 1995, or A-0068-1B-A, dated April 26, 1995 . The specialform source capsule is constructed in accordance with 0. L. Shepherd andAssociates Drawing No. A-0068-10 dated January 30, 1969.

(b) Contents


Cesium 137 as cesium chloride sources doubly encapsulated in stainlesssteel tubes which meet the requirements of special form radioactivemateri al.


12,000 curies.

81

NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


6. Use of packaging fabricated after August 31, 1986, is not authorized.


a. The package shall be prepared for shipment and operated in accordancewith "Inspection Operation, Handling and Maintenance Procedures" in theJ. L. Shepherd and Associates submittal dated Hay 1, 1995.

b. The package must meet the "Acceptance Tests" and "Checkout andMaintenance Procedures" in the J. L. Shepherd and Associates submittaldated February 20, 1990.


9. Expiration date: April 3b£.,200i. ^ ;•/;

-. - REFERENCES

0. L. Shepherd and Associates' application dated September 12-, 1974.

Supplements dated: January>20; 4 9 7 5? February 20, 1990? February 6, and May 1, 1995;and April 11, 1996. t > v ~ \ .. : L ^

'FOR THEiJgSi NUCLEAR REGULATORY COMMISSION

f-;^;'. i-" jWilltam D./TJ*avers, Director?>'" • x .^Spentvfuel project: O.f f ice

Date:

Sv;;/';^:>|rid-SafeguardsofvNuclear^JMaterial Safetyf d '<'

82

7¥J¥J¥JSJSJSU^7¥J¥^^7^7^7^7^7^2^7^'^7^,7l^\7f\7W\

^NRC FORM 618(3-S6)10CFR71




6003

b. REVISION NUMBER

17




62. PREAMBLE






Safety Analysis Report for M-130 shippingcontainer dated December 30, 1968, assupplemented.


4. CONDITIONSThis certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No.: M-130

(2) Description ,/ ? ^ ;

The Model No. M-I3jl^sjppping container,j;s|an upright cylinder 84 inches indiameter by 158 injcfief overall"height, '^ne container,walls consist of afinned 1-inch thi.cK^pute^ either carbon steel,carbon steel y\%%sta^tHss steel clady,# solid stainless steel, 10inches of lead^(ri.eld-ingâhd:ajlîfjGh?:th'ic;l<:jnrier pressure vesselfabricated from carbonI'sieellclad;with'stainless steel. The top of thecontainer, is coVpred}^withta:shie;1de^ closure Head which is bolted to thecontainer and seaisîh&ptessuie Vessel-/? An access opening with a boltedshield plug ,is provided in^hefcjlbsure head for loading and unloadingspent fuelv /, '' V-;/MV'\',.^ ''•'''

The pressure vessel has an inside diameter of: 55 inches. The centralregion contains a secondary heat exchanger (not used during shipment)surrounded by 1/2-inc^thick carbon steel backup cylinder 29 inches indiameter. The annulus which remains between the backup cylinder and thepressure vessel provides a space 13-inches wide and 130-inches high forspent fuel. The spent fuel is contained in the annulus by module holdersdesigned for the particular core to be shipped.

The container has external penetrations to the pressure vessel for steamand water relief lines and a fill and drain line (which are capped duringshipment) and a pressure sensing line which remains open to a pressuregage during shipment. The container also has penetrations which do notopen to the pressure vessel for secondary heat exchanger lines (which arecapped during shipment) and a temperature sensing line.

The container is supported on its transport vehicle by an "A" framestructure. Gross weight of the loaded container without its supportstructure is approximately 228,000 pounds.

83

a33 (b) Contentsa




5.(a) Continued

(3) Drawings

The packaging is constructed in accordance with General ElectricDrawing Nos. 247E209, Sheet 1, Rev. R; Sheet 2, Rev. K; Sheet 3, Rev. T;Sheet 4, Rev. U; Sheet 5 of 5, Rev. F, and 247E228, Rev. F.

(x) S3G-3/3A irradi'ated thermocouples;and' thermocouple cases.

C

Irradiated fuel assemblies, activated corrosion products and structuralparts containing up to 40 gallons of residual contaminated water. Thefuel assemblies and structural parts are of the following types:

(i) S3W/S4W fuel subassemblies of core type 2.

(ii) S5W fuel modules of core types 2 of,3.

( i i i ) -S5WLcorner fuel modules of cor.e types 2 or 3.

(iv) DIG fUeT.modules of core types^Jlfor 2. "'"'

(v) DIG reiiqyjble fuel a'ssembli^sf^f core typ.ls 1 or 2.

(vi) Sie/S26|puel modules withJonfrol rods. '•

(vi i ) .: SI|/|!2C "peki;pher.al! (i'etfrtoftii s$h//<{- I- .

[viii) S3G^^!AVue^t^pjdi(i^'wHh.tor...without control rods.

( ix) "•"''

(xi) S8G tull size fuel cell with,-or without control rod.

(xii) S8G partial size fuel cell with or without control rod.

(xiii) S5W-4A recoverable irradiated fuel modules with control rod.

(xiv) S7G recoverable irradiated fuel cells,

(xv) D2W fuel cells with control rods,

(xvi) NR-1 fuel modules with or without control rods,

(xvii) ATC fuel modules with or without control rods.

(xviii) A1W-3 recoverable irradiated fuel modules. Fuel modules thatuse control rods shall have control rods inserted.

at*:i iiCm ax JK m TK as as as as a* BK TK aj; a* as as as as TK as as as as as as m as as m as as as as ax m a * ax as m at as as an asm at

'.ymLiti yMLytiaiitC ytLymi iwC a t l t t :

3

i

NRC FORM 618A(3-96)

Page 3 -

5.(b)(2)



Maximum quantity of material per package.

(i) 52 fuel assemblies as described in 5(b)(l)(i).

(ii)

(iii)

(iv)

(v)

(vi)

(vii)

(viii)

(ix)

(x),

(xi)

(xii)

(xiii)

(xiv)

12 fuel assemblies as described in 5(b)(l)(ii) or 9 fuelassemblies as described in 5(b)(l)(ii) and 4 fuel assembliesas described in 5(b)(l)(iii).

6 fuel assemblies as described in 5(b)(l)(iv) and 4 fuelassemblies as described in 5(b)(l)(v).

9 fuel assemblies as described in 5(b)(l)(vi) and 8 fuelassemblies as described in 5(b)(l)(vii).

10 fuel assemblies as described in 5(b)(l)(viii).

9 fuel assemblies as described in 5(b)(l)(viii) and 1 fuelassembly as described in 5(b)(l)(nx).

9 fuel assemblies as described in 5(b)(l)(viii) and 1structure as described in 5(b)(l)(x).,

4 fuel'eelIs as described in,£(b^(l)(xi) or 2 fuel cells asdescribed>. ih 5(b)-(i) (xi) /andX2k¥uel eel Is as described in5(b)(i;)D(xHK -Vf-\ ;p£> ••'•;6 fueitasserilbTies as describe^ in 5(b)(l)(xii i) .

8*;fuefl, c e f l ^ s described? jh 50)4$) (xiv).

4 fuel eell.s/^.s described in.5(b)r(l)(xv) .plus 2 corner fuel

^4/fuel modules'xa#iieseribed in 5(b)(l)(xvi).'{?:•'... '-''•.v/%.f^" ' \ --. -

10.-fuel modules as described in,.5;(b)(l)(xvii).

for contents described in ;5(b)(l)(xviii), 6 fuel modules or 8fuel modules^ as described in supplement dated March 30, 1992.

(3) Shipments shall be further limited by thermal requirements as follows:

(i)

(ii)

Shipment of contents specified in 5(b)(l)(iv) and 5(b)(l)(v)and limited in 5(b)(2)(iii) shall be made no earlier than 75days after shutdown and shall have a decay heat load not toexceed 33,500 Btu/hr per shipment.

Shipment of contents specified in 5(b)(1)(vi) and 5(b)(1)(vii)and limited in 5(b)(2)(iv) shall be made in a stainless steelM-130 container and shall have a decay heat load not to exceed18,960 Btu/hr per shipment.

85\J^^^JJ^J^J]^JJ^^]^^J^JT^J^^

NRCFORM618A(3-96)



5.(b)(3) Continued

(iii)

(iv)

(v)

(vi)

(vii)

(viii)

(ix)

(x)

(xi)

Shipment of contents specified in 5(b)(l)(viii), 5(b)(l)(ix),and 5(b)(l)(x) and limited in 5(b)(2)(v), 5(b)(2)(vi), and5(b)(2)(vii) shall be made at a time after shutdown, asdetermined from Bettis Atomic Power Laboratory report WAPD-0P(PP)S-4401 dated June 29, 1979, and shall have a decay heatload not to exceed 28,620 Btu/hr for the shipboard core and30,000 Btu/hr for the prototype core.

Shipment of contents specified in 5(b)(l)(i) and 5(b)(l)(ii)shall be made no earlier than 72 days after shutdown and shallhave a decay heat load not to exceed 33,500 Btu/hr pershipment.

Shipment of,conterttSispecified in 5(b)(l)(xi) or 5(b)(l)(xii),as 1 limited 'by 5(b)(2)(vii),:shall have a fully loadedcontainer heat load not to exceed 15,400 Btu/hr per shipment.

^Shipment of contents specified in 5(b)(l)(xiii) and limited in5(.b.X(2)(ix) shall have a heat loacLnotfto exceed 23,800 Btu/hrand shay be made no earlier th.a*n;92 days after shutdown.

|pShipnie|p%f contents^speciffed%"n 5(b)(l)(xiv) and limited in5(b)(2)^x|,shairh;ave; a 'heajjjo.ad not to exceed 22,400 Btu/hrand shfrlHbe made no'eariiefgthan 122 days after shutdown.

Shipmerit^f^contents spe;cifêcl ijn/5(b)(I)<xv) and limited in5 $ } $ ) Q ^ ^ h a l l JhaVe ajhât 1/fadVnot to exceed 19,100 Btu/hrand sh.a11. be^mide inoVeafTier thah:420 days after shutdown.

Shipm&vjUciif conteintii^pecitfi'ediin 5(b)'(;l))(xvi) and limited in5(b)('Z)(xii) sj)|>l!>|iê a, heat* load npf to exceed 6,000 Btu/hrand shall be madefnbvearTier^than 50-days after shutdown.

Shipment of contents specified<in,5(b)(l)(xvii) and limited in5(b)(2)(xi i i ) shall have a heat load not to exceed 27,400Btu/hr and'shallvbe.made no-earlier than 195 days aftershutdown. 'y-\

Shipment of contents specified in 5(b)(1)(xviii) and limitedin 5(b)(2)(xiv) shall have a heat load not to exceed 43,800BTU/hr and shall be made no earlier than 400 days or 175 daysfor A1W-3E and A1W-3J fuel, after shutdown.



Except for the contents described in5(b)(l)(viii) and limited in 5(b)(2)(v)

For the contents described in 5(b)(l)(viii)and limited in 5(b)(2)(v)

86

100

50



6. For shipments involving the contents specified in 5(b)(l)(ii) or 5(b)(l)(iii),the Model No. M-130 package shall be inspected to verify that boron poison

S plates are in the module holders.

7. For shipments involving the contents specified in 5(b)(l)(viii), 5(b)(l)(ix), or5(b)(l)(x), the thermocouples and thermocouple cases if included or the vacantmodule holder shall be located in the mid-position of either cage and moduleholder assembly.

8. Shipments shall be made in the dry condition, except for residual water aslimited in 5(b)(l).

9. Container number three (M-130-3) has been modified by adding two 4-inch thick by8-inch wide steel plates welded between fins 25 and 50 and between fins 110 and135 at approximately 14.75 inches from the.bottom of the container. The coolingfins in this localized area.are removed to permit attachment of the platedirectly to the outer shelli of the container.

10. Container number four (M-130-4) has been modified by adding a 2-inch thick by 4-inch wide steel plate welded between fins 32 and 49 at approximately 18.4 inchesfrom the bottom,of the container. The cooling fins in this localized area areremoved to permit attachment of the plate directly-to the outer shell of thecontainer. 5 \" , •

11. Containers M-130-3, M-13jD§4l -JH136-6>and M-13o|j. may be used for the contents ^, v > > ^ yspecified in' 5(b)(l)(v1i$) sind 5(b)(l)(x) bniy.§;,ContainersM-130-10 and M-13015 may be used for the.cbrit.ents specified i n 5 ( f O ( l ) ( v i i i ) , 5(b)( l ) (x) , and5 ( b ) ( l ) ( 1 i i ) ' l j y •'%'* Vf

12. Container M-130-11 mayte^.used for NR-1 shipments%ily.

13. For shipments involving;the-contents specified/in 5(b)(l}(xvii) which do notcontain a full complement of \fueX;mq<iules (i.e.; one position is occupied byeither two flux thimbles or a va'ejjtnjf.fpel* module holder with pocket shieldplug), that position .shall be located'in the middle module holder of either halfof the cage assembly.. .

14. Expiration date: December 31,<1997.

87

!



REFERENCES

Safety analysis report for M-130 shipping container, MA0-E8-703 dated December 30,1968.

Supplements: Naval Reactors letters A#2256 dated February 24, and G#1931 datedMarch 3, 1969; General Electric Company letter ONP-74520-526 dated April 3, 1972;Naval Reactors letter G#3207 dated April 27, 1972; General Electric Company letter0NP-74520-528 dated April 28, 1972; Naval Reactors letter G#3250 dated June 6, 1972;General Electric Company letters ONP-74570-635 dated October 25, 0NP-74570-654 datedDecember 4, and 0NP-14570-666 dated December 12, 1972; 0NP-74570-682 dated January 12,0NP-74570-698 dated January 31, 0NP-74570-687 dated February 6, ONP-74390-65 datedMarch 26, and DLGN-85570-854 dated September 24, 1973; and DLGN-85570-901 datedJanuary 10, 1974; Naval Reactors letter G#4061 dated January 29, 1974; General

DLGN-85570-923 datedElectric Company letters DLGN-85570-924 dated February 15,March 6, and DLGN-85570-969 dated\May-24, ;i974>4Naval Reactors letter G#4991 datedNovember 25, 1975; General El^ctirc Company 1 etteVs-Of|P-74340-JTT-73 datedDecember 17, 1975; CGN-8557Q-A145 dated September 9, CGN^85570-1146 datedSeptember 10, and CGN-855;7(H148 dated September 14, 1976;/Bettis Atomic PowerLaboratory letters WAPDr;R(K)-1378 dated August 30, 1976, antf ,WAPD-OP(PP)S-4401 datedJune 29, 1979; Naval Revactprs letters G#6197 dated July 13 '1979, G#7022 datedJuly 14, WAPD-LP-(CES)SE-1K7O; daited July 1981; and WAPQ-LD^(CESySE-181 dated September1981; WAPD-LP(CES)SEv96 date^F/eb>uary 1982, G#7136^ate;<i> March 17, 1982; G#7160 datedM y 18 1982 G#7582; d t d S ^ S b K 7 > 9 8 3 G#C8^56J|f d t d S t b 2 d

1; WAPLP(CES)SE96 date^F/eb>uary 1982, G#7136^ate;<i March 17, 1982; G#716May 18, 1982; G#7582; dated Se^SgbeK 7, >9,83jx G#C8^56J|f dated September 2, andG#C875689 d t d S t b 2 3 f p | 7 1G#CB748OO8 fdtlfl 19i'G#C885931 dG#C87-5689 dated September 23,<J$JS87; ;G#C'87~8008 ;daredJ3.anuary 19i'G#C88-5931 datedMay 12, and G#C88-5961 dated $$$&&, 1908; G"#C89-£g25fdated MarcW 29, and G#C89-2863dated August 11, 1989; G#C92-0W9^dated;W#eh,30/^11?G#9^-0372?;dated October 20,1992; and G#C93-10935 " ^ '

t(JEj)j;J^MjCLEJAF^5EGULAIpRY COMMISSION

Will ram*D. Travers, pirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and/Safeguards^

Date

? 4

88tys7K2£UW7W7fUSUiU£L7K7K7f{ffiTKm;





13


USA/6058/B( )F

d. PAGE NUMBER

1


42. PREAMBLE


b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OFTHE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Department of EnergyWashington, DC 20585

Cintichem, Inc., application datedMarch 31, 1985, as supplemented.

c. DOCKET NUMBER 7 J - 6 0 5 8

-(.CONDITIONS f •;•.: '. ' ' . . ' , . - >This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable/and the conditions specified below.

5.

(a) Packaging

(1)

(2)

Model No.:, B-3^

Description£ • • • < ^ V ^ T * - ' - ^ v 1 - ' -i <M%% <-, •:

The packaging cons3;stssb# a lsead shielded!steel weldment in the shape ofa right hollow tcyl^deJrs«ith,^l?anomUnd^recessed'r-plug type gasketedand bolted lidf\ Th1pp%k>gTng^"pfovii.aeâjininiinum of.'-jPinches of leadshielding. Pifclcagi^^lîfesînc^^pftjjlig/^nd tie-down devices and a

• j ^ - . ^ i i w M n - r d u ; ^ ^ ^ w ^ { t of the loaded packagingdrain to'the cei s 30,00P"-poun'd55;f?f-$?

'yr^yjiThe outeriishelldiameter and 57 inches^hig1/2-inch and 174-inch in

1 IP

|feVl^^fstructibtând is 41 inches in

|wo^lam^nates ir;§ of plate material174inch in ttf$kn)#^ Theînne^shen is of 1/2-inch thick

steel plate.^Tne internal cavity dimensions-saW 26-1/2 inches indiameter and 43-174 inches high. The lid isfof the same construction asthe sides and bottomVand is secured to/the body of the packaging bytwelve, 1-1/4-inch diametef"by', 2-inch long high strength bolts and sealedwith a silicone 0-ring.

(3) Drawing

The packaging is as described and constructed in accordance withCintichem, Inc. Drawing No. 330E2053E, Revision E.

897&,7W{7&7W{7&7W{7W7W{W7$SJ£U£J!iU£J£3£^

NRCFORM618A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)


g (b) Contents


(i) Byproduct and uranium enriched in the U-235 isotope, U-233 orPlutonium as solids, non-powder, and dry, which will not decomposeat temperatures up to 525*F and packaged within DOT Specification17H steel drums.

(ii) Byproduct and uranium enriched in the U-235 isotope, U-233 orPlutonium which meets the requirements of special form radioactivemateri al.

(iii) Byproduct material and uranium enriched in the U-235 isotope,U-233, or piutpntum as solids,; non-powder, and dry which will notdecompose at temperatures' tip to 525/F, packaged within a nominal1/2-inch thick "(24-inch OD) polyethylene High Intergity Container(HIC)., Liquids must be solidified in Chemtree Iron Oxide mix in astee_K£o'ntainer. Small items, including^glassware, must be placedin l-'gal steel containers and compressed (as required).

(2) Maximum quantity>,of/material per package ,"

For the contents ^spîbed in. 5(b)(l)(j)jand 5(b)(l)('ii):

For the -contents;! desor/lbed in,:

sST Not to'exceed 400 maftsi thermal decaV.r-.*i-S ••• '•' ^•'•''-• - - ' - "• ' "

H

B "î" •-.xiif:/*, ('i?ti..'si

g

B

The HIC must beclim;ited. tp;200 Aj qiiantit.ies-of solidified liquidradioactive matdâ;Tôd^'°^;mPre/^^tr-^P-:^2 quantities of other•—"—J--:/- *•-''•"'^'-'tx Th,6Ma||mum thermal decay heat load must notradioactive materialexceed 15' watts.

For the fissile-^contents described in 5(b)(l)(i), 5(b)(l)(ii), and5(b)(l)(iii) not'to exceed the following: "

Fissile "Maximum.per 'Materi al Package (grams)

U-235 350U-233 200Plutonium* 200

or, pro-rated mixtures such that the sum of the ratios of the quantityof each fissile material to its maximum per packaging does not exceedunity.

*Plutonium in excess of 20 curies per package must be in the form ofreactor fuel, fuel elements, metal, or metal alloy.

90

WWWWWW3rawwwwwwm5gwwra.3K:gi:wwww

NRCFORM618A(3-96)

7.

8.

9.

10.

11.

12.




For contents containing special nuclear material:

Minimum transport index to be shownon label for nuclear criticality control: 10.0

For gamma-emitting special form materials, at least 5 inches of additional leadshielding may be added as required as a lining on all sides within the internalcavity.

The total weight of the contents including additional lead shielding as may berequired shall not exceed 9,000 pounds.

Prior to each shipment, the lid 0-ring sh'al]; be inspected. The 0-ring shall bereplaced with a new 0-ring^}if inspection shows any defects or every twelve (12)months, whichever occurs first. ---;' .

Prior to the shipment of contents described in 5.(b)(lHi), the package must beleak tested as specified in Section I of the application.

In addition to the requirements of Subpart 6 ofslp CFR Part 71:

(a) Each package shali|be.;maintained in accordance with Section I of theapplication, as supplemented.;' and :V#~

(b) Each package, sh^all.be operated and. prepared for shipment in accordancewith Section I jo'f tha^Bpplication,.;^isuppl-iemented.

Fabrication of addit;ional.^packaugi"9$; is not authorized.

The package authorizedi/by -this c§p£tf^G.ateJs hereby approved for use underthe general licensee provisions W/jip\'CFR-§7k 12.


9 1

^

CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONNRC FORM 618A(3-96)


REFERENCES

Cintichem, Inc. application dated March 31, 1985.

Supplements dated: August 30 and October 31, 1985, and October 2 andNovember 27, 1990.

Department of Energy supplements dated July 15 and December 21,-1992, andNovember 20, 1995.


Date:

, William D. Traver'sv-.Director. v-'Spent Fuel Project Office; -

Office of Nuclear Material-Safetyand Safeguards .-'- /

sr 0'

92

rwww wwwwwwwwwwwwwwww: rmNRC FORM 618(3-96)10CFR71




6078

b. REVISION NUMBER

22




3

2. PREAMBLE




Combustion Engineering, Inc.2000 Day Hill RoadWindsor, CT 06095-0500

Combustion Engineering, Inc. applicationdated July 9, 1996.

c. DOCKET NUMBER 71-60784, CONDITIONS


5.

(a) Packaging

(1) Model Nos.:\- 927A1 and 927C1

(2) Description <?-:.->•. '>'"'V

A steel fuel bundlesshipping•rcbrrt'airrerJctf^sisting of a strongback andfuel bundle clampanj;:assembl^;' stiockjmolded to a steel outer container.The fuel bundles ^-.;êpara.te'd''-byu3/'l,6.f'|0i1ck, high\carbon steelsegmented separ^tor?bjx»jcl« permanenily^tached.' to the strongback. Thesegmented separa tor ' 'b |b ;p5;^ (welded) insegment's to fp.m^conf4-n'6pusjBloc)Stfdr thef'ejrtire âctive length of thefuel assembly.;"| He' ode;l>iNov1§27A;^-VRackage-/'t's approximately 43" indiameter/,by 189~"; Joilg'wiifi an.apprb)<lmate jgross weight of 6,700 lbs . TheModel No. 9.27C1 package iâpjirpx^mateTy^S11 in.diameter by 216" longwith an approximate gross^'eight.of 7,300 lbs . <

(3) Drawing •//» , -

The Model Nos. 927AI"and 927C1 containers are constructed in accordancewith Combustion Engineering, Inc. Drawing No. E-5022-8051, Sheets 1through 4, Rev. 0.

(b) Contents


(i) Model No. 927A1: unirradiated fuel bundles consisting of 0.38"diameter uranium dioxide fuel pellets clad in 0.028" thick zircaloytubes in a 14 x 14 square array with a 0.58" pitch. Each fuelbundle consists of a maximum of 176 fuel rods with a maximum 5.0w/o enrichment in the U-235 isotope, and contains not more than19.6 kg U-235.

93

wNRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


5.(b) (1) Contents (Continued)

(ii) Model No. 927A1: unirradiated fuel bundles consisting of 0.381"diameter uranium dioxide fuel pellets clad in 0.026" thick zircaloytubes in a 14 x 14 square array with a 0.58" pitch. Each fuelbundle consists of a maximum of 176 fuel rods with a maximum 4.76w/o enrichment in the U-235 isotope, and contains not more than19.6 kg U-235.

(iii) Model No. 927A1: unirradiated fuel bundles consisting of 0.33"diameter uranium dioxide fuel pellets clad in 0.025" thick zircaloytubes in a 16 x 16 square array with a 0.506" pitch. Each fuelbundle consists of a maximum of 236 fuel rods with a maximum 5.0w/o enrichment in the U-235 isotope, and contains not more than20.76 kg U-235.

(iv) Model No. 927A1: unirradiated fuel bundles consisting of 0.31"diameter uranium dioxide fuel pellets clad in 0.024" thick zircaloytubes.in a 16 x 16 square array with a 0.472" pitch. Each fuelbundle consists of a maximum of 231 fuel rods with a maximum 5.0w/o.enrichment in the U-235 isotope, and contains not more than11.68 kg U-235.

(v) Model No. 927CJV unirradiated fuel? bundles consisting of 0.33"diameter urift|iifi dioxide pellets "clad in 0.025" thick zircaloytubes in .a 16J£c>16; square'array;wi£h a 0.506" pitch. Each fuelbundle\cofeists^of/.a maximum of 2?_6 fuel-rods with a maximum 5.0w/b enrichment '-fri^the U-i-235 isotope, *<and contains not more than22.77 WXXAii«* "'

(vi) Model No. "S2 Ci:f'"''--tuhtrrad-lated--fAiie1 -bundles consisting of 0.324"diameter uranium di.p i'ide-'ifuiel pellets clad in 0.0235" thickzircalpy tubes in a W/x; 1%square array "with a 0.501" pitch. Eachfuel bundle consists of 264 fuel rods with a maximum 3.6 w/oenrichment in the U-235 isotope, and contains not more than 16.43kg U-235.


Model No. 927A1: Two fuel bundles weighing not more than 1400 lbs. each.

Model No. 927C1: Two fuel bundles weighing not more than 1506 lbs. each,



Each fuel assembly shall be unsheathed or shall be enclosed in an unsealed,polyethylene sheath which will not extend beyond the ends of the fuel assembly.The ends of the sheath shall not be folded or taped in any manner that wouldprevent flow of liquids into or out of the sheathed fuel assembly.

94I^

NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONf. (3-96)

5Page 3 - Certificate No. 6078 - Revision No. 22 - Docket No. 71-6078


(a) The package shall be prepared for shipment and operated in accordancewith the Operating Procedures of Chapter 7 of the application, assupplemented.

(b) The packaging must be maintained in accordance with the MaintenanceProgram of Chapter 8 of the application, as supplemented.

8. Fabrication of additional packagings is not authorized.

9. The package authorized by this certificate is hereby approved for useunder the general license provisions of 10 CFR §71.12.


REFERENCES

Combustion Engineering, Inc. application dated July 9, 1996.

FOR THE U.S, NUCLEAR REGULATORY COMMISSION

Date:

i am D. Tfavers •, Di reelSpent: FueT^Project Office

'/Office of Nuclear Material Safetyand Safeguards •"'

95

NRC FORM 618(845)10 CFR 71





5C.PACKAGE IDENTIFICATION NUMBER



\ PREAMBLEa. This certificate is issued to certify that the packaging_and contents described in Item 5 below, meets theappiicabie safety standards set forth in Title 10, Code



a. ISSUED TO INeme and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


afety Analysis Report for Bettis DisposableWaste shipping container dated September 30, 1969.

• c. DOCKET NUMBER

A. CONDITIONS J '""This certificate is conditional upon fulfilling therequirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging ^ x"s.--..

(1) Model m.: Bet^s|^rsposableJWaste

(2) Description W$£?? 4

wm

The :p'a1:kagin'gj|ton;^|t;Sjreusable t M 0 v ^ a ^

o

measuringvaultffndby ^ g p ^ | ^ ^ ]concreW"j)n th'e^Sottomis surr'qunêd byoverpack^sâ weldment

l l t ^ j i i

s^J^Jpjbncrête vaa3i- enclosed in a.^^^^—.-,,. y. a ^y r e c j concrete block~~~- im/T//r/---it3feis centered in thet 15" /4f(p-e by^J" deep or 27" squarej % su^îfncled by;î8" of structuraljmS3>:$3l5" on €jjf}top; the larger cavity

> a "d>by 9" on the top. Theu y t i pa^rv - \ysn\x rt^ i uiuci i \* v ^vt-n Jk/M^ »Jj %J-*U I C\^ udHCJUJ SV* SX.66 I XUD6S XO 1 / * -steel plate^lncj is sized ana constructed t^spugly enclose the concretevault. The I j f l is similarly constructed^rfd is secured to the overpackby a bolted and gjrsjiete^d closure. Tihe oveYall dimensions of the packageare 64" square by'Vo.l^hKjlW -The ross weight is approximately 16,000pounds. N *'"* ^

(3) Drawing

The packaging is constructed in accordance with Westinghouse ElectricCorporation Drawing Nos. 945F976, Rev. 4; 930C940, Rev. 4 and 976C870,Rev. 3.

96



(b) Contents


Radioactive material in the form of waste material packaged in smallercans or pails or as unpackaged solid waste sealed in poured concrete.


Total radioactivity per package shall not exceed five times an A2quantity and the plutonium activity per package shall not exceed twotimes an A2 quantity. The total f i s s i l e material per package must beless than the exempt quantities defined in 10 CFR §71.53.

6. Only reusable steel overpacks?ffab'rfcated beforeÂug'ust.Sl, 1986, are authorized foruse. fVVv'^ ""**€; ».

7. The lid of the vaults^sjitall be poured in such a manner thai; both packaged andunpackaged waste are^Sealed in concrete. In addition to the 5 inches of structuralconcrete specifiedîrf section 5(a)(2) of this cer t i f icate for,jthe top (lid) of alarge cavity vault-ân a'ddTfclpnal concrete thickn.es's^pj' at le'efst 3 inches shall beppured so that thfe/^vault c§^|yvand i t s contents vaj:eîurrounded«jby at least 12inches of structural concreiJef|-'<>\ p-^:-^ / ;';0^$- 'l* ''

Expiration date:TcfDecember 9'7.V

i

•

i Safety Analysis Report" for B£t§*i>s)(Dt ^ WAPD-0(A0)-5029dated September 30, 19§9| ^^^^f^^'lu]']\K^ * ^ " ^

Supplements dated: July^JX 198Z, an%Juêf8:;'\âTicjj,De^fber 18,,/1992.

FOR THE U.S. NUCLE%-REGULATORY COMMISSION

/ - . ' •

Iiiiic

Charles E. MacDonald, ChiefTransportation BranchDivision of Industrial andMedical Nuclear Safety, NMSS

Date:

t

i •'I

97





6206

b. REVISION NUMBER

22


USA/6206/AF

d. PAGE NUMBER

1


2. PREAMBLE




Framatome Cogema FuelsP.O. Box 11646Lynchburg, VA 24506-1646

B&W Fuel Company applicationdated April 23, 1990, as supplemented.


4. CONDITIONS f. ' ;;. !

This certificate is conditional upon fulfilling the requirements of 10.CFR Part 71, as applicable, and the conditions specified below.

5.(a) Packaging ^ -.

(1) Model No.:,..Model B

(2) Description x ^ ^

(3)

A fuel assembly sh|gp;ing. container consisting of a steel strongbackclamping"assembly^sffqck-«mounled"to a sjtejp; outer container. Two,3/16-inch thick, $^f i .nch high fand:,f^]g|ength stainless steel platescontaining 1.5% rai'1®yih^bqr;p'riâê,vRQsi.%1.Qoed between: adjacent fuelassemblies. jfie|pufef%potainer is VpprSximajb'ely 40;.;i.nches in diameterby 200 Jhchesv§fBrig. 'tGfMk• "'Weight o^theXloaded'container not to exceed7,600 pounds.•^^. . /"^-• ' '^ '[[[-t^ )}?&> >/;'

Drawings,'..f: ^Vv"fe%£vsl,. • - : -^@~^V >'r<' '•''•V'"'^:.\ /? )' : ^ ^ > . "'^-./z' ,;;~'''

The container is construct/^d?4;riâôr'dance with-B&t; Fuel Company DrawingNos. 1215464,;Rev. 1; 1215465^ReV. 0; and 12,15466, Rev. 1.

(b) Contents . . .

(1) Type and form of material^ ' i,.\ .

Unirradiated, sintered U02 pellets in fuel rods. The maximum innerdiameter and the minimum outer diameter of the fuel rod cladding, guidetubes and instrument tubes are in accordance with Table 3 of B&W FuelCompany supplement dated October 27, 1995; and the minimum guide tubeouter diameter and minimum wall thickness are in accordance withFramatome Cogema Fuels supplement dated February 7, 1996. The locationsof the guide tubes and instrument tubes are in accordance with Figures 2through 5 of B&W Fuel Company supplement dated October 27, 1995. Therods are assembled into fuel assemblies. The fuel assemblies may containinserted control rod assemblies.

98

rNRC FORM 618A(3-96)



5. (b)(l) Contents (continued)

Fuel assemblies as described above have the following specifications:

Assembly Type

No. fuel rods

No. non-fuel tubes

Fuel rod pitch, in.

Maximum fuelpellet 0D, in.

Tube material

Maximum active fuellength, in.

Maximum enrichmentw/o U-235

Maximum U-235Loading (kg)

15x15

208

17

0.568

0.3707

15x15

208

17

0.568

0.3742

Zr-4 -. Zr-4 .. Zr-4

144 . 144 144

5.05 5.05 4.98

17x17

264

25

0.496

0.3232

Zr-4

145.825

5.05.

17x17

264

25

0.502

0.3252

Zr-4

144

5.05

15x15

204

21

0.563

0.3671

Zr-4

144

5.05

25.1978 25.6758 23.7220, : 24.3108:' 24.6126 24.2355

(c)

(2) Maximum quantity of-material per;pa

Two fuel.,assembTies\' '/^t^l-,quantity^fâdt'p'ajEtive material within apackage may not e^ceedâ/Type A quantity. ,";;;<

Transport Index--"for;Crt$icaliiyConftr,olx_ :

Minimum transport index to<;bje;;shpjtyn orilabel for nuclear cr i t i ca l iCy l 'cont ro l : 6.3

6. Each fuel assembly must be unsheathed or must be enclosed in an unsealed,polyethylene sheath which will not extend beyond the ends of the fuel assembly.The ends of the sheath must not be folded;of-taped in any manner that wouldprevent the flow of liquids into or out of the sheathed fuel assembly.

7. There must be a bow clamp to restrain each spacer grid and end fitting. Theratio of assembly weight to the number of clamp bows must not exceed 168 poundsper clamp.

8. The weight of the contents (fuel assemblies, control rods, spacers, etc.) mustnot exceed 3,360 pounds.


10. In addition to the requirements of Subpart G of 10 CFR Part 71, the packageshall be operated and maintained in accordance with Section 7.0 of theapplication, as supplemented.

99

JlUKiKi&^^^^MPre^^^ÛKigLgUIU^

NRC FORM 618A(3-96)


B

g33g

8M

S

8«8

gM

i




REFERENCES

B&W Fuel Company application dated April 23, 1990.

Supplements dated: July 23, 1990; May 4, August 18, August 25, and October 14, 1992;September 24, 1993; and April 8, May •£?. and)November 23, 1994; February 26,March 17, April 7, July 31, Octqb>fes27vUn'd'Decemb,4Va, 1995.

,--•=• ' - ^ - v 5

Framatome Cogema Fuels supplement dated February 7, 1996; >.,

U'.'\T. C v xFOR THE U.S. NUCLEARJtfGU&TORY COMMISSION

•'V fS5$\?.pen^Fuei>Pf43e^ Office t~K-Mh ^<MA4mice-of^NUelevarT Ma'tirj al Safety

Date: 3 19J3-A Qj^i

~*s?

v-'-O

1 0 0

NRC FORM 618

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESICATE NUMBER b. REVISION NUMBER




2. PREAMBLEa. This certificate is Issued to certify that the packaging and contents described in Item 5 below, meets theapplicable safety standards set forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DESIGN OR APPLICATION 'a. ISSUED TO (Warns and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Chem-Nuclear Systems, Inc. applicationdated May 14, 1984, as supplemented.

rc. DOCKET NUMBER

;/

A. CONDITIONS ^ N,.. ^This certificate Is conditional upon fulfllling.thejrequirements of 10 CFR Part 71, as applicable, and thfr'conditions specified below.

5.

(a) Packaging

(1) Model /in

(2) Description

Theinchesplate. „inch thick^eerwails o¥$ffl

pfjsjfcl pf/s/ifeel ant! honeycombskage%^46, OQtepounds.

r,0XimafeeMllli3f2 inchestn length and 58i r§o f 2-inch thick steel

of leaifcwithin the walls and 2-y ! < A V | 1 ™ Tft? casWc*5 i s secured to the cask

body by twen$y>four, 3/4-indWdfameter bo l ts .^d is sealed by acompressible pio^yurethane seal. Li f t ing demces are attached to the l i dand body of the cask! !„-

A/-*" yL, ^.A^ S,/Y <ylThe cask is positioned wHhih^an ^verpack approximately 139-1/2 inches inoverall length and 89-3/8 inches in diameter. Aluminum honeycombmaterial is confined by an outer steel shell 3/8-inch thick and an innersteel shell of 1/4-inch thickness. The overpack cover is of the sameconstruction as the rest of the overpack and is secured to the walls byeight, 5/8-inch diameter bolts. Lif t ing devices are welded to the outershell of the overpack cover.

(3) Drawings

The package is constructed in accordance with Nuclear Waste SystemsDrawing No. D-6930-1, Rev. F (Sheet 1 of 2) and Chem-Nuclear SystemsDrawing No. D-6930-1, Rev. E. (Sheet 2 of 2).

101

^\m$gj^)jJ!&n^}J^}j»)^^

NRC FORM 618A(6-83) CONDITIONS (continued)



5.(b) Contents


(i) Greater than Type A quantity of byproduct material as processsolids, either dewatered, solid, or solidified, in secondarycontainer(s) which meet the requirements for DOT Specification 7Apackaging; or

6.

(2)

(a)

(b)

(ii) Greater than Type A quantity of byproduct material as solid metalcomponents in secondary containers, as required.

Maximum quantity

Not to exceed ]|)ijnfermal watts of byproduct^Watejri a l . The contents mayinclude fiss fT-e materials provided the mass litin;bs of 10 CFR §71.53 arenot exceeded^'Not to exceed a Type A quantity oj^transuranic materials.

rtaining water and/or ojpgsfijy? substances which couldte combustible gas£||£djBxermination must be made by

\r by anajvsis/of^^^presentjf&ive package suchi I ane:

For any p ^ fradiolyt'ieVllytests arra/measurthat t|ie=>f oil owi nthe expected ship

(i) ffhe hydrWild b \r-nf 1 ammataa sjp r

(ii)

those frathan 5%.

p | | p geriod oftWme that is twice

/ -6/a moljtrj quantity that^ i a l j r j t limits for othery ^ j a s void if present

7ft3 aCU.7 psia and

The%&etondary^ assure

ity mu5.tcbe inerted with alitiffted to 5% by volume in^^yg y

ns of the package which coifhcHiave hydrogen greater

For packages to be delive^f ttr?a opfiri&r for transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for gas generation is made. Shipment period begins whenthe package is prepared (sealed) and must be completed within twice theexpected shipment time.

For any package containing materials with radioactivity concentration notexceeding that for low specific activity material, and shipped within 10days of separation, or within 10 days after venting of drums or othersecondary containers, the determination in (a) above need not be made,and the time restriction in (a) above does not apply.

102

^

RQtt&&RSrlWiKWtf^^

NBC FORM 618A(6-83)




7.

8.

9.

10.

11.

12.

The lifting lugs on the outside of the overpack shall be covered during trans-port to prevent their accidental use for the purpose of tie-down or lifting.

Shoring shall be placed between the secondary containers (or activated com-ponents) and the cask cavity to minimize movement during normal conditions oftransport.

The package shall be prepared for shipment and operated in accordance with theoperating procedures in Chapter 7 of the application as supplemented.

Fabrication of additional\b

Each package must be maintained in accordance with t h e maintenance program inChapter 8 of t h e a p p l i c a t i o n as supplemented.

ââflngHafleQAiigust 31, 1984, is not authorized.

The package authoriz^by this certificate is'he"general license pno^fsions of 10 CFR §71.12.

13. Expiration date^

Chem-Nuclear System,^, Inc. ap

Supplements dated:^=August$j

(âpproved for use under the

1994.

COMMISSION

^Cask CertificationStorage and TransporvSysteiiis Branch•" " " n off, In^Mtri al and

Safety , NMSS

Date 04/13/95

1 0 3

' w w ^

I

sNRC FORM 618(&«5)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.a.CERT11 IBER b. REVISION NUMBER




2

PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafetystandardssetforth in Title 10, Code



. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

J. L. Shepherd and Associates1010 Arroyo AvenueSan Fernando, CA 91340

1?

J. L. Shepherd and Associates applicationdated September 5, 1979, as supplemented.

I0c. DOCKET NUMBER ,76280

4. CONDITIONS \ \ ^ ? ^This certificate is conditional upon fulfilling.thejrequlrements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging ^

(1) Mode^No.: A

(2) Description

A-0109A-OHt odiameter

;radiato_r in A-0'(i^0erpack""*

Sped, S&e\ weldment (Modelenclosure (Model

# r^ icyHnder , 31 inchesmim bol t |p^p plug.^closure. The

N | | ^ p m ^ l l ^ e d | teêyliQ|er enclosing a shock absorbingand thermal inlu^ô"n^cof&k^ûe^b(xnled layelslof balsa wood (11lbs/cuê. densi ty ,%2^#e»îckf | 4 the sidjs/. The irradiator isheld induce at each erffij MpvofdWetween^"6 irradiator and insidewall of th§^yserpack is fYHeii with hardwqo|jspacers. The overpackcover is secured by 30, 5/8-inch diamete%4bolts. The dimensions of thepackage are 50.5 4righes, diameter by «73 inches long. The weight of theshielded irradi.atbf irÔ^lb^TanitPthe weight of the overpack is3,400 lbs, totaling l6>400^b^ "

(3) Drawings

The overpack and irradiator are constructed in accordance with J. L.Shepherd and Associates Drawing Nos.: A-0109-A1, dated June 6, 1969;A-0109-10, dated February 3, 1970; A-0109-20, dated February 5, 1970;A-0117-B, change D (not dated); A-0117-C, dated April 2, 1970; andA-0117-C1, dated April 2, 1970.

1 0 4

iit

iI

NRC FORM 618A(6-83)



5. (b) Contents


Cobalt-60 as metal, doubly encapsulated and heliarc welded instainless steel. The source(s) is in an annular configurationapproximately 6 inches in diameter by 6 inches long. The source(s)must meet the requirements for special form radioactive material.


30,000 curies

6. The overpack must be modifdeopbpttie addition oT^nJtless than 14-1/4-inchdiameter vent holes in |fie/#uter shell (two each irfêvtop cap and cap side,two in the bottom, aQd\f?rtwo side tiers of 4 holes each,ât 90' separation,with each t ier 1 ocatiSKMabout one foot from each end). T{j,e/holes must be sealedto prevent the inleâge of water but not so as to affect <t$îr capability ofventing in the ev£p$ o1^%es. ^ y #J^

7. In addition to requir

(a) The package^must be mdescribed Km the J, LFebruary ^ 1 9 9 O ' J |

(b) The packag¥fmist ijef|?ithe 0perating^Prod|submittal dated Fe

8. The package authorized by this feergeneral license proH-slspns of 10 CF

Part

;ordari<^wBh the Maintenance Programajjfljilrsubmittal ^ t e d

fCed âccordance withepherdoind Associates

iy approWd for use under the

9. Expiration date: January^1, 2000.

J. L. Shepherd and Associates' application dated September 5, 1979.

Supplements dated: November 29 and December 31, 1984, January 16, 1985,November 22, 1989, February 2, 1990, and December 6, 1994.


L<2

Date: 01/11/95

Cass R. Chappell, Section LeaderCask Certification SectionStorage and Transport Systems BranchDivision of Industrial and


105

^NRC FORM 618(3-96)10CFR71




6294

b. REVISION NUMBER

21


USA/6294/AF

d. PAGE NUMBER

1


32. PREAMBLE




Combustion Engineering,P.O. Box 107Hematite, MO 63047

Inc.


Combustiondated July

c. DOCKET NUMBER

Engineering,27, 1990, as

71-6294

Inc. applicationsupplemented

4. CONDITIONS ,., ,"'; .{';. T- , 7 l >

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as'applicable,'ard the conditions specified below.

(b)

• w

(a) Packaging

(1) Model No.:

(2) Description

A maximum 10.80-iminimum 14 -gau.gesealed welded Sot

quire? by^lT-Tnch^ôngîner container constructed of'^-il bfo1 tedj and, gf^fted top fila,nge closure and

T^--"^^.ontji|^îs ^centered;;and supported in a.A—^+^.AXI?1^^..^ •;•••;+u ^-gaijgg head and DOT

plywood, hardboard,-is 660 pounds.

(3) Drawings >;

The packaging,i?% constructedV(i^f4V'cQraatic'e;vwith jCombustion Engineering,Inc. Drawing No's-'..-D-5007-8086', -Revf 6, and" B-500T^8112, Rev. 1.

Contents , ^,>


(i) Sintered uranium oxide pellets and rejected pellets enriched to amaximum 5.0 w/o in the U-235 isotope.

(ii) Uranium oxide as powder enriched to a maximum 5.0 w/o in the U-235isotope.

(iii) U308 powder, placed in polyethylene bags then pressed and compactedinto blocks, with a maximum enrichment of 4.5 w/o in the U-235isotope. Water may be injected into the blocks.

1 0 6

WWww:^

NRC FORM 618A(3-96)



5.

6.

(b) Contents (cont'd.)


Maximum weight of contents within the inner container is 427 pounds,including radioactive material, secondary containers, and otherpackaging material.

(i) For the contents described in 5(b)(l)(i):

320 pounds of pellets, with the U-235 content not to exceed 6.4kg. Pellets must be packaged in trays in accordance withCombustion Engineering^ Inc. Drawing Nos. D-5018-2001, Rev. 1,and NFM-Dr4263, Rev. 2-r"or^NFM-E-4661, Rev: 2 and NFM-D-4721,Rev. JL Trays containing pelle.ts must contain a maximum of9.07 kg; and a minimum of 6.7 kg of, pellets with a maximumpellet diameter of 0.4 inch. '''-'".-

(ii)Fdr,Tthe contents described in 5(b)(l:>(i"i;)»:

:.;220 pounds; of powder, with tbpJU-ZiS content not to exceed 1.5;: kg. PoWper jTiust bei^packaged^fipfsecondary^containers in

accordanc%4nth Cornbustion Engi^6ering, InCi Drawing Nos.: NPM-C-338|,fRev. OMot Rev.. 3 | , |nd NFM-D-4750, Rev. 1.

(c)

(iti) For^he conteht'Sv-describeS in-^(b)(l),(iii):

.. 3O.4Cfegf-o0U3Oa,; =Wit,h:itheHi-235 Content notto exceed 1.15 kg

\ -per p^k.agV,;|jhe!ij^O8 blocks jhall be ptaiced in perforated>valumin.%"-"cansV;whi^;;^^^^ packaged in secondary'Containers in ace<3^ante\with Gombustioh) Engineering, Inc.Drawing Nos. NPfe'C^33^9;rRev^0 or Rev. 3, and NFM-D-4750,R e v , V ' " l - . ' ' s •'•'••'

Transport Index for Cfiticajity Control

(1) For the material described in Items 5(b)(l)(i) and 5(b)(l)(ii):


(2) For the material described in Item 5(b)(l)(iii):

Minimum transport index to be shownon label for nuclear criticality control 1.3

Prior to each shipment the insert (containment vessel) gasket shall be inspected.This gasket shall be replaced if inspection shows any defects or every twelve(12) months, whichever occurs first.

1 0 7

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NRC FORM 618A(3-96)



7. For the contents specified in 5(b)(l)(i), the pellet trays and wood spacers mustprovide a snug axial and cross sectional fit in the inner container. Forpackages with fewer than 16 loaded pellet trays, wood spacers or pellet trayswith wood spacers inside must be substituted for pellet trays.

8. For the contents specified in 5(b)(l)(ii), powder cans and wood spacers mustprovide a snug axial and cross sectional fit in the inner container. Forpackages with fewer than two loaded powder cans, a wood spacer or a powder canwith a wood spacer must be substituted for the powder can.


(i) Each packaging must meet^hejacceptance^ tests and be maintained inaccordance with Chapter 8\of theâppti.catton; and

(ii) The package must^bje^prepared for shipment an$\op;erated in accordance withthe Operating^Rrocedures of Chapter 7 of the application.

10. The package authorized-by this certificate is herebvâppfbved for use under thegeneral license p'r6visfbris;of 10 CFR §71.12. '^'^ <x *

11. Expiration datet^March

Combustion Engineering

Supplements dated: October1!^;August 17, 1995.

ing, Inc^lpp^c^n^datedlJul^y^llÔ^ ;.•/;«.nu... *3^^«.^JALu.:Ui5^d juy#28, 1994- and

iflE UVS^NUCLEA'RxREGULATORY COMMISSION

Date:

f]:l i^ftrD^/Trayers, Di rectorSpent "Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

108

wwwwNRC FORM 618(3-96)10 CFR 71








5

I, PREAMBLE


b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other,applicable regulatory agencies, including the government of any country through or into which the package will be transported.


Public Service Company ofColorado

2420 W. 26th Avenue, Suite 1000Denver, CO 80211


Public Service Company of Coloradoapplication dated March 28, 1996.


4. CONDITIONS


(a) Packaging

(1) Model No.: FSV-4.

(2) Description

The FSV-1 is a sta:ij|i€ss steel-encased,^d|p|eted uranium-shielded cask.The cask body is afeylrinlier 208-lhcheV jojig and 28 inches in diameter,except.for the^t,o;pf;larige/area, which Xs^l inches in diameter. Thecavity is approximately?".T .inchesvijf^anieter; and 187.6-inches long.

The cask;may be;#sed/'in ,pne: of, :s.even .configurations (A through G)depending jjn co1ftent'sV3;£o^^ and;;D! are used to shipsolid, nori-fissiff ' irr£dia^ configurations use an outerlid consisting of a 3.75-i^n}^ijc1c?s-ta4nless steal plate and a 2.25-inchthick depleted}uranium shield/V'^he lid is bolted to the cask body by 241.25-inch diameter fasteners. 'The primary seaVis a silicone elastomericseal ring between the outer lid and cask body.' Configuration B does notrequire an inner container. Configuration C uses a supplemental stainlesssteel shield ring arid cover pi ate. 'Configuration D uses a supplementalcarbon steel shield ring arid cover plate.

Configuration E is used to ship Fort St. Vrain (FSV) high temperature gasreactor (HTGR) fuel elements. This configuration uses the stainless steelinner container (as shown in General Atomic Drawing Nos. GADR 55-2-1,Rev. C, and GADR 55-2-2, Rev. A) as the containment vessel. The innercontainer lid is a stainless steel shell containing depleted uranium4.15-inches thick. The inner lid is secured to the inner container bodyby 12 0.5-inch diameter fasteners. The primary seal is a siliconeelastomeric seal ring between the inner lid and inner container body.Configuration E is equipped with an impact limiter on the upper end.

1 0 9

"IB NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION

" " (3-96)

3 Page 2 - Certificate No. 6346 - Revision No. 26 - Docket No. 71-634639 Configurations F and G are used to ship solid non-fissile irradiated and

contaminated hardware from the FSV HGTR. These configurations use a 4.75-3 inch thick steel outer lid. The lid is secured to the cask body by 24B 1.25-inch diameter fasteners. The primary seal is a molded silicone

elastomeric seal ring between the outer lid and cask body. ConfigurationsF and G both use an impact limiter on the upper end. Configurations F andG also use a burial canister with a 12-inch thick carbon steel plug. The

ijj shielded spacer in the burial canister is used only in Configuration G.iB The overall weight for the FSV-1 package is 46,025 pounds for

Configurations A, B, C, and D and 47,600 pounds for Configurations E, F,and G.

(3) Drawings

*M

The FSV-1 package is .constructed .in accordance with the followingdrawings:

* Configuration A

National LeadCompany Drawing Nos.: 70086F, Rev. 7; 70296F, Rev. 2; andGeneral Atomics'Drawing No. 1501-003, Rev. .&..'';'/

• - " • ' • ' . . < • /

Configuration B \ > .; ;";

\ Same as. for Configuration A except that-a0;inner container is not** required. ' "tj"' .'''-'•• ,,/ 7?iltV

Conf igurat i ons ;C and: D

3 In addition to :the drawings for Configuration A, General Atomics DrawingNos. GADR 55-2-:ip.,;:lssue;<D, andjGADRC55^14, Issjyre'.N/C (optional).Configuration C U'ses-a,supplemental stain!ess steel shield ring and coverplate constructed in accoVdancefw|.th Drawing No. GADR 55-2-11, Issue B.

3 Configuration;D uses a supplemental carbon steel shield ring and coverplate constructed in accordance with Drawing ^G. GADR 55-2-11, Issue A.

Configuration E '

In addition to the drawings for Configuration A, General Atomic DrawingsNos. GADR 55-2-1, Issue C; GADR 55-2-2, Issue A; and GADR 55-2-3, Issue B.

Configurations F and G

In addition to the drawings for Configuration A, General Atomic DrawingsNos. GADR 55-2-1, Issue C; GADR 55-2-2, Issue A; GADR 55-2-12, Issue C;

g and GADR 55-2-13, Issue A.

s3

H

1 1 0

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NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96) y

Page 3 - Certificate No. 6346 - Revision No. 26 - Docket No. 71-6346 |

5. (b) Contents |

(1) Type and form of material(i) Irradiated fuel elements consisting of graphite body, hexagonal in |[j

horizontal cross section, approximately 31.2-inches high and 14.2inches across the flats. Prior to irradiation, each fuel elementcontains thorium and uranium enriched to a maximum of 93.5 w/o inthe U-235 isotope, or

(ii) Solid, irradiated, and contaminated hardware, which may includefissile material, provided the quantity of fissile material does notexceed a Type A quantity and does not exceed the mass limits of 10CFR §71.53 and neutron source components, or

(iii) Solid, nonfissile, irradiated.and contaminated hardware which hasbeen removed from the Fort St. Vrain High Temperature Gas CooledReactor and the surface contamination does not exceed 51 millicuriesper package.


Decay heat not to exceed 4.1 kw and:

(i) Item 5(b)(1XQ), above:

Six fuel elements each containing a maximum of 1.4 kg of enricheduranium, having -a thorium/uranium ratio greater than 8.1:1 andweighing\a£pr6ximately 300 pounds.; The gross weight of the caskcavity contents', including the component spacers, inner container,and irradiate fuel elements shall not exceed 4,430 pounds. £Contents must b,e,shipped in Configuration E. jj

(ii) Item 5(b)(l)(ii) above:..'••"

The gross weight of the cask cavity contents, including appropriatecomponent spacers, liners, inner containers, shield rings and solid,nonfissile, irradiated and contaminated hardware shall not exceed3,720 pounds. Contents must be shipped in ConfigurationsA, B, C, or D.

(iii) Item 5(b)(1)(iii) above:

The gross weight of all of the cask cavity contents, includingburial canister and spacers, with or without supplemental shieldingshall not exceed 4,430 pounds. Contents must be shipped inConfigurations F or G.

1 1 1

jg? w w a w w s^^ j at at ww w atzwww www w wwwwwwwww www wwww wwwarew www WJNRC FORM 618A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)


5. (c) Transport Index for Criticality Control


6. As needed, appropriate component spacers must be used in the cask cavity whenshipping the contents described in paragraph 5(b) to limit movement of contentsduring shipment.

7. For transport of the contents of Item (b)(l)(ii) in Configuration D, the doserate measured on the surface of the package must not exceed 200 mr/hr. For thepurpose of this requirement, the surface of any personnel barrier may not beconsidered the surface of the package.

a8. The Model No. FSV-1 cask may be,wrapped-with reinforced plastic when shipping

the contents described in Item 5.(b)(l)(i,i) or, (iii) provided the heat generationrate does not exceed 500(watts'.' The applicable,requirements of 10 CFR §71.87must be satisfied prior to wrapping the cask. '{>, c,

9. Use of packaging fabricated after August 31, 1986, is not authorized.

10. In addition to the requirements of Subpart G of .ip, C0R Part 71:

(a) Configurations A,;;B:,-J,C, and p. o.f..the Model^FSV-l shipping cask shall beprepared for shipm$nt|and operated in accordance with the OperatingProcedures of Sect0nV7.O, Volume' I,\of>^£ application, as supplemented.The package shall BeCmaintained in accordance with the-Maintenance Programin Section 8.%,\yoTunie :I,,,.of the appl/icatTon?«as supplemented.

* (b) ConfigurationssEyiF; .and <G of the f odel FS?V^-i(shipping cask shall beprepared for shipment' and< operated in. accordance with the OperatingProcedures of Secti;6ri!7.0:", Volume tiv<ofvthe application, as supplemented.The package,shalf bei'maintained;>in. accordance with the Maintenance Programin Section 8.0, Volume II, 6f,t^e>application, as'supplemented.

(c) The main flange seals must be replaced within twelve (12) months prior toS any use of the packaging and must be replaced'if inspection shows anyS defect. . „•'a - • . • . -.,

(d) The silicone 0-ring on the inner container primary plug in Configuration E% must be replaced within the twelve (12) months prior to any use of the

packaging and must be replaced if inspection shows any defect.

| _gJK7^MMJ£U£U£JgJSU&JSU&M^7&7&7&MJ£JSU£JSJ£^

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12. Effective date: Hay 1, 1996 Expiration date: May 31, 2001.

REFERENCES

Public Service Company of Colorado application dated March 28, 1996.


William D. Travers, QirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

?•; Date: April JL, 1996

M l *"&:?*..,>••

113

j

NRC FORM 618(8-8S)10 CFH 71


FOR RADIOACTIVE MATERIALS PACKAGESa. CERTIFICATE NUMBER

6347

b. REVISION NUMBER


USA/6347/AF

d. PAGE NUMBER o. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theapplicablesafetystandardsset forth inTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATIONa. ISSUED TO (Name and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

General AtomicsP.O. Box 85608San Diego, CA 92186

General Atomic Company Application datedFebruary 19, 1982, as supplemented.

c. DOCKET NUMBER

4. CONDITIONSThis certificate is conditional upon fulfillinsyheyequirements of 10 CFR Part 71, as applicable, and the'conditions specified below.

(a) Packaging

(1) Modejyjb.: FS

(2) Desdfcfption5

Innerycontcont&iliersteel drum,the ipier cocontented is

(3) Drawing

J^gage stieel drum. Inner" f t * ID iD'8-25" high, 16-gageaffd outef7container and withinl i t e . <^retal weight, including

rJSThe packaging^ constructed in accordance^Drawing No. F F E - 6 ^ Issue D. „ V

nth General Atomic Company

(b) Contents


Fuel element consisting of a graphite body, hexagonal in transversecross-section approximately 14.2" across the flats and 31.2" high.Dispersed in columns within the fuel element body there is a maximum 1.41kg U-235 plus U-238 and Th-232. The U-235: U-238: Th-232 atomic ratiois about 1:0.07:8.3. The atomic ratio of carbon to the U-235 is in therange of 1800 to 1.


One fuel element containing not more than 1.41 kg U-235 and weighing notmore than 320 pounds. Total quantity of radioactive material within apackage may not exceed a Type A quantity.

114

f f f l j S J * ^ ^

NRCFORM618A CONDITIONS (continued)






(i) The package must be operated and prepared for shipment in accordance withthe operating procedures of Chapter 6 of the application.

(ii) Each packaging must meet the Acceptance Tests and Maintenance Program ofChapter 7 of the application.

7. The package authorized by 1$i i ipte l f t i f ' i taê^sCk£|feby approved f o r use under thegeneral l i c e n s e prov isôf t^bf 10 CFR § 7 1 . 1 2 . <

8. Expiration date:

General Atomic Companîpp

Supplements dated: /(March

COMMISSION

Date:

REFERENCE

dated February 19

2

1 1 5

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6357b. REVISION NUMBER c. PACKAGE I] BER d. PAGE NUMBERNUN e. TOTAL NUMBER PAGES

2. PREAMBLE




Babcock & Wilcox CompanyP.O. Box 785Lynchburg, VA 24505

Babcock & Wilcox Company applicationdated February 28, 1991.


4. CONDITIONS - . : . - * , , ,


(a) Packaging

(1) Model No.: NNFD-1O

(2) Description v ; ^ ; l \ , ,-'J&J'?'The packaging consists of a'cWtaiifment^ssel, 5-9/16 inches OD by

' • ' . ' - • ' *

The packaging corilfjts of acWtaiifment^ssel, 59/16 inches 0D by22-3/8 inches hi§h^';;constru?ted;:fr6m saînch scheduled 40 steel pipewith a screw-type^cVpând a' welded- bottom"plate. The, containmentvessel is cenfeêdranclMupported.;ihVC^5-galloh DOT .specification 17Cor 6C steel "drum ,by --iliaiistri a! i ca,*ie,#iberMard.,

• %W-%n • ' : ^ : ' ! - ; : - : i : ^ v 1$:-;. .yrThe nominal gross eight^pf; thajplpkagingând contents is 350 pounds.

-'• O s '.?•:• "•-->" "" " ' , -'v(3) Drawing -\ .. ..V£;.4W>/. .; ,;. ,.'

The packaging'is constructed'^n accordance with Babcock and WilcoxFuel Company Drawing No. 1198767E.

1 1 6

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s

S



5.(b) Contents


Uranium metal, alloys or compounds. Uranium may be enriched to any degreein the U-235 isotope.


Contents shall not exceed 100 pounds, and the U-235 content shall notexceed 350 grams. Maximum quantity of radioactive material within thepackage may not exceed a Type-A quantity.

(c) Transport Index for,CriReality Control

Minimum Transport.index to be shown

on label for nuclear criticality control: 2.1

In addition to the requirements of Subpart G of 1,0 CFR PaV*t 71:

(a) Each package must meet the Acceptance Testsfand Maintenance Program in!! Chapter 8 of the app3ication9 •-•-.»•

(b) Each package shall b%,6perated'<and pr.epayjcj;'for shipment in accordance withthe Operating Prjacedureisvin Chapter JxOi rtfie application.

7. The package authorized ^vthiV'lcertificat'eiis he^epy. approved for use under thegeneral license; provision^of^lO..CFjR::§71ii2. / V ~.;

8. Expiration dateY •'•'h~

Babcock & Wilcox application dated February 28, 199,1.

Supplement dated: March 21, 1996. --•



and Safeguards

Date:

111

H

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s

WWWwwNRC FORM 618(3-96)10CFR71




6386

b. REVISION NUMBER

14


USA/6386/B(U)F

d. PAGE NUMBER

1


42. PREAMBLE






Safety Analysis Report for 235R001Shipping Container dated August 11, 1970,as supplemented.

c. DOCKETNUMBER 7 1 - 6 3 8 6

4. CONDITIONS ' x "> -This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1)

(2)

Model No.: .235R001

Description % \ ^ . «=-"*,«••• <''?

The 235R001 shippirrgltiontainef*. s"truptu|e^| horizontal, having an oblongcross section andK^s|fabricai'ed frorn,0#lJ4rinch thick;carbon sheet s tee l .The con t a ine r ' s &&%ich.es .1 on'g ianjd' hSsî^ maximum weight of 4,640pounds,~ empty^).f; he^?o,b1 |ig 9.r.os.s se^tfnitdime'nsions;:are approximately35.5 inches fi1;ghlby '33|p//^jach^ was originallydesigned to sSipKun.lr^ ATG/A4W type.Subsequently, the'ôiitainlr'ha'sl b^nâdapted'^to ship A1W-3 fuel modulesusing a ^rongback,^ farâl'.^TW^R3:^VV?mo;8ules uîpg module supportassemblies, standard' aizeôrfpîrtâl/SSG^fuel modules by use of a specialframe assembly and cradle'î|iR%';;S3G-3 .refueling^modules using cellsupport assemblies, rodded%rûnfodded DIG fuel; modules, rodded ASNPPfuel cel ls and:rbdded or unrodded D2W fuel^celis. The loaded containermaximum weight is 12,421 pounds. x,,

(3) Drawings

The packaging is constructed in accordance with Container ResearchCorporation Drawing Nos. 235R001, Rev. C, 235R004, Rev. C, and 235R005,Rev. 0, and Westinghouse Electric Corporation Drawing Nos. 973D425,Rev.l, 903E693, Rev. 3, Sheet 1, 2 and 3 of 3, and 947J076, Rev. 0.

1 1 8

Unirradiated fuel assemblies of the following types:



5.(b) Contents


(i) A1G and A4W reactor cell without upper mechanism and withcontrol rod, leadscrew and shipping fixture installed on roddedtype modules.

( i i ) A1W-3 rodded-type module without upper mechanism and with controlrod, leadscrew, and control rod holddown device instal led.

( i i i ) A1W-3 unrodded-type module.

(iv) Standard size S8G reactor cluster with regular or substitutesupport adapters and regular control rods or Boral poison rodswith control rod holddown devices instal led. If only one cellis shipped per container, a dummy load^shall be installed forbalance.., . - -

(v) Partial size,S8G reactor clustery'iyalh regular or substitutesupport adapter's, anjd rregul ar control rods or Boral poison rodswith control/rod holddown device:;; ins ta l led. If only one cellis shippe3f|pfr container, a dulnmy^oad shall be installed forbalance,., "~.fC'-l, ': r ' <:rr./v'

(vi) S3G-3 refuel ing ; eel Is,i with'a. max(imUm'-of one 0-1 reactor cellassembly per/container. : q r-'"-•

(vii) DlG fuel^moduTe', rpddedv. *--•>:>'

(v i i i ) DIG removable fuel' assembly (RFA), unrodded.

(ix) A1G fuel cluster, fueled end only of full A1G reactor ce l l ,rodded. • ''. , . '•'-*

(x) ASNPP fuel cell with control rod, and control rod holddown deviceinstal led.

(xi) D2W side or central fuel cells with control rod and control rodholddown device.

(xii) D2W corner fuel cells, unrodded.

(xiii) STC fuel cells, unrodded.

(xiv) D2W fuel cell and shear block with control rod inserted inrodded fuel cell.

119

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5.(b) Contents (continued)


(i) One fuel assembly as described in 5(b)(l)(i), 5(b)(l)(ii),5(b)(l)(iii), 5(b)(l)(x), or 5(b)(l)(xiv).

(ii) Two fuel assemblies as described in 5(b)(l)(iv), 5(b)(l)(v),

(iii) Four fuel assemblies as described in 5(b)(l)(viii)

(c) Transport Index for Criticality'Control

Minimum transport-ifiplex^to be shown on " :;v,:.p plabel for nuclear crit icality control:

2(1) For the.;cbntents described in 5(b)(l)(ii) ^-t ,and limited^-in, 5(b)(2)(i): ^>^ v 100

'" " ' 7.0

(4)

! 6. Expiration date: July 31, 1997.

31.3

25.0

(5) For contents described in 5(b)(l)(iv) aiid:>>5(b)(l)(v), and limited in/5(b)(2)Cif), andshipped with regular control,--rods": '/ 25.0

(6) For contents described in 5(b)(l)(iv) and5(b)(l)(v), and limited in 5(b)(2)(ii), andshipped with bora! poison rods: 32.0

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NRC FORM 618A(3-96)


REFERENCES

Safety Analysis Report for 235R001 Shipping Container, WAPD-OP(R)RD-357 datedAugust 11, 1970.

Supplements: Knolls Atomic Power Laboratory letter AlG 25-159, datedOctober 2, 1970. Bettis Atomic Power Laboratory letters WAPD-0P(R)RD-444, datedOctober 9, 1970; WAPD-0P(R)RD-476, dated October 26, 1970; and WAPD-0P(R)RD-488,dated October 30, 1970. Knolls Atomic Power Laboratory letters AlG 25-181, datedApril 9. 1971; and AlG 25-191, dated May 11, 1971. Bettis Atomic Power Laboratoryletters WAPD-0P(R)C-94, dated May 16, 1972; WAPD-0P(R)C-199, dated December 13, 1972;and WAPD-OP(R)C-229, dated March 6, 1973. Naval Reactors letters G#5078, datedJanuary 26, 1976; G#5776, dated September 8, 1977; G#5905, dated January 23, 1978;G#5923, dated February 22, 1978; G#6095, dated .August 17, 1978; G#6208, datedMarch 8, 1979; G#6373, dated Septejnber'4, 1979; e#68i3, dated October 17, 1980;G#C85-0467, dated July 17, <l-985; ;G#C88-8112, dated October 18, 1988; G#90-03655,dated August 10, 1990; G#92-03560, dated June 15, 1992; arid G#96-03371, datedMarch 15, 1996. ' :


Dated:

^ . ^ • f William D. -|||8rers, Diredtoir u ¥§,'%}* ^"Spenf'Fuel;sPwg'ect.'Office^'•

r.m ^^v^^-Office.ofrilutfea^ateria?::

tTliam D. -ll ajrers, Director

Safety

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^NRC FORM 618(3-96)10CFR71



i. a. CERTIFICATE NUMBER

6400

b. REVISION NUMBER




9

2. PREAMBLE




Westinghouse Electric CorporatiotP.O. Box 355Pittsburgh, PA 15230


Westinghouse Electric Corporation applicationdated August 7, 1981, as supplemented.


- ( . C O N D I T I O N S . - ;K. ' - ' • ' , • • •This certificate is conditional upon fulfilling the requirements of 10,'CFR Part 7i, as applicable; and the conditions specified below.

5.

(a) Packaging

(1)

(2)

Model

Description X 5 ^ % _ ,,<V7

A protective over^cfewhich^provides •i'nfpagt and therni'al protection forits contents. Th^njier she^l,Xsavi|yf|g;approximately 76" x 76" x 172"constructed ofAS/ie^tthtck-'and'Hu-gauge.SiTld steel. Closure of thec f / ^ f j g g / pcavity. 4s by 1^4^11061^^ rubber gasketwhich is! bolfeti%Q ttfrCimai-jri;ifnhe. i hk"KTC JFlievdavity-is centered andsupportedsin 'ap/MiJer 3/16" th^ki ifeel j£ek>,t by approximately 32" ofpolyurethane fo|m.insult]on atithiS.end afid-10" on the sides. AremovabTeVsectVojiôi^ 34" of polyurethanefoam insulation encased Wyêlv'with a siliconevrubber gasket is boltedto the mai'n outer steel ja'clcet#AvThe overal 1 dimensions of the packageare approximately 8' x 8' x Ô'V Vent holes, are provided on the sidesand ends of the .container. Set into each corner of the outer containerare standard I.S.O. steel.castings. The total weight including weight ofthe contents is 45,00,0"pounds'.

(3) Drawings

Packaging is constructed in accordance with one of the following sets ofdrawings: (1) Protective Packaging, Inc, Drawing Nos. 32106, Sheet 1,Rev. F and 32106, Sheet 2, Rev. 0; or (2) Westinghouse ElectricCorporation Drawing No. 2020D08, Sheet 1 and 2, Rev. 0; or (3) Babcockand Wilcox Company Drawing No. ll-D-2130, Rev. 0; or (4) ProtectivePackaging, Inc., Drawing Nos. 32106-1, Sheet 1, Rev. F and 32106,Sheet 2, Rev. 0, as modified by Nuclear Packaging Inc. Drawing No..E.G.-60-01D, Sheets 1 and 2, Rev. 0; or (5) Protective Packaging, Inc.Drawing No. 32395, Sheets 1 through 9, Rev. B, as modified by SandiaLaboratories letter dated May 8, 1980; or (6) Lawrence Livermore NationalLaboratory Drawing Nos. AAA81-108683-00, Rev. 0 and AAA81-110194-00,Rev. 0.

122

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NRC FORM 618A(3-96)



5.(b) Contents

(1) Large, decontaminated equipment waste of such size as not to fit into a55-gallon drum (with legs or other readily removable appendages removed).Not to exceed 200 grams plutonium within the package.

Equipment waste surfaces containing more than 0.5 Ci must be decon-taminated to a smearable level of no more than 150,000 dpm/100 cm2 priorto fixation or until successive decontamination cleaning operations donot reduce the smearable contamination levels by more than ten percent.After fixation, equipment waste surfaces must have a smearable level ofcontamination of no greater than 10,000 dpm/100 cm2. Outer surfaces musthave a smearable level of contamination of no greater than 20 dpm/100 cm2.Prior to fixing of contamination, Targe equipment waste must be inspectedto insure that: (a): all sharp or protruding objects have been removed,blunted or protected with packaging material, and (b) pipe caps, gasketedblind flanges,-covers, etc., have been installed wherever possible.Following such inspection, the inner surfaces containing more than 0.5 Cimust be fixed with "strip" or "clear" coating, the inner surface(s) mayalternativelycbe .fixed with a polyurethane foam. ,. -

The large equipment ,waste must be encTq$ed/3n a tight-fitting, 1-inchthick plywood box-?cpnstructe'd in accordance with Westinghouse ElectricCorporation's Drawing;? No,. 1620E43, Shejtj^/l, 2, 3, arid. 4, Rev. 3; a tightfitting 3/16" thicfecbrrugated steel boxseonstructed in accordance withRockwell Hanford- Operations' Drawing. No^H-2-91888, Sheet 1, Rev. 0(modified or'Urimodif.ie^jôr encôsedîW' a tight fitting box constructedin accordance w'iin/General Electric,;CompanyvDrawing Nos. 908E614, Rev. 1,and 908E619, Rey.:.: 2,>6r 9p,8E6,48;j ,Rey!..O ori908E649, Rev. 0; or enclosedin a tight, fitting-box-?constructed;xin>accordance wjith Babcock and WilcoxCompany Drawing 'Ntf^'LRC-70p^.;iHv.^Bev/;2V>

:The space; between the equipmentand the box must be fille'4Mtt^.;:JFoam4i(r'jminimum 'foam thickness) andbetween equipment (1/2" mihfmunt'ffoam thickness)-. Alternatively,gloveboxes contaminated and fixed as described above may be broken downas follows: '-•/'

Glovebox windows are removed-and separately packaged in 12-mil thick PVCbags and sealed. The inner bag is tape sealed and the outer bag is heatsealed.

Glovebox panels are cut to dimensions to fit inside the 3/16" thickcorrugated steel burial crates constructed in accordance with RockwellHanford Operations' Drawing No. H-2-91888, Sheet 1, Rev. 0 (modified orunmodified). All sharp or protruding objects are removed, blunted, orprotected with packaging material. The glovebox panels are bundled suchthat internal box surfaces are facing inward. Cut glovebox panels fromnot more than one glovebox are banded with metal strap banding such thattwo metal strap bands in each direction are placed around the length andwidth of the glovebox sections. The glovebox window and cut panelpackages are enclosed and foamed in place within the box.

Blocking or dunnage is placed within the box to ensure a one inch foambarrier on the sides and bottom of the box. Likewise, dunnage isprovided between the banded glovebox sections to maintain a 1/2" thickfoam barrier between banded packages.

*i

123

NRC FORM 6 1 8 A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)



(2) Decontaminated hard waste items, such as equipment, metal cans, tools,etc., must be double bagged within 12-mil thick PVC with each bag heatsealed. The total fissile quantity of all the sealed packages in onecontainer must not exceed 200 grams.

Hard waste surfaces must be decontaminated to a smearable level of nomore than 150,000 dpm/100 cm2 prior to fixation or until successivedecontamination cleaning operations do not reduce the smearablecontamination levels by more than 10 percent. After fixation, hard wastesurfaces must have a smearable level of contamination of no greater than10,000 dpm/100 cm2. Prior to fixing-;of contamination, hard waste must beinspected to insure that sharp or protruding objects have been removed,blunted, or protected with packaging material. Following such inspection,the outer sur-faces must be fixed with "strip" or "clear" coating. Hardwaste itemsosuch as furnace shells, muffles, or/other items with largecavities riot accessible for decontamination must,be filled with foamwithin the, castles. Surfaces that are notêasiTy; accessible, e.g.,interiorsrof small -diameter tubing and piping which'were in contact withprocess'material^,?must have been swabbed<or^ immersed in cleaningsolution to insure%removal :oTf^re"sidualvma|;erial. Open ends of the tubingand pjping must be! sfa/led using mechanical.; fittings.

Alternately, Tar5ge^heavy.:waTl edprdcessjglassware must be painted insideand outsnde tq\fix"c'onâM^ in 12-mil thick PVC

1 i mi ted ' to *' less < Han .vtfwo (Ô.i;;"i nv i box J

and outsnde tq: f i x c ' o n t ; ^ in 12-mil thick PVCwith each bag^hVat-sealed'.- The gTas(s.ware;/iriirs:t-''be secured in a boxconstructed iri^ccdfdanGesW.itH,.General Eleqtric Company Drawing No.nocoijA:? Dm. h;! .<ru'ik'nv ™Vr+!;u:-«n^ ,:;-i+u foam an(j total activity

Alternately,;, stainless ste^t'rJansfer' tubes and TIE PA filters must bedouble bagged, in!; 12-mil thick PVC with eachvbacj heat sealed. Thetubes/filters must be, secured in a box constructed in accordance withGeneral Electric Company Drawing No,...272E81-28, Rev. 0. The box must befilled with foam aricTtotal*activity" limited to less than 0.5 Ci in a box.

Alternately, round steel ducting must be capped and secured in a boxconstructed in accordance with General Electric Company Drawing No.272E81-29, Rev. 0; 272E81-30, Rev. 0; or 272E81-31, Rev. 0. Outersurfaces ducting will have a smearable level of contamination no greaterthan 20 d/m/100 cm2. The box must be filled with foam and total activitylimited to less than 0.5 Ci in a box.

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NRC FORM 6 1 8 A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-9S)

Page 4 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400 j!


* Sealed packages and boxes of hard waste must be enclosed in a tight-fitting, 1-inch thick plywood box constructed in accordance withWestinghouse Electric Corporation's Drawing No. 1620E43, Sheets 1, 2, 3,and 4, Rev. 3; a tight-fitting 3/16" thick corrugated steel box

5 constructed in accordance with Rockwell Hanford Operations' Drawing No.* H-2-91888, Sheet 1, Rev. 0 (modified or unmodified); enclosed in a tight

fitting box constructed in accordance with General Electric CompanyDrawing Nos. 908E614, Rev. 1 and 908E619, Rev. 2 or 908E648, Rev. 0 or908E649, Rev. 0; or enclosed in a tight fitting box constructed inaccordance with Babcock and Wilcox Company Drawing No. LRC-70019 H,

3 Rev. 2. The space between the packages and the box must be filled with3 foam to a minimum thickness of 1 inch. Void spaces between the sealed3 packages must be filled with foam (1/2" minimum foam thickness).33 (3) Glove box absolute,(HEPA) filters must'be: double bagged within 12-mil3 thick PVC, with each bag heat sealed and packaged within DOT3 Specification 17H or 17C steel drums (maximum size of 55 gallons). Eachg drum must^belined with a sealed plastic liner and equipped with a

standard drumvclosure. Each drum must not exceed a fissile quantity of60 grams.; SealeclVdrums must be enclosedifraîght-fitting 1-inch thickplywood box constructed in accordance wi|:h Westinghouse Electric

g Corporation's Drawing No. l£20E43, Shee€s^, 2, 3, and 4, Rev. 3; atight-fitting 3/l^V,thidk cojrirugate^ ,sjte,ei'box constructed in accordancewith Rockwell .HanfojrÔperatapjis'' Drawing/No. H-2-91888, Sheet 1, Rev. 0

j, (modified or Un|nodi fejd);-. e^ncToseîn^îght. fitting box constructed ins accordance witH'-jGenenaT/ Electric Comp^tfy/Drawing Nos. 908E614, Rev. 1 and* 908E619, Rev.-Z,\or 9Q8E648,' Rey. ;Oy£of 9Q'8j649, Rev .0; or enclosed in as tight fitting^box-c^hstr'Mctedi'ijiiJacdorda^ce^'witn Babcock and Wilcox

Company Drawi ngTjio..: LR.Q-70019 H,;R|y.,2f. The space between the drums anda the box must be- iille(f'''wit foarafvttf- ffl'inimum thickness of 1 inch. Voidg spaces between drums must^|^jfi|ied with;" foam (1/2" minimum foama thickness)',-/',-' v>//> .*.'•;• "' -.-• .

a (4) Soft waste items/such as sheeting, gloves, ,paper, pr.efilter media,a polyethylene bottles;.vshoe covers, etcs, must be double bagged in 12-mila thick PVC, with eacfrxbagpieat'seated (bag size must not exceed 22" x 16"a x 10") and packaged within DOT Specification 17H or 17C steel drumsa (maximum size of 55 gallons). Each drum must be lined with a sealeda plastic liner and equipped with a standard drum closure. Each drum must« not exceed a fissile quantity of 60 grams. Sealed drums must be enclosed« in a tight-fitting 1-inch thick plywood box constructed in accordanceC with Westinghouse Electric Corporation's Drawing No. 1620E43, Sheets 1,z 2, 3, and 4, Rev. 3; a tight-fitting 3/16" thick corrugated steel box* constructed in accordance with Rockwell Hanford Operations' Drawing No.^ H-2-91888, Sheet 1, Rev. 0 (modified or unmodified); or enclosed in a^ tight fitting box constructed in accordance with Babcock and WilcoxC Company Drawing No. LRC-70019 H, Rev. 2. The space between the drums and5 the box must be filled with foam to a minimum thickness of 1 inch. Void5 spaces between drums must be filled with foam (1/2" minimum foam* thickness).

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(5) Liquid waste (decontamination solutions only) must be solidified inconcrete in a 30-gallon drum which must be sealed in a plastic bag andcentered and supported in a DOT Specification 17H or 17C 55-gallon steeldrum by absorbent material. The 55-gallon drum must be lined with asealed plastic liner and equipped with a standard drum closure. Each drummust not exceed a fissile quantity of 60 grams.

Alternatively, liquid waste is solidified in concrete in maximum size one(1) gallon packages which are double bagged and heat sealed in 12-milthick PVC and placed with a DOT Specification 17H or 17C steel drum(maximum size of 55 gallons). The drum is lined with a sealed plasticliner and equipped with a standard ..drum closure. Each 55-gallon drum mustnot exceed a fissile quantity of 60 grams. For drums smaller than 55gallons, the totals fissile quantity of all the sealed packages (drums) inone container^must not exceed 200 grams. Sealed drums must be enclosedin a tight-fitting 1-inch thick plywood box constructed in accordancewith Westinghouse Electric Corporation's Drawing No. 1620E43, Sheets 1,2, 3, and ,4, Jtey. 3; or a tight-fitting 3/16."?thick corrugated steel boxconstructed in accordance with Rockwell hjariford Operations' Drawing No.H-2-91888, Sheet. l^Rev. 0 (modified or unmodified); enclosed in a tight-fitting box constructed in accordance with" General Electric CompanyDrawing Nos. 908E6Hjl-Rev. l}:;and;90?E6i9^.Rev. 2 or 908E648, Rev. 0 or908E649* Rev. 0; oîeTncloseat in a tight fitting box constructed inaccordance with Babioe|c and WiTcoX/Company Drawing No. LRC-70019 H,Rev. 2. Thesspatebetween the drums nd/the, box must be filled with foamto a minimum thjcknessipfi inch. ; Void spaces between drums must befilled with foam" (1/2" "minimum fo'am^thickness).

(6) Uranium 233 oxide; anjci..,thorium,;oxide in"-the* form of 1'ntact LWBR-type fuelrods with the following lîtaîdns::; /'", •/•,'

(i) Rods must be packaged Within the Model No. 6400 packaging asdescribed.in Section 1 of WAPD-LP(FE)-220, Rev. 3 (February 1983);

(ii) The fuel content must not exceed 50 kg U-233 per shipment;

(iii) All rod storage containers must be filled to capacity (at least 70%of cross-sectional area) with rods or aluminum shim stock;

(iv) Each rod storage container must contain not more than one sub-container of 5/9 or 12 w/o BMU seed rods;

(v) Each rod storage container must weigh not more than 2,000 pounds;

(vi) The fuel rod heat generation must not exceed 30 watts; and

(vii) Operating Procedures and Acceptance Tests and Maintenance Programmust be modified to meet the requirement of Item 11 of thisapproval.

126£L2£JBJ^^ ^ F&2gU£U&J£U3U&.25U3&JEJ

wwwwi^^ 'NRC FORM 618A(3-96)




(7) Liquid analytical residues from the dissolution of spent reactor fuelrods, solidified in cement (see table, p. 3 of application*). The cementis contained in 1.5-gal steel can closed with a slip cover lid. The twoprimary cans are packed in a secondary steel can sealed with a press fitlid (see Figure 2 of application*). The secondary containment packagecontents are placed within a radiation shield (lid secured with six (6),l/2"-13UNC bolts with welds in accordance with application*) centered ina DOT Specification 17-C 55-gal steel drum (see Figure 1 ofapplication*). The drums are sealed with styrene-butadiene rubber gasketcontained with a standard drum closer. Total weight of the drum will beless than 1,450 1b, and each drum will not exceed a fissile quantity of12 g and 435 Ci of fission products.

Six (6), 55-gal sealed drum assemblies will be enclosed in a tight-fitting 3/16-in thick corrugated steel box constructed in accordance withRockwell-Hanford Operations' Drawing No. H-2-91888, Sheet 1, Rev. 0(modified or unmodified). The space between the drums and the box mustbe filled with foam to a minimum thickness of 1 inch. Void spacesbetween drums-.must be fitted with foam to a minimum thickness of1/2 inch. Two (2) corrugated steel box assemblies may be transported inthe packaging. '.

* U.S. Department :bfEnergy letter dated^April 15, 1983.

(8) Uranium 233 oxide arid/thorium oxide fnHhe form of intact LWBR-type fuelrods with the following limitations: iS , ;.

(i) Rods must be packaged as shown-,in,-Figure 4, Application datedJuly 8, 1983V.and contained within-the Model No. NNFD-SA-2packaging (Certificate of Compliance No. 5910);

(ii) The fuel content must not exceed 2.0 kg U-233 per shipment;

(iii) Each loaded LWBR Rod Transport Box must weigh not more than 99pounds; *" "

(iv) The fuel rod heat generation rate must not exceed 2 watts; and

(v) Operating Procedures and Acceptance Tests and Maintenance Programmust be modified to meet the requirement of Item 11 of thisapproval.

127

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jj Page 7 - Certificate No. 6400 - Revision No. 22 - Docket No. 71-6400


* (9) Maximum of four (4) Cf-252 sources with the following limitations:

* (i) Each source must be doubly encapsulated with the inner capsules meeting the requirements for special form radioactive material;SS (ii) The total Cf-252 content must not exceed 6.1 mg;3 (iii) The sources must be packaged in a shielded container as describedS in Chapter 1 of WAPD-LP(CE)P0B-591 (January 1984); and38 (iv) The decay heat generation from the source material must not exceed3 one watt. ~ .8 >.-> ::--.-> " ' •• •<•.-'.,, -',-.•

3 (10) Compressed kryptph-85; gas in mixture with, other non-radioactive gasesg that are chemically compatible with the 3AA2015 cylinder. No fissileg material (Requirement of 5.(c) does not apply).> Shipment of krypton-853 gas is subject to the following limitations: ; ",.

g (i) Radioactiyjly^not to exceed 2,700,,curfes. Maximum internal decayw heat not êxceed 15 watts. Maximu.ifi volume of krypton-85 ands other non-rftfipactive gases shall?tifo% exceed11480 liters at STPg (1 atm, 25-";C|;;V-- ''••'•'«' :?'M':

i (ii) The max;imumr^;i3i|iaT; fill pressur&Shall not exceed 500 psig at

(iii) The D0Têcificaî,qn'3M2pl5 gas dyTinder shall be certified foran :'opera1fih'g lp.ad ;o£-< 25:015 ip^s^ât Teast once every 5 years bytest-ing td- 3:,<3,60*"Dsiat:/-";iv-" 'v^v"T.y -''- t:>j

a (iv) A miniijium of 24 houns'âêrJ loading with krypton-85 gas the kryptong packaging-primary containment shall haveâ leak rate of less than

0.0014 microcuries per second. The leak test shall be performedwith the containment vessel within the lead shield container priorto placement Within: its .thermal overpack;

(v) Content of the package shall be verified by mass spec analysis;

(vi) Acceptance, maintenance and use of the krypton package shall be inaccordance with the procedures and requirements of Chapter 7 and 8of Westinghouse Idaho Nuclear Company, Inc. Report No. WIN-236,

Z Revision 1, March 1988. The retaining ring shall be tightenedj? around the gas cylinder to a 40 to 50 inch-pound torque;

l (vii) The position and securement of the krypton package within the Model~ No. 6400 is as specified in Westinghouse Idaho Nuclear Company,I Inc. Drawing No. 059888;

(viii) Krypton package must be enclosed within a tight fitting plywood boxconstructed in accordance with Westinghouse Idaho Nuclear Company,Inc. Drawing No. 059886.

128^

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6. The polyurethane foam must be Instapak 200, or equivalent.

7. The maximum weight of the contents including secondary packaging, dunnage,shoring and bracing must not exceed 30,000 pounds.

8. Sufficient dunnage, shoring and/or bracing must be utilized to minimizesecondary impact of the secondary packaging within the cavity under accidentconditions.

9. Protrusions from secondary packaging such as lifting eyes, etc., must bepositioned such that.they will not contact the cavity walls, or shoring must beprovided to prevent puncture of the cavity walls by the protrusions under theaccident conditions.

10. Contents must be positioned in the cavity such that the center of gravity ofthe loaded package is substantially the same as-the center of gravity of anempty package,. y ;

11. The cavity of the overpatkfjriust be :vented through an absolute filter toequalize pressure between; the'outside and inside of the overpack.

12. Contents packaged under tf)e>conditions of this certificate of compliance areexempt from the requirements-'of 10 CFR §71.63. /Condition 5(c) of thiscertificate of compliance/ris 'h'jbt applicable where the fissile material isexcluded as provided^by 1(L.CFR/§71.53. . , '

13. In addition to the requirements; of;Subpart G of 10 CFR Part 71, the packagemust be prepared for shipment, op^ra|ed!,' and maintained in accordance with"Operating Inspection; and Maintenance' Procedure No. CSK-003, Rev. 0," includedin the Westinghouse Electric Corporation supplement dated April 14, 1992.



129

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NRC FORM 618A(3-96)



REFERENCES

Westinghouse Electric Corporation application dated August 7, 1981.

General Electric Company supplement dated: October 1, 1981.

Babcock and Wilcox Company supplements dated: March 8, 1982; and January 10, 1985.

Department of Energy, Division of Naval Reactors, supplements dated: April 22, andJuly 8, 1983; and March 5, 1984.

Department of Energy, Chicago Operations Office, supplement dated: April 15, 1983.

Department of Energy, Washington, DC, supplement dated: June 6, 1988.

Westinghouse Electric Corporation supplement dated: .April 14, 1992.•.. V


o?^ 5

Date: *

'^ Win 1 i am JD/~:T,ravers, Di rector, .Spent Fue'&Rroject Office"dffice^flNuclear Material Safety

d Safeguards';

y. • •

130

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a^^NRC FORM 618(3-96)10CFR71




6406

b. REVISION NUMBER




4

2. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item S below, meets the applicable safety standards set forth in Title 10,Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."





U.S. Energy Research and DevelopmentAdministration application datedJuly 19, 1977, as supplemented.


4. CONDITIONS " ' '•


5.

(a) Packaging

(1) Model No.: ,None specified ; , ,

(2) Description •.-; : _, . :%'x '•-'-*

Specific packaging?!s.not required. Saflty is independent of packaging.

(b) Contents ' .-, , V § ^ . . ; t , :\>,v*?^ , / J ; ^ ' *.;',

(1) Type and form>ofimatefei^i;; :,,;;;:. -•.; ;:<S^" .-I///-':

Unirradiated fuel aslsembTTes p;f;trie.followiJng types?'•

(i) S5G Fuel Experiment ^s5embly(FEA|^in the Model No. FEA shippingcontainer. "-• ~f//'->l'ky>^'' "c ''r c ; :-' ;

( i i ) S5G Double Fuel Experiment Assembly (DFEA) in the Model No. DFEAshipping container. . "

( i i i ) A1W-3 Removable Uninstrumented Subassembly (RUS) in theModel No. 25.0 shipping container.

(iv) A1W-3 Prototype "A" Module or A1W-3 Shipboard "A" Module in theModel No. 2.7/3.6 shipping container.

(v) Rodded instrumented SIC fuel module in the Model No. 7481E12shipping container.

(vi) SIC fuel module or SIC peripheral assembly in the Model No. SICbird cage shipping container.

(vii) S1W-3 Removable Subassembly (RSA) in the Model No. S1W RSA/MetalBox.

(vi i i ) S5W-2 Removable Subassembly (RSA) in the Model No. S5W RSA/BirdCage.

1 3 1

.wwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwwI 4

B3

3

333

3

3333

33i

33


Page 2 - Cert i f icate No. 6406 - Revision No. 10 - Docket No. 71-6406

5.(b) Contents (Continued)


( ix) S5W-R2/R3 or S5W-2 module in the Model No. S5W New Modulecontainer.

(x) A1W-2/R2 cluster or half cluster in the Model No. 658C shippingcontainer.

(x i ) S3G-2A/2B fuel module in the Model No. 7481E12 or Model No. 9SK218shipping container.

( x i i ) D2W rodded fuel ceT]h)or^nrpdded^ corner type D2W fuel module in aModel No. 658HÂB^shi^pingin^storage container. Rodded type fuelmodule sha-TNTv.ha"v'e a control rod atid^control rod holddown deviceinsta l led. : ' "'"*'; >\

(x i i i ) S7Gomit cell or reactor cell assembly inVa;,.Model No. 658E1ABsh.ippingând storage container, with jshi^ping clamp installed.

(xiv) Advanced Tfi&tiiCore (ATC) welded.^fupîuster or ATC cage assemblyfuel c lus te^ l^Model iNo^ 66tfBg|g)Cl container.

(xv) DIG fuel mo^vftejjfifi a mo!de.lh572Al^^-572Bl shipping container and. m e DQmn\iaKi»n~ciiQis,flc:o'QmK;i-V/--'/«Dtfl5v.55;n o Mnôi No - 573A1 o r 573B1

holddown deviceVeed not \b'e^ i n'smTl ed; |i n; t eW-DTGûe;iftmo'clul e. .>.

(xvi) DlG>RemdtoBXefêJ^^ 573A1 or 573B1

(xvii) PWRto|e 1 ( S e e d V % l S ^ u ™ ^ e d se^fuel assembly or PWRCore 2 (S.eed 1 or 2)vunrodded seed fuelâlssembly, in unspecifiedshippingêb'ntainers. %-!;>

Core 1 (Seed 2i':3-of;4)/unrodded seed fuel subassembly or PWRCore 2 (Seed 1 or 2) urirbddecP seed fuel subassembly, in unspecified

(xv i i i ) PWRCorshipping containers.

(xix) S8G rodded fuel cel l in unspecified shipping container with controlrod holddown device insta l led.

(xx) S5G type unit cel l in a Model No. 658E1AB shipping container.

(xxi) A1W-3 Prototype Peripheral Subassembly or A1W-3 Prototype CenterSubassembly in the Model No. 2.7/3.6 shipping container.

(xx i i ) S7G Partial Fuel Cell Subassembly in a DOT specification (Type 20WC-3) container.

1 3 2

Tll&T^Tll&JgJSUgJgJSUSJSJ^

•i NRC FORM 618A,; (3-96)

; Page 3

SirtiftiAiAiAirtiAi/)*: an Silîiîl aif aYW Mi Ml Ml Ml S4A4/aYaYaYa/! a<! a<la<! aYaYaYaY!s§/aY aYaYaYiiCmCONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION £

»

- Certificate No. 6406 - Revision No. 10 - Docket No. 71-6406

3 5.(b) Contents (Continued)

;i (!)

: (2)

Type and form of material (Continued)

[xxiii) S5G Central Subassembly

(xxiv) S3G-3 Removable Noninstrumented Fuel Assembly (RNFA) inNo. 95K-218 shipping container.

Maximum quant i ty of material per package

(i) One fuel assembly as described in 5 (b ) ( l ) ( i ) , 5(b)( l ) ( i

5 (b) (1) (v i i i ) h 5(b)(?1)(ix)V 5(b)( l ) (x) , 5(b)(1)(xi) , 5(

5(b)( l )(xvi i4) , 5(b)( l)(xix) , 5(b)(.l)(xx), 5(b)(l)(xxii5 (b) ( l ) (xx i i i ) , and 5(b)(l)(xxiv).

( i i ) Two fuel assemblies as described in 5(b)(T)(xv).

( i i i ) Three fue1;::>ssemblies as described;-in C5(b)(l)(xxi).

(c) Transport Index for C r i f f c a l i t y Qpjftvpl >'• ; v 4 ^

Minimum t r a n s p o r t index^tjlbe'shown,,qn. : ' i ^label for nuclear cr^ticî^yxbfitrdi'": , ... .v^t.- - •

si(1)

i (2)

(3)

(4)

(5)

(6)

(7)ii

For the"contfht4#elcrlb:e;d Hn, 5(.b)j(|KYv)ii;5(b) (1 )s(vi),

For the contents^ described in 5(b)CI)(iiiJV-

5(b)(1)(xviii), and; 1 fnijiedîh-5{b^(2)-fi):

For the contents described in5 ( b ) ( l ) ( v i i i ) and l imited in 5 ( b ) ( 2 ) ( i ) :

For the contents described in5 ( b ) ( l ) ( v i i ) and l imited in 5 ( b ) ( 2 ) ( i ) :

For the contents described in5 ( b ) ( l ) ( x v i ) and l imited in 5 ( b ) ( 2 ) ( i ) :

For the contents described in5 ( b ) ( l ) ( i ) and l imited in 5 ( b ) ( 2 ) ( i ) :

For the contents described in5 ( b ) ( l ) ( i i ) and l imited in 5 ( b ) ( 2 ) ( i ) :

1 3 3

i

ii

»

a Model S•«**

b ) ( l ) ( x 1 1 ) , i

) ^

i

i

*•*

•

*•*i•

100 jj*i

62.5 J

\

31.3 J

15.7 «

•

41.7 I

100 Ji*ii

NRC FORM 618A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)



REFERENCES

U.S. Energy Research and Development Administration application dated July 19, 1977.

Supplements: Department of Energy letters G#5868 dated January 4, 1978, withenclosures; #6291 dated July 13, 1979; G#7609 dated September 30,1983; G#C85-0435 dated April 19, 1985; G#C87-8027 datedDecember 23, 1987,; -and G#92r03690 dated September 11, 1992.


Date: ^ 13JSM <t4 r\; "

Wi 11 i am D^Tyavers,' Di rectorivSpent;Fue/;?Prbject Office

Office of Nuclear Material Safety. s and Safeguards

134

SUSJSJSJSUS^

NRC FORM 618(3-96)10 CFR 71




64A1

b. REVISION NUMBER

6


USA/6441/B( )F

d. PAGE NUMBER

1


32. PREAMBLE





Safety Analysis Report for D26 Power UnitShipping Container dated August 4, 1969,as supplemented.

c. DOCKET NUMBER 71-64414, CONDITIONS . .'

This certificate is conditional upon fulfilling the requirementsof 10,,CFR Part 71, as applicable,-and the conditions specified below.

5.

(a)

«i

Packaging

(1) Model No.: D2G;Power Unit

(2) Description ;x , ;/;../

The D2G Power Unit shipping container assembly consists of five mainassemblies; (1) the parrel assembly, (2)?fcK| upper cover, (3) the lowercover, (4) the main shipping skid, and (5)p;the barrel trunnion supports.To prepare the power uptfShipping container,for'/shipment of a power unit,the container barrel i^rotated\to the.veVtica/l'position, the upper coveris removed and the-power unit is loaded intd-'the" barrel and secured in thecontainer with eight, (8);4shipping studs\,./The'"'upper cover is then installedand the container is rotatecl|tp<the. horizontal position for shipment. Thecontainer assembly is 31 fee^Aoftg/^nd .8-1/2 feet wide and it is attachedto a government owned permanently ••assigned depressed center railroad car;the maximum height above the rails is 13 feet, 10 inches in the shippingconfiguration. The power unit is shipped complete with design control rodsand mechanisms installed. .

135

7^/!fLgQIL^

3

s

1«

S

3

M

£3M

3

£

M

3

£33

3

NRC FORM 618A(3-96)



5.(a)(2) Description (continued)

The closure head in a Type A and Type B power unit contains an integralbolting flange. This type of power unit is retained in the container bymeans of eight shipping bolts which clamp the power unit to the barrelupper flange of the shipping container. The control rods in a Type A or Bpower unit are restrained in the power unit by means of control rod hold-down latch pawls located in the upper control rod drive mechanism. TheType C, D, or E power unit is also retained in the container by means ofeight shipping bolts but because the closure heads on these power units donot include a bolting flange, a special shipping ring is used to clamp theclosure head and core cartridge assembly to the barrel upper flange of theshipping container. The control rods in a Type C, D, or E power unit arerestrained in the power unit by means pf rebound and outmotion latcheslocated in the latching;po.Ktionjbfihe; control rod drive mechanisms. Thecontainer assembly%eighs about 100,000 "poiinds. empty and about 270,000pounds loaded. x;>' "'';, >,

(3) Drawings <ff^" '••--'..

The packaging isCcSnsjtructed in accordance w-itpBalclwin-Lima-HamiltonCorporation Drawi%lNo^s.. R-126361, Rev./EfeanidR-126347, Rev. K, andWestinghpuse Electr^c^Corporatiori-Drawing^Nos. 955F632, Rev. 5, and972D940,.Rev. 5. i # P : ? ;. " M - \ ' ^^,M .-.',.

(b) Contents

(1) Type and• .•- ' ' .^Y?£«?''

Unirradia^ed enir JiejEr u) ^^ Type A, B, C,D, or E power unftsfcojr»|Tsti;ng^ unirradiated fuelassemblies c losure heafr, me|fian:||(ns\ and associated hardware, with alldesign control"<rods and mecn^hp||^hstal.Ted. ,F..\':.>'

(c)


One power unit as described in 5,(b)(l).

Transport Index for Criticality Control

Minimum transport index to be shownon label for nuclear criticality control: 100


136

NRCFORM618A(3-96)



REFERENCES

Safety Analysis Report for D2G Power Unit Shipping Container, 0NP-74252-13 datedAugust 4, 1969.

Supplements: Bettis Atomic Power Laboratory letters WAPD-DP(CH)-1252, dated November30, 1973; WAPD-DP(CH)-1466, dated October 18, 1974; Knolls Atomic Power Laboratoryletter C6N 85542-250, dated February 5, 1981; and Naval Reactors letterNR:RR:ESSNIDER G#92-03731, dated October 7, 1992.



and Safeguards

Date:

v'; *'

- ""J

!k137

^^ssjgiJsyjEU^j^^iy^i^Ti^j^^?^^

wNRC FORM 618(3-96)10CFR71



. a. CERTIFICATE NUMBER b. REVISION NUMBER




2

1. PREAMBLE



d. ISSUED TO (Name and Address)

United States Enrichment Corp.2 Democracy Center6903 Rockledge DriveBethesda, MD 20817


Safety Analysis Report on the "Paducah Tiger"Protective Overpack for 10-Ton Cylinders ofUranium Hexafluoride, Report No. KY-665, June 16,1975, and Supplement 1, dated May 20, 1977, assupplemented.

c. DOCKET NUMBER 71-65534. CONDITIONS

This certificate is conditional upon fulfilling the requirements of I0.CFR Part 71, as applicatle;,and the conditions specified below.

(a) Packaging

(1)

(2)

Model No.:^PVducah Tiger / / • •

Descri ptrion<.•?

A protective ovefâ&k which jD^QYides/impailtând thermal resistance forthe Model No. 48X|^ônj cyHfi|en. / t h f f i n d e r i & J welded steel, andis 48 inches in d t l p j ^ f , 124 "inphe4 T;al#5f and has a'"5/8-inch thick wall.The cylinder has a^#'./9vft'lfcV-oJume|/

)irftil!is rated aiÔO psig servicepressure. Thejgroti,e^|;1^joverpack.rh'a;f|oSeral/l/dimens;ions ofapprox.i,mately^l^ im^M^T\Tne\i^^J2 M}îfes. j]ie overpack consistsof two "parts ,"?&ô.dyx1fn-e^ and; secured by four,-3/8-irich ra^|l*%peg|jhtf6|'!syjja^xeight^l'-3/4-^(ih guide pins, f i t tedi th S/^înch hFigfigstkeri'g.th, .atc:h^p.T.its f.'|he clos«dr assembled overpackonsists^pfan ovuter4y8^0#^<i^sliieiFbacked'Jnf both long sides top

1 /withwith S/^înch hFigfigstkerig.th,^.atc:h^p.T.its^f.|he clos«dr assembled overpackconsists^pfân ovuter4y8-^0#^<i^sliieiFbacked'Jnf both long sides, topand bottont'by^two, lO-^gaugi^fa^nlesSwSteel breakaway plates. The valveend is prote'Gted b / 8 i ' 5 % t i l ipand bottontby^two, lOgaugi^fa^nlesSwSteel breakaway plates.end is prote'jGt,ed by a 3/8-ine'5%tainles"s' steeiNspreakaway plate. Acentrally located 3/16-inch steel shell, 60J1n"ches in diameter x 128inches long is separated from the outer,shell'by f i re retardantpolyurethane foam. .'Thev.cyl \nder J^,held in the overpack by rubber shockisolators. Four mild' steel "brackets are provided on the body forl i f t i n g . Four, 2-inch bolts are used in conjunction with the ISO cornerf i t t ings for tie-down. The maximum gross weight of the package is37,500 pounds.

(3) Drawings

The Paducah Tiger overpack is constructed in accordance with MartinMarietta Energy Systems, Inc., Drawing Nos. M-1209-NRC-1, Rev. 0;M-1209-NRC-2, Rev. 0; and M-1209-NRC-3, Rev. 0.

1 3 8

NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION

<3?&ge 2 - Certificate No. 6553 - Revision 9 - Docket No. 71-6553

5.(b) Contents

(1) Type and form of materialSolid uranium hexafluoride (UF6) at not more than 4.5 w/o U-235 isotopeenrichment, and an H/U ratio of no more than 0.088.

(2) Maximum quantity of material per package.

The maximum weight of UF6 not to exceed 21,030 pounds (9,540 kg). Themaximum U-235 content not to exceed 640 pounds (290 kg).

(3) Transport Index for Criticality Control

Minimum transport index to be shown onlabel for nuclear critical/)ty. control: 0.4

6. Each Model No. 48X cylinder,must be inspected; tested, maintained, assembled,and used in accordance-with American National Standards Institute (ANSI)N14.1-1990. The cylinders must be designed and fabricated in accordance withANSI N14.1-1990,or. an earlier version of ANSI N14.f in/effect at the time offabrication. The,cylinders must be fabricated in accordance with Section VIII,Division I, of;the American Society of MechanicalÊjigineers (ASME) Boiler andPressure VesseJI'Code and-must be ASME Code stamped'.

/ v v%t": X - ' • / ^ ' : ,'?'-•7. In addition to~ the requjrernents of^Subpart ,G£oj|;10 CFR Part 71, each package

shall be maintained, re^jauikedf operated andJpr^pared for shipment in accordancewith Paducah Gaseous, Dif,f4jônNPlarititStaadard,i)Verating ProcedureCP4-CU-CH6423,; Rev.. ^.datedl^February 9,v,p§6jfand/UnitedCorporati on • siippl eme,n,t| datelli^'ayj/^^-iggB^j^" /•/•;/}',•*

Use of Model No-. 48A¥eyH'njlder;S^ls..npt!iauth,orized^v ^

9. Use of Model Nb;:'"'i8X cy^'fnd^rs eT^fif^-285'sêel is/no',t authorized.

10. The package authdfêd by this cent\i/ilfcate is "hereby \approved for use under thegeneral license provisions of 10 CFR §71.12. < - W /

11. Expiration date: November\30i:. 1998* .-.,- <'X

REFERENCES

Safety Analysis Report on the "Paducah Tiger" Protective Overpack for 10-TonCylinders of Uranium Hexafluoride, Union Carbide Corporation Report No. KY-665, June16, 1975, and Supplement 1, May 20, 1977.

Supplements dated: June 10 and 14, 1988; July 1, 1993; August 15, 1994;March 29, 1995; March 28, 1996 (GDP 96-0061 and 0062); and May 29, 1996.

FOR THE U.S. NUCLEARJ£GU4rA-T0RY COMMISSION


and SafeguardsDate: ^ \ ZV [^

139





6568

b. REVISION NUMBER


USA/6568/A

d. PAGE NUMBER


4. . PREAMBLE




Tennessee Valley Authority1101 Market StreetChattanooga, TN 37402


Tennessee Valley Authority applicationdated August 16, 1976, as supplemented.

c. DOCKET NUMBER 71~6568

4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10;GFR Eart 71, as-applicable,'and the conditions specified below.

- / / • • - .

(a) Packaging |<

(1) Model No Ij;)

(2) Description

falfin ,sffape 93 \ i f fc^ ' long and;j32.5 inches iniHfha^Sî/înrhiE»irafh?ir.k. is encased within t\

The cask' is _ , . . , - . , . . , .—^ , ,diameter. Lezidîî'dihgr'S^^^MochfelSKick,, is encased within theinner-and oiA|V!£te§^s^ a laminated steel basepi ateâssembTy/if Jti&c€oyjefclisflSfsf&ll^ptatefassembly-'secured to the topflange by 36^|te^>boiaf.;; I r f c ^ l ^ f thel^pjof the:cask is a partiallength.steel s^|â^^2ni]^c^;t|J3()q.k_nes^J'îlicone;;0-rings provide sealsat the top, cove$v!fnj^-a't^ container is right circularsteel cylinder w'fth~ a^cap,a"E|ty|j!'f\\150'"cU ft . The,total weight, whenloaded, is,approximately"

- *z(3) Drawings

The packaging is constructed 'in accordance with the following ATCOR Inc.Drawing Nos.: 0568-B-0005, Rev. Ht 0568-C-0008, Rev. E; 05268-B-0010,Rev. E; 0568-B-0016, Rev. D; 0568-B-0018, Rev. A; 0568-B-0025; and0568-R-0001, Rev. 0.

1 4 0

aNRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION M(3-96) "»


5. (b) Contents


Process solids, either dewatered, solid, or solidified waste, insealed containers, and limited to the following:

(i) Materials in which the radioactivity is essentially uniformlydistributed and in which the estimated average concentrationper gram of contents does not exceed:

0.0001 millicurie of radionuclides for which the A2 quantityin Appendix A of 10 CFR Part 71 is not more than 0.05 curie;

0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 0.05 curie, but notmore than 1 curie; or

0.3 millicurie of radionuclides for which the Ag quantity inAppendix A of 10 CFR Part 71 is more than 1 curie.

(ii) Objects of nonradioactive material externally contaminatedwith radioactive material, provided that the radioactivematerial is not readily dispersible and the surfacecontamination, when^averaged\oyer an area of 1 square meter,does. notVexjceed 0.0001 mi 111 effrie (220,000 disintegrationsper!'mjnute) per square centimeter of radionuclides for whichthe A, quantity in Appendix-A of 10 CFR Part 71 is not morethan 0lO5 curies or:0.001 millicurie(2,200,000r disintegrations per minute) per square centimeter

\ for pth'en3radiqnuelides; i

(2) Maximumtquantity of materjia] per package

Greater than Type A quantity of radioactive material with theweight of the package contents and secondary containers notexceeding 12,500 pounds.

1 4 1



6. (a) For any package containing water and/or organic substances which couldradiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package suchthat the following criteria are met over a period of time that is twicethe expected shipment time:

(1) The hydrogen generated must be limited to a molar quantity thatwould be no more than 5% by volume (or equivalent limits for otherinflammable gases) of the secondary container gas void if presentat STP (i.e., no more than 0.063 g-moles/ft3 at 14.7 psia and70*F); or

(2) The secondary container and cask cavity must be inerted with adiluent to assure that oxygen must be limited to 5% by volume inthose portions of the'package which could have a hydrogenconcentration greater than 5%.

For any package delivered to a carrier for transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for. gas generation is made. Shipment period begins whenthe package is prepared (sealed) and must,be"completed within twice theexpected shipment timeV '7'•?</'''/'

(b) For any package sh^ejdvWithYn:--iO/days-4^reparatio,n, or within 10 daysafter venting of diymsVor other, secoridapyl^cpntainers, the determinationin (a) above need no|"b^made^ and thesjt|iie restriction in (a) above doesnot apply. •Ko; ^"^P'-V • -- -:^<*-'£0 .'••/•/.

7. In addition to the requj^eriientsfof Subpart. GI of ICTCFR Part 71:

(a) Each package must;berfaifiWinWivin aceorciance with; Reactor Cleanup Caski T dMaintenance Program in the siipp^ment^'dated February 20, 1991.

(b) The package must be prepared for shipment and operated in accordance withthe Reactor Cleanup Cask Operating Procedure :in the supplement datedFebruary 20, 1991. > •. ' :'

8. The package authorized by this certificate must be transported on a motorvehicle, railroad car, aircraft, inland water craft, or hold or deck of aseagoing vessel assigned for sole use of the licensee.

s 9. Fabrication of additional packagings is not authorized.

10. The package authorized for use by this certificate is hereby approved for usepgunder the general provisions of 10 CFR §71.12.

142

'WWWWj

8BS

NRCFORM618A(3-96)

CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION


11. Expiration date: April 1, 1999. This certificate is not renewable.

REFERENCES

Tennessee Valley Authority application dated August 16, 1976.

Supplements dated: October 8, 1976; October 5, 1979; October 23, 1980;February 20, 1991; February 29, 1996.


Date:

William D. Trayers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material

Safety and Safeguards

1 4 3

BFNRC FORM 618(3-96)10 CFR 71





23




32. PREAMBLE




Scientific Ecology Group, Inc.1560 Bear Creek Rd.Oak Ridge, TN 37831-2530


Scientific Ecology Group, Inc.application dated December 27, 1990,as supplemented.


4.CONDITIONS ,. ., ,. ' , .This certificate is conditional upon fulfilling the requirements' of 10 CfiR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model No.:"<£-_82B

(2) Description \>-

annulus=.cask fabricated inThe packaging cons|ts|£j.pf ^ j ^the form/of a righit|:ci;rcular cyli'hder ^ndll'hree different types of innercontainers. The sêfded,caskYAclosedll^pne end an'C'a l i d closure at the

25j^ncgai^;n;diameter frjM^S inches in<h'eight. The caskof lead

| ^ u r ; s ^ .ffange connecting thetwo shells. Tfreêask outer shell1 tiisurrouhde'd by.atone-inch layer ofinsulating mater?al.v nfl-"canned,.in- llVgauge^steel. r>. *

The lid, sealed by a siTicqne^jftJitâsket, is bolted to the cask body. Acylindrical shield plug is TbCciteH in the cen£eV'bf the cask lid and issealed by a si'licpne flat gasket. Lifting,and"t'ie-down devices areattached to the cask body. Impact skirts, consisting of removable ringsof shock absorbing foam, are attached to.the ends of the cask.

ii

(3) Drawing

The package is fabricated in accordance with the following ScientificEcology Group, Inc. Drawing No.: STD-02-076, Sheets 1 through 3,Revision 7.

144

NRC FORM 618A(3-96)



5.(b) Contents


Byproduct material consisting of dewatered, solid radioactive waste,including spent ion exchange resins, filter sludges, solidified evaporatorconcentrates, spent filter cartridges, and contaminated or irradiatedsolid materials.


Greater than Type A quantity of byproduct material, which may contain notmore than a Type A quantity of fissile material, provided the fissilematerial does not exceed the limits specified in 10 CFR §71.53. The caskcontents must be contained within one of the following inner containersand limited as follows:"

(a)

(b)

Single disposable cylindrical containers constructed of metal orhigh integrity plastic with tightly fitted covers. A maximum decayheat load of 205 Btu/hr.

Two pallets/with four, 30-gallon drum size containers per pallet.Drums to be constructed, of metal or high integrity plastic with atightly fitted, cover. A maximum.decay heat load of 84 Btu/hr.

1 " T T V(c) One pallet wlihfthree, g a l 1 on idifum size containers. Drums to be

constructed oAinetal or high integrity plastic with tightly fittedcovers. . A/maxitfum^ctecay heat l.oaxfof/liS Btu/hr.

6.(a) For any package containih^water.'and/or organic substances which couldradiolytically.generate ;Ci%bustabTe..g.ases^Vdetermination must be made by testsand measurements or by anal-ysis ,of;fa=-Representative package such that thefollowing criteria ;are met over4'Xpjeir:iod-of..time that-is twice the expectedshipment time: '»\ ,• *•' -

(i) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent, limits for other inflammablegases) of the secondary container gas void if present at STP (i.e., nomore than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

(ii) The secondary container and cask cavity must be inerted with a diluent toassure that oxygen must be limited to 5% by volume in those portions ofthe package which could have a hydrogen concentration greater than 5%.

For any package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination for gasgeneration is made. Shipment period begins when the package is prepared(sealed) and must be completed within twice the expected shipment time.

(b) For any package containing materials with radioactivity concentration notexceeding that for low specific activity material, and shipped within 10 days ofpreparation, or within 10 days after venting of drums or other secondarycontainers, the determination in (a) above need not be made, and the timerestriction in (a) above does not apply.

j



7. The total weight of the package must not exceed 50,000 pounds and the weight ofthe contents (including dunnage, etc.) must not exceed 8,195 pounds.


(a) The package shall be prepared for shipment and operated in accordance withOperating Procedure STD-P-02-024, Rev. 3, in the supplement datedMarch 7, 1996.

(b) The package shall be maintained in accordance with the maintenance programin the supplement dated March 13, 1991.

9. Except for close fitting contents, sufficient dunnage, shoring, and/or bracingmust be utilized to minimize secondary impact of the contents within the cavityunder accident conditions of .transport..;;I..; ,

10. Prior to each shipmen^,Vthe seal on the main cover; and the seal on the shieldplug cover, if opened^ "or if the security seal is broken, must be inspected.

^ The seals must be^replaced if the inspection shows any Visible defects or everyZ 12 months, whichever occurs first.

11. The packaging^must be %ea|cH.ested in accordanceivftth Section 8.2.2 of theThe packaging^must be %ea^t,ested in accordance,i$j;jthapplication. -- ° I ^ C ' - .—•—•.. -'''"vkS? /,V'~1

12. The package authorized b^h^ce r t f f i ca teU^hWeby approved for use under thegeneral provisions of ldf^§.'\§Zl..r2:'.r>it'-.^./<%'sst

13. Expiration date:

Scientific Ecology Gr6up,;Incorporated^ap^n^Mtin-^at'ed December 27, 1990.

Supplements dated: March 13% 1991; and March 7, 1996.,-^ );

FOR'THE''0".iSf NUCLEAB- REGULATORY COMMISSION

Date:

William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear MaterialSafety and Safeguards

^

NRC FORM 6181MB)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES.a.CERTIFICATE NUMBER




1s. TOTAL NUMBER PAGES

32. PREAMBLE

a. This certificate is Issued to certify that the packaging_and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Codeof Federal Regulations.Part 71, "Packaging and Transportation of Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJ3ESIQN OR APPLICATIONa. ISSUED TO (Name end Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Siemens Nuclear Power Corporation2101 Horn Rapids RoadRichland, WA 99352-0130

% %

Advanced Nuclear Fuels Corporation applicationdated October 15, 1990, as supplemented.

u l» t«=. \ ^ ij f,= uc. DOCKET NUMBER * ^ 7 4 / 6 5 8 1

4. CONDITIONS ^ \ J i ^'•^J; ^This certificate Is conditional upon fulfilling.the^requirements of 10 CFR Part 71, as applicable, and the/conditions specified below.

Qfuel Bdr^dje^.-consisting'sof a strongback and~u^|ck;-™oiinê3 t,â^steelôiuter container.ri,).<n |)£2iIj<iofig/ jbe'el separators are bolted(on)taineWis appoîmatel^.43" diameter by 216"M P « ^ - J * u d i n g contents, is 7,400

(a) Packaging (€

(1) Model N o , ^

(2) Descript<rofi

A steel felfippiifuel bun^l|s claf[Minimum 378" t h i |between fuj | |1 ong. The nupounds. v ^

(3) Drawings

The packaging is/.constructed and assembled fhâccordance with:

Jersey Nuclear Company'Dr^tngô.-jV )A

JN-200002, Rev. - ,

and Exxon Nuclear Company, Inc., Drawing Nos.:

XN-NF-303,359, Rev. 2XN-NF-303,360, Rev. 1XN-NF-303,898, Rev. 1XN-300,607, Rev. 1XN-300,609, Rev. 1XN-NF-303,364, Rev. 1

and Siemens Nuclear Power Corporation/Advanced Nuclear Fuels CorporationDrawing No.:

EMF-303,897, Rev. 2

1 4 7

I

t

I

I

iiit

Ii\ijt

NRC FORM 618A(6^3) CONDITIONS (continued)



5.(b) Contents

(1) Type and Form of material

Unirradiated fuel rods consisting of uranium dioxide fuel pel lets clad inzircaloy or stainless steel tubes. Uranium is enriched to a maximum of 5.0w/o in the U-235 isotope. Cladding must have a minimum wall thickness of0.02 inch and a minimum nominal pellet-clad radial gap of 0.003 inch. Themaximum length of the active fuel region is 196 inches. Fuel rods must be inone of the following configurations:

(i) Fuel assemblies consisting of a maximum of 204 fuel rods in a 15 x 15square array with a max'tn m Koto|3&Kfuel rod pitch of 0.563 inch and amaximum assembly c^sjpseetiorr m ^4 |yf jnches square. The fuel rodcladding must JjaW^fh 0D not less than Ck4^6 inch and not greater than0.430 i nch . ^Qp Tuel rod arrangement is asfsjfewn in Figure 11.1 of theapplication

(ii) Fuel assesquare g*»a maxi/nuflf asseicladdjWmust h0.380rtnch. The

ion.

ês consisting of a maximummaximum nominal

section ofnoi-fte&s t

d ariianqiem

( i i i ) Fuel |s?sembwith (mfoimunF £|!emtfcladding mus^f&Ân0.500

, . ' ^ rods in a 17 x 17i tcbAf 0.496 inch and

are. The fuel rod5 inch ajjul not greater thanshown ip^ igure 11.2 of the

Bin a square arrayaare. The fuel rodnot greater than

^ i e r . The rod&4,ui a maximum nominal)t have an 0D not less

con(iv) Any number of ftcontainer^6qnsists o fdiameter o ^ ^ i n c h e s . TheMuWôd claddimthan 0.260 liMj^nd not greater than 0.500*

(2) Maximum quantity of

Total weight of fuel assemblies, or fuel rods and rod containers, not toexceed 3400 pounds, and

(i) For the contents described in 5 (b ) ( l ) ( i ) , 5 ( b ) ( l ) ( i i ) , and 5 (b) ( l ) ( i i1 ) :

Two full length fuel assemblies. Two short fuel assemblies may besubstituted for each full length fuel assembly provided the two shortassemblies are shipped end-to-end and the total fuel length does notexceed the maximum fuel length for a full length assembly.

i i ) For the contents described in 5(b)(1)(iv):

Two rod containers.

1 4 8

^

ft»ft«ftffftgj^

NRC FORM 618A(6^3)






6. Each fuel assembly must be unsheathed or must be enclosed in an unsealedpolyethylene sheath which will not extend beyond the ends of the fuel assemblies.The ends of the sheaths must not be folded or taped in any manner that wouldprevent the flow of liquids into or out of the sheathed fuel assemblies.

7. Hydrogenous shims are not permitted within the fuel assemblies.

8. Separator blocks, shock mountsâ.\accordance with Tables 2 ' ^

clamp assemblies must be in^ $ e application.

The fuel assembly cro^s\s*ection is defined as the rorods on the edge of^t^ assembly.

9.

10. Rods containing gado»ligja or other neutron poison

oh times the number of

11. In addition to requi

(a) The package^shall bethe procedês in Chai

(b) Each packaging s|Chapter

(c) Each packag|Fmj sheapplicationr*\

12.

13. Expiration date: May 31/199,

The package authorlêjj by this cergeneral license prov'fafans of 10 CF

ized but not required.

accordance with

Procedures in

Chapiln* 4.0 of the

apn&ved for use under the

SFEMCES

Advanced Nuclear Fuels Corporation application dated October 15, 1990.

Siemens Nuclear Power Corporation supplements dated September 18, 1991, April 22, 1992,and January 25, 1994.


Date: 3>Lc/«/

William D. Travers1, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

149SÂg&^^




. a. CERTIFICATE NUMBER

6601

b. REVISION NUMBER

25


USA/6601/A

d. PAGE NUMBER

1


42. PREAMBLE






Chem-Nuclear Systems, Inc. applicationdated August 23, 1985, as supplemented.


4.CONDITIONS . . - ; : • 0 . '• , >This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model Nor^-CNS 8-120A

(2) Description " -->>*.*.-

The packaging is%j-steel-encased, ]eadrsfrielded shipping cask whichweighsâpproximaitely; 70,OOO^pounds-whjen^lbaded. The, cask is 73.5 inchesin diameter by 9|Sirfches high, w i th anfe^fective cavity 62 inches indiameter by 75.intheViongJ.;:---Gamina^|fjjSpiing. equivalent to 4.5 inches oflead " - > < • • • * - - - • -

two,thickbolts and a s"i;lico1ie,d?rinci witHin'a recessed groove on the flange of thecask.Shackles are used for liîpg^jWa. packaging anfl;;the lid. lie-down isaccomplished through a sêfF.stru'ct'ureVwhich is not attached to thepackage. The"lid provides 'several threaded and sealed access plugs andthe base has a drain line. C

(3) Drawings ' N'V :'

The package is constructed in accordance with Chem-Nuclear Systems, Inc.Drawing No. 29008-1, Sheet 1 Rev. 2, and Drawing No. 29008-1, Sheet 2,Rev. 2.

1 5 0

NRC FORM 618A(3-96)



5. (b) Contents


Process solids, either dewatered, solid, or solidified, or solidreactor components, in secondary containers, and limited to thefol1owi ng:



0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie, butnot more than 1 curie; or

0.3 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 1 curie;

(ii) Objects of nonrad.ioactive material externally contaminatedwith^radioactive material^ provided that the radioactivematerial is not readilydispersible and the surfacecontamination, when averaged, over an area of 1 square meter,does ntrtrexceed 0.0001, milTi curie (220,000 disintegrations per' mfn'ute) fper' square centimeter,/pf/radionucl ides for which theA2 quantity;in Appendix A of, 10.CFR part 71 is not more than0:05 curie,: or p.001 millicurie (2,200,000 disintegrations perminute) pef square.centimeter for other radionuclides.

(2) Maximum quantity-of material per package

Greater than Type A quantity of radioactive material, not toexceed<2,000 times a Type A quantity, 40 thermal watts, and 20,000pounds including weight of the contents, secondary container(s)and shoring. The contents-,may include fissile materials providedthe mass limits of 10 CFR §71.53 are not exceeded.

6. Except for close fitting contents, wood shoring must be placed between thesecondary container(s) (or activated components) and the cask cavity toprevent movement during normal conditions of transport.

7. Prior to each shipment, the lid gasket must be inspected. The gasket must bereplaced if inspection shows any defect or every 12 months which ever occursfirst.

8. Prior to each shipment, a determination must be made that closure sealreplacement is current with the seal replacement schedule in Section 8.2.2 ofthe application.

1 5 1



9. The packaging must be leak tested once every 12 months in accordance withSection 8.1.3 of the application.

10. The drain line and access plugs must be appropriately plugged and sealed priorto transport.


(1) The hydrogen generated must be limited to a molar quantity thatwould be no more,than 5%-volume (or equivalent limits for otherinflammable gases); of the;secondary container gas void if presentat STP (i.e.,-no'more than Oi.063'g-moles/ft3 at 14.7 psia and70*F);1dr -v".

(2) The.secondary container and cask cavit^;must be inerted with adiluent to assure that oxygen must be limited to 5% by volume inthose portions of the package which;coQld/have hydrogen greaterthan 5%; <. . ;/';,y

For any package delivered to; a carrier for transport, the secondarycontainer must b£:pV:epared for shipments™ the same manner in whichdetermination for^as; generation is'made. Shipment,period begins whenthe package^ is,prepared; (sealed) ;and\must be completed within twice theexpected shipment timfe.' '"'".'V\..\;^V' u/.'<'

(b) For any package;shipped;with:in;10vdays of preparation, or within 10 daysafter venting of drums'or othersecondary containers, the determinationin (a) above need not be made,^and the time restriction in (a) above doesnot apply. ''•'''"'!'"< '

12. The package authorized by this certificate must"be" transported on a motorvehicle, railroad car, aircraft, inland water craft, or hold or deck of aseagoing vessel assigned for sole use~of the licensee.


(a) Each packaging must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application; and

(b) The package must be operated and prepared for shipment in accordance withthe Operating Procedures of Chapter 7 of the application.



|7K

a"S

SBr

wwao^o^w w> z w w ^ w AQizw

g

NRC FORM 618A(3-96)



REFERENCES

Chem-Nuclear Systems, Inc., application dated August 23, 1985.

Supplements dated: December 30, 1985, January 16, 1991, October 29, 1991,January 7, 1992, and January 29 and March 19, 1996.

Northeast Nuclear Energy Company supplement dated: February 9, 1984.


Date:

William D. travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

153

*

IIIIIIii

NRC FORM 618(8-86)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESI.a. CERTIFICATE NUMBER





2




3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATION "a. ISSUED TO {Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Amersham Corporation40 North AvenueBurlington, MA 01803

Amersham Corporation application datedNovember 27, 1991, as supplemented.

' a DOCKET NUMBER

4. CONDITIONSThis certificate is conditional upon/ulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging ^

(1) Model No.:%"02

(2) Description-

The cask Systemstainless1:a centralClosure _,._-stainless steel

<• s

)WMoo

" * 20".;~T,he cask is a

eequclosure is 'equippe

eljeil^uraniu^shielding. The^drain anj^yent plugs. The cask

is mounted 01^^19" "x 2lUre^p(M[jj^f\stesWskid wi^four , 1/2-inch boltsand a tie-down/system consis^grof^t3bufpfj/2-incJi^dTameter threaded rodswhich connect a e amp ring at We7 top of the caslTto^ channel brackets weldedto the skid. A protective cage constructed of^^T/^-inch square steel tubingand perforated 18 gauge-^teel sheets tack\.welded to the tubular framesurrounds the cask and'nis^boi^tedAt^^he fkid by four, 1/2-inch bolts.Maximum gross weight of the padeaging^is 410 pounds.

154

•- .•:.:.:•-•::"••: •• ^ " f t M ^ K - ^ r - r V , . ..7-;:""-..--1

faftiwreftftftffftgftgftsftft^




(3) Drawings

The cask and other system components are constructed in accordance withTechnical Operations, Inc. Drawing Nos.: 70290, Sheet 1 to 4, Rev. D.

(b) Contents


Metallic iridium 192 sources which meet the requirements of special formradioactive material. __.. ? ,

(2) Maximum quantity, ofpvateri al per package/ ,.?

10,000 curies/v> •/%

(3) Maximum decay heat per package y.%

100

6. The name plate ljius.t be fabrlca|ed\of /material/ cjfaSe of res\sting the fire testof 10 CFR Part 71-, and maintBMfrg/theif^legibiri^* Q

,Part/

pment iTp accordance withthe<aDb,lii:cati ori'i.' Jas! suDb1?emented^f>^

P(b) The package musi mee^tCe^ce"pia^'^e|fs^lj^Maintenan<:e Program, Section

8.0 of the application, asUupp,!:^fn'ted^ $(§& *fO

8. The package authorized^§y^this certificate is hereby approved for use under thegeneral license provisibnsibf 10 CFR §71.12. ^ V ^

9. Expiration date: March 31, 1998. y'> •••/'- -<T V~*

REFERENCES

Amersham Corporation application dated November 27, 1991.

Supplements dated: April 20, December 1, 1992; and March 19 and 26, 1993.


Charles E. MacDonald, ChiefTransportation BranchDivision of Industrial andMedical Nuclear Safety, NMSS

APR 1 1993Date:

155

NRC FORM 618(M6)10 era 71


FOR RADIOACTIVE MATERIALS PACKAGESLa. CERTIFICATE NUMBER

004£b. REVISION NUMBER




2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theappiicablesafety standardsset forth inTitle 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATION 'a. ISSUED TO INcwe and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Safety Analysis Report - Packages SRL 4.5Ton Californium Shipping Cask, DPSPU 74-124-6,December 1974, Rev. 1, March 1976,as? supplemented.

/71-6642'c. DOCKET NUMBER

4. CONDITIONS ^ S^.C "' ' * . - ' ' - 'This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model No.: -14V5-Ton

(2) Description^ ~$^z£-- * [,

f / | h - e l S e S?A c k * i ?%t f ° ' ^ ^L to r , m 1 E ^ 0 # s - .The outer container is ad/4-inch thjek, 61^||^-inC"hX0D|spKec1|c>Jl|§te6l sê^V f i l led 'wi th borated7aw e?ten%-. P°^^^M^^^î l '* i1^'!? l^<; :û ' ' '^^^ll is fitted with nine(9) fusible?;pj:ugs aoU||^|ejitâjHe'||or!|ieh'ef b i ases generated in the WEPmaterial. '^Jpyiinîf^l^conta;^^^^ 4-inch diameterby 6-3/8 inchfes^high rs c^mraVTÎ^^teciîpflie sphere-and surrounded bylead of 2 inches,>1.9 inches a^t i . fs^kHel l thickness/on the bottom, sidesand top, respectively. The containment vessel is .arTintegral part of theouter container, ancTSs held by a 31-1/2-inch long 4-1/2-inch OD tube weldedto a 3/4-inch thick 22-l/2rinch diameter top platV mounted to the outercontainer closure assembly;.- ^Closure of the containment vessel isaccomplished by a flange platWandsleev^ insert assembly. The sleeve is a27-inch long, 4-mch OD tube f i l l ed with lead and water extended polyesterand is gasketed and bolted to the top closure assembly of the container. A22-1/2-inch diameter protective cover bolts to the closure assembly sleeveA hexagonal shaped assembly, approximately 5 feet across the f lats mounts, tothe spherical shell as a base. Four equally spaced l i f t i ng lugs are providedaround the upper hemisphere. The cask gross weight is approximately 9,500pounds.

^


Page 2 - Certificate No. 6642 - Revision-No. 5 - Docket No. 71-6642

(3) Drawings

The SRL 4.5-Ton Californium shipping cask is as described, and is constructedin accordance with E.I. duPont de Nemours Company Drawing Nos.: ST5-15813,Rev. 33; ST5-15814, Rev. 29; ST5-15815, Rev. 0; ST5-15816, Rev. 0; ST5-15817,Rev. 0; and ST5-15818, Rev. 5.

(b) Contents

(1) Type and form

Californium 252, as sealed sou.rcepwhjich^meets the requirements of specialform radioactive material %±.\fi ^ '£ Cs? (( ,? /f

(2) Maximum quantity offma'tferial per package. *^/ yyX

46 curies (85 mg>/ O _

6. Prior to each shi,pment the^WEP shielding space sha-H^bV vented, using the1/4-inch angle valve whrcji^swthen closed. ./'fk^

In addition to ,the requirements! of SoBplHjG ;ofi/&€FR Part

(a) The packag'e^nustOperatingSeptember

(b) The packagedescribed in

8. Use of packaging f'appicated after.

9. ; jy i:

...„ i's \ 1^198!6:f!) i s not^authori zed.

The package authorized^y^this certif icate is hereby<appiroved for use under thegeneral license provisiori's^of 10 CFR §71.12. ¥ ^ V '

10. Expiration date: October 31,

REFERENCES

Safety Analysis Report - Packages SRL 4.5-Ton Californium Shipping Cask, DPSPU71-124-6, December 1974, Revision 1, March 1976.

Supplements dated: September 18, 1991.


OCT 0Date:

Charles E. MacDonald, ChiefTranspor tat ion BranchDiv is ion of Safeguards

and Transpor ta t ion , NMSS

157

* r 8 ^ ^ ^

NRC FORM 618<W6)10 era 71


FOR RADIOACTIVE MATERIALS PACKAGESLa.CERTIFICATE NUMBER



U S A / 6 6 9 7 / B ( )d. PAGE NUMBER

1o. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the appiicabiesafety standards set forth in Title 10, Code



. ISSUED TO (Name end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

U.S. Department of EnergyEH-33Washington, DC 20585

General Electric Company Applicationdated November 29, 1979, as supplemented.


4. CONDITIONSThis certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the. conditions specified below.

(a) Packaging • . . .,

(1) Model,No.: GE-85tiiO;j

(2) Description t r

The packaging.:^a %BeTv>raniurn Shielded shipping cask surrounded bya laminated p^ywppd pmjtectiye-jack'etv^' ';'- :/'.

The shielded ca|k\risf>an>'gprlght ;cir4u;lar cylinder, consisting of an innershell, 2 7:/8 ineh'fe§ I "X '-6H/8-:..indftfes\;*h-TJghX made of l'/8-inch thickstainless,.steel which>is uKro.bn^ed by^l-i3/l6 inches of depleted uraniumand enclosed in a 7-inch 0D/>c tf0^-1/2-inch high x 1/8-inch thick stainlesssteel outer'Shell. : ' W - •"-•

Closure is by means of six, 3/8-inch diameter bolts and a 1/8-inch thickNeoprene rubber gasket between body and lid. The shielded cask ispositioned in a two-piece protective jacket of solid plywood laminationswhich is bolted to a rectangular pallet made of aluminum. The protectivejacket is 15-1/4 inches OD x 20-1/2 inches high and together with thepallet, weighs 80 pounds. The cavity of the shielded cask contains aleak tight, steel inner container. The gross weight of the loaded packageis approximately 285 pounds.

(3) Drawings

The package is constructed in accordance with the following GeneralElectric Company Drawing Nos.: 277E696, Rev. 6; 277E712, Rev. 6;174F482, Rev. 5; 289E795, Rev. 3; 195F169, Rev. 2; 289E796, Rev. 5;161F443, Rev. 5; or 135C5982, Rev. 4; or 106D3830, Rev. 8 with 153C4613,Rev. 1.

158

Sfow



5. (b) Contents


Byproduct material as a liquid or solid within an innercontainer shown in General Electric Drawing Nos. 161F443, Rev. 5;or 135C5982, Rev. 4; or 106D3830, Rev. 8, used with the liner shownin 153C4613, Rev. 1.


Greater than a Type A;, quantity of byproduct material as a solid withthe decay heat;'>lxoad not ;exc.eed/ing,.5O watts.

Byprodtfct<:tfaterial as a liquid is limited to 100 ci of Mo-Tc.

6. Liquids must be^further packaged in a leak t ight polyethylene bottle withinthe inner container. Each polyethylene bottle must, be .sealed and tested inaccordance wri,th Attachment D of General Electr ri:c

rs'letter dated November 29,1979, or Appendix A^-in^he September 3 , 199-r|ÛJp4plemerit.'

7. Prior to each shipment]t|he package %id Neo|fn6tie gasket must be inspected. Thegasket must be replacM;wtVa netf Neôprenejfgas^ket if inspection shows anydefect or*ev,ery twelve^§|0 fmoaffe^whjcheyôccurs f i rs t . , In each shipment,a new Vit6n--0-ring!^musr^be?a,s^Sd to seal-thînrier.container.

8. The inner e6htaine^mustj>evtp^ tightness prior toeach use inâccordajicVw'th ^tta'chm'e'nti ;D;pf General Electr ic 's l e t te r datedNovember 29'^1979,:O]S^^ 3 , 1991, supplement.

9. The radiation dose rate must njoVexceed-1,0.0,0i millirem per hour, at adistance of 3 feet from the surfaî; of*the depleted uranium cask, when thewooden protective jacket is not in place. . ."

' v-/ * : ^

10. In addition to the requirements of Subpart-Gof 10 CFR Part 71:

(a) Each package must be maintained in accordance with the Maintenance Programin the October 4, 1990, and September 3, 1991, supplements; and

(b) Each package shall be prepared for shipment and operated in accordancewith the Operating Procedures in the October 4, 1990, and September 3,1991, supplements.



159

^\jsy&\u&M\m&isM&A/mjG^}j#iimîAf\ii^



REFERENCES

General Electric Company application dated November 29, 1979.

General Electric letter dated February 21, 1985.

DOE supplements dated: February 27, 1985; January 31 and October 4, 1990; andSeptember 3, 1991.


•- "" CharlesJ€.(^Majsponald, ChiefTransportatfbp BranchDivision of Safeguards

and Transportation NMSSV

Date: SEP l 9 1991 ^<£"tJ)

160

NRC FORM 61818-86)10 CFR 71



1.a. CERTIFICATE NUMBER

fi717

b. REVISION NUMBER

Q


I ICAS C 7 1 7 \ P f\l\USA\6717


4- • 4 -PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



a. ISSUED TO (Nairn and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation application datedOctober 10, 1990, as supplemented.

c. DOCKET NUMBER71-671C717

A. CONDITIONS < ^JjThis certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No.:'^6717-B

(2) Description,

sts

top and bottdm,-^!us molded p*of1yuretiijirie'•fffler tcKpos'ition and securethe radiograph^ ofdevice within'tnevdrum. M^ximunTgrbss weight of thepackage not to exceid 100 pounds. Vv'5-"'

The maximum gross weighVofrth,e^secqridary.packaging (device and moldedpolyurethane filler) not to-'exceedT: V ^

i) 65 pounds for the Model Nos.: Century, Century S, Century SA,Century S Universal, Century SA Universal, C-10, 35, 35S and 35SA;

ii) 60 pounds for the Model Nos.: 20V, 40V, 20VS, 40VS and U-110;

iii) 45 pounds for the Model Nos. Pipeliner Model 1, Pipeliner Model 201and Mariner; and

iv) 54.5 pounds for the Model No. MX-IC-100.

(3) Drawings

The overpack must be constructed in accordance with Amersham Corp.Drawing Nos. 93590, Rev. C; 93690, Rev. C; 93790, Rev. D; 93890, Rev.B;and 93990, Rev. C.

161

^



a) Packaging (continued)

4 (3) Drawings (continued)•

The radiographic devices, as secondary packaging, authorized for use in§ the overpack are constructed in accordance with the following Drawingi Nos.:

•

•

i

For the Model No. Century: Gamma Industries Drawing Nos. 821-1001-101,Rev.- dated 7/2/76; and 821-1001-005, Rev. 4;

For the Model Nos. Century S and Century SA: Gamma Industries DrawingB Nos. 821-1001-439A, Rev. A; 821-1001-101, Rev. - dated 7/2/76; anda 821-1001-005, Rev. 4;i* For the Model Nos. Century S Universal and Century SA Universal: Gamma

Industries Drawing No. 821-1001-441A, Rev. - dated 2/15/82; and821-1001-101 Rev. - dated 7/2/76;

For the Model No. C-10: Gamma Industries Drawing Nos. 821-1005-018 Rev.-dated 9/27/93; and 821-1001-101, Rev. - dated 7/2/76;

For the Model Nos. 35 and 35S: Gamma Industries Drawing Nos.821-1001-105, Rev.- dated 9/15/70; and 821-1001-002, Rev. 2C;

For the Model No. 35SA:= Gamma" Industries Drawing Nos. 821-1001-105,Rev. - dated 9/15/70; and 821-1001-003, Rev.' 2C;

For the Model Nos. 20V and 40V:. Gulf Nuclear, Inc., Drawing Nos.1000-51-03, Rev. - dated 12/14/83;:A-31, Sneets 3 & 4, Rev. 1; A-31-21Sheets 1, 2 and 3, Rev. 1; arid A-31-34 Sheet 1 and 2 of 4, Rev. 1.

For the Model Nos. 20VS and 40VS: Gulf Nuclear, Inc. Drawing Nos. A-31Sheets 3 and 4, Rev. 1; A-31-1 Sheet 1, Rev. 1 and Sheet 2, Rev. - dated1/15/83; A-31-12, Rev. - dated 1/4/84; A-31-16, Rev. 2; A-31-18, Rev. 1;A-31-20, Rev. 1; A-31-21 Sheets 1, 2, and 3, Rev. 1; A-31-31 Sheets 1,2and 3, Rev 2; A-31-32, Rev.2; A-31-34 Sheet 1, Rev. 1 and Sheet 2,Rev. - dated 1/11/84; 1000-50-14, Rev. -; and 1000-50-13, Rev. 2;

For the Model No. U-110: Arnersham Corp. Drawing No. 93691, Rev. - dated10/9/90; 93692, Rev. A; and Gulf Nuclear, Inc., Drawing No. A-31-21Sheets 1, 2 and 3, Rev. ],

For the Model No. Pipeliner Model 1: Amersham Corp. Drawing No. 93591,Rev. A; SK 2473, Rev. - dated 4/1/88; and SK 2473-1, Rev. - dated1/21/88; and Gamma Industries Drawing No. 811-1001-287, Rev. 1;

For the Model No. Pipeliner Model 201: Gamma Industries DrawingNos. 821-1001-019B, Rev. 5; and Drawing No. 821-1001-235, Rev. 5;

i

* For the Model No. Mariner: Gamma Industries Drawing Nos. 821-1001-024,Rev. 1; and 821-1001-351, Rev. 1; and

For the Model No. Magnaflux Model MX-IC-100: Magnaflux Corp. DrawingNo. C-211626, Rev. - dated 2/9/78.

__

ffltftffiSFti^^


Page 3 - Certificate No, 6717 - Revision No. 9 - Docket No. 71-6717

Contents


Iridium-192 as sealed sources which meet the requirements of special formradioactive material.


(i) 35 Curies contained in the Model Nos. 35, 35S or 35SA.

(ii) 100 Curies contained in the Model No. MX-IC-100.

(iii) 120 Curies contained in the Model Nos. Century, Century S, CenturySA, Century S Universal, Century SA Universal, Pipeliner Model 1,20V, 20VS or U-110.

(iv) 220 Curies contained in the Model Nos. 40V or 40VS.

(v) 240 Curies contained in the Model Nos. C-10, Pipeliner Model 201 orMariner.

6. The source shall be secured in the shielded position of the radiographicdevice by the shipping plug, source assembly, and locking device. Theshipping plug and source assembly used must be fabricated of materials capableof resisting a 1475°F fire environment for one-half hour and maintaining theirpositioning function. The ball st.bp.Qf the source assembly must engage thelocking device. The flexible cable of the source assembly and shipping plugmust be of sufficient length and diameter to provide.positive positioning ofthe source in the shielded position.


(a) The package must be prepared for shipment and operated in accordance withthe operating procedures in Chapter 7 of the application, assupplemented.

(b) The drum should be assembled without a gasket and with the clamping ringtightened until the maximum gap between the lug nuts is 3/16-inch.

(c) The package must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application.

8. The packaging authorized by this certificate is hereby approved for use underthe general license provisions of 10 CFR §71.12.


163M^ju^^



REFERENCES

Amersham Corporation application dated October 10, 1990.

Supplements dated: December 3, 1990; March 12, April 1, July 18, October 25, andDecember 20, 1991; Hay 14, July 2, September 21 and 27, 1993; May 20, 1994.


Z&4 /v hCass R. Chappel.l, Section LeaderCask Certification SectionStorage and Transport Systems BranchDivision of Industrial andMedical Nuclear Safety, NMSS

JUN 0 8 19341Date:

164

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12


USA/6722/Ad. PAGE NUMBER


„ PREAMBLE

a, This certificate is issued to certify that the packaging and contents described in Item S below, meets the applicable safety standards set forth in Title 10,Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."




Tennessee Valley Authority applicationdated July 9, 1975, as supplemented.

c. DOCKET NUMBER 71—6722

4. CONDITIONS x . / . , . ' ' • *

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71/& applicable; and the conditions specified below.

(a) Packaging

(1)

(2)

Model No.: BS^33-180

Description ^.:£-.rv\^ ., -4>.;/

The shipping cas^sâ, cylin~d}ifcfal ;stee]||eldment with overall dimensionsof 843nches in d$anietef and 97^1/4 lincnies in length".; The effectivecavity is 76-^/2 i ncfiesxin diameter :by?^Fl/4, inches} long. The outershell is fabr4c|ited|p^ôncentrij:^yetf;"cqnîxsting:bf three, one-inchthick;iand l/^-irich tht^K9ca^bH}istj|^ptat^^/The--i.nher half-inch thickshell i.ssepaWajfclHJvfiroiiflihe; onef1n|hv"thidi#|liells .by.a 1/4-inch thickasbestois.sheelfsi The fliajige'isJtHree inche^thickr-with 36 tapped holesand a grobve io(kôm6^te>^;isifi^0mS'-r^ng. The top cover is securedg ^ ^ pto the flange ring '^6^MfeA?:32q^Gra'(le L7 1-1^2-inch bolts. A 10-inch deep steel impact' 1 iliJ^tlHs^mdunted to the*top cover to act as ashock absorber. The cask 1s^m16uhted to a tie^down frame by sixteen, 1-1/4-inch high Strength steel bolts. Other/cask features include a drainline, access port to the inner container(s) and a reinforcing steel shellto protect the cask seaK>Threaded access plugs are installed on the topof the liner. A bottom side drain is also provided. Maximum grossweight is approximately 51,100 pounds.

(3) Drawing

The packaging is constructed in accordance with the following ATCOR Inc.Drawing Nos.: 0568-C-0024, Rev. F; 0568-D-0022, Rev. F; 0568-D-0023,Rev. D; 0568-C-0026, Rev. B.

1 6 5

::wwwwwwwwwwwwwwwwwwwww:rawww:rawwwwai[;NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION

g (3"96>

(a) Contents



Solids or solidified waste, and limited to the following:



0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of .10 CFR Part.71 is more than 0.05 curie, but notmore than 1 curie; or

0.3 millicurie of radionuclides for which the A? quantity inAppendix A of 10 CFR Part 71 is more than 1 curie.

(ii) Objects of nonradioactive material externally contaminatedwith radioactive material, provided that the radioactivemateri-al"is not readily dispeVsible and the surfacecontamination, when-averaged over an area of 1 square meter,does no%iixceed 0.0Q01 millictfKie (220,000-disintegrationsper min tTtei per square centimeter of radionuclides for whichthe^Aj quantity in Appendix A/of 10/CFR Part 71 9s not moretficinf 0.05- curie,; or0:001-:;mil 1 icafire

. (2y2O0^Op.O disintegrations per^minute) per square centimeterfor^ther;cadjonuclidesS ^

(2) Maximum quantity ;of jniatef^Fper'package

Greater than Type A quirit'ity of radioactive material with theweight of the contents (including containers and shoring) limitedto 18,000 pounds- and 20 thermal watts.;

166



6.


(a) For any package containing water and/or organic substances which couldradiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package suchthat the following criteria are met over a period of time that is twicethe expected shipment time:

(1) The hydrogen generated must be limited to a molar quantity thatwould be no more than 5% by volume (or equivalent limits for otherinflammable gases) of the secondary container gas void if presentat STP (i.e., no more than 0.063 g-moles/ft3 at 14.7 psia and 70*F);or

(2) The secondary container and cask cavity must be inerted with adiluent to assure,that oxygen must be limited to 5% by volume inthose portions of the package which could have a hydrogenconcentration greater than 5%.

For any package delivered to a carrier for transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for gas generation is made. Shipment period begins whenthe package is prepared (sealed) and must be completed within twice theexpected shipment titjie

6. (b) For any package shipped within;10 days ofipreparation, or within 10 daysafter venting of drums or other, secondary^containers, the determinationin (a) above need not: be made, and theJtfjne restriction in (a) above doesn o t a p p l y . .--I:1-}; ~^ ..;.•'.';"••' "':-•" .'•.

7. In addition to the requirements/of Subpart G of ,10 CFR Part 71:

(a) The package shall; bV;prep'ared for shipment and operated in accordancewith the operating procedures Jn the supplement dated March 21, 1991.

(b) The package shall be maintained in accordance with the maintenanceprogram in the supplement dated January 17, 1991.

8. Dunnage must be provided in the shipping cask cavity sufficient to preventsignificant movement of the inner container(s) relative to the outer packagingunder normal conditions of transport.

9. Prior to each shipment all threaded pipe plugs in the cask are sealed using anappropriate sealant.

10. The space between the inner container(s) and cask cavity must be dry prior todelivery to a carrier for transport.

11. Prior to each shipment, the package lid seal must be inspected. The seal mustbe replaced with a new silicone 0-ring if inspection shows any defects or everytwelve (12) months, whichever occurs first. After seal replacement the packagemust be leak tested to 1 xlO std cm /sec.

12. All eight (8) lifting shackles must be shrouded by the appropriate covers priorto transport to prevent its use as tie-down devices.


1 6 7I

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8

NRC FORM 618A(3-96)



14. The package authorized by this certificate must be transported on a motorvehicle, railroad car, aircraft, inland water craft, or hold or deck of aseagoing vessel assigned for the sole use of the licensee.



REFERENCES

Tennessee Valley Authority application dated July 9, 1975.

Supplements dated: February 10 49-7,7*,nSeptember..|7J;; ,-19.90; January 17 andMarch 21, 1991, and September.4,, 1992. "' 7 ; .,-.

Date:

,^> fFOR THE U.S. NUCLEAR REGULATORY COMMISSION

^ © > e "l^Pen't Fue' '-Er oject OfficeMff / &,0ft$ce ofsMci ear MaterialNp^;v f-/^td^Sa'fegufds ,

, Director

Safety

r - i . ; i: V*Wf

%x --\;/'"V '^

^•'"V>v'v^v VN

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1 6 8

^NRC FORM 618(M6)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.«. CERTIFICATE NUMBER

6786b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER



PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theappllcablesafety standards set forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATIONa. ISSUED TO IName and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Department of NavyNaval Support Force AntarctiaFPO San Francisco, CA 96601

Aerojet Application dated February 18, 1971,as supplemented.

c. DOCKET NUMBER ' 1 ^ 7 . 8 6

4, C O N D I T I O N S ... '<; • S\ f .This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Mode]/No's.: UR*PJB|8\and URIPS-8B

(2) Description

p g ^ , injches in overallheightj withj'an out | r)^^ i f le|er,^t | l^ ;^ incHes, anfetotal weight ofapprbx'. ljeOOyppunds^Yxthejconipbnen^^ depleted uranium shield(470 j i b s . ) , ^ t b p housiiig^cpyerrbolts^flcessediahd caulked over), anelectrical adaf l to fc^ j !^^ f in guard,stiffened by e^||ftt4irTfbs^6i^h|Cins^ffetsurface. fltje housings are equippedwith l i f t i ng and tieido^MpMces. ,'liTModel Nbr URIPS-SB differs fromModel N0//URIPS-8A in the^%-lecs|mc cortyerter^.'system. The thermoelectricgeneratorinayVbe secured i i i^shipping frame identified in DrawingNo. 1138459, Rev. A. <*%*"

<-7 >-V<

1 6 9

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(3) Drawings

The package is constructed in accordance with the following AerojetCompany Drawing Nos.:

7.

8.

11384411138442, Rev. C11384571139240, Rev. A1139245, Rev. A11392461138459, Rev. A1138443, Rev. B113844411384361138437, Rev.{B1138435 X1138440, ReWA1138453 "~v>"

8-Watt URIPS-8A AssemblyGenerator HousingCooling FinsFin GuardShipping Package URIPS-88-Watt URIPS AssemblyShipping Frame-URIPS-8

oTop ..Poverif "iBdt%m /Cover

Fuel Cap'siDe^Shield Uranfajn^Fuel Liner ^/?%W-2 Shield Plug 4^,-,InsulationCopper Pluc

(b) Contents

(1) Type and form

Strontium 90requirements^g||

(2) Maximu

56,850

In addition to the requirements ofV

(a) The package must be^'p/epared for shipment and operated in accordance withthe operating procedures^rn,,the sunplement^da^ed June 18, 1991.

*"V T^V « f 7 ~VS& V(b) The package must be maintained in 'accordance with the Maintenance procedures

listed in the supplement dated June 18, 1991.

The package authorized by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12.

Expiration date: April 30, 1998.

1 7 0

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REFERENCES

Aerojet Nuclear Systems Company application dated February 18, 1971.

Supplemented by Naval Nuclear Power Unit letter dated: December 10, 1971, and Oak Ridge

National Laboratory dated: December 28, 1972; and February 27 and March 27, 1973.

Department of the Navy application dated: June 8, 1990.

Supplements: Department of the Navy letter 5104 Ser 455/1U59999U8 dated June 18, 1991.

Charles E. MacDonafd^ChiefTransportation Branch „Division of IndustryaT:v|ndMedical Nucle.af5'afet>tNMSS

Date:APR 0 7 1993

171

^

^ ^NRC FORM 618(3-96)10CFR71








6

2. PREAMBLE



L ISSUED TO (Name and Address)

VECTRA Technologies, Inc.6203 San Ignacio Ave., SuiteSan Jose, CA 95119


VECTRA Technologies, Inc., applicationdated March 30, 1995, as supplemented

c. DOCKET NUMBER

4. CONDITIONS ^ |.. / • . . " . - <This certificate is conditional upon fulfilling the requirements'of lO.CFR Part 71, a"s applicable, and the conditions specified below.

• ' ' . V ' '

(a) Packaging <,..<-.'•'

(1) Model No.: iF-300

(2) Description

A sta inless steel ififtc'ajsecf, depleted u r a t i ^^ shielded cask. The cask iscylindrical in sha|e^564înch^|vVlin dfamet¥n, and a maximum of 210-incheslong with maximum da^t%Pdimensfo'ns^bJ^î/2^nches r;in diameter by180-1/4-incheVlohg>;7fhtelding i s ! p o ^ i d . ^ b y ^ inches of depleteduranium, 2-l/8<inches ;of4:sta!i'n:le|ss;êT, ;afn^-a'mininium of 4-1/2 inches(550 gallons) of,a : wate^ dthyteneig^col mixture. •-/-..

Two closure headsrafe'j)rovidecifvfo^. i£h%^h}pment of "BWR and PWR fuelassemblies. The heads -:are?Jf4lf|a3linl,ess isteel fb^gings and end plateswhich encase the 3-inch thie|ldepletedvuraniumishielding. Either closurehead may be used for packagingvsolid irradiated/hardware.

The closure heads are secured ;to the cask body by means of 32, 1-3/4 inchstuds and nuts. The cask is sealed/with a metallic ring gasket.

The cavity is penetrated by a vent l ine at the top and a drain l ine at thebottom. These l ines are sealed by bellows stainless steel globe valves andvalved quick-disconnect couplings. Stainless steel pipe caps may be usedin l ieu of the quick-disconnect couplings. The vent l ine is also equippedwith a 350-400 psig rated rupture disk. All valves are housed in protectedboxes on the cask exterior .

1 7 2

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NRC FORM 618A(3-96)



5.(a) Packaging (continued)


Neutron shielding is provided by a liquid-filled, thin-walled, corrugatedcontainment on the cask exterior. This cylindrical structure is separatedinto two longitudinal compartments, each equipped with two expansion tanks,fill and.relief valves. The fill line from each compartment is terminatedby a stainless steel globe valve in a protected box (separate from cavityboxes) on the cask exterior. The stainless steel globe valves may bereplaced by stainless steel blind flanges. The vent line from eachcompartment goes to an expansion tank which is provided with a pressurerelief valve set at 200 psig. :

The cask has three; types of fuel baskets which can be interchanged toaccommodate various fuels. The PWR basket holds seven assemblies, theunchannelled BWR basket holds eighteen assemblies, and the channelled BWRbasket holds, seventeen assemblies. The channelled and unchannelled BWRfuel baskets may be provided with supplementary shielding (depleteduranium) near the cask closure.

The cask is shippeUJio.rizontally with the. bottom supported in a tippingcradle between two^pedestaW and the upper end resting in a semi-circularsaddle; the upper Sendfis pinned to the saddle. The cask supports arewelded to the franifjirg ?pf a 37-1/2-foot 3 ojrig by 8-foot wide structural steelskid. The skjd.jmay 0so have installed,, ori it an auxiliary cooling system,consisting of twddiesieT.engines dr^vihg'two blowers which dischargecooling air to; the corrugated surface of the cask via common ducting.Neither installationVnor/operation of all or part of this auxiliary coolingsystem is a requirejneiitt' of this :package approval.

The entire cask and cooiing^system.is covered by a retractable aluminumenclosure. Access to the enclosure is via locked panels in the side and alocked door intone end. Although the Model .No..'IF-300 cask can betransported for short distances on the highway, its principal mode oftransportation is by railroad.

The gross weight of the cask is approximately 140,000 pounds,other external components weigh approximately 45,000 pounds.

The skid and

(3) Drawings

The Model No. IF-300 shipping cask is described by the following GeneralElectric Company Drawing Nos.: 159C5238 - Sheet 1, Rev. 9; Sheet 2, Rev.3; Sheet 3, Rev. 9; Sheet 4, Rev. 8; Sheet 5, Rev. 5; Sheet 6, Rev. 8;Sheet 7, Rev. 4; Sheet 8, Rev. 5; Sheet 9, Rev. 8; Sheet 10, Rev. 5; andSheet 11, Rev. 2, and Pacific Nuclear Systems, Inc. Drawing Nos.:420-11-3000, Sheets 1 through 9, Rev. 1; 420-11-3001, Sheet 1, Rev. 1;420-11-3002, Sheets 1 and 2, Rev. 1; 420-11-3003, Sheets 1 and 2, Rev. 1;420-11-3004, Sheets 1 and 2, Rev. 1; 420-11-3005, Sheets 1 and 2, Rev. 1;and 420-11-3006, Sheet 1, Rev 1.

i

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5.(a)(4) Basic Components

The basic components of the Model No. IF-300 shipping cask that areimportant to nuclear safety are listed in Section IX, Table IX-1.

(b) Contents


(i) Irradiated PWR and BWR uranium oxide fuel assemblies. PWR assembliesmay be shipped with or without control rods. Partial fuelassemblies, that is, assemblies from which fuel pins are missing,must not be shipped unless dummy fuel pins are used to displace anamount of water equal to: that displaced by the original pins. Thespecific power of. each fuel assembly must not exceed 40 kW/kgU andthe burnup of each fuel assembly must not exceed 35,000 MWD/MTU. Theminimum cooling time of each assembly must be no less than 120 days.Prior to irradiation, the BWR and PWR fuel assemblies must have thefollowing dimensions, and specifications: '-',•••

Group I fuel assemblies

$\ PWR : ; BWR

Fuel form i i - J \ •' -.-.-•Clad^U62Jpelle.ts Clad U02 pellets

''.:•••-• •;•: ."•';? ^ - i J l x o K , S S -':'-' Zr or SS

M a x i m u m initial U ^ ,; .;••-.v<-content/assemblyy kg; ; ':> ;'4

Maximum initial U-235 </;yss!< •;•%;• * w

enrichment, w/o "'•'i-i&>i

Maximum bundle crosssection, in \

Fuel pin array

Fuel diameter, in

Fuel pin pitch range,in

Maximum active fuellength, in

:r.J\f 465

4;0

\l 8.75

14x14/15x15

0.380-0.460

0.502-0.582

145

198

4.0

5 « 7 5

7x7

0.500-0.600

0.647-0.809

146

1 7 4

NRC FORM 618A(3-96)




Group II fuel assemblies

Fuel form

Cladding material

Maximum initial Ucontent/assembly, kg

Maximum initial U-235enrichment, w/o

Maximum bundle crosssection,,in

Fuel pin array

Fuel diamete^-.^in ... _

Fuel pin pitch, rjange, in

PWR BWR

Clad U02 pellets Clad U02 pellets

Zr or SS Zr or SS

Maximum ^lengthj in

475

4.0

8.75

.16x16/17x17

0.376^0.400

ir0,507

, 150

198

4.0

5.75

8x8

0.475-0.505

0.630-0.645

150

(ii) Solid irradlated^hardwajre, which-may. include fissile material,provided the quantity/bf#issile material does not exceed a Type Aquantity and does'noi^xie^d; the,mass limits of 10 CFR §71.53. Asneeded.,-, appropriate component spacers must be used when loadingirradiated,hardware into the cask cavity to limit movement of thecontents during,accident conditions of transport. Use of a steelliner is authorized provided: •. (1) its outside dimensions areapproximately those of ,the cask cavity inside dimensions, (2)constructed of single thickness of steel plate with full penetrationwelds, (3) thickness of steel plate does not exceed one inch, and (4)the liner is provided with a drain and vent to insure water removal.


(i) Maximum decay heat per package not to exceed 40,000 Btu/hr. Maximum5,725 Btu/hr/PWR assembly. Maximum 2,225 Btu/hr/BWR assembly.

(ii) Seven PWR fuel assemblies, seventeen channelled BWR assemblies, oreighteen unchannelled BWR fuel assemblies.

(iii) Above fuel assemblies to be contained in their respective fuelbaskets as shown in 6E Drawing No. 159C5238 - Sheet 6, Rev. 8, orPNSI Drawing No. 420-111-3000, Sheets 1 through 9, Rev. 1.

1 7 5

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NRCFORM618A CONDITIONS (continued) U . S . NUCLEAR REGULATORY COMMISSION(3-96)


5. (c) Unloaded package - contents and maximum quantity of material

Greater than a Type A quantity of residual radioactive material consistingof mixed-fission and activation products adhering to interior cavity andfuel basket surfaces.

(d) Transport Index for Criticality Control


6. The end of life total calculated residual gas that could become available fromthe fuel pins must not exceed 0.50 Ibjnoles for content 5.(b).

7. The maximum gross weight of the cavity contents must not exceed 21,000 pounds.

8. For the shipment of irradiated fuel assemblies/ the,cask cavity (containmentvessel) must be promptly inerted following removal.of the water from thecavity. The cask^cavity must be purged at least three times with argon,nitrogen, or helium.- Each" purge volume mustjbe\equivalent to or greater thanthe cask cavity voluifte^ After the finalpurge, -the cavity must be promptly

atm pressure.<. • ' • ' ' ' . • :

9. Known or suspected f-atjfa'id fuel assembliesr5(w;ds) and fuel with cladding defectsgreater than pin holesland hairl ine crackîfTre not authorized.

Group I fuel assembês^hi-ph. are 15x|5; jtype,^R;{fuel assemblitmaximum in i t i a l ^ô'nsie^t;''of;439-:kilogra"ms per-Assembly and a rof 60 months may Ifave;#. maximum, asisembTy burnup of 45,000 MWD/MTU.

11

12. The cask contents shall be so limited that under normal conditions prior totransport, 62 times thejieutron dose rate plus 6.3 times the gamma dose ratewill not exceed 560 mrem/hr"at a distance of six feet from the side of the cask(ten feet from the cask center-line).

13. The neutron shielding tanks must be filled with approximately a 50/50 volumepercent mixture of ethylene glycol and water during the months of Octoberthrough May.

14. Replacement globe valves other than the valve specified on Drawing No.159C5238-Sheet 4, Rev. 8, must be tested as stated in Subsection 6.6.3.2 of theapplication.

1 7 6

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15. The packaging must be maintained in accordance with the requirements of .Subsection 10.2 of the application. During inactive periods, the maintenanceand testing frequency may be disregarded provided that the package is broughtinto full compliance with these requirements prior to the next use of thepackage.

16. The cask cavity must be equipped with a rupture disk device with a burstpressure within the range of 350-400 psig (443°F) including all tolerances.

17. The uranium shielding material must be separated from all steel surfaces with aminimum copper thickness of 4-mils, except that the stud bolts attaching theshield assemblies to top of the unchannelled BWR basket must be coated with aminimum of %-mil of copper.

18. A shutoff valve must not be installed between each neutron shield tank and itsrespective thermal {expansion tank.

19. The cask may be, wrapped with reinforced plastic during shipment, provided thatthe decay heat of the contents does not exceed 1.5 KW. The reinforced plasticused to wrap the cask-must not be greater than,.0.015 inches thick or have athermal conductivity ]"ess than 0.0242 Btu/hr-ft-T. The reinforced plasticwrapping cannbt be used'as the cask surface for purposes of complying with 10CFR §71.87. _ }•&•?;.•;.;, -•< ' • -zf-

20. The package author jzedfSyHhe, certificate isshereby approved for use under thegeneral license prbyasiqns^pfiilO CFR §71.12.

21. Expiration date: Septejnbe>^3b,, 2000. : .. v

• \ ^ ; y '% - ; • • ; • • ; / ; • • • • ' <

-*:''''Vj'\ REFERENCES

VECTRA Technologies, Inc.\ application dated March 30, 1995.

VECTRA Technologies, Inc., supplements dated: April 27, and August 18, 1995.«i

Date • < t l



and Safeguards

111 i

•s*rwriy/virrre7\wv»<Nwr>wr^ply^yi^w^wn»r>W'^^

NBC FORM 618(8-85)10CFR71

CERTIFICATE OF COMPUANCEFOR RADIOACTIVE MATERIALS PACKAGES






PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theappllcablesafetystandardsset forth inTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DESIGN OR APPLICATIONa. ISSUED TO (Name end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Tech/Ops Inc. applicationdated March 31, 1986, as supplemented.

' c. DOCKET NUMBER

4. CONDITIONSthetrequire

CONDITIONS <K \ J <3Qj <This certificate is conditional upon fulfillingtthetrequirements of 10 CFR Part 71, as applicable, and the'conditions specified below.

(a) Packaging

(1) Mod£U,No.:

(2) Description\-

A r?adsteel

uraniumdeple^dassembles. ..._ . . „ _threaded/hglddown caps

(3) Drawings

(b)

welded 10-gauge stainless11" etgrig. The source

l a t e ^ v e r and a depletedtionflPin the center of the

r'psules|Sn,cf the source cable'd by lodcing assemblies and

iscjtpfjroximately 65 pounds.

The packaging is^cbnsJbfcucted iriyac-cp2dance with Tech/Ops, Inc.Drawing Nos. AI500SU90f Slre|tsp£through 7, Rev. C or AI500SU90,Sheets 1 through 3, Rev. - ; AI500SU91, Sheets 1 and 2; AI500SU92;and optional Drawing No. AI500SU93, Rev. A.

The threaded holddown caps used to secure the source cable assemblieswithin the titanium tubing shall be fabricated in accordance withTech/Ops, Inc. Drawing No. SK2334-2, Rev. D.

Contents


Iridium 192 as a sealed source which meets the requirements of specialform radioactive material.


120 curies

178

NRC FORM 618A(6-83)




6. The source shall be positioned within the titanium tubing by a source cableassembly which meets the parameters shown in Tech/Ops, Inc. Drawing No. 42402-1,Sheets 1 through 3, Rev. K.

7. The name plate shall be fabricated of materials capable of resisting the firetests of 10 CFR Part 71 and maintaining i ts legibility.


(a) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures of Chapter 7 of the application, as supplemented.

(b) The packaging must meet the ftccei;Chapter 8 of the appli<^tjpinj\s

?sts and Maintenance Program offti

9. The package authorized ( ^ t h i s c e r t i f i c a t e i s herebyvap)*roved for u s e u n ( jer thegeneral l i cense prov^J&ons of 10 CFR §71.12. "

10. Expiration da t e : August 31 , 2000.

Tech/Ops, Inc. appl icat ion

Amersham Corporatioirisuppl August 13, 1990.

cTORY COMMISSION

Date:SEP 0 3 1995

itfppWl, Sect^n Chief3erti n cati olf jSecti on

Spent Fuel Projec-t^O/ficeOffice of Nuc^ear^Material Safety

1 7 9

^







USA/9009/B( )Fd. PAGE NUMBER e. TOTAL NUMBER PAGES IKJ4 I

2. PREAMBLE






General Electric Company applicationdated January 27, 1984, as supplemented.

c. DOCKET NUMBER 7 1 - 9 0 0 9gggggg

ggggg

i

4. CONDITIONSThis certificate is conditional upon fulfilling the requirements of 10.CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model No.: FL 10-1 / '.

(2) Description ^ {: V

Two, 16T-gauge 55-gia3l|n drums welded endr.to end, approximately 68 incheslong and 22-1/2-inches^ in diameter.-.TheSbuter drum closure shall beaccomplished bylvat TeasVa- 12-gauge-boitrlpcking ring with drop-forgedlugs, one of whichjs ^Jtreaded;to receive aj'ieast a 5/8-inch diameterbolt and lock niit?^The^pressufe vessel support mechanism consists of woodsupports, steeTjfinner^sTeeye'and nut ringto receive the containmentvessel, and fireVresdstant phenolic foam, formed in^place to an averagefinished density of atMeastX£j,\pounds per cubic foot for the main body and10 pounds perVcubic foot fbr,'tlh;e>.cap. Gas relief holes shall be providedin the outer stqel drum.

The containment vessel is,a 304L stainless steel 5-inch Schedule 40 pipe,approximately 53-1/2 inches long, with a 304L stainless steel 1/2-inchthick welded bottom plate and a 304L stainless steel 300 pound slip-onflange and blind flange which is fastened by eight, 3/4-inch steel bolts.The flange closure is gasketed by two fluoroelastomer 0-rings with apressure tap between the two 0-ring grooves. During shipment, the 0-ringgroove pressure tap is sealed with a pipe plug with threads wrapped inteflon tape. A 1/4-inch stainless steel valve is screwed into the blindflange of the containment vessel. The valve is sealed by a pipe cap(threads wrapped with Teflon tape) and is protected by a 2-1/2 inch highsection 5-inch Schedule 40 pipe welded to the top of the flange. Thepackaging has a maximum gross weight of 515 lbs.

(3) Drav/ings

The Model No. FL 10-1 package is constructed in accordance with GeneralElectric Company Drawing No. 112D3018, Rev. 2.

180

ggg

\2&U3U3U£J&7¥J¥(2&J!U3!U£J£J!U!&S!U£J&J^

NRCFORM618A(3-96)




(b) Contents


(i) Uranyl nitrate solutions enriched in the U-235 isotope, provided theU-233 content is not more than 1% of the U-235 content; or

(ii) Uranyl nitrate solutions having a combined concentration ofuranium-233 and uranium-235 not exceeding 250 grams per liter and anH to fissile material atomic ratio not less than 80 provided theU-233 content is not greater than 20% of the combined U-233 andU-235 content; or

(iii) Uranyl sulfate;,Solution (U02SQ4)/containing uranium-235; or

(iv) Dry compounds and mixtures of uranium^235; or

(v) Uranium oxide interspersed with graphite<or,silicon carbide plusplastic-packing material; or ..- '. .:

(vi) Uranyl nitrate solutions enrich&diirivithe U-235 isotope having aU-235 concentration not-tp,exceedf^fO grams peV liter.

(2) Maximum quantity o||ma^eriali,p,e^r\pac,ka|'e^!

(i) For the p;nt%||descri bed i n ^ p f l ) (i) and 5 (b) (1) (i i ) :

Nptx to :exc$e373.67;^^ 21 watts decay heat,

18 watts decay heat.%

(iii) For the contents described in 5fb)(l)(iv):

Not to exceed 4.5'kilograms^'fissile material and 30 watts decayheat.

(iv) For the contents described in 5(b)(l)(v):

Not to exceed 300 grams fissile material and 10 watts decay heat,

(v) For the contents described in 5(b)(l)(vi):

Not to exceed 10.1 liters of solution.



181

. aU. iii at. iJU W ymi ywi i lx )M£ sMi SMI « ( ymC i l C

N R C F O R M 61JBA CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


£ 6. The solution contents of the package shall be contained within a bottle having* one of the following specifications:

jj (a) For contents described in 5(b)(l)(i), 5(b)(l)(ii), and 5(b)(l)(iii):

s (i) SI it-vent polyethylene bottle per Drawing No. CAPE-1170-37,

(ii) Duo-vent polyethylene bottle per General Electric Company DrawingNo. 112D3013, Rev. 0, or

3 (iii) Stainless steel bottle as shown on General Electric Company DrawingS Nos. FRO-140 and FRO-140A.3g (b) For contents described in 5(b)(l)(vi):a - • . , . : • • • • " < •

g Slit-vent or duo-vent polyethylene bottle per Nuclear Fuel Services, Inc.,H Specification. U-l, Rev. 1, and Drawing No. 5B-U-740, Rev. 1.g _ .H 7. For shipment of solutions, the shipment must be completed no later than 365 daysH after the stainless-steel or polyethylene bottle is-closed. After filling withB solution, the minimum remaining free volume within the stainless steel org polyethylene bottle must\be at least 0.44 liters:/a 8. The polyethylene bottles:may be packaged within, the metal inner containerp described by Chester-Jensen Company,.Inc., Drawing Nos. 1092M-1, 1093M-1,

1095M-1 and 1096H-1, IssQe\%, date'd April 2,6,Jl971.

9. The packaging for the polyethylene bottles; shal.l.'include a flexible restrainingdevice (such as reconitnended fff.ARH-l.81i? "Vibratibn testing of L-3 and L-10Shipping Containers*):placed.^etwefen :thevc.ap assembly of the polyethylene bottleand the closure flange of. tji'e pressure'..vessel tp assure that the polyethylenebottle will vibrate at the >ame<>fpeMe)icy as the pressure vessel duringt r a n s p o r t . .• '''•'•'•',''•'.'V' '"'-' '-'

10. Dry compounds and mixtures which shall be packaged within sealed metal cans orDOT Specification 2R containers and placed Within an inner container constructedand leak tested as specified onvGenVal Electric Illustration AFL 1105.Following the gas leak testing specified on the Illustration, all innercontainer welds shall be tested using a liquid penetrant method in accordancewith Article 6, Section V, ASME Code. Alternatively, the inner container shownin the Illustration may be constructed of 300 series stainless steel pipe withan outside diameter of 4.500 ± 0.031 inches with a wall thickness rangingbetween 0.095 and 0.140 inch.

11. Appropriate steps shall be taken to assure that from the time of sealing to the- time of delivery to the consignee, the pressure in the containment vessel wills not exceed 40 psig.

12. Prior to each shipment of more than a Type A quantity of radioactive material,* the space between the double 0-ring shall be tested at 100 psig and leak- detection performed by a method capable of detecting a leak greater than 10'3

* atm cc/sec at standard temperature and pressure. No package with a detectable* leak shall be delivered to a carrier for transport.

182

rffl w atrag laniranirwwwwsK w wwwwwwwwai: atanti;NRCFORM618A(3-96)



13. In addition to the requirements of Subpart G of 10 CFR 71, a test shall beperformed on each containment vessel and associated 1/4-inch stainless steelvalve (without its associated pipe cap) initially and once each year at 300 psigand the leak detection performed by a method capable of detecting a leak greaterthan 10'e atm cc/sec at standard temperature and pressure. Any chamber thatfails to pass the test shall be withdrawn from service and repaired to meet thetest. For shipment of contents of not more than a Type A quantity ofradioactive material, this test shall not be required.

14. The fire resistant phenolic foam shall be in accordance with AEC Materials andEquipment Specification SP-9 or as modified by ORGDP Reports K/TL-729 andK/P-6567S.

15. Prior to release of the package for shipment, a radiation survey should beperformed, including a determination of surface contamination, to assurecompliance with 10 CFR §§71.47 and 71.87.

16. In addition to the.conditions in this certificate, each packaging must meet theAcceptance Test Section 8.0 of the current Safety Analysis Report of January 27,1984 as revised April 26 and Hay 16, 1984.

17. In addition to the conditions in this certificate, the packaging shall beprepared for shipment and operated in accordance with the Operating Proceduresof Section 7.0 of the current Safety Analysis Report of January 27, 1984 asrevised April 26 and May:l6.Y 1984. : V

18. The package.authorized.!by 'this.certificate isIhereby approved for use under thegeneral license provisions ofV/10 CFR §71.12V , ;

19. Expiration date: June 30j;JL999.

' REFERENCES

General Electric Company application dated January 27, 1984.

Supplements dated: April 26 and May 16, 1984; and February 8 and June 7, 1994.

Westinghouse Electric Corporation supplement dated: May 15, 1984.

Nuclear Fuel Services, Inc. supplement dated: July 3, 1996.


Date: 1 liaise.


and Safeguards

183

*pat at ME at at at acaE. at MK.at.




1. a. CERTIHCATE NUMBER

9010

b. REVISION NUMBER

38




9

3

gB

3gggggM

g

gg

2. PREAMBLE




NAC International, Inc.655 Engineering Drive, Suite 200Norcross, GA 30092


Nuclear Assurance Corporation applicationdated February 27, 1996.

c. DOCKET NUMBER 7 1 — 9 0 1 0

4. CONDITIONS f;;^ I".-} ~Z~ - ^

This certificate is conditional upon fulfilling the requirements pf 1OJCFR Part 71 , as applicable/and the conditions specified below.

g

g

(a) ,vS\Packaging

(1) Model No.:

(2) Description ^ | J \ •''?£>- /'sMt Â depleted uranium, wateâ"nd,lead; shieldWvJhifpping cask^' encased in stainlesssteel, and equipped w^th^fT§ra>4mpabtiii:imlt)e^^.The cylindrical cask body is195-1/4 inches:iong^%r-f/fetches OD. 4fif;p.rincfpal shielding consists of 2-3/4 inches oKdeplet^^rar i i^^- j f / f l jTI^f^t f l ;e||ând finches of (borated)water-ethyl ene glycd3^m.i'Xture;.'^;';;; '-' ::«"^v WfZ .&*"'

A 7/8-inch thickistainlls's;;;f|ê'l'>oute^^He^^ t6âiJ solid stainlesssteel forging at tach e n d ^ : \ t h e ^ ^ . ^ | i e 7 6 u t e f she!}fpf the cask issurrounded by a 174-inch thick stêi'jiwatfr jacket thatci^' also attached to theend forgings. A wafer expansion tattK^s welded to tfi|;Xwater jacket shell. Theinner cask cavity is /icfpied by a 1/2-inch thick, <s|ainless steel cylindricalshell; welded at i ts top end; to the upper cask,forging and i ts bottom end to acircular plate. " -* >, K .. < (

^'7

There are four separate configurations of the cask.

Configuration (A): The containment vessel is a right circular stainless steelshell, 12-5/8 inches ID by 178 inches inside length by 1/4-inch thick, locatedwithin the inner cask cavity. The containment vessel is closed and sealed by a5-inch thick, composite steel and uranium closure head, twelve, 1-inch diameterbolts, and silver plated, metallic 0-ring. Eight of the twelve closure bolts areused to secure the containment vessel to the upper cask forging. Closure of thecask cavity is by a 1-1/2-inch thick steel closure head, eight, 1-inch diameterbolts, and elastomer 0-ring. The radioactive contents are positioned andsupported within the containment vessel (inner container) by an aluminum basketand internal support structure.

184

NRCFORM618A(3-96)





Configuration (B): The containment vessel is the 1/2-inch thick inner cavityshell. The 1/4-inch thick inner container is not used. The cask cavity isclosed by two closure heads. The inner head is a 6-inch thick, composite steeland uranium plate secured to the upper cask forging by twelve, 1-inch diameterbolts and sealed with a silver plated, metallic 0-ring. The outer head is 1-1/2-inch thick steel plate secured to the top of the upper cask forging by eight, 1-inch diameter bolts and sealed with an elastomer 0-ring. The radioactivecontents are positioned and supported within the containment vessel (inner caskcavity) by a modified aluminum basket and internal support structure.

Configuration (C): Same as Configuration (B), above, except the radioactivecontents are positioned and supported-within the containment vessel (inner caskcavity) in a stain!ess,steel structure containing Bora! sheets positioned so asto provide necessary neutron absorption.

Configuration (D):.. Same as Configuration (B) above, except that the radioactivecontents are positioned and supported within the containment vessel (inner caskcavity) in a 3-element"stainless steel structure^as;shown in NAC Drawing No..347-291-F12, Rev. 2, and;the cask must be enelds.ed; in a closed shippingcontainer. -•' ' '-tX- "•'-' '' *£'•'

The package, including impact limbers* has an|overall length of 237 inches andan outside diameter of. 75^Mhes.~ the maximum§yeight of the contents is 3,000pounds. The weight.,bRthe%ackage is approximately-49,250-pounds.

( 3 ) D r a w i n g s ^ \\ ?(-%;>; ' /A'" ','•'• '-•"" '?'}•'" ' > "

The Model No. NLl-1/2i'shippjng' cask;isxcbnstrdcted in accordance with thefollowing National Lead*-'Company^Driv/ing: Nos.-: ~ \

General

70514F,70514F,70885F,70885F,70885F,70885F,70887F,

Sheet 1, Rev.Sheet 2, Rev.Sheet 1, Rev.Sheet 2, Rev.Sheet 3, Rev.Sheet 4, Rev.

Cask and Trailer/General ArrangementSpent Fuel-Cask Detai1sSpent Fuel Cask DetailsSpent Fuel Cask DetailsSpent Fuel Cask Details

Sheet 1, Rev. 1, Outer Closure Head

Configuration (A)

70516F, Sheet 1, Rev70562F, Sheet 1, Rev70562F, Sheet 2, Rev70562F, Sheet 3, Rev. 0,

8, Spent Fuel Cask General Assembly10, Inner Container6, Inner Container

Inner Container*70562F, Sheet 4, Rev. 0, Inner Container*

185

NRC FORM 618A(3-96)


Page 3 - Certificate. No. 9010 - Revision No. 38 - Docket No. 71-9010


(3) Drawings (continued)

Configuration (B)

70888F, Sheet 1, Rev. 3, Spent Fuel Cask General Assembly70886F, Sheet 1, Rev. 2, Basket Concept70884F, Sheet 1, Rev. 2, Inner Closure Head

Configuration (C)

70888F, Sheet 1, Rev. 3, Spent Fuel Cask General Assembly460-052-F8, Sheet 1, Rev. 4, Rockwell Fuel Basket-NLI-1/2 Cask*460-052-F9, Sheet 1, Rev. 3, Container r Fermi Fuel, Rockwell Basket, NLI-1/2

C a s k , A s s e m b l y o f * •.;•; , :\ V '•'•-• V .• . .•> • . . > v ' • ..'

Configuration (D) ' "-•

70888F, Sheet 1,-Re.v. 3, Spent Fuel Cask General Assembly347-291-F12, Rev. .Ijner - 3 Element, NLI-1/2 Cask^ Fuel Movement Project*

*Nuclear Assurance C6rporatiortfdrtawings. ....

(b) Contents 4\" ^ ,

(1) Type and form oj

(i) Irradiated PWRc^'BWR uranium oxide"fuel assemblies of the followingspecifications:-;-" * 'v:'v_. •% s •

s;-;

< -" */

Fuel form

Cladding material

Maximum initial fuelpin pressure at 100°F,psig


t isPWR

Clad U02

Zr or SS

550

475

pellet

' BWR

Clad

-Zr ,.or

200

197

->>• s \

UOj pellet

SS

ConsolidatedFuel Rods

Clad U02 pellets

Zr or SS

550

950

Maximum average initialU-235 enrichment, w/o 3.70

Maximum bundle crosssection, inches

Fuel pin array size

8.75

14x14/15x1516x16/17x17

2.65

5.75

7x78x8

3.70

8.75

Pins from 7x7, 8x8,14x14, 15x15, 16x16,17x17 in triangularpitch

186 t

a NRC FORM 618AC (3-96)ag Page 4 - Cer t i f icate No. 9010

5.(b)( l ) ( i ) (continued)

g Maximum active fuelg length, inchesM

a Maximum specif ic power,g kW/kgUM

a Maximum average burnup,\ MWD/MTU

a Maximum decay heat, kW

a Minimum cooling time,

I d a y S /-••S v / /

"î^~isi if !sii^ >î^ *!kî^ !3 K<1 t^f1 "^^^ !x c£! iAic! oiciC! ! i i ^ !3t^j^ !s^2! dcii 2&&j£T! i ^ *^CJ^ * ^ ^ i ^ i ^ i ! *x^^ t jC^ iîc! ! uc! ikic^ ^ f1 ^t^td ^f! ^&^£! "53 '

CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION g

*

- Revision No. 38 - Docket No. 71-9010 g

PWR

144

40

40,000**

10.6

. . .V- ' v i50*

*

Consolidated aBWR Fuel Rods p

145.25 144 s

*

27 40 Ji

34,000 40,000 5

10.6 0.6 ^

•

••.- 120 4,380 j

5 The PWR type assembly may.be shipped either with or without burnable poison 8S rods or control rods. ; S3 " * JWVSV. • " S

3 *Four (4) fuel rods may have a .minimum cooling time of.'1-20/ days. :< £3 **PWR fuel assembly may have a maximum average burnup/;#o|f;56,000 MWD/MTU £8 provided the minimum cooling ^me^prior-Tto"shipment;^?; 450 days, and the g3 neutron shield f l u i d contains;?1.6 weight"percent\b;orloif. (The borated f l u i d «r may be l e f t in the shielding ^t|n|.s'during the shiplenf of other ;contents.) s

S ( i i ) Irradiated metal l id/ fu l i !s of the fqldpwingj/specifications: g

H -. " . ' - ^s f? Fermi-1: , . . ! - ' :^ ' l v / x - EBR-IT. Blanket a

8 Fuel form .; „ '/^'l'--^\Jrdlr\Xa$finp^ybdenumy'' Uranium metal gH .; \ , al loy^ns^ \ i 4 : j cyl.indrical slugs ^

a Cladding material ; >8 //g Max. i n i t i a l U§ content/assembly, kgM

g Max. avg. i n i t i a lB U-235 enrichment, w/o

g Max. bundle crossg section, inches

g Fuel rods per canisterga Max. active fuelg length, inches

p Max. averageI burnup, MWD/MTUgg Max. decay heat, watts

g Min. cooling time,a davs2E 2&2&JK. M FP, 7^ , /9K %& ?SU£USU& ws 2IK flK

Zr

; "1l8.7./assy.v300/16 ;assy.

26.0

2.93 sq

140

30.5/assy122/cask

2,840

20

5,000

/ •• - g;.'Aluminum containers g

,J *( 292/container gcask'load g

0.21 (3.88 kg 5Pu/canister) «

4.875 dia Ji

157 *

2,400 J

300 j

365 Ji

H 8a NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION g« (3-96) 5M B

£ Page 5 - Cer t i f icate No. 9010 - Revision No. 38

f (111)

£ Fuel form

£ Cladding material

£ Maximum i n i t i a l U£ content/assembly-kg

g Maximum average i n i t i a l U-235g enrichment

jj Maximum bundle cross-sectionjj inches£ ' •'•• -» Intact fuel rods per canister,jj maximum '

jj Canisters per cask

£ Max. active fuel length,finches

£ Maximum average burnupMWp^MJUj

£ Maximum decay heat, wat ts^S

^ Minimum cooling time^d^ys;j$//%

J (iv) Irradiated RWR fbr-BWR':'c specifications;:/ c /•;a • ' - • ; ' ' ' • ' " " i v »s . ^

c Fuel forms * , " -5 Cladding material

^ Maximum i n i t i a l fuel pin • s v5 pressure at 100°F, psig

£ Maximum i n i t i a l U£ content, kg

£ Maximum average i n i t i a l£ U-235 enrichment, w/oH

£ Maximum bundle cross£ section, inches

£ Maximum active fuel£ length, inches

i Maximum specif ic power,£ kW/kgU

a£

p ^ pife, we, ^ ^ ^ejf^Tfejfftjif^ w^ 7f ^ 2 R M ^R ?R f

4 ^ }}

•" . . . . r . • - - , ' ' . \

- • " • ; • . ! '. > . ^ ' : :

wanium.pxi

- Docket I

Research

Uranium r

Aluminum

54.5

Natural

1.36

7 ;

3 intact

120.5^- ;;

de fue'/lf-rt

" dtfa# uio^j pe l l et s

Zr or SS

•'55a-':'' '- '

58.2

4.9

8.75

150

44

1 8 8

^o. 71-9010 B

Reactor B

netal rods B

*i

ii

ii

i

fuel jj

i

)^s of the fol lowing g

'--''-BWR Rods |

' V 'Clad U02 pel lets j

Zr or SS j |

•

200 S»*

75 i•

5.0 B

5.75 fi

•150 B

ii

60 B»

*i

rw wwy«£ wwwwwwwi«oiojzagw)jgw

NRC FORM 618A(3-96)



(iv) (continued)


Maximum average burnup,MWD/HTU

Maximum decay heat, kW

Minimum cooling time, days

PWR Rods

60,000

1.65

150

BWR Rods

75,000

4.0

150

* For the shipments of irradiated PWR fuel rods, the neutron shield fluid must contain1.0 weight percent boron (the borated fluid may be left in the shielding tanks duringthe shipment of other contents).

(v) Solid, non-fissile, irradiated hardware and neutron source components.

(vi) Byproduct and special nuclear material in the form.of irradiated uranium andplutonium oxide fuel rods. Prior to irradiation, the maximum averageenrichment in U-235 plus plutonium not to exceed 3.70: w/o ancj the maximumenrichment not to exceed 4.0 w/o. ; CJ

(vii) Irradiated PWR uranium; oixide fuel: assembliesi|including additional irradiatedfuel rods inserted an~d£.secured in the guidj thimbles. The fuel assembliesmust conform to the itiîmum*active dimei)s;iortS;;as described in Item 5(b)(i)except that maximum initial U content mus^5 be' 495 kg and the maximum averageinitial U-235 enriGhmeht/sharll be 3.35<:w/;or^ '

,'-• '•'•,• 'i'/.<f{f<>< ': • •• • ••;-*-'" .p'-.X'

(viii) Irradiated Connecticu^yankee fuel assembly Wi/tha maximum average initialU-235 enrichment of 4.;0Vwy4o,-|ancj each i of/the J5. x 15 fuel, rods clad bystainless steel. 204irocjsyas'semb.lyj acttve'length of)l.21.4 inches.

(ix) Irradiated MARK42 fuel asseifibîels^consisting of three concentric fuel tubeswith PuO2-Al powder metallurgy'cores clad with type) 6063 aluminum, containinga total of 3.35 kgô/ plutonium. The plutonium>was initially enriched tocontain 78.28 w/o Pu-239* 2.27 w/o Pu-241 and 0.15 w/o Pu-238.

(x) Irradiated MARK 22 fuel assemblies consisting of two concentric fuel tubeswith uranium-aluminum cores clad with type 8001 aluminum, containing a totalof 3.2 kg of uranium-235. The uranium was initially enriched to contain 66w/o to 80 w/o uranium-235. The irradiated MARK 22 fuel assembly has an activelength of 150 inches, a maximum burn-up of 1226 MWD and a minimum coolingtime of 150 days.


(i) Items 5(b)(l)(i) or 5(b)(l)(vii) above: one PWR fuel assembly; two BWR fuelassemblies; or one consolidated fuel canister. Fuel assemblies to becontained in their respective fuel baskets as shown on National Lead CompanyDrawing No. 70562F, Sheet 1, Rev. 10, or 70886F, Sheet 1, Rev. 2. Theconsolidated fuel canister to be contained in Configuration (A) fuel basket asshown on National Lead Company Drawing No. 70562F, Sheet 1, Rev. 10.

(ii) Item 5(b)(l)(ii) above: four canisters per cask. The fuel canisters and fuelbasket must be in accordance with Configuration (C) above.

189



5.(b)(2) (continued)

(iii) Item 5(b)(1)(iii) above:

(a) three canisters of unfailed fuel containing up to seven fuel rods percanister. The fuel canisters and fuel basket must be in accordance withConfiguration (D) above; or

(b) up to six canisters containing one defective fuel rod per canister. Thecanisters are 2.75-inch I.D. failed fuel rod canisters as shown onNuclear Assurance Corporation Drawing No. 340-108-D2, Rev. 10, and areplaced in the six-rod capacity liner as shown on Nuclear AssuranceCorporation Drawing No. 347-029-20, Rev. 1. The maximum decay heat loadfor a defective fuel rod is limited to 5 watts; or

(c) up to three canisters containing either one defective fuel rod percanister or up to 10 failed fuel filters per canister. The canisters are4.00-inch I.D. failed fuel rod canisters as shown on Nuclear AssuranceCorporation- Drawing No. 340-108-D1, Rev. 10. The fuel basket is inaccordance with Configuration (D) above. The weight of the filters islimited to 12.5 pounds per canister. The maximum decay heat load for thedefective fuel rods and the failed fuel, pTiers is limited to 5 watts percanister. Plutonium content of the filters not to exceed 20 curiesplutonium per package. . ..._-->."-'

(iv) Item 5(b)(1)(iv) aboyej. the fuel rods will; b> shipped in Configuration (A) or(B). PWR fuel rods, withii)urnup in excesvbfj45,000 MWD/MTU and BWR fuel rodswith burnup in excess of 50,000 MWD/MTU will be shipped in Configuration (A)only. The maximum i'nitiaT'uranium conteiitislimited to 58.2 kg per packagefor PWR rods and'75, kg, per package for. BWR rods; and

(a) up to 25 PWR fuellrodY or up t.o 251 BWR?fuel rods,per cask. Up to 2 ofthe 25 PWR rods may have a maximum .burniip of 65,000 MWD/MTU; or

(b) up to 18 PWR fuel rods, with'a maximum specific power of 60 kW/kgU and aminimum cooling time of 300 days, per caski

(v) Item 5(b)(l)(v) above, weight not to exceed-1,600 pounds.

(vi) Item 5(b)(l)(vi) above, the maximum mass of U-235 plus plutonium must notexceed 4.0 kg. Fuel rods must be contained in fuel baskets as shown onNational Lead Company Drawing No. 70562F, Sheet 1, Rev. 10, or 70886F,Sheet 1, Rev. 2.

(vii) Item 5(b)(1)(viii) above: One Connecticut Yankee intact irradiated fuelassembly.

(viii) Item 5(b)(l)(ix) above: One irradiated MARK 42 fuel assembly in either intactor sectioned form, using Configuration (C) above. If sectioned, each sectionmust be seal welded in a shipping can as shown on Martin Marietta EnergySystems Drawing'Nos. M-12821-CP-105E, Rev. 0, and M-12821-CP-106E, Rev. 1.Four shipping cans will be loaded into a MARK 42 Segment Dry Shipping Canisteras shown on Martin Marietta Energy Systems Drawing No. M-12821-CP-102, Rev. 1,along with a shipping canister spacer, as shown on Martin Marietta EnergySystems Drawing No. M-12821-CP-103, Rev. 1. The shipping canister will be

190

NRCFORM618A(3-96)

CONDITIONS (continued) U . S . NUCLEAR REGULATORY COMMISSION


(5)(b)(2) (continued)

(ix)

loaded on top of a carrier spacer as shown on Martin Marietta Energy SystemsDrawing No. M-12821-CP-112, Rev. 0. A maximum of 2 shipping canisters may beloaded into a cask. Intact fuel assemblies will be shipped in a MARK 42Element Wet Shipping Canister as shown on Martin Marietta Energy SystemsDrawing No. M-12821-CP-114, Rev. 0. A maximum of one intact assembly may beloaded into a cask.

Item 5(b)(l)(x) above: Two MARK 22 fuel assemblies or one MARK 22 fuelassembly with the two cores separated, using Configuration (C) above. Eachassembly or core will be shipped in a shipping canister as shown on SandiaNational Laboratory Drawing No. R21563, Sheet 1, Iss. B.



6. Irradiated fuels described in items 5(b)(l)(i), 5(b)(l)(ii), 5(b)(l)(iii), and5(b)(l)(iv) above may not have a maximum burnup which exceeds 1.25 times thespecified maximum average burnup.

7. The cask cavity and containment vessel (inner container) must be dry (no freewater) when delivered to a carrier for transport..; Residual moisture must bepromptly removed from the cask cavity and containment vessel by the methodsdescribed in Section XV of"the, application. Removal of the residual moisture fromcask cavity when package.is used... .in Configurations (B), (C), or (D) is not requiredproviding the decay heat load does not exceed 2.0 kW:

8. For the shipment of irradiated fuel assemblies or ei canister of consolidatedirradiated fuel, the cask cavity canister of consolidated irradiated fuel (ifpresent), and containment.vessel must be promptly inerted following removal of thewater from the cavity. For content! not vacuum dried, the cask cavity andcontainment vessel must be purged at least three times with argon, nitrogen, orhelium. Each purge volume must be equivalent to or greater than the cask cavityand containment vessel volume. After the final,purge, or following vacuum drying,the cavity and containment vessel must be promptly filled with argon, nitrogen, orhelium at 1.0 atm pressure.

9. Known or suspected failed fuel assemblies (rods) and fuel with cladding defectsgreater than pin holes and hairline cracks must be shipped inConfiguration (A).

10. The consolidated fuel canister must be provided with vent and drain lines(openings) to permit free draining of the canister. No valves can beinstalled on the vent and drain lines.

11. The cask may be shipped in a closed shipping container (Configuration D) providedthat the closed shipping container and the transport vehicle (trailer) meet theapplicable requirements of the Department of Transportation. Tie-down deviceswhich are a structural part of the cask and the cask support structures must complywith 10 CFR 71.45.

12. When the cask is shipped in a closed shipping container the center of gravity ofthe combined cask, closed shipping container and trailer must not exceed 75.0inches.

191

Ib



13. When the cask is shipped in a closed shipping container, the internal heat loadmust not exceed 750 watts.

14. The neutron shielding tank must be filled with a mixture of water and ethyleneglycol (52% by volume). This mixture must not freeze or precipitate in atemperature range from -40°F to 330°F. The neutron shield tank may be empty whenthe cask is in Configuration D.

15. The structures used to support the package on the transport vehicle must be asdescribed in the application.

16. Any system used for cooling down the package must be provided with a pressurerelief device set so that during the cool-down process, the maximum pressure in thecontainment vessel cannot exceed 310 psig when the package is used in Configuration(A) or 365 psig when the package is used in Configuration (B).

jj 17. As needed, appropriate component spacers must be used in the cask cavityc to limit movement of contents during shipment.s* 18. Shipping cans used,for sectioned MARK 42 irradiated fuel'assemblies must

s be seal welded and must be leak tested to lxlO"7 std cm /sec.

19. In addition to the requirements of Subpart G of IP'CER Part 71:

(a) The package shall be'prepared for shipments arid operated, in accordance with the

p g ^ j k p ^ i poperating: procedures v|n.'Section,XV" of thefapjpjication, as supplemented.

' (b) The package shall\:bje maan^jned and te' tetQiTi accordance-with the maintenanceprogram in Sect ion VI of>^ê:apjpt1icatiqn|?:as .supplemented.

(c) When the package ifiô b'e used for. the^transpdrt of authorized contents havinga decay heatHoad o|vpreatey

:<thab.;4i0:k^ psig.hydrostatic test of thecontainment cavity, "and;:a;\405.:,pijg,^ydrdstatfc test/of the water jacket andexpansion tank shall be peVfoê^fs/par^pf the maintenance program asspecified in Section XVI of tfi'ei-applncation!

20. The package authorized by this certificate is hereby approved for use under thegeneral license provisions of,10 CFR §71.12.. ~ x

21. Effective Date: April 1, 1996. Expiration date: April 30, 2001.

REFERENCES

Nuclear Assurance Corporation application dated February 27, 1996, as supplementedMarch 26, 1996.



and Safeguards

March 29, 1996 192

2£U3&&7&7¥35SJ£L&Mx*aaU£^

- y - ' v ' ""*,* - w . . • * -J, '-,<


FOR RADIOACTIVE MATERIALS PACKAGES1.8.CERTIFICATE NUMBER



USA/9011/B ( )d. PAGE NUMBER


2. PREAMBLEa. This certificate Is issued to certify that the packaging and contents described in Item 5 below, meets theapplicable safety standards set forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATIONa. ISSUED7O (Name and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Advanced Medical Systems, Inc.1020 London RoadCleveland, OH 44110

€

Picker Corporation application datedSeptember 25, 1973.

; bc. DOCKET NUMBER71-9011

4. CONDITIONS < %..// '"' " '•> ;'(t.'This certificate is conditional upon fulfilling.the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model

(2) Description

An ov|nRack thead assemblamaple panelsReinfoijciihg

provided^tp>facil1tat&fo/36" x 42"^x^4p.5" witfra n

^ protection for a teletherapykf4fi lamlinated 2 x 4 hardwood

v » r 6 gacfe;steel panels.w#fd&a together and spaced to

s^Jmn 6 inches. Skid runners areejMmensio,ns df the overpack are^ p i g h t of:4,000 pounds.

(3) Drawings

The packaging is cons'trubted^frf Accordance with the following drawings:Advanced Medical Systems, Inc. Drawing No. D-MEH-00-00004, Sheets 2 and 3through 10, Rev. F.; Advanced Medical Systems, Inc., Drawing No. C-200004-and Picker Corporation teletherapy Head Drawing Nos. E-182545A, Rev. F-and E-182972A, Rev. I.

193

SJlXlaM&Ua&MU9MA&JKda&Mii9i!>iawr!iJa&^^KMaB^

ft«^lfr>reftfo^

i"1 '1" / CONDITIONS (continued)


5. (b) Contents


Cobalt 60 sealed sources that meet the requirements of specialform radioactive material. The sources are to be packaged in asecondary inner container (teletherapy head) as described in Item5(a)(3).


13,680 curies, with a radioactive decay heat load not to exceed200 watts. ^ O ' T ; ^

6. In addition to the reauêments of Subpart^G 0 0 CFR Part 71, each packageshall be maintainedjôperated and prepared for^Jn'iDment in accordance with theoperating procedjirlsând maintenance program in supplement dated June 26, 1991.

7. The package atftfiorized by this certificate is herghv Approved forthe general Îcen^pjcovisions of 10 CFR §71.JL2^X *^/?.

8. Expiration ^ t e : Augu^©^ l y y b ^ ^ / mZ O

Picker Corporation

Supplements datid1:' $$& &M pi l pJTnd Jifpf26, 1§$L.

use under

-A

T h a r l e s ^ T ^ c ^ n W ;TransporitationV Branch

i i J k j F S f d

Date:AUG 0 8 1991

VL, / J)ivi]SijDn^6f Safeguards^" X\f "i'ra^^TTrahsportation, NMSS

194

^









5

2, PREAMBLE



3, THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address)

Transnuclear, Inc.Two Skyline DriveHawthorne, NY 10532-2120


Transnuclear, Inc., application datedMarch 25, 1991, as supplemented


4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10.CFR Part 71, as applicable^ and the conditions specified below.

5.

(a) Packaging

(1) Model No.:. TN^8:AND TN-8L .,-, -

(2) Description N „> x « ' ;,fVJ

The TN-8 and TN-8L;; are; lead, steel and re.fin-shielded irradiated fuelshipping casks. Y-Kejc^sks approximatesfaîght circular cylinder 1,718 mmin diameter and ,5,516 Inm "long.'~ThV;c%\%|^*'consists of. three stainlesssteel scjuare pressure/'veSsels weldedr-^qcsn end, pi ateând a circularstepped top flarige; separated by a: T-s)ia:ped.4<:6pp'er p|ate and surroundedwith B4C + Cu plates'^ EachfcaVity /is 230 jx 230 mm and 4,280 mm long. Themain shielding cpnsists,;pf;_135 'np;:o .<l a.d,: 26 mm of: steel and 150 mm ofresin. A wet cement layer''Is-<]ocat'e>d"between the lead and the outershell. Radial copper finsf-atkJy/eWed'to'the outer-shell and cover thesurface of thecask betweeri.îfch.end drum. The'Model No. TN-8 has 150rows of fins and. the Model No'. TN-8L has 104,rows of fins.

The lid is a welded stainless steel shell containing lead and resinshields. The pressure vessels are; closed and sealed by sixteen, 1-1/4-inch diameter bolts and two silicone rubber or Viton 0-rings locatedwithin recessed grooves on the top flange. Each extremity of the cask issurrounded by circular stainless steel drums reinforced by radial gussetplates and filled with balsa wood. A disk shaped impact limiter,constructed of carbon steel and balsa wood, is fastened to each drum withfour, 1-1/4-inch bolts. The vent and drain lines which penetrate theinner cavity are equipped with positive closures. In addition, all accessports are protected by the impact limiters.

The lid of the cask may be replaced with a modified lid which increasesthe cavity length to 4,362 mm or to 4,394 mm with the lid plate removed.This arrangement will be referred to as "Configuration X."

Trunnions are used for lifting and tie-down of the package. The packageweighs approximately 36,000 kg.

195



(3) Drawings

The Model No. TN-8 packaging is constructed in accordance withTransnuclear Drawing No. 9317.01, Rev. J. The Model No. TN-8L isconstructed in accordance with Transnuclear Drawing No. 9317.138, Rev. A.The materials of construction and welds shall be in accordance withAnnexes A, B, and C to Chapter II of the application.

The lid for Configuration X is constructed in accordance with TransnuclearDrawing Nos. 9040-500-1, Rev. 1, 9040-500-2, Rev. 1 and 9040-500-3, Rev.0.

(b) Contents

\ (1, l*. «, ft™ f-UrUl

(i) Irradiated PWRctiraitiurn oxide fuel assemblies of the following«nprif i rati'nnc'f - •speci f i cati pns5:

Fuel forni ; ; ; Cl ad U02 Pel 1 etsCladding materi al Zr or SSMaximum xijiitjval U content/assembly, kg>^ 469Maximum avefagfe.initial U-235 \^'.</ '

enrichment}î^h\Zr cladding, yr/oj/^p ,3 .2ximum avenfg#feinitial|U^^35 '*' '£%?Maximum n g . v | ^ £%?enrichment'îth' SS cladcliVigjW/^^' 4.0

Maximum bund|fecôss s'ection, in>-::g>; . 8 . 5Maximum ^c|ive;«f&e,l~-length, in:o?

;Vs~ , ; ,* 146Mihimum^lco^jlirig^ljle^dayv ''f%0r>:' ^f.:/;' , •150Maximum\welight/fu;eli'aMe'nb]y^ //>/-'.- ( 733; and

Group I

"V'K\ '4$-*Xt\"'";-'T ^':-Initial fuel pin-pres^re^t^.lOQ'F,' psig . <, 250Maximum^'average burnupv'MWbyMTU , 38,500; orGroup II fuel assemblies

Maximum average burnup,.MWD/MTU 36,000

For the casks in Configuration X, the minimum cooling time ofthe fuel assemblies shall be 1,460 days with the lid plateinstalled and 2,190 days with the lid plate removed.

(ii) Solid non-fissile irradiated hardware. As needed, appropriatecomponent spacers must be used when loading irradiated hardware intothe cask cavity to limit movement of the contents during accidentconditions of transport.

1 9 6

wwwwwwNRC FORM 618A(3-96)

CONDITIONS (coniinued) U.S. NUCLEAR REGULATORY COMMISSION


(iii) Intact BWR and PWR fuel rods. The rods shall be constrained by abasket or grid structure; initial U-235 content shall be les's than15.0 kg per rod bundle; cross sectional area of the rods, tubes, andfull length structural material shall not be less than 29.6 squareinches; and the bundle cross section shall not be greater than 8.5inches. Maximum weight per bundle shall not exceed 733 kg. TheGroup I and Group II burnup limits of paragraph 5.(b)(l)(i) apply.


(i) For the contents described in Item 5.(b)(l)(i), Group I fuelassemblies:

Three PWR assemblies. The maximum decay heat load is not to exceed35.5 kilowatts per package .and 12 kilowatts per assembly for theModel No. TN-8,packaging{and 23.7 kilowatts per package and 7.9kilowatts per assembly for the Mo.del No. TN-8L packaging.

(2)

(ii) For the contents described in Item 5.(b)(l)(i), Group II fuelassemblies:

Three PWR assemblies. The maximum decayvheat load and the maximumfree^gas volume are not to exceed the limits listed in the tablebelow: - ^,\

Decay HSat'jpShipment, kw

% ^Maximum Free, Gasfr-

nT (NTR)1 iS, ;

•• l.S-\-.3.0 -9.0

15C021.027.0

"•<"•Qi558'

"/// '': 10 :483;-*.0".44l0.4080.384

ConfigurationMaximum Freefor 3 Assembi

m3 (NTP^b

0.6010.5850.5200.4750.4390.413

XGasies

Notes: (a) Decay heat load per assembly must notexceed 7.9 kilowatts for Model No. TN-8Lpackaging.

(b) NTP conditions are 25*C and one (1) bar.

197

ffira? arazaza7a7a<:acaTa7Wazaza7WWWaTa7 a? a o gNRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


5.(b)(2) (Continued)

(iii) For the contents described in Item 5.(b)(l)(iii):

Three rod bundles. The maximum decay heat load and maximum free gasvolume are not to exceed the limits listed in Paragraph


g Minimum transport index to be shown on£ label for nuclear criticality control: 100

6. Group I and Group II fuel assemblies, either Zr or SS clad, and bundles of PWRand/or BWR fuel rods that individually meet all the appropriate specificationsof 5.(b)(l)(i), 5.(b)(2)(i), 5.(b)(l)(iii), and 5.(b)(2)(iii) above may bepackaged in any combination.

7. PWR assemblies may be shipped either with or without burnable poison rod,thimble plug, or control rod assemblies.

8. As needed, appropriate component spacers may be used'Mn the cask cavity toproperly position the\fueV assemblies. :".v"W

* 9. The maximum weight of the .contents (fuel assemblies, component spacers, inserts,* irradiated hardware, etc.) must not exceed, 2,200: :kg.

10. The cask cavity must be, dry (no free water).when delivered to a carrier fortransport. Residual mpisture must be promptly removed from the cask cavity bythe methods described in AnnexI to Chapter VlI1/of the application. Forcontents 5.(b)(l)(i) and 5.(b)(l)(iii), the cavity must be promptly backfilledwith 1.0 atm of helium, nitrogen, or argon,gas}.

11. Known or suspected failed fuel assemblies (rods) and fuel cladding defectsgreater than pin holes and hair!i-ne cracks are not authorized.

12. For contents 5.(b)(l)(ii), the dryness verification test is required but leakagetests for containment assembly verification are not required.

13. The package contents must be so limited that under normal conditions oftransport, the total dose rates must not exceed 17 mrem/hr at one meter from thesurface of the package.

14. Any system used for cooling down the package must be provided with a pressurerelief device set so that the maximum pressure in the containment vessel cannotexceed 7 atmospheres during the cool-down process.

15. The systems and components of each packaging must meet the periodic tests andcriteria specified in Chapter VIII of the application. The K ** verificationand shielding efficiency verification tests in Chapter VIII of the applicationmust be performed on each packaging within the two year period preceding anyshipment of contents listed in 5(b)(l)(i) and 5(b)(l)(iii). The K ffverification and shielding efficiency verification tests need not Be performedon packaging during periods (which may exceed two years) when only irradiatedhardware as specified in 5(b)(l)(ii) is shipped.

3•

3^ 198OSJSJBM



16. In addition to the requirements of 10 CFR Part 71:

(a) The package must be prepared for shipment and operated in accordance withthe Operating Procedures in the application dated March 25, 1991.

(b) Each package must be tested, repaired, and maintained in accordance withthe Acceptance Tests and Maintenance Procedures in the application datedMarch 25, 1991.

17.

18.

All valves, fittings, seals, and relief devices must be of the type, size, modeland manufacture as indicated on the design drawings. The resin material must beof the specifications stated in Annex A to Chapter II of the application.

In accordance with Annex L to Chapter VIII, at periodic intervals not to exceedtwo years, the thermal performance of the cask must be analyzed to verify thatthe cask operation has not.degraded below that which is licensed*. Followingthe initial acceptance tests, the heat source.may be that provided by the decayheat from the loading of the package, provided that the heat source is equal toat least 25% of the design heat load for the package.. Each cask that fails tomeet the thermal acceptance criteria given in Annex L of the application must bewithdrawn from service until corrective action can be completed or the licenseamended to limit the package to a lower heat load. "

19.

20.

21.

*The thermal performance 'test js not required;altperiodic intervals when themaximum decay heat load',p'erT-package does not Exceed 25% of the design heat load.

The Configuration X lid shall be operated and maintained in accordance withAnnex N to Chapter VIII, in;the application dated March 25, 1991.

The package authorized by this certificate is hereby approved for use under thegeneral license provisions of>10 CF.R §71.12.

Effective date: June 1, 1996. ,*/>Expiration date: May 31, 2001.

REFERENCES

Transnuclear, Inc., application dated March 25, 1991, and supplements dated April 22,1991', and April 22, 1996.

ULATORY COMMISSION


and Safeguards

Date: May J_, 1996

1997¥^7&7¥t2£3SUW7f$7W7K7W7W7W7W7WWMJSUBJ&7¥{7¥{ffl7¥,7¥{7&




a La. CERTIFICATE NUMBER

£

*8

Bgsw58ggM

B

5





4

2. PREAMBLE






Transnuclear, Inc., application datedMarch 25, 1991, as supplemented


4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of lOJCFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

B

«

(1) Model No.: " TN-<

(2) Description

The TN-9-js a. lead^fteel;. andrifes]n shiitd||i irradiated fuel shippingcasks. J-rThe casks jpilqximates?^ figfit'.x&yûlar cylinder 1,718 mm indiameter"and 5,756*g§,ong. /|heycavftytc^n'sists of three rectangular,stainless steehp.re1s;;sjIr-£^ a circular-stepped, top ffcsiijge.^J^^ bays are dividedinto a total o^^feyj?n3sâ!re!!c0Apar^tin(^t1s,|^d^ 150 mm and 4,520 mm long.The main-«hieVd^g"^dnsi^';pfl28\i|in{of Xea%^26 mniôf steel, and 150 mmof resiri.'f.A we c§iii t:4]. ei!?j,is;;1;QCT ejd be€Vfeen the; lead and the outershell. Radial cdêK^Yns\a^Tw^ded'itoy';£h>e outer/--shell and cover thesurface ofVthe cask betweeêach>^B|j.d dr,um:. ^.y)

The lid is a"'vjetdgd stainless" steel shell containing lead and resinshields. The pressure vessels are closed and-sealed by sixteen, 1-1/4-inch diameter bolts and. two silicone rubber or Viton 0-rings locatedwithin recessed grooves oh the; top'flange. Each extremity of the cask issurrounded by circular stainless steel drums reinforced by radial gussetplates and filled with balsa wood. A disk shaped impact limiter,constructed of carbon steel and balsa wood, is fastened to each drum withfour, 1-1/4-inch bolts. The vent and drain lines which penetrate theinner cavity are equipped with positive closures. In addition, all accessports are protected by the impact limiters. Trunnions are used forlifting and tie-down of the package. The weight of the package isapproximately 36,000 kg.

(3) Drawings

The package is constructed in accordance with Transnuclear Drawing No.9317.03, Rev. J. The materials of construction and welds must be inaccordance with Annex A, B, and C to Chapter II of the application.

200



5.(b) Contents


(i) Irradiated BWR uranium oxide fuel assemblies of the followingspecifications:

Fuel form Clad U02 PelletsCladding material Zr or SSInitial fuel pin pressure at

100*F, psig 200Maximum initial U content/

assembly, kg 201Maximum average initial U-235

enrichment, w/o . . 2.65Maximum bundle cross section, in , , 5.52Maximum activecfuel length, in 144Average.burnup, MWD/MTD 36,500Minimum cpoling time, day 150

a Maximum weight/fuel assembly, kg 3005

(ii) Solid non-fissile irradiated hardware^. As needed, appropriatecomponent spacers\must be used when^/lbiding irradiated hardware intothe cask cayitylto^limit.^movemjent^o^vthe contents during accidentconditions of transport'. • .^$c?

(2) Maximum quantity/fof.mate^ial per package":- '• ', ••'.• • • • • . - > ' . • • • ' •

(i) Seven BWR assemblies.' The maximum decay;heat load per package isnot to exceed 24.4 ;kilowatts-.and 3.5 kilowatts per assembly. Asneeded, apprppriate^ component • spacers may be used in the cask cavityto properly positionline,J|;uel assemblies.

- - v : ^ ! n r ;: ;. • [ •(ii) The maximum weight of the.contents (fuel assemblies, component

spacers, inserts, irradiated hardware,\etc.) must not exceed2,110 kg ' ; . . ,.



6. The cask cavity must be dry (no free water) when delivered to a carrier fortransport. Residual moisture must be promptly removed from the cask cavity bythe methods described in Annex I to Chapter VIII of the application. Forcontents 5.(b)(l)(i), the cavity must be promptly backfilled with 1.0 atm ofhelium, nitrogen, or argon gas.

201

«

ggggI

a»gg




(a) The package must be prepared for shipment and operated in accordance withthe Operating Procedures in Chapter VIII of the application.

(b) Each package must be tested and maintained in accordance with theAcceptance Test and Maintenance Procedures in Chapter VIII of theapplication.

8. Known or suspected failed fuel assemblies (rods) and fuel with cladding defectsgreater than pin holes and hairline cracks are not authorized.

9. For contents 5.(b)(l)(ii), the dryness verification test is required but leakagetests for assembly verification are not required.

10. The package contents must be!so limited that-under normal conditions oftransport, the total dose"rates must not exceed*14'mrem/hr at one meter from thesurface of the package; v : ;

11. Any system used for cooling down the package must be provided with a pressurerelief device set so that the maximum pressure inches'containment vessel cannotexceed 7 atmospheres during the cool-down process!,' '•'•-'••'

12. The systems and components; of, e.acHi packaging .must-meet the,periodic tests andcriteria specified in Chapter VIII.;oft[ie application. Each packaging thatfails to meet these qriteTfeta must be.withdrawnift'om service until correctiveaction has been completed.""%•

13. All valves, fittings^<seVjs;rfahrf:reliief.:d6v.fces must/be of the type, size,model, and manufactur^as'indicated!onr;the;-design-drawings:™' The resin materialmust be of the specifTcat^on^^ta'tep^:'tnJ'Atfnex-'A.'to Chapter "II of theapplication. , ';'}' "i\\ , ^ / ^ y ; ""• '-:i -<;'•'''

14. In accordance with.Annex L to Chapfer^Vfll, at"periodic intervals not to exceedtwo years, the thermal performance of the cask must, be analyzed to verify thatthe cask operation has not degraded below that.which is licensed*. Followingthe initial acceptance tests, the heat source 'may be that provided by the decayheat from the loading of the package,'provided that the heat source is equal toat least 25% of the design heat load for the package. Each cask that fails tomeet the thermal acceptance criteria given in Annex L of the application must bewithdrawn from service until corrective action can be completed or the licenseamended to limit the package to lower heat load.

* The thermal performance test is not required at periodic intervals when themaximum decay heat load per package does not exceed 25% of the design heatload.

202

NRC FORM 618A(3-96)




16. Effective date: June 1, 1996 Expiration date: May 31, 2001.

REFERENCES

Transnuclear, Inc., application dated March 25, 1991, and supplements dated April 22,1991, and April 22, 1996.

ATORY COMMISSION

Date: May 1996"S^k\

William D. Tray^rs, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

anc' Safeguards,?^'"';"

y*-i? '* ,

i/^.;

203 rJ

WWWWNRC FORM 618(3-96)10CFR71



[. a. CERTIFICATE NUMBER

9019

b. REVISION NUMBER

23




4

2. PREAMBLE





General Electric Company application datedSeptember 14, 1993, as supplemented.

c. DOCKET NUMBER 71-90194. CONDITIONS ^ Vs _/,' :';~' fi >

This certificate is conditional upon fulfilling the requirements'of lO.CFRFart 7-1, as applicable/and the conditions specified below.

(a) Packaging

"(1)

(2)

Model No..;v

Description

^*î} *y ,

5The packaging consfisfpflup jtoMwo 5rg§Mn or up to'-three 3-gallon,11.25-inch-ID, mini§uiiB.24-gauê4ij;teel))pa|i^contained .in a 13.75- to14.05-inch dian(eter1B^plnrna1^27^n0hjTop inner container. The innercontainer-,is cflp'i%r\S^^^f;-,18~gdi^'p^^ûmô^j.^ gauge maximum steel,with bolted mîskef^^MlHHî^^'siimo^B rubber) top flangeclosure.v-^The inri|r|jgbntaJlier;Hsj!ce||tered and^-aipporte.d in a 22.5-inch-ID, 18-gaug;e ste^îBS-gî'lonâpa^ b$ solid, insulatingmaterial ebmôsedWf^fifr'^ foamy..;(7-9 pounds per cubicfoot). DrumPclosure i ^ p r M S M p y ^ a ^ g a u g e dr% cover and a 12-gaugeclosure ring?with drop forge^'/ll%^dril1ed and^ttixeaded for a 5/8-inch-diameter bo l t ed ,nu t . A bom liner 1 ocated.;be:tween the inner containerand steel pails' Is required for the contentsâs specified. The maximumweight of the package, ..including contents, not to exceed 370 pounds.

(3) Drawing

The container is constructed in accordance with General Electric CompanyDrawing No. 112D1592, Rev. 14.

204

NRC FORM 618A(3-96)



5.(b) Contents


(i) Uranium oxide powder enriched to not more than 5.0 w/o in the U-235isotope. The maximum H/U atomic ratio shall not exceed 1.6.Exclusive of the boral liner, the mass of moderating materialswithin the inner container when added to the total mass ofmoderator within the fuel shall not exceed 5.2% of the weight ofthe uranium oxide.

(ii) Uranium oxide as pellets or a mixture of powder and pelletsenriched to not more than 4.10 w/o in the U-235 isotope. Themaximum H/U, atomic' ratio shall not, exceed 0.45. Exclusive of theboral liner', .the mass of moderating materials within the innercontainer when added to the total mass of moderator within the fuelshall not exceed 3.7% of the weight of the uranium oxide.

(iii) Uranium-bearing materials in the form of. solids, or solidified ordewatered.materials. Uranium may be: enriched, to not more than 5.0w/.o in theU-235; isotope. Uranium-bearing materials may includeoxides, carbides, silicates, or other compounds of uranium. Theuranium compound:density shall not-exceed 10.96 g/cm3. Compounds ofuranium may Sh mixed with other nb#~fissile materials. Any degreeof moderation" ap'ay/. be present. :'r.fr

(2) Maximum quantijy;p.f maternal per package ./'//.y ' :

Weight of}contents/bovi\liner;and;steel pails shall not exceed 209pounds per. packagei'-ajt ..-;'•/:-,.. -yl--/</ .--..'

(i) For the. contents des'GjSiped^in 5(b)(l)(i),. the maximum contents perpackage shall be limited'in accordance with the following table:

Maximum U-235Enrichment

w/o2.853.063.504.104.314.604.85

/Maximum U02 PerWithout boral liner

kqs46.042.033.027.025.023.021.0

PackageWith boral liner

kas70.065.050.040.038.035.031.0

5.00 20.0 30.0

205

p I*NRC FORM 618A CONDITIONS (continued) U . S . NUCLEAR REGULATORY COMMISSION(3-96)

*


5.(b)(2) Maximum quantity of material per package (Cont'd)

(ii) For the contents described in 5(b)(l)(ii), the maximum contents perpackage, with the boral liner inserted inside the inner container,shall be limited in accordance with the following table:

Maximum U02 PerMaximum U-235 Package, withEnrichment, boral liner,

w/o kgs3.06 50.0

4.10 30.0


Maximum 17.63 kg uranium per package with the boral liner,

(c) Transport Index for Criticality ControlMinimum transport index to be shown on^;;-:';label for nuclear.qriticality control:Tl"V;C,' 0.4

6. Powder or pellets may cdnt|in any quant ity o]fjgadolini urn oxide, provided thetotal mass of uranium bx}ide. plus gadoiinium^bxide does not exceed the uraniumoxide mass limits in, 5(b)j(2}.. * *:>s<;Cr

7. For contents described^ n . 5 ^ and/or ammoniumbicarbonate additives;(brother additives'in which the H/C ratio is greaterthan 1.0 and the tota1rC^H^d0nsify.,in"tli^:ajd^iti've does not exceed 0.72grams/cm3) are permitted in.the Ud|; powder to; the extent that the C/U ratio doesnot exceed 1.27. ! , ;, \\.\ V

8. In addition to the requirements ofVubpart G of 10 CFR Part 71:

(a) The package must be prepared for shipment and operated in accordance withthe operating procedures in' section 5.1 of the application.

(b) The package must meet the acceptance tests and maintenance program ofsections 5.2, 5.3, and 5.4 of the application.


10. Expiration date: November 30, 1998.

S

1 NRC FORM 618AC (3-96)



REFERENCES

General Electric Company application dated September 14, 1993.

Supplements dated: September 22, 1993; August 24, 1995; and February 21, andMarch 20, 1996.


Date:


and Safeguards

207




a I. a. CERTIFICATE NUMBER

9023

b. REVISION NUMBER




42. PREAMBLE



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN Ok APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Nuclear Assurance Corporation6251 Crooked Creek RoadSuite 200Norcross, GA 30092

Nuclear Assurance Corporation, applicationdated November 18, 1991, as supplemented.


4 . C O N D I T I O N S . ;• ;-.,; -"-,;.,•,

This certificate is conditional upon fulfilling the requirements of lO.GFR Part 71, as applicable^ and the conditions specified below.

(a) Packaging

(1) Model No.: NL^lO/24 Vr » .. , ^ y '•"<,

(2) Description <-<; •''>:"•,'./ ''"'" ixh":- \ ._.~~_ -;' %"%/ .-j-

A lead, Water, dep$|jtejluraniumyr£rid higfefemperature^polymer shieldedshipping cask, encpfijclin stainless stetljtequipped with balsa impactlimiters., and rnount^^p'a^raiixi'ar.vihlillî'considereorlto be an integralpart of the pac|agi"ngSfofc;normal condiî.ofts of*transport. The cask bodyis 204.5 ;incheNsJ ;'ong~B^^ The^rincipal shielding consistsof 6 inches of?ifeadf;a^d''9i-ihche^ plates areencased in the ¥q|tcfni! eridffbr'gitig;a'ncl: cask inner closure head. Hightemperature .polymer^>sfte"4t'is' e^ncasedvin thebottom ,ehd and positionedbetween the innerr inôute,r/'e!J;bsure heads-at the top'' end.

The lead shield is bonded betê'erfJd.75-irich stainless steel inner shelland a 2-inch stainless steel outer shell. <TlVe outer shell is surroundedby a 0.75-inch stainless steel water jacket shell. The three shells arewelded to stainless steel forgings at both ends. Four water expansiontanks are mounted to the rail car and are connected to the water jacket bya flexible metal hose.

The primary containment vessel is comprised of the 0.75-inch inner shelland the inner closure head. It is 179.5 inches long and has a 45-inchinside diameter. The inner closure head is held in place by sixteen boltsand is sealed with a metallic 0-ring. Secondary containment is providedby the outer closure head which is bolted and has a Viton or silicone 0-ring seal. There is no direct penetration between the containment cavityand the ambient. The two penetrations into the containment cavity arefrom the space between the inner and outer closure heads, which has asingle penetration through the cask body connecting i t with the ambient.The two lid penetrations are sealed with 1.5-inch quick-disconnect valvesand metal 0-ring seals each in a valve box arrangement.

The radioactive contents are positioned within the containment cavityusing neutron poisoned aluminum baskets and internal support structures.The PWR and BWR fuel basket cavities are lined with neutron absorbersleeves composed of a silver-indium-cadmium (80-15-5 w/o) alloy.

208

NRC FORM 618A(3-9B)



5.(a)(2) Packaging (continued)


An auxiliary cooling system, mounted to the rail car, is used to maintainthe cask and fuel temperatures so as to facilitate handling and cool down.

The fully loaded cask, excluding the railcar, is approximately 194,000pounds, which includes a maximum gross weight of the cavity contents of34,100 pounds (fuel, spacers, fuel basket, etc.).

(3) Drawings

The Model No. NLI-10/24 shipping cask is constructed in accordance withthe NL Industries, Inc., and National Lead Company Drawing Nos. asspecified on page XVIIL-1, Rev. 9, and page XVIII-2, Rev. 8, in SectionXVIII of the application.

5. (b) Contents


Irradiated 'PWR ahd BWR uranium oxide fuel .assemblies of the followingspecifications:

Fuel form x

Cladding material . -V ,

Maximum in i t i a l U ','b <content/assembly, kg-.:

Maximum average ; init i at-U-235 enrichment, w/o

Maximum in i t i a l U-235. .;content/assembly, kg^

*!># r<-ft ->\" sv

• PWR x •;f 'Clad U02 p e l l e t s

; Z r _ o r ; S . S ^ ; - / /

:;: ' - '475. •:•:• :<--^'* ' > , • : * '^ . s . J.' •

16.6

BWRClad U02 p e l l e t s

Zr or SS

200

' 2.8

5.6

Maximum bundle crosssection, inches

Fuel pin array size,number of pins

Maximum active fuellength, inches

Maximum specific power,kw/kgU

Maximum average burnup,MWD/MTU

Minimum cooling time,days

9.00

14x14/15x1516x16/17x17

144

40

35,500

150

5.75

7x7/8x8

144

27

29,700

150

The PWR type assemblies may be shipped either with or without control rods.

BFwar a? w ar azw w w w w w w wazarataz at at a?atraEat aza?w w Wat at tt3aE>gt az ti: at a?wagWWwww sec



5.(b) (2) Maximum quantity of material per packageThe maximum decay heat load per package not to exceed 70 kilowatts, and:

Ten PWR fuel assemblies or twenty-four BWR fuel assemblies.

Above assemblies must be contained in their respective fuel baskets as shown onNL Industries, Inc., and National Lead Company Drawing Nos.:

70652F, Sheet 1, Rev. 7 PWR Fuel Basket,Sheet 2, Rev. 5 10/24 Rail Cask

70653F, Sheet 1, Rev. 7 BWR Fuel Basket,Sheet 2, Rev. 5 10/24 Rail Cask

5.(c) Transport Index for Criticality Control^

Minimum transport index $o be shown on ' !-.///label for nuclear crit icality control: 100 .

6. The maximum gross<weYght of the cavity contents must n6t) exceed 34,100 pounds(fuel, spacers, basket, e tc . ) . ;'%^.

7. The containmentyvessel^nMSjtvbe dry (no free watej£)X,when delivered to a carrierfor transport.. -Residua14rf#sture musXbe prbmpj|>y/removed-from the containmentvessel by the methods deprived; in^gct\on/XV]|:9:fethe application. Thecontainment vessel must ^p^pmptly/fflJedKwiflhîllium to J-."0 atm pressure.

* 8. Known or suspected fi||ed\l;u^>;assemblies^ô^^pan^fuel with cladding defects* greater than pin hol^-^nd^^^/^rteT'c^ck^taj^ôâ^horize'd.

S 9. The cask contents mus%be;^p llmp^drjund^pormailô^ditipnf of transport that3 the following mea;sured4dp;s^ ;ates-«b,ei sa; gC^1

S a) at one meter/from the exte^naijj^l^cial^m.idplane surface of the package:S 625 times tKeVn,eutron dose Va^^plls 2.5*/timesfts|ie gamma dose rate willS not exceed l,06Q;n)inirems per hour; and y.x'->"^S -'' \ ' "S b) at one meter from th^rexternal^surfac&^f the bottom of the package:g 115 times the neutronxdose|fatefpTus( 2.0 times the gamma dose rate will£ not exceed 1,000 millirems per hour.«S 10. The neutron shielding system and auxiliary cooling system must be filled with a5 mixture of water and ethylene glycol (53% to 58% by weight ethylene glycol).

g 11. The neutron shielding system must be equipped with two pressure relief valvesg (one on the cask and one on an expansion tank) set at 220 psig.BB 12. Any system used for cooling down the package must be provided with a pressure\ relief device set so that the maximum pressure in the containment vessel cannotB exceed 233 psig during the cooldown process.sf 13. The systems and components of each packaging must meet the criteria for the6 periodic tests specified in Section XVII of the application.i

2 1 0

3^

IWWWWmWWjKWWWWWjacjitWaKJiitaf ywCaLytLXKl




(i) Each packaging must meet the acceptance tests and be maintained inaccordance with Section XVII of the application, and

(ii) The package must be prepared for shipment and operated in accordance withthe Operating Procedures of Section XVI of the application.

15. Prior to first use, each packaging shall meet the criteria for the acceptancetests specified in Sections XIV and XV of the application, except that theprototype railcar test, meeting the stated design criteria, need be performedonly once.

16. Packaging is authorized for rail mode of transport only.

17. Expiration date: March 31, 1997.

REFERENCES

Nuclear Assurance Corporation application dated November 18, 1991.

Supplement dated: February*7,.^.992. . • '.

p; ' S V F O R THE U . S . .NUClliAR REGULATORY COMMISSION

Date *S

- ' ' 7 ;^ - - - William D. T r i e r s , 'Director^v '-'oX'Spent FUe'l; Pr'oject^Office ->'.

^Of^c^VpfvNuclear; Material Safety; an/d/lS;a;feguards>-'

*i

2 1 1

j

NRC FORM 618(8-85)

10 OFF? 71


FOR RADIOACTIVE MATERIALS PACKAGES1.a. CERTIFICATE NUMBER





2. PREAMBLEa. This certificate is issued to certify that the packaging_and contents described in Item 5 below, meets the applicable safety standards set forth In Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJDESIGN OR APPLICATIONa. ISSUED TO (Name and Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation applicationdated August 3, 1995, as supplemented.

» Uc. DOCKET NUMBER

4. CONDITIONS <This certificate is conditional upon fulfillingktlT&requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model NosV? 741

(2) Description

A steel ^.y-..-consist of anmaterial j êppositioned*^ ....Tamper-proVlrsealshipping p l \ i %protection during transport340 pounds. '''"

(3) Drawings

P Prêctor.primary components---*-*--'-fa pol^yrethane potting

thje contents are securelyvice and shipping plug,

packaging andîp 1/4-inch thick steelg m^lfjanism for additionalaf tfre package is approximately

The packaging is constructed itfâccordance with the following AmershamCorporation Drawings:

(i) Model No. 741 and 741E - Drawing No. R74190, Sheets 1-5, Rev. B; DrawingNo. R67692, Rev. A; Drawing No. R67691, Rev. A.

(ii) Model No. 741A, 741B, 741AE, 741BE - Drawing No. R74190, Sheets 1-5,Rev. A; Drawing No. R85790, Sheets 1 and 2, Rev. A; Drawing No. R85791,Sheets 1 and 2, Rev. A.

Model Nos. with an E suffix have an electrical circuit.

212

NRC FORM 618A(6-83)




(b) Contents


Cobalt-60 or iridium-192 as sealed sources which meet the requirementsof special form radioactive material.


33 curies of cobalt-60; or240 curies of iridium-192 (output).

Output curies are det^rjnineOKaecondance with American NationalStandard N432-1981K |R)adMologicTlî^Wfor the Design and Constructionof Apparatus io\J?alfima Radiography." ^-stf,u *>

The source shall be ^ûred in the shielded position ofêhe packaging by thesource assembly, fifo source assembly must be fabricatea^ftikmaterials capable ofresisting a 1475 *F^fire environment for one-half hpjâriq>maintaining theirpositioning fundgH^n. xjfte^purce assembly must —*-*•-/^~ •>£-•"-- J-..J— Tp g gsource assembly|rmjfstpositioning of

7. In addition toe

(a) The package" shalwith the Qjf|rati

(b) The packag8.0 of the

8. The package authorised by thisgeneral license prov^fans of 10

9. Expiration date: Februanf 28.^2001.

Amersham Corporation application dated August 3, 1995.

Supplements dated: August 15 and November 22, 1995.

the Jacking device. Thetojjrovide positive

m shieldCalsembly.

accordanceion; and

Program of Section

ed for use under the


Date:


and Safeguards

2 1 3JKJi^

NRC FORM 618(&S5110 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESLaXERTIFiaWB NUMBER b. REVISiON NUMBER C.PACKAI IMBER <J. PAGE NUMBER o. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theapplicable safety standards set forth in Title 10, Code



a. ISSUED TO (Name end Address!



Amersham Corporation, Inc. applicationdated October 12, 1995, as supplemented.

•ft R* "c. DOCKET NUMBER

. CONDITIONSThis certificate is conditional upon fulfilling the'requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging {,

(1) Mode

(2) Description

and 684BE684&.684E, 684A, 684AE/5S

the ^the soysce ldcfcing\taec;The totJa^weight o" '

(3) Drawings

sicons*1

Projecto^. Primary componentsracingSCpolyurethane

" ZS" tube. The... ^ ^by a source cable

Tampj^jproof c§|als are provided on•~jd$M^ shipping plate is bolted over

xôr addJlfonal ppê'ction during transport.225 pounds.

The packaging isic dns.t'fcuctejd inâc-CjOgdance with the following AmershamCorporation, Inc., DrawingÎos|^ Y

R68490, Sheets 1 through 5 of 5, Rev. B, and

for 684 and 684E:R67691, Sheet 1, Rev. AR67692, Sheet 1, rev. A

for 684A, 684AE. 684B and 684BE:R85790, Sheets 1 and 2, Rev. AR85791, Sheets 1 and 2, Rev. A

2 1 4

^

\fff^

NRC FORM 618A(6-B3)




8.

(b) Contents


Cobalt-60 or iridium-192 as sealed sources which meet the requirementsof special form radioactive material.


11 curies of cobalt-60; or240 curies of iridium-192 (output)

Output curies aref|le^ri™eo^n™a€So|danrce with American NationalSatandard N432.-U9.8'0* "Radiological SafeCôr the Design and Constructionof ApparatusIgp'r^Gamma Radiography." ? X

The source shall bjêcured in the shielded position ofHt& packaging by theshipping plug, sour"Ge^ssembly, and locking device. .T je lapping plug and sourceassembly must befifebri^cated of materials capablejjrf£î sting* a 1475°F fire

nd maintaininggbr?c|

environment for/pfie-hal^hjball stop of th^source a'scable of the sotfrce assemdiameter to pratfide posit

Tositioning function. Thei d f e Th f l i b l

The name platek^shaltest of 10 CFR^rt

In addition to

(a) Each packagftfof Chapter 8

req

usthe appli

The flexiblebe of sufficient length andce in the^shielded position.

i

isting the fire

Program

(b) Each package mus'lMj.ewepared for shipment andêrated in accordance withthe Operating Procedures of Chapter 7 of the, application.

9. The package authorized by this ce»i%fi^p;e<Ws hereby approved for use under thegeneral license provisions of 10 CFR §71.12.

10. Expiration date: January 31, 2001.

2 1 5



NRC FORM 618A(6-83)


REFERENCE

Amersham Corporation, Inc. application dated October 12, 1995.

Supplement dated: December 28, 1995.


Date:

William D. Travers, Directori SpmticfueJ Project Office^Of?M*teNWl^ear Material Safety

and SafegOa^s.

2 1 6

NRC FORM 618

CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES.CERTIFICATE NUMBER





22. PREAMBLE

a, This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theappiicabiesafety standardssetforth inTitie 10, Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATION *». ISSUED TO (Nime end Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation, application datedSeptember 16, 1991, as supplemented.

£"=»>

C. DOCKET NUMBER

4, CONDITIONSThis certificate Is conditional upon fulfilling;theRequirements of 10 CFR Part 71, as applicable, and the'corjdi.tions specified below.

(a) Packaging / ^ .,

(1) Modeled!. 676 arfd^676E, 676A, 676AE,

(2) Description

o..6Z6B.E

c-

tube by a source cablelocking; dey\ce:^nliclJshi.^|i)g'||j]!ijg^Tamp6MB>/'oof seals are provided onthe pa'c^kagingâ^/^--^^4544)^h[5j?H.!i?^^te§3^^fiiPPing^plate i s bolted ovethe source loelcin'gfcêchan^MftifliFbr idd ional protection during transpo

(3)

the source loelci'h'gtêcKaijî^br^fTîohal protection during transport.The totaf .weight of^theCoaqicagi^g jiSpapproximaêjly 545 pounds.

Drawings ^S^W

5. (b)

(1)

(2)

The package is cofts truqjted in accordance with the following TechnicalOperations, Inc., Dra^jhgôs.^V A

(i) Model No. 676 and 676E - Drawing No. 67690, Sheets 1-5, Rev. H;Drawing No. 66025, Sheets 2 and 3, Rev. Al.

(ii) Model No. 676A, 676AE, 676B and 676BE - Drawing No. 67690, Sheets 1-5Rev. H; Amersham Corp. Drawing No. 85790, Sheets 1 and 2, Rev. B.


Contents


Cobalt-60 as sealed sources which meet the requirements of special formradioactive material.


330 Curies.

jitiumj^jt^&jii!j*^K»uwAMttA2m2^^

Si^S7 !f^^

NBC FORM 61SA(6-83)



6. The source shall be secured in the shielded position of the packaging by theshipping plug, source assembly, and locking device. The shipping plug andsource assembly used must be fabricated of materials capable of resisting a1475°F fire environment for one-half hour and maintaining their positioningfunction. The ball stop of the source assembly must engage the lockingdevice. The flexible cable of the source assembly and shipping plug must beof sufficient length and diameter to provide positive positioning of thesource in the shielded position.

The nameplates shall be fabricated of materials capable of resisting the firetest of 10 CFR Part 71 and maintaining their legibility.

7.

In addition to the requirements^pf

(a)

of 10 CFR Part 71:

ftThe package shaR ^prepared for shipment and operated in accordancewith the OperaQpVProcedures in Section T^f.K(dated September 1991) ofthe applica^T-qnT and " f\

(b) The packaitpoiust meet the Acceptance Tests an^Ma^ltenance Program ofSection/fikO o^t-h^ application. ^ ^ s JL,

by approved for use underThe package authorize_the general Ipr-ovisions

10. Expiration elite:

Amersham Corporation^ppl

Supplements dated: €ebruary 20,September 6, 1994; ancfj^bruary 3,

0§, September 4 and 11, 1992;

FOR THE U.S. %CLEAR REGULATORY COMMISSION

Cass R. Chappell,'Section LeaderCask Certification SectionStorage and Transport Systems BranchDivision of Industrial and


Date:ffl 0 B 995

218

_ . , - -

^

NRC FORM 618

10 CFR 71



I.O.CERTIi IMBER b. REVISION NUMBER C.PACK IBER d.PAGENUMBERIENUW e. TOTAL NUMBER PAGES

_ PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



a. ISSUED TO {Name and Address)

Department of the NavyNaval Support Force, Antarctica651 Lyon StreetPort Hueneme, CA 93043-4345


Teledyne Energy Systems application datedNovember 12, 1990, as supplemented.

REG*.mMBER71-903.07/c. DOCKET N

CONDITIONS cv " W ' ^ V f »N

This certificate Is conditional upon fulfilling>thVrequirements of 10 CFR Part 71, as applicable, and th&'conditions specified below.

(a) Packaging

(1)

(2)

J^Nos.:

D&cription

#3.000 and

The^major componentsIiield,, housing flange, andi-"fti,mension& and weights for the

M«f3Q,00SentlnJl-8

Weight Hb)

2,7003,200

(3) Drawings

The packagings are Gon^tructea7in>avecordance with the following DrawingNos.: ^ >•* ^

Model No.MW-3000Sentinel-8

Drawing Nos.Martin Co. Drawing No. 471A1000000Isotopes, Inc. Drawing No. J-30856-003-10000

(b) Contents


Strontium 90 titanate doubly encapsulated in Hastelloy fuel capsulewhich meet the requirements of special form radioactive material.

(2) The maximum quantity of material per package

Model No. Quantity

MW-3000Sentinel-8

25,000 Curies40,000 Curies

219,

*£rttrX&ii&t^JM&&*&^

NRC FORM 618A(6-83)



II

\

\

I

\

6. Eye-bolts shall be removed or covered during transportation to prevent theiruse as tie-down devices of packages.

7.

8.

9.

The MW-3000 and Sentinel-8 shall have their top steel cover plate bolted tothe outer wrought steel shield at all times except when maintenance operationsare being performed on the generator which require removal of the top steelcover plate.

Fabrication of additional units is not authorized.

In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) The package shall be^p^gared feMpi^flfc?and operated in accordance withthe operating pr-ofeed6res'in the supplernen^dated February 1, 1991.

(b) The package «s%TT be maintained in accordance -wU-h the maintenance programin the suptf|pent dated February 1, 1991. xJ,

10. The packagesjgauthofeedby this certificatethe general/Jjcense^p^i&lfrsjons of 10 CFR K7pgthe general

11. Expirationittete: Oct

Teledyne Energy^stem

Teledyne supplement daf

Department of theWvy

proved for use under

September 20, 1995.

FOR THE U.S. NUCL^R'REGULATORY COMMISSION

liam D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand Safeguards

Date:

I

220

^

f

NRC FORM 618(M6)

10 CFR 71" *CERTIFICATE OF COMPLIANCE


R 5 ° U L A T 0 B Y C ° M " " S S " " <

^-CERTIFICATE NUMBER




i, PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



3, THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATIONa. ISSUED TO Warns and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation application datedSeptember 24, 1993, as supplemented.

» c. DOCKET NUMBER 7IsS032

4, CONDITIONS • • <^J%J) ^ ' ^ - f <uThis certificate is conditional upon f u l f i l l i n g ^ requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging^ ^

(1) Model No.:

h(2) Description *

A-steel %6asmf^MTwttfn^d^hdium-19Z Jource changer.

ilrt'ej sBfe ho ld |» asselb,ly sg ^

hol'd dowWs^esdQ^ce aprooY^^sealk^weigh't'of the

(3)

and sourcesecures the

in^tM^crimpecl^U" tube. Tamper-" ' " " ^ on thel^packaging. Total

i 905ppunds.; ^ f

The packaging constructed in accordance with the TechnicalOperations, Incf D?awing\No<65002\ Rev. F, Sheets 1, 2, and 3.

"v p~\ lr*\(b) Contents


Iridium 192 as sealed sources which meet the requirements ofspecial form radioactive material.


240 curies

2 2 1

^^


6. The source shall be secured in the shielded position of the packaging by thesource assembly. The source assembly must be fabricated of materials capableof resisting a 1475° F fire environment for one-half hour and maintaining itspositioning function. The cable of the source assembly must engage thesource hold-down assembly. The flexible cable of the source assembly must beof sufficient length and diameter to provide positive positioning of thesource at the crimp of the "U" tube.

7. The nameplates shall be fabricated of materials capable of resisting the firetest of 10 CFR Part 71 and maintaining their legibility.


(a) Each package must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application, and

(b) the package shall be prepared for shipment in accordance with theOperating Procedures of Chapter 7 of the application, as supplemented.


10. Expiration date:. October 31, 1999.

REFERENCES .

Amersham Corporation application dated September 24, 1993.

Supplements dated May 10, and August 1, 1994.


I Cass R. Chappell, Section Leader88 Cask Certification Section

Storage and Transport Systems BranchDivision of Industrial and

B cm on «MM Medical Nuclear Safety, NMSS• :{)tr c U 1934

i Date:

222

i/«M«MaMim^BX«M«Mi»M«mBMaMBM«MnMaMaM»M»M»a<««»«a»«g«»a»gMB»gM»»(

V Y»\'7iV Y»YY»VY«Y7»Y Y»Y Y»Y.Y»Y.Y»Y Y»YY»Y7*Y Y»YY»\"/iv Y»YY»Y.Y»Y7»Y

NRC FORM 618(B-86110 CFR 71



9033

b. REVISION NUMBER

10

c. PACKAGE IDENTIFICATION NUMBER d. PAGE NUMBER

1


2'REAMBLEa. This certificate Is issued to certify that the packaging and contents described in Item 5 below, meets theapplicable safety standards setforth inTitle 10, Code


b. This pertlficate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.



'Amersham Corporation application datedSeptember 24, 1993, as supplemented.

Pi' c. DOCKET NUMBER

4. CONDITIONS C;, ' ^ J > ~ * " V ? <vThis certificate is conditional upon fulfilling the-requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a)

oPackaging

(1)it* -V;*

Model No.: 660v^66pE, 66QA,- 660AE;f66flB or

Description ~^f / £* \ \'':^fj

660BE,

(2) Description

p a ^ g e is approximately 53 pounds.

(b)

(3) Drawings^./

The packaging i^constructed in accordance with the following TechnicalOperations, Inc.,-Drawing^: ^ <If

(i) Model No. 660B - Drawing No. 66025, Sheets 1, 2 and 3, Rev. F;

(ii) Model No. 660 - Drawing No. 66025, Sheets 1, 2, 3, and 4, Rev. B;or Drawing No. 66030, Sheets 1, 2, 3 and 4, Rev. -;

(iii) Model No. 660A - Drawing No. 66030, Sheets 1, 2 and 3, Rev. A; orDrawing No. 66030, Sheets 1, 2, and 3, Rev. D.


Contents


Iridium-192 sources which meet the requirements of special form radioactivematerial.

2 2 3

NRC FORM 618A(6-83)





(i) 140 Curies for the Model No. 660B or 660BE package.

( i i ) 120 Curies for the Model No. 660, 660E, 660A or 660AE package.

The source shall be secured in the shielded position of the packaging by the sourceassembly. The source assembly must be fabricated of materials capable of resist inga 1475 °F f i re environment for OBe-HBpfphjffttrs

and maintaining their positioningfunction. The source assemh^puJtênga3ge='"6hl (yoking device. The source assemblymust be of sufficient ideftglRând diameter to proAqê} positive positioning of thesource within the depjit^d uranium shield assembly. V J k

7. The source assembl^ôr use with this packaging is 1 imited- fao Technical Operations,Inc. Model No. 424^<Las shown in Technical Operations?, v | hc . Drawing No. 42409,R e v-C-The name pi ate^must beof 10 CFR P a r t m and

In addition tqjrhe re

The pack |^8.0 of the appl

10.

(a)

(b)Procedures^"

The package authorised5 of<

The package^sjhaProcedures Vri.C

license provisions

11. Expiration date: October 31^2000! A

of reflating the fire test

Program of Chapter

cordage with the OperatingZ. il emented.

^ved for use under general

REFERENCES

Amersham Corporation Application dated September 24, 1993.

Supplement dated: March 31, 1994; June 28, 1995.


AUG 1 0 1995Date:

Cass R. Chappell, Section LeaderCask Certification SectionSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

224

ggggp

ggggggggggggggg£





9034

b. REVISION NUMBER

11


USA/9034/AF

A PAGE NUMBER


2, PREAMBLE




General AtomicsP.O. Box 85608San Diego, CA 92186-9784


General Atomic Company applicationdated October 4, 1995, as supplemented.

c. DOCKET NUMBER 71~90344. CONDITIONS , ., •; . ' • ,.


5.

(a) Packaging

(1) Model No.: TRIGA-I

(2) Description XS x

the inner veslel ^e7approximatel^31?^nches/in height with a 1/4-inchthick wall >n4'-?l^^liiins1dK!dii;aiStfer,i/0^-top.:pf the inner vessel isa threaded pipe(':'c$P an^the bo^tbmuis alwelded l/4>inch thick flat disc.The inner vessel .is^cerjtered! and^suppprted within-ihe outer packagingby eight,- 3/8^Wch:;;dfametery;bnace"dV~Support spacer, rods. The voidbetween*the inner vessel/^djhle^outerpackaging)"is filled withvermiculite tamped to a M.riiniUni"density of 4.!5_.lbs/ft .weight including contents' s!<;>a"pproximately,:-23j5 pounds.

Maximum gross

(3) Drawing

The packaging is constructed in accordance with General Atomic CompanyDrawing No. T0S396C160, Rev. G.

225

± ^



5. (b) Contents


TRIGA fuel elements containing uranium-zirconium-hydride orerbium-uranium-zirconium-hydride with nominal fuel composition (excludingerbium content) as described in Table A.1-1 of the October 4, 1995application, and clad with stainless steel, aluminum or incoloy. Uraniumenriched to a maximum 93.5 w/o in the U-235 isotope. The H to Zr atomicratio within the fuel meat must not exceed 1.65.


U-235 content not to exceed 1.39 kg, contained in a maximum of 71.5-inch diameter ;fueTselement's, .or?a;<maximum of 25 0.5-inch diameterfuel elements,.with nominal fuel composition (excluding erbium content)as described in table A.1-2 (Rev. 1) of the October 4, 1995, application.For enrichments greater than 5 weight percent U-235, uranium content notto exceed an A2 quantity.

(c) Transport Index for dtijicality Control ;:

Minimum transport inclex^fo be shown on .,.<.'- ;•label for nuclear cr ideality control: s > ;.'

; }p\ 0.4

6. In addition to the requirements;,of 'SuB^rt<G;of/l|;'CFR Part 71:.

(a) The package shalt;ie; prepared fpr> shipmeny-and;fpp6|rated in accordance withthe Operating ProceJ^ures? df;Chapter ;8 6f the application;.

(b) The packaging-must me§t.-the Acceptance>Iests and Maintenance Program ofChapter 9 of the application./^^ <; v * <" :•<••'

7. The package authorized' by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12.

8. Expiration date: December 31, ,2000.. \

REFERENCES

General Atomic Company application dated October 4, 1995.




and Safeguards

Date: 3 | -226

NRC FORM 618M6I

CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES{.CERTIFICATE NUMBER



USA/9035/BfU)d. PAGE NUMBER


2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



3, THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJDESIGN OR APPLICATION 'a. ISSUED TO IName and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation application datedSeptember 6, 1994, as supplemented.

0i RE'c . DOCKET NUMBER

A. CONDITIONS ^J 'Thfs certificate (s conditional upon fulfilllngjherequirements of 10 CFR Part 71, as applicable, and tha'conditions specified below.

(a) Packaging

(1) Model >£:_'; 680, 680E^f.80A, 6jB0AE .. 689B "a|d|6'j

(2) Description ' ri&f f f~ { %,1^0f C'"\A steel ren^cased.Uraniqm>si)T!elided Gami a^Ray^Projector. cîmary componentsconsist of-an outer.st^îitfeiini^Tnl^rpai^bra^fij^ polyurethane pottingmaterial^4epl^te^S%^niW5h'aepd;}j1(a$d.'an' "S^/M^be. Th^1 contents are securelypositione^Tin the' S;^fcube^By| al]s.du)|<c«âble^)t:king ^[eVice and shipping plug.Tamper-propf^seal's^îl^^^^dejlj.lp'riyt-^^pacâigT'ng and 1 /4 - th i ck steelshipping pTate is ^l'te'dvoverîH^so^Vc^î^Gking mechanism for additionalprotection during transp'ort/.^JhiaViiiax'imum/height p.f^the package is 450 pounds.

.-•/?.<' ' i . ' A] --%" f^%^(3) Drawings !^/f)) * " e \S^

The package is construcêdîn accordanc^r-with Sentinel, Amersham CorporationDrawing No. R68090, Rev. B^ShYet's^ttJj and" lock Drawing No. R85790, Rev. A,Sheets 1 and 2; 85791, Rev/A,"Sheets 1 and 2; 67691, Rev. A; or 67692,Rev. A; as appropriate.


5. (b) Contents


Cobalt 60 as sealed sources which meet the requirements of special formradioactive material.


110 curies (output)

Output curies are determined in accordance with American NationalStandard N432-1980, "Radiological Safety for the Design and Constructionof Apparatus for Gamma Radiography."

227 / »

^^NRC FORM 618A(6-83)


iIi

IIi

(f

!

8

1


age 2 - Certificate No. 9035 - Revision No. 11 - Docket No. 71-9035

6. The source shall be secured in the shielded position of the packaging by theshipping plug, source assembly, and locking device. The shipping plug, sourceassembly used must be fabricated of materials capable of resisting a 1475 "F fireenvironment for one half hour and maintaining their positioning function. The ballstop of the source assembly must engage the locking device. The flexible cable ofthe source assembly and shipping plug must be of sufficient length and diameter toprovide positive positioning of the source in the shielded position.

7. The nameplates shall be fabricated of materials capable of resisting the fire testof 10 CFR Part 71 and maintaining their legibility.

8. In addition to the requirements ofSubparjt, G p f 10 CFR Part 71:

(a) The package must meet f^SA^ceptance Te§tl=4nd Maintenance Program ofSection 8 of the atfpjxteation; and ^ € ?

(b) Each packageSection 7 of

be operated and prepared for sh gjlient in accordance withapplication. ^

9. The packagegeneral license^ovisio"

10. Expiration datek^, April 3

Amersham CorporationVappli

Supplements dated:

pprovexhfor use under the

stLEAR REOPLATORY COMMISSION

pp Section LeaderTfication Section

Storage and Transport Systems BranchDivision of Industrial andMedical Nuclear Safety, NMSS

Date: April 28. 1995

228

« i j ^ ^ ^

^

NBC FORM 618IMS)10 CFR 71



9036

b. REVISION NUMBER

R


1


9

flEAMBLEa. This certificate is issued to certify that the packaging and contents described in Item S below, meets the applicable safety standards set forth in Title 10, Code

of Federal Regulation's, Part 71, "Packaging and Transportation of Radioactive Material."

b. This pertificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASISOF A SAFETY ANALYSIS REPORTOF THE PACKAGEJ3ESIGN OR APPLICATION 'a. ISSUED TO /Name end Address) ~ b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Source Production & Equipment Co.113 Teal StreetSt. Rose, LA 70087-9691

Source Production & Equipment Companyapplication dated November 13, 1989, as

"amented.' 1' &

C. DOCKET NUMBER

CONDITIONS <K \ * £ * 71-90*310 t-This certificate Is conditional upon_fulfilllng;Jhe'requirements of 10 CFR Part 71, as applicaele, andTne/condtfions specified below.

(a)

(b)

Packaging

(1) Model

(2) Description

The p gradi ographi ca rectangularfittingsjjmd so1/8" carbon steW oshield equipped with twomay house on,e>"pigtail typ'

a uranium shielded% configuration is that of

w i d | J 7.5" deep. All_4 ^ protected and enclosed with a

Ehe ilmlpreceptacle consists of a uranium^tGip^rcal loMU" tubes, each of which

„ r.a _ , r _^ r . . : i a l form soured The overpack is a 12-gallon, 20- d^2;2-gage steel drum partiallWWled with foam. The weightof the source changer, is 51 to 70 lbs. Th^teight of the overpack is 19to 22 lbs. Up to 8lj-bs^of^ncil/l4ryM]uipment may be included within theoverpack. The maximum gvpss^eigjit ofthe package is 100 lbs.

(3) Drawings

The package is constructed in accordance with Source Production &Equipment Company Inc. Drawing Nos. 11489-1, Rev (4); 11489-2, Rev. (3);and 61090, Rev. (0).

Contents


Iridium-192 as sealed sources that meet the requirements of special formradioactive material.


Two sealed sources with a combined activity not to exceed 240 curies.

229

^S^^-^^^^Z-*^^

f

1i

II

•t

II|I

ngy\W7YgAr

NRC FORM 618A(6-63)

U.S. NUCLEAR REGULATORY COR/MISSIONCONDITIONS (continued)


6. Tungsten shield pads, with dimensions up to approximately 2-inches diameter and1/2-inch thick, may be welded to the inside surface of the source changerhousing.

7. The nameplate shall be fabricated of materials capable of resisting the fire testof 10 CFR Part 71 and maintaining its legibility.


a. The package shall be prepared for shipment and operated in accordance withthe Operating Procedures of Section 7.0 of the application dated November13, 1989, as supplemented June 19, September 24, and October 17, 1990.

b. The package must meet iheM|c%piia1iQfefgstând Maintenance Program ofSection 8.0 of the apppiation dated Noveinb|r 13, 1989, as supplemented June19, and Septembenf2|ri990.

The package authored by this certificate is hereby amoved for use under thegeneral license provisions of 10 CFR §71.12.

10. Expiration dateFÔcto^-^ 1 "nnn ^ ^ ^

Source Production |t=EquipmJuly 13, 1990.

d Jêmber§L3, 1989, and

Supplements dated: JuneDecember 6, 1993; &%

5l990jôvember 29, and

U.S.*NUCLEAR*REGULATORY COMMISSION

fection LeaderSection

SpentFuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

SEP 1 5 1995

Date:

230

NRC FORM 618(3-96)10 CFR 71



I, a. CERTIFICATE NUMBER

9037

b. REVISION NUMBER

11


USA/9037/AF

d. PAGE NUMBER

1


22. PREAMBLE



3, THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

General AtomicsP.O. Box 85608San Diego, CA 92186-9784

General Atomic Company applicationdated October 4, 1995, as supplemented.


4. CONDITIONS . .„. . . .

This certificate is conditional upon fulfilling the requirements of 10 CFR. Part 71, as applicable, and the conditions specified below.

33

is

(a) Packaging

(1) Model No.: TJfrGA-II - ,

(2) Description >;<>:, . „ --''W'

TRIGA fuel element.Shipping'contafneW>>fhe outer packaging is a steeldrum, .approximai«lyk2£.5--inches- ijrdja;i|ter by 57.5-inches high. Theinner vessel^ITS a-^incfi Schedulev;4Cp^fc>0T|?steel pipe. Dimensions ofthe inner ve;ssj;i aretapproximite^y/5p'1nc})es^;in height with a 1/4-inchthick wall andv£/,:5,jinchV™^ top of the inner vessel ia threaded pife cap ancf;>iW-bottom>is a/wefded 1/4-inch thick flat disc.The inner vessil nsT'centere^. arid -^supported within .the outer packagingby eight,. 3/8-irichvdXame^f^-:brVced, support spacer rods. The voidbetween the inner vesseifKnd'\\t;fie 'outer packaging' is filled withvermiculitevtamped to a minimum density of 4.5 lbs/ft3. Maximum grossweight including contents is approximately*330 pounds.

(3) Drawing ; " .

The packaging is constructed in accordance with General Atomic CompanyDrawing No. TOS396C161, Rev. F.

2 3 1

£J£J£JK

aNRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


5. (b) Contents


Special function TRIGA fuel elements containing uranium-zirconium-hydrideor erbium-uranium-zirconium-hydride whose fuel portion has nominalcompositions (except erbium content) as described in Table A.1-1 of theOctober 4, 1995, application, and clad with stainless steel, aluminum orincoloy. Uranium enriched to a maximum 93.5 w/o in the U-235 isotope.The H to Zr atomic ratio within the fuel meat must not exceed 1.65.


U-235 content not to exceed 1-39 kg,, contained in a maximum of 71.5-inch diameter ftiel;>^lemehtsv^6r/-a/maximum of 25 0.5-inch diameterfuel elements, ,whose;fuel portion has nominal compositions (except erbiumcontent) as .described in Table A. 1-2 (Rev.il);of the October 4, 1995,application^For enrichments greater than 5>weight percent U-235,uranium content not to exceed an A2 quantity. ;.

* (c) Transport Indjsx forVGrJReality Control

g Minimum transport ind^fq be shpwnr.qnlabel, for nuclear cri|^c|lity control: ,5;^> °*4

In addition to tKe requ^pBiî^:8fjSuâirt-6<d^^'CFR.Part 71:

(a) The package'}shalTSetpre1>'^ accordance withthe Operating, Procedyesjo-Ttha'piielri'S; of'the appl i cation,

t mppf AhfiÂrrpntahce^psts ,and Maintenai(b) The packaginûstêfit^^'^Mpt^hceês^^rjd Maintenance Program ofCh 9 f " " ^ f i t i o ^ | p ^ </* 'Chapter 9 of""îe,appfication.,^|(p^.v .:i</./ . >

7. The package authorize^;By^this certificate is hereby\approved for use under thegeneral license provisions of 10 CFR §71.12. I v

8. Expiration date: December 31, 2000.^ - '

REFERENCES

General Atomic Company application dated October 4, 1995.



W\ (William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

Date:232

&

^

NRC FORM 618(W6)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.«. CERTIFICATE NUMBER 9039

b. REVISION NUMBER IBER d.PAGEJJUMBERSEJ4I e. TOTAL NUMBER PAGES

. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORTOF THE PACKAGEDESIGN OR APPLICATION 'a. ISSUED TO INama and Address! ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation applicationdated May 11, 1995, as supplemented

c. DOCKET NUMBER03ft

A. CONDITIONSCONDITIONS v^s^ « * ? # ^This certificate Is conditional upon tful(illlngxthb\equlrements of 10 CFR Part 71, as applicable, and trie'conditions specified below.

(a) Packaging^

(1) Mod'e-l^No.:

an(2) Descffptioii^&U. -%m\l

e overpack consists ofan M S ^ ^ 8 3 - z ^ 8 ^ ^ * ^ ^ ^ f Q | s s a i p & i u g e clfinfclosure ring fastenedby a bqlfr; 1.5rincffes 9;fm|l|^2J81.?o^-Mil-28^:frigh temperatureinsulatipjf;-, and a moldemfubp|^zedChi^r finJirCliaterial. Overalldimensionsj>f the overpacKAaWapproximatel^dlS.5-inch diameter by24-inch higliOMaximum weight including £ggterits is 105 pounds.

(3) Drawings ^ ^

The radiographic devices, as secondary packaging authorized for use inthe overpack are constructed in accordance with the following Sentinel,Amersham Corporation Drawing Nos.:

Model No.

Overpack533616644713

Drawinq Nos.

R715, Rev. BR53390, Rev. AR61690, Rev. AR64490, Rev. AR71390, Rev. A

233

ft^^

NRC FORM 618A(6-83)




8.

10.

(b) Contents


Iridium 192 as sealed sources that meet the requirements ofspecial form radioactive material.


(i) 120 curies (output) contained in the Model No. 533, Model No.644 or Model No. 713 radiographic device.

( i i ) 240 (output) flraneOc|3itarined in the Model No. 616radiogra£h|XcfevicB. *•= v? (J *

Output cQjIes are determined in accoroanê with American NationalN432-1980, "Radiological Safe*5\for the Design and

ruction of Apparatus for Gamma Rawwraphy."

ted £&»those assemblies asC4240H, Rev. F, Sheet 2,

Source assembidentified iand Sheet 3

Separate mol^d f i l l e r sto ensure a.srlug fi

Nameplates sfbSjpl bof 10 CFR Part 71

9. In addition t(rxtoe r

in this packaging ar,ations, Inc. Dr

Nos 42409, (p9. B.

Wuiographic device

(a) The packageîfoall be prwith Sectionîbf the applic1

andas supplement

resisting the fire test

71:

ted in accordance

(b) Each package musts&e tasted and maintained in%accordance with theacceptance tes t s and Mwtgdanc j j r j l a ra i^n section 8 of the application,as supplemented.

a n c ^ p r ^

The packaging authorized by this cer t i f icate is hereby approved for use underthe general license provisions of 10 CFR §71.12.


234

^

U.S. NUCLEAR REGULATORY COMMISSIONNRCFORM618A(6-83)



REFERENCE

Amersham corporation application dated May 11, 1995.

Supplement dated: November 29, 1995.


/ " • " • ' ^ /

WiTliam D. tr'ayers, DirectorSpent Fuel Project OfficefiS£dPof>lui:lear Material Safety

Date

235

uiK^^

i

;E

NRC FORM 618(8-85)10 CFR 71



9049b. REVISION NUMBER 0. PACKAGE IDENTIFICATION NUMBER






3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORTOF THE PACKAGE DESIGN OR APPLICATION 'a. ISSUED TO {Name and Address) " b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

II

i

Advanced Medical Systems, Inc.1020 London RoadCleveland, OH 44110

\S.

Advanced Medical System, Inc. applicationdated September 28, 1990, as supplemented.

C DOCKET NUMBER^ 9 0 4 9

4. CONDITIONSThis certificate is conditional upon fulfilling;theVequirements of 10 CFR Part 71, as applicable, and ths'condi.tions specified below.

(a) Packaging

(1) Mode'MNo.:

(2) Description

cavi ty-;drai T^biiie^i

It isf1anged

a ^ ^ i n l e s ^ t e e l or fusible plug" c r ip t io^ fs as follows:

VCasVH§ight, inCask^Jjetmeter, inCavity ifpght, inCavity diameter, inLead s h i e l J " ^ProtectiveProtective jacket width, inPackaging weight, 1b

ty diameter, in . 7.0shieldingfwL _ A A- <XlO.Oactive jackeirHeiiKt, m 38.9

40.758,100

(3) Drawings

The packaging is constructed in accordance with the following GeneralElectric Company Drawing Nos.:

212E246, Rev. 7106D3870, Rev. 11706E790, Rev. 4

106D3855, Rev. 4129D4690, Rev. 0

2 3 6

NRCFORM818A(MI3)



5. (b) Contents


Byproduct material meeting the requirements of special form radioactivematerial.


Radioactive decay heat not to exceed 780 watts.

jj^ents during accident6. Shoring must be provideconditions of transpo

7. Package contents be delivered to a carrier dry.

8. Prior to each sh0fliengasket must be yarflacedoccurs first. .Cavitythreads of pipe*T?lug,

9. In addition tojlhe reqprepared for spTpmenChapter 7.0, aijrfSection 8.2 of the ap

10. Fabrication of a

11. The package author^general license pro'v^tfons of 10

V)12.. Expiration date: DecemDef 31,^2000.

icone rubber 1ection shows

inspected. This12 months,

e sealant applied to

'the package must be;ing Procedures of

•tenance program of

for use under the

Advanced Medical System, Inc. application dated September 28, 1990.

Supplement dated: October 9, 1995.


Date: Jl


and Safeguards

237

NHC FORM 618(W6)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES' a. CERTIFICATE NUMBER





2PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standardsset forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORTOFTHE PACKAGE.DES1GN OR APPLICATION 'a. ISSUED TO IName and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Source Production andEquipment Company, Inc.

113 Teal StreetSt. Rose, LA 70087

-, v

Source Production and Equipment Company Inc.,application dated March 13, 1989, as

^supplemented.

c. DOCKET NUMBER

A. CONDITIONSCONDITIONS Cv %J-> '->•'/ <This certificate is conditional upon fulfillingthe'requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model NqyT?

(2) Description

A steel encased,consist of .'.'._,_.and a ZJigcalloy^S"Zircalloyunit rest:ernbleshigh by '4?3,,

-..^.âmmilRay^Projector^ Primary components1, int^rn^;lb1facing, depleted uranium shield,rconteM'sâreêcurely positioned in the

(3) Drawings

The packaging«''iWonstructedlinvaccordance wi,tOource Production andE i t C ' h I D i N 1 8 8 l ^ t (

p g g OEquipment Compa'hy, Inc. Drawing Nos. 12688-l^tRev. (2); 788-1, Rev. (4);and 788-2, Rev. ( 0 ) . r l . , ^- *

•-i jr;? -dh- W "y^The packaging may also be Is shWr'Tn Source Production and EquipmentCompany Drawing No. 1000, Rev. (0), provided fabrication was completedprior to June 8, 1989.

The oyerpack is a 12 gallon open head 20 or 22 gauge National Motor FreightClassification 100-H, or succeeding issues, Item 260 steel drum constructedin accordance with Source Production and Equipment Company, Inc. DrawingNo. 53189-2, Rev. (2).

(b) Contents


Indium 192 as sealed sources which meet the requirements of special formradioactive material.


225 curies238

^

^WNRC FORM 618A(6-63)


ge 2 - Certificate No. 9056 - Revision No. 10 - Docket No. 71-9056

6. The source must be secured in the shielded position of the packaging by theshipping plug, source assembly, and locking device. The shipping plug and sourceassembly used must be fabricated of materials capable of resisting a 1475°F fireenvironment for one-half hour and maintaining their positioning function. Thesource assembly ball stop must engage the locking device. The flexible cable ofthe source assembly and shipping plug must be of sufficient length and diameterto provide positive positioning of the source in the shielded position.

7. The nameplates must be fabricated of materials capable of resisting the fire testof 10 CFR Part 71 and maintaining their legibility.

8.

9.

ackage in private carriage the4J(b)

For transportation of more thaik4|5k;urrfteshipment must be in accordatê{fwith 49 C

For transportation of<^mWe than 45 curies per package^- a common carrier, thepackage must be witMJâ protective overpack as describetrând constructed inaccordance with

10. In addition to ttfieSreq

(a)

(b)

The package shallthe Operating Procedt?August 2^1989,

The package mu:Section 8|"0 of

11. The packaging ^ |general license Wjyisio

12. Expiration date: T}ec.ember 31,

operated *in accordance withapplicatiori, as supplemented

tenance Program offatiuary55, 1992.

approved for use under the

T}ec.

REFERENCES

Source Production and Equipment ComfiranyL.Im- ap*p,Tication dated March 13, 1989.AS h\ 1^

Supplements dated: July 6, August 21 and August 28, 1989; July 27, 1990; July 10 andNovember 4, 1991; January 5, 1992; and June 21, 1994.


r\-

ate: 12/22/94



239





9057

b. REVISION NUMBER

8




22. PREAMBLE



S

M

9

5ggH

M

£


General AtomicsP.O. Box 85608San Diego, CA 92138

Gulf Energy & Environmental Systems applicationdated August 3, 1973, as supplemented.


4. CONDITIONS ,. '"•" C , (?*' -^V-This certificate is conditional upon fulfilling the requirements'of 10,'CFR Part 71, as applicable/and the conditions specified below.

(a) Packaging

(1) Model NbA?:

(2) Description

New, Irum, free^qf observable, ... _...,-.v.- 0^^ypbbd/^heet^8-gauge bottom head

sheet(anxd 18%Mge Wf6^STe]hiad^M%tîtmone onlmpre corrugations inthe cover n e S @ ^ p ^ f ^ r y { | | ! | t | j ^ ^ e r j^^fclosij.r4e'shall beaccomplished B^^^lleasjE/ai^ZHgajigevbolt-TQeking vîig with drop-forgedlugs, ohe/of wh^h^J^ :fiâî:^,(^t^|Bi^s>at leas^S/8-inch diameter boltand lock nut. Gfossu<%ighjtenoi&T;G exeeea 260 —1-'-4*'~

(b) Contents ' '-'/.--^^ v '^*iH v" _ r>

(1) Type and form of material \...

Solid uranium bearing materials. Cranium may be enriched to any degreein the U-235 isotope.

240

WWWWWWWW:raNRC FORM 618A(3-96)





Total contents not to exceed 200 pounds. Fissile material not to exceed350 grams U-235. Total quantity of radioactive material within a packagemay not exceed a Type A quantity.



6.

7.

8.

9.

Special nuclear material shall ;be contained in secondary plastic bottles orjars, metal cans or jars or heavy plastic bags securely tied closed within thesteel drum. Metal secondary containers must be capable of venting to avoidrupture of the package in the event the package is exposed to the thermal test ,10 CFR §71.73 (c) (3).;

Shipments are restricted to transport between the licensee's Sorrento ValleyFuel Manufacturing Facility and other on-site facil i t ies.

In addition to the requirements of;;Subpart G.of 10 CFR Part 71:

(a) The package shall?fie'|>repared,fpr shipniehit and operated in accordancewith the Operat.ing^oc.edures in the.;appjication dated August 16, 1990.

V " s ' " ' ' 1 " ' " ? ' * • / , ? - ' ' •;•',' ' " ' • • . - o - . - - ••, •

(b) The packaging _mu,sty,be'Maintained in;accorclance:-with-the Maintenance

Program.:in the-appit£ationr dated August 16, 1990.

Expiration date: September? 30, 2000..' s j

: '".- "RtFteCES •'"•'Gulf Energy & Environmental Systems application dated August 3, 1973.

General Atomics supplement date^ August 16, 1990.


Date:


and Safeguards

241

2&2!U&^7$U£UBJ3£J£UEJS!JSJ&Jf{^

NRC FORM 618(3-96)10 CFR 71




9067

b. REVISION NUMBER

5




32. PREAMBLE






U.S. Department of Energy applicationdated November 7, 1991, as supplemented.

c. DOCKET NUMBER 71-90674. CONDITIONSCONDITIONS j Q ' L ^ ^ /f%

This certificate is conditional upon fulfilling the requirements^of IO;GFR~ Part 71, as Applicable;'and the conditions specified below.

(a) Packaging

(1) Model No.: /BCL-3

(2) Descriptionr<o

packaging is provided withosuref:;;iifting and tie-downforftfie contents is

Exteri or /diajneter, i h\Cavity heigtvti in.Cavity diame^r)j in.Lead shielding'* ' in . ,Loaded weight, lb..^;>^./. (Incl 110-lb. skid)

(3) Drawings

The packaging is constructed in accordance with Battelle Memorial InstituteDrawing No. BCL3-01, Sheets 1 & 2, Rev. C.

The inner can assembly is constructed in accordance with Battelle MemorialInstitute Drawing No. BCL3-38, Rev. B.

242

NRC FORM 618A(3-96)



5. (b) Contents

(1) Type and form of material.




(i) Fissile mater,iaV;not:,to "exceed 100 grams U-235 equivalent mass,

(ii) Fissile material not to exceed 2,000 grams U-235 equivalent mass,

(c) Transport Index,for Criticality Control

Minimum transport-index to be shown onlabel for nuclear critical ity control: ,. , -

7.

8.

9.

For contents described) iiK5(b)(l)and limited in 5(b)(2||i|:

For contentsand limited in

) : • / . :

0.4

100

The U-235 equivalent mass must bevdetermined;.by the.-foilowing method:

U-235 equivalent mass^ equalsU^235,rmass plus-1.75 times U-233 mass plus1.60 times Pu'mass. ' •h?;-ft[''\.'- -/

Plutonium in excess of-20 curies per package must be,in the form of metal, metalalloy, or reactor fuel elements.

At the time of delivery of the loaded, package to a carrier for transport, thepackage contents must be (1) dry (contents of inner can assembly must notdecompose up to a temperature of 750*F) and the fissile material unmoderated (H toX atomic ratio less than 2) and (2) so limited that the dose rate will not exceed10 millirem per hour at three (3) feet from the external surface of the package.

The maximum gross weight of the cavity contents must not exceed 40 pounds (innercan assembly, radioactive material, etc.).


(a) Each package shall be maintained in accordance with Section 8.0 of theapplication, as supplemented.

(b) Each package shall be operated and prepared for shipment in accordance withSection 7.0 of the application, as supplemented.

243rJ&J3k7BJ&7&M*M.7¥J&7¥J£J3kIBJ&JEJ&JgJ3&£J£^

a NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


ig 11. The package authorized by this certificate is hereby approved for use under the

general license provisions of 10 CFR §71.12.

12. Expiration date: May 31, 1997.

REFERENCES

g U.S. Department of Energy application dated November 7, 1991.

g Supplement dated: April 10, 1992.

FOR THE U.S. NUCLEAR REGULATORY COMMISSIONi

nug . ,. •, William D. Travers,c.Directorg -v Spent Fuel Project/Office

V . ' Office of Nuclear Material SafetyV and Safeguards

Date: S \ a C 1^V> ":"'--v-'5?- *fS'-

244J^





9068

b. REVISION NUMBER

5




2, PREAMBLE



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa, ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


U.S. Department of Energy applicationdated November 7, 1991, as supplemented.


4, CONDITIONS =.;" " ! 'This certificate is conditional upon fulfilling the requirements of 10CFR Part 71, as applicable, and the conditions specified below.

S

99

(a) Packaging

(1) Model No.: BCL-2

(2) Description.

A steel encased, Te'a.d %jli4ed^shJBiJi.ria^^fg^Jhe packaging is providedwith a recessed, •pliigrtypj^'n^d'ia^fga^gât' $0$p$ closure; lifting andtie-down devices^ôd^^dYaîn^ninêX'p^n'etVatio^^Xontaîjinent for thecontents is'^rovid^^Bân^rie^'dafnjiêmbl/pr^by material in specialform. The packaging^ shielding as follows:

Exterior heigfit,;/in. " '"</;lf%;: vi8'v2 ,.-':~yExterior diameter,^,in.Cavity height, in.7)Lead shielding, in.'Loaded weight, 1b.

15.55.25 •:

. ;Vlf?J60 (incl 110-1 b. skid)

(3) Drawings

The packaging is constructed in accordance with Battelle Memorial InstituteDrawing No. BCL2-01, Sheets 1 and 2, Rev. D.

The inner can assembly is constructed in accordance with Battelle MemorialInstitute Drawing No. BCL2-47, Rev. B.

245

?}&M{T&T£JBJ£J!£J&1&T&7^WL]&T^7^^

w ,

3(1) Type and form of material

5M

£gg

(2) Maximum quantity of material per packagegg

NRCFORM618A CONDITIONS {continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)


5. (b) Contents

7.



(i) Fissile material not. to exceed 50 grams U-235 equivalent mass.

(ii) Fissile material riot to exceed '2-j-OCfO grams U-235 equivalent mass.g

w

(c) Transport Index, for Criticality Control

Minimum transport.index to be shown on -'label for nuclear c r i t i c a l i t y control: , ^

For contents describeUMn 5,(b)(I).. <>#-' ';••and limited in 5(b)(2)f(i|: -•;..:) | . $ ; '-0'.'4

For contents descj^ibe^rin. 5(,b)(.t)>:>t..! „ ' 5 % .:i and limited'in 5(bj)i(,2);(i;t)^,^ . ^ C J I " 1 ,-./;/ ipO

6. Plutonium in excess oTVZO/'c^pieis^pentpacjtag'e-'rtustl^e'iH the. form of metal, metal

The U-235 equivalent mass musk\.be 4eteiR|n$ned by'tfte following method:

U-235 equivalent-,mass equals l) 235 filass plus 1.75 times U-233 mass plus 1.60times Pu mass. .."

8. At the time of delivery of the loaded package to a carrier for transport, thepackage contents must be (1) dry (xoriteirts -of inner can assembly must notdecompose up to a temperature of 750"F) and the fissile material unmoderated (H toX atomic ratio less than 2) and (2) so limited that the dose rate will not exceed10 millirem per hour at one meter from the external surface of the package.

9. The maximum gross weight of the cavity contents must not exceed 20 pounds (innercan assembly, radioactive material, etc.)


(i) Each package shall be maintained in accordance with Section 8.0 of theapplication, as supplemented.

(ii) The package shall be prepared for shipment and operated in accordance withSection 7.0 of the application, as supplemented.

246

J£JFt7¥i7¥J£U&J3USJ!SJE^^

ISNRC FORM 618A(3-96)




12. Expiration date: May 31, 1997.REFERENCE

U.S. Department of Energy application dated November 7, 1991.

Supplement dated: April 10, 1992.


Date:

William D. Travers, DirectorSpent Fuel Project,OfficeOffice of Nuclear Material Safety

and Safeguards

'*':< .'

• s

247

NRC FORM 618(&S5)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESa. CERTIFICATE NUMBER

9069

b. REVISION NUMBER

10


1


A2. PREAMBLE

a. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theapplicable safety standards set forth in Title 10, Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive MateriaL"


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATIONa. ISSUED TO /Name end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Westinghouse Electr ic CorporationP.O. Box 355Pittsburgh, PA 15230

Westinghouse Electr ic Corporationapplication dated October 30, 1981,

.as5sup"p3emented.knTifC^f

> uc. DOCKET NUMBER

4. CONDITIONS . %J ' <^/ .This certificate is conditional upon fulfillingjnsy-equirernents of 10 CFR Part 71, as applicable, and the/conBjtions specified below.

(a) Packaging

(1) Model /

(2) DescrTption

Steel' overpaiand avrO gauthe shells i

ygthe overpjcklatch pife?a strongbadcbb l

ThJtnd

absorber pfa||s are 1 ocateJrUWeen the""fuelequipped witn\jfpfting, tie-down and pressu*weight of the pfckage is 8,600 pounds.

x 47" x 206")he volume betweenng materiallower sections ofhigh strength 5/8"

..ithin the overpack by(i hfick mounted). Neutron^"emblies. The package is

ief devices. Gross

)nsulj

per ajers an

in plac•"•'•• (^hf

Drawings

The packaging is constructed in accordance with Westinghouse ElectricCorporation Drawing No. 1581F50, Sheets 1 and 2, Rev. 1. Fuel rodcontainer is constructed in accordance with Westinghouse ElectricCorporation Drawing No. C5650D55, Rev. 1.

2 4 8

RKiW^^



5.(b) Contents


(i) Unirradiated U02-Pu02 PWR fuel assembly with the following maximumactive dimensions and maximum compositions:

Cladding MaterialEnvelope, inEnrichment

PuO2 in PuO2, plus U02 w/oPuO2 fissile in PuO?, w/5^U02 fissile in U

Fissile, kg %Fuel lengthy VDecay heat^Uad, watts/pkg

( i i ) Mixed

Zr7.784 x 7.784

»(b)0.71

16.6440

in natural UO, as pressed sinterec" J of minimum n nnA" * " -**

Petfet diametRodJiameV"FifeTlenPufipin PPuO, .EissiUO

(iii) Uraniuirods of

kllets fu l ly clad ins fuel rods of the

3X1de as> foil owing sp"

Pellet diameterRod diameter (nom), inFuel length (max), in

U enrichment (max), w/o

>&ST CladfStJ~s

0.0.

.446

.47670.04.02

clad unirradiated

AL Clad

0.4060.475

61.02.5

"For three plutonium isotopic cases:Case 1,

the PuO2 enrichment (a) is 6.0 w/o; fissile PuO2 (b) is 71 w/o.Case 2,

the PuO2 enrichment (a) is 4.4 w/o; fissile PuO2 (b) is 81 w/o.Case 3,

the PuO2 enrichment (a) is 3.03 w/o; fissile PuO2 (b) is 85 w/o.249

NRC FORM 618A(6-83)



5.(b) (2) Maximum quantity of material per package

(i) For the contents described in 5(b)(l)(i)

Two fuel assemblies,

(ii) For the contents described in 5(b)(l)(ii)

Not more than 94 kilograms Pu contained within the fuel rodcontainer described in 5(a)(3).

(iii) For the contents described rin 5(b)(l)(iii)

Two inner cpn^if#fas descntM=/n/5(a)(3) containing not morethan a tnlraKnr70 kiloarams U-235.^-^1 .

(c) Transport Index

6.

7.

8.

Minimum transpo/ton label for nu^$ear

Two (2) neutstainless stdemust be inst

Fuel rods mult,equivalent mimust be fittednoncombustible1

must assure thto-metal square

to be shownrfckcality control:

absorbecontaini

ed betwee

t h i c k , © ! ! length,on or 0 . @ t h i c k OFHC copperuel assenffljes.

iner,gn~no more than an6adedi*Juel rod containers

blqgfe, of which theby wfwcj5 they are secured

e than^r equivalent metal-iner. "^

JIWW "^WEach fuel assembly imM be unsheatneKFor must be eneJWed in an unsealed,polyethylene sheath wh4^i will not extend beyond th^pends of the fuel assembly.The ends of the sheath fnustv#ot be folded or jkped in any manner that wouldprevent the flow of liquids^lftojpr-d$- e||thePsheathed fuel assembly.Alternatively, the fuel assemblymaynre enclosed in an elongated plastic bag orsheath along its full length. At the bottom end of the fuel assembly, the bagwill be cut off or folded back to assure that the entire cross section of thelower end of the assembly is unobstructed. When the folding is used, theportion of the sheath that is folded back will be cinched with tape near itsend to hold it in place, and the length will be such that when the assembly isloaded in the packaging, the folded sheath will be clamped in place in at leasttwo grid locations. The top end of the bag may be gathered together and tapedclosed. However, the top end then will be slit on all four sides. The slitswill run perpendicular to the axis of the assembly and will extend the innerdistance between the top nozzle pads and spring clamps (approximately 60percent of the length of each side). The slits will be made in a plane nearthat formed by the top of the pads and clamps.

250'«"«M»^-'»'*^*"**!»"«'-*«i*a«^«^«^

NRC FORM 618A(6-83)





(a) The package must be prepared for shipment and operated in accordance withChapter 6.0 of the application.

(b) Each packaging must meet the acceptance tests and maintenance program ofChapter 7.0 of the application.

10.

11 .


Expiration date: January 31, 1997.B

Westinghouse E l e c t r i c Corpor%,ioff a p p l i c a t i o n dated

Supplement dated J a n u a r y ^ , 1992.

Department of Energy^,stfppJLejnents da t ed : April 2.and

30, 1981.


Date:

2 5 1

&K^^ M 7»: W . W TWYaY-YA Y«YYl&rtY.W ^



FOR RADIOACTIVE MATERIALS PACKAGEStfE NUMBER b. REVISION NUMBER




PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the appiicabie safety standards set forth in Title 10, Code

of Federal Regulations, Parf 71, "Packaging and Transportation of Radioactive Material."

b. This certificate does not reiieva the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATIONa. ISSUED TO IName and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

VECTRA Technologies, Inc.1010 South 336th StreetSuite 220Federal Way, WA 98003

• V

VECTRA Technologies, Inc. application datedJuly,2J, 1994, as supplemented.

~c. DOCKET NUMBER

4. CONDITIONSThis certificate is conditional upon fulfilling-the'requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a)

The

high

inner she;ll is molded,body) seqfcfons of the _neoprene ga^Ket at the st'eare providednjpr l i f t ing ,minimum 14-gauge T id andgauge locking rincf^ith^d.and lock nut. The package

'polytnjgthane foam.The^pyerpack is a right

d i a l l e r with a 34-1/2-inch-gauge galvanized steel

rigi;<J?polyurethane foam. Theof {zftVupper and lower (lid and

, .yucu by^r f r toggle clamps, and a. ed joint betweetf^the two sections. Four lugsThe steel drunfei^minimum 18-gauge steel with a

a gasket. JJpsure of the drum is by way of a 12-igeo^fprged^1ugs and a 5/8-inch diameter boltKoss;:;weight is approximately 750 pounds.

(3) Drawing

The packaging is constructed in accordance with Nuclear Packaging,Incorporated Drawing No. X-60-200D, Rev. C, or X-60-200D-SP, Rev. J.

252

^^NRC FORM 618A(8-83)




(b)

6.

7.

8.

9.

10.

11.

12.

13.

Contents


(i) Radioactive material in the form of dewatered, solid or solidifiedmaterials meeting the requirements of low specific activitymaterial, contained in steel drums.

(ii) Radioactive material meeting the requirements of special formradioactive material, contained in steel drums.

(iii) Radioactive material in the form of solid metal pieces or activatedsolid metal components,repnjlaiqfid in steel drums.

(2) Maximum quant i ty <spf

-Oerial per packa

Greater than^ype A quantities of radioactivecontents norfeo exceed the generally licensed m10 CFR §§7^18 and 71.22. Plutonium in excessmust be Mh "must meepthe . ^decay heaf not t

The maximum weight of c

The steel d*?um>mustOctober 20, f994.

The drum must/be se

Contents must ^drum under normal^br accidenal^

<The lifting lugs

of metal, metal alloyents of special

3 w

rial. Fissile material^limits as specified in

curies per packageeacto.^fuel elements, orioactive material. Internal

t to exceed 550 pounds.

o|l|he supplement dated

rusions^win not puncture the

rendered inoperable for t^tt6wn during transport.

10 CFR Part 71:In addition to the requiremefes fff Si^bpapt G

(a) The package must meet the Acceptance Tests and Maintenance Program ofChapter 8.0 of the application; and

(b) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures in Chapter 7.0 of the application.

The packaging authorized by this certificate is hereby approved for use underthe general license provisions of 10 CFR §71.12.

Expiration date: December 31, 1999.

253

;.Sw.. m*Ti*Tim". i ".W.-. ^^ j&mAiy^^^^

frt#3^w'rfw«

NRC FORM 61SA(6-83)

U.S. NUCLEAR REGULATORY COPJIMISSIONCONDITIONS (continued)


REFERENCES

VECTRA Technologies, Incorporated, application dated July 21, 1994.

Supplements dated: August 22 and October 20, 1994.


DateJSL 2 0

V .ass R. Chapperj ^Section LeaderCask Certification^Ict^onStorage and Transport.<^s,tems BranchDivision of Industrial ar2"

Medical Nuclear Safetyi

254

NRC FORM 618

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1. a. CERTIFICATE NUMBER b. REVISION NUMBER


USA/9071/B( )d. PAGE NUMBER s. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafetystandardssetforth inTitielO, Code




ANEFCO, IncorporatedP.O. Box 433Ridgefield, CT 06877


ANEFCO application received June 14, 1976,with report, "Safety Analysis Report CaskAPr101),

x\-. as^suppl emented.

'c. DOCKET NUMBER 71^9071;A. CONDITIONS <;. . ..> ~'-\Jj ,.


^•<;~•zy./i(a) Packaging

(1) Model No.: '-AP-101

(2) Descript ion^

; *.---

Jh m a

^tS/jOf'^WO hlthte5 "staiiinches

steePcylindricalshells. The'Jnner^kI]Mis/5^8rn'nch^th3:iG.k by |8/>4nch IDj^he outer stainlesssteel shell « 1 _ s 5 l - l / ^ i ^ ^ i k ^ j , ^ l ^ 1 n d g p D and âj3-l/2-inch pouredlead shield f^Ts thl^pac.fe_ be^fe6n|3>The""^gtier shellpisi-surrounded by a0.140-inch thfcjc^stainless^stegl^tlêKm^l -s.ft^fld separated by a 0.125-inchthick stainless';'<s;fceel spacer wireyV-Tife cavity is/28NS:inches in diameter by167 inches long. i~'The, base is a welded stainlesfs^steel construction with 3inches of poured leVd. The flanged l i d is of stainless steel and lead.Closure is provided by £wjenty,| l-l/2-inch<d|ameter bolts and a GASK-O-SEALclosure seal. There are two/p~enfi|at"ipps into the containment vessel fordrîn lines which are plugged and gasKeted with a neoprene seal. The caskis equipped with removable, canned balsa impact limiters at each end. Theoverall dimensions of the cask with impact limiters in place are 84 inches indiameter by 236 inches long. The cask has four l i f t i ng trunnions, tworedundant pairs for l i f t i n g . Three of the trunnions are used for tie-down ofthe cask for shipment. The package gross weight is approximately 62,000pounds.

2 5 5

&fy!rf:>S^^

" ' " ' ' " ' CONDITIONS (continued)


9.

(a)

(b)

Packaging (Continued)

(3) Drawings

The packaging is fabricated in accordance with ANEFCO, IncorporatedDrawing Nos. SC-101, Rev. A; SC-102} SC-103, Rev. A; SC-104, Rev. B;SC-107, Rev. A; SC-108; SC-110, Rev. A; and SC-111.

Contents


Greater than Type A uan|gtyj®fpy.prioduct material in the form of dry,solid, metallic was ejXaxer-'m'i* Wid^q|jrvated reactor components.

(2) Maximum quantf|yvof material per package

The package must?Wmust be drainedjWall ex

Weight of^cqrvtents not to exceed 10,000 poundsiÎnternal decay heat ofcontents iioi to exceed 300 watts. ^<?v <^-t

,-im-In preparatio/rî^^shipment^the cask cavity

t^r.^-A^vacuunr p0âust be ifsed to reduce thePCess"uHe oorr^sp^'raiq to the^measured temperature

below'jtlie vapor pressureA,c, need not be vacuum driedyemfiedqniSt to contain

cavity pressure'rbelow theof the drainedjWater. Thedetermined for ai? least*,90provided the "empty"liquid prior tbj>e|ich T

Except for close{cavity to limit

8. In addition to the Requirements

must^beûsed in the caskconditions of transport.€4

a. The package must beôperated and maintained in accordance with procedures insupplement dated December 12, 1991.

b.

c.

Prior to each shipment the55 gask£bê>llc-losure seal must be inspected. Thegask-o-seal closure seal and the cavity drain 0-ring seals must be replacedwith new seals within the 12-month period prior to shipment, or earlier ifinspection shows any defect.

The package must be leak tested prior to each shipment in accordance withoperating procedures in supplement dated December 12, 1991.



256!M&jaija!j9&/&&&ijaij&sj&ja&a&ia&A&^^



REFERENCES

ANEFCO, Incorporated Safety Analysis Report Cask AP-101, received June 14, 1976.Supplements dated: July 21, August 6, and October 21, 1^76; April 2, and September 12,1986; and September 26, and December 12, 1991.


DEC 1 7 1991 p*Date:

>"--!. >

Charles E^MScDqnald, ChiefTransportation BranchDivision of Safeguards

and Transportation;, NMSS

i4 ? ^

%j

7

• ' - ^ \ % X 7< -\^J-r "\r^

257^ m

NRC FORM 618(3-96)10 CFR 71




9073^ i~ PREAMBLE

b. REVISION NUMBER




4




Scientific Ecology Group, Inc.P.O. Box 25301560 Bear Creek RoadOak Ridge, TN 37831-2530


Scientific Ecology Group, Inc., applicationdated January 26, 1994.

c. DOCKET NUMBER 71-90734.CONDmONS


(a) Packaging v V

(1) Model No..; 10-142A

(2) Descnptiorfe^S' '

-' . V ,''"'

A steel encase|iiyead shielded caskfor solid radioactive material.The overall d jferfeions of the caskfa|e> 101-incht'diameter by 120-inchheight. The cscsKvcon sisiisliof twpôffjcentric carbon steel cylindrical

1/2-inchouter shell

..__._ ..._,., ........ ._,, „ -r,_ —-,..- thick weldedsteet pi at^sV tthe |)"aSe 'is" VfeTded to HWsteelCbyl i ndri cal shel Is. Astepped weldfed;>1 <1V- seûêd^byîghit Ratchet'binders, is comprised oftwo, 3-:inch thicfeXste^pltes containing openings for a secondarylid of similar coristruoî6^1th an.additional 1-inch thick upperplate. The secondary lid/is secured to the primary lid througheight, 1-indh diameter bolts. The containment cavity is 66 inches indiameter by 72 inches high. The package design is provided with alid test port. Toroidal impact limiters are located at the top andbottom of the cask. The impact limiters are 10-gauge stainless steelfilled with rigid polyurethane foam. Interior and exterior surfacesof the cask body and interior surfaces of the upper lid are coveredwith 12-gauge, 304 stainless steel cladding and seal welded.

The primary lid is closed by means of eight ratchet binders. The29-inch diameter secondary lid is closed by eight, 1-inch diameterstud bolts. Both lids are sealed using silicone gaskets bonded tothe lid plates. Lifting is facilitated with three lugs welded to theprimary lid. The secondary lid has a redundant Neoprene seal, and acentrally located lift lug.

All exposed side walls are covered with a stainless steel thermalbarrier. Four skewed lugs, welded to the outer shell, are used fortie-down. The package gross weight is approximately 64,000 pounds.

258

>

wwwwNRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3'96) Page 2 - Certificate No. 9073 - Revision No. 19 - Docket No. 71-9073

5. (a) (3) Drawings

The packaging is fabricated in accordance with Scientific EcologyGroup, Inc., Drawing No. STD-02-107, Sheets 1 and 2, Rev. 0.

(b) Contents


a Dewatered ion exchange resins, solid waste, or activated solida components; in secondary containers; and limited to the following:


0.0001 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie;


0.3 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 1 curie.

(ii) Objects of nonradioactive material externally contaminated withradioactive material, provided that the radioactive material isnot readily dispersible and the surface contamination, whenaveraged over an area of 1 square meter, does not exceed0.0001 millicurie (220,000 disintegrations per minute) persquare centimeter of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie, or0.001 millicurie (2,200,000 disintegrations per minute) persquare centimeter for other radionuclides.


Greater than Type A quantities of radioactive materials which maycontain fissile contents not to exceed the generally licensed masslimits as specified in 10 CFR §§§71.18, 71.20, and 71.22. Internaldecay heat not to exceed 400 watts and the maximum weight ofcontents, including secondary containers, not to exceed 10,000pounds.

259M,



6. (a) For any package containing water and/or organic substances which couldradiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package such thatthe following criteria are met over a period of time that is twice theexpected shipment time:

(1) The hydrogen generated must be limited to a molar quantity that wouldbe no more than 5% by volume (or equivalent limits for otherinflammable gases) of the secondary container gas void if present atSTP (i.e., no more than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

(2) The secondary container and cask cavity must be inerted with adiluent to assure that oxygen must be limited to 5% by volume inthose portions of the package which could have hydrogen greater than5%. , .,-; • ...

For any package delivered to a carrier for transport, the secondarycontainer must be prepared for shipment in the 'same manner in whichdetermination for gas generation is made. Shipment period begins when thepackage is prepared (sealed) and must be completed'within twice theexpected shipment.time. .,_ .

(b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drums'or other-secondary;c%"tainers, the determination in(a) above need not baVmade,1 and:the;time Restriction in (a) above does notapply. ,•/:..''"' '.. -'•'.:

7. Except for close;,fittjngôntejvtsv dunnage -mustê provided in the shipping caskcavity sufficient to prevent significant moyeltieht of >the contents or secondarycontainers relative to;£he outer packaging under normal conditions.

8. In addition to the requirements-of Suppart G of 10 CFR Part 71:

(a) Prior to each.shipment, the packaging lid seals must be inspected. Theseals must be replaced with new seals if inspection shows any defects orevery 12 months, whichever occurs first. The cavity test port must besealed with appropriate sealant applied to the pipe plug threads.

(b) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures in chapter 7 of the application.

(c) The package must meet the Acceptance Tests and Maintenance Program inchapter 8 of the application.

9. The package authorized by this certificate must be transported on a motorvehicle, railroad car, aircraft, inland watercraft, or hold or deck of a seagoingvessel assigned for the sole use of the licensee.

2 6 0^lKJSJSUSJSUSJKJSJS^SJ&^^^7^7¥\7'PJ'SJ^,7^7VJSJSî

NRC FORM 618A' (3-96)



10. Packagings fabricated after March 28, 1980 must be constructed of A-516 Grade70 carbon steel.



REFERENCES

Scientific Ecology Group, Inc., application dated January 26, 1994.


/ . • • :

Jillijam D. Trav^rs^ Director,iSpenVFuel Pro|ec|;Office .Office, df NucTea|£Material Safety

Date: M \ ^ 10f,(

«te

m

m

i

m2 6 1





9079

b. REVISION NUMBER

16


USA/9079/A

d. PAGE NUMBER

1


4L PREAMBLE




VECTRA Technologies, Inc.One Harbison Way, Suite 209Columbia, SC 29212


Nuclear Packaging Inc. applicationdated March 30, 1988, as supplemented.


4.CONDITIONS -/.-• '„ -. ~\' ^.This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

£ga,sgggggM

£g»g

5.

(a) Packaging

(1) Model No.: NUPA%:l D-2.0

(2) Description ^,fk ,

Steel encased, lead shielded cape-for rad&fctive material. The cask is a

cask cavity

and a 7/8-inch thjck,.outeHi;|teel ;shelt#?Eeich^s^- is comprised of two, 2-inchthick steel, piate%^Tded together.'tojtfjorm ailfc-ynch thick base which isintergeral lyweld^to^t .he winner and .|iutejr^s|e'ei shells-of the side wall. Asteel flange is weidedJfQ*tfi^ of the side wall atthe top. The lid is comprise 'bfrffWq^ 2-1hch thicks-steel plates, which arestepped and welded together to/?ma^^ith'"tfie steel;^flange. The cask closuresare sealed by a Neoprene gasket Wcated between, the l id and steel flange,positive closure of the l id is accomplished by eight rachet binders. The lidcontains a centrally located shield plug;comprised of two, 2-inch thick steelplates and one, 1-inch th icks tee l piate~stepped and welded. The shield plugis sealed by a Neoprene gasket, and eight, 3/4-inch studs and nut are used toprovide positive closure.

Tie-down is accomplished by four tie-down lugs welded to the cask body. Thereare four cask l i f t ing lugs, three l id l i f t ing lugs, and one shield plug lift inglug. The package gross weight is approximately 48,000 pounds.

(3) Drawings

The Model No. NUPAC 14D-2.0 packaging is fabricated in accordance with NuclearPackaging, Incorporated Drawing No. X-20-215D, Revision C.

262^ TfK, Ty 2!U&JSJSU5U£iJ$£2£3£U£i. JSSJSUKIK.^KJKJKJKJKTKJSiJKJKSKJSkiSJSi

- , L -

NRC FORM 618A(3-96)



(b) Contents


Process solids, either dewatered, solid or solidified, in secondarycontainers, and limited to the following:

(i) Materials in which the radioactivity is essentially uniformlydistributed and in which the estimated average concentration per gramof contents does not exceed:


0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 0.05 curie, but not morethan 1 curie; or

0.3 millicurie of radionucl.ides for which the A2 quantity in AppendixA of 10'CFR;;Part 71 is more than 1 <|urie.

(ii) Objects of non^d|oactiye-material\,externally contaminated withradioactive;material,provided tha^the radioactive material is notreadily dispe.rsa'bTe and the surfax-Mcontamination, when averaged overan area,of l^sqiiare,meter; does;nq^?exceed 0.0001 millicurie(22O,Oppfdisiift^0rations per mirruCe) pe'r square centimeter ofradionuclides for!which the A2 quantity in Appendix A of10 CFR P;art'tlJ is

v np^ ipbre thati O.O^/curie, or- 0.001 mi H i curie(2,200,000 disintegrations per;jninutey per square centimeter forother radiqnupl'fdes.'"'• '••/<<:•. ~"'-',/•-

(2) Maximum quantity of material|per package

Greater than Type A quantity of radioactive material which may containfissile material provided the fissile material does not exceed the limitsin 10 CFR §71.53. The weight of the contents and secondary containersshall not exceed 14,000 pounds and the internal decay heat load shall notexceed 7 watts.

263K7K



?k J. (a) For any package containing water and/or organic substances which couldS radiolytically generate combustible gases, determination must be made by testS and measurements or by analysis of a representative package such that the§ following criteria are met over a period of time that is twice the expected

shipment time:

(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP (i.e., nomore than 0.063 g-moles/ft at 14.7 psia and 70°); or

(2) The secondary container and cask cavity must be inerted with a diluent toassure that oxygen must be limited to 5% by volume in those portions of

* the package which could have hydrogen greater than 5%.

a For any package delivered to a carrier for transport, the secondary containers must be prepared.for"shipment in the same manrier/in which determination for gass generation is made; Shipment period begins when the package is prepared£ (sealed) and must be completed within twice the expected shipment time.

s (b) For any package slipped, within 10 days of prepâriiiion, or within 10 days aftera venting of drums orpother secondary containers^the determination in (a) above*~ need not be made, andMhe ,time restrictioh, i#ta) above does not apply.

7. Except for close .fitting c^Htents shoring^must|eg|i:laced between secondarycontainers and;;the cask cav3$y^to present moyemenS-during normal conditions oftransport. <•" : ^ M ^ $ # > - > ., .„. " 1 ^ ;// -V.«

8. The lid and shield piu%14>f$ing lugsmustnqtr te useUrfor lifting the cask, andshall be coveredvin trar®i^^,^;tj:!,;-;!/«i:î J:fi

:' ^<]

9. In addition to the"'r^quireWntôf^fibp'a^G of 10 CFR Par% 71:

(a) Prior to each shipment, the packaging lid seals, if)opened (or if security sealis broken), must "be/inspected. The seals mustvbe>replaced with new seals ifinspection shows any defects or every twelve (12) months, whichever occursfirst. Cavity drain lirte and .optiqnaTHvent/test connection must be sealed withappropriate sealant applied to the-'pipe*1 plug threads.

(b) Each cask must meet the Acceptance Tests and Maintenance Program of Section 8.0of the application. In addition, the cask must be leak tested at least onceevery twelve (12) months in accordance with Appendix 8.4 of the application.

(c) The package shall be prepared for shipment and operated in accordance with theoperating procedures of Section 7.0 of the application.

10. The cask body and each cask lid must be marked in accordance with 10 CFR §71.85(c).

11. The package authorized by this certificate must be transported on a motor vehicle,railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vesselassigned for the sole use of the licensee.

k

* 264

cWgT3i£ww:^wwW3fnir:nmatoit w w s+oEMOif w aEwac

NRC FORM 618A(3-96)



A . The package authorized by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12.


REFERENCES

Nuclear Packaging, Incorporated application dated March 30, 1988.

Supplement dated: April 26, 1988 and February 23, 1993.

. FOR THE U.S. NUCLEAR REGULATORY COMMISSION

late: H

William D. Travers, DirectorSpent Fuel Project Office

~;^.Office of Nuclear H|terial Safety7 $ ^ and Safeguards .'-.#4X' ""'v

' ' / • , " « '

2 6 5

NRC FORM 618{S-851

10 CFR 71











3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEX1ESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Chem-Nuclear Systems, Inc. applicationted November 24, 1987, as supplemented.

"c. DOCKET NUMBER

4. CONDITIONS ^ xvl5 V ^ i£?j;This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model^No.: CNS

(2) Description

steel

_ , ypackage weight is about 26,0004

(b)

5-1/2pounds.

(3) Drawings

The packaging is constructed in accordance with Chem-Nuclear Systems,Inc., Drawing Nos. C-110-E-0005, Sheets 1, 2 and 3, Rev. 5; andC-112-B-0006, Rev. A.

Contents

Type, form and maximum quantity of material per package

(i) Greater than Type A quantity of by product material as solid metal.Decay heat not to exceed 600 watts; or

(ii) Decay heat not to exceed 5 watts, and:

Process solids, either dewatered, solid, or solidified in a secondarysealed container meeting the requirements for low specific activitymaterial; or

2 6 6



Solid reactor components in secondary containers, as required, that meetthe requirements for low specific activity material.

6.

7.

8.

9.

10.

(a) For any package containing water and/or organic substances which couldradiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package suchthat the following criteria are met over a period of time that is twicethe expected shipment time:

(i) The hydrogen generated must be limited to a molar quantity thatwould be no more tha£S5%-by%volume (or equivalent limits forother inflamm7abê'i.ga:s6s)=6 t|ie? secondary container gas void ifpresenttat^JP'î.e. , no moreM:(/anJO.063 g-moles/ft3 at 14.7 psiand 7Q-*F,k or - ^ ! v

psia

(ii) The^srecondary container and cask cavity^must be inerted with aJi5uent to assure that oxygen must be, limited to 5% by volume in

of the package whêhôul d'Jvave hydrogen greater

f'~\For ajiy^package ajijêr'ed toj^carr|iejj| |S^ transport,^the secondaryc0nta3.rj.er must be^pjiipared ftr s.hipnienj p> the sameQilnner in whichdetermination for^^^\g^njej^M£jraJsî)a5,&^ Shipment«ge.riod begins whenthe package i|\,prepa1^dfe(ieale^yaod|f^' be/completed within twice theexpected sht.pmipit ^M^Sbw^^TT^^'^*^ '!Al

^J|^âinMrj^!ep|i2^withj^|i"dioact'iAQ'ty concentration not

r venMng of drums or other,. .. ,v. (a) above need not be made,

and the tfnjeêstriction frl>|(ia) aDove does nojfâpbly.

Shoring must be provided to minimize movement of^contents during accidentconditions of transport.yi.

7Maximum gross weight of the coirteiivlrs, secondary container, and shoring islimited to 5,000 pounds.

The lid closure to the cask shall be secured by twelve, SA-354, Type BD,l-l/4"-7 UNC x 2-1/4" long bolts torqued to 320 ft-lbs ± 10% (lubricated) or420 ft-lbs ± 10% (dry).

The cask shall be delivered to a carrier dry and the cavity drain line shallbe sealed with appropriate sealant applied to threads of pipe plug.

267



11

12.

13.

14.

Prior to each shipment, the leak test described in Section 8.2 of theapplication must be performed. No package is to be delivered to a carrierfor transport with a detectable leak using the method of Section 8.2.

Radiation measurements shall be made to determine that the dose rate does notexceed 30 mrem/hr at one meter from the surface of a dry loaded cask.

Prior to each shipment, the lift lugs must be removed from the packaging.

The contents described in 5(b)(ii) shall be transported on a motor vehicle,railroad car, aircraft, inlajKi iptt|S\eraft,; or hold or deck of a seagoingvessel assigned for soiefi»lse0bf fie i'Wen'sjBe?

%Vtf15. In addition to ^requirements of subpart G of'l&CFR Part 71:

(a) The package, shall be prepared for shipment ancNiperated accordance withthe Oper'a^ngJProcedures in Chapter 7 of J;h>^ppMWtion.

^maintained in apc^pnce with^the Maintenance(b) The padicageadicProgr^in

16.

.7.

The package'' authorizetiifm: this ^ r t , i f i c \ t§ t»hereby approved for use underthe general3 license ptMmTOn^ot^dH-FR4§S^2. * . <ztJ

'MChem-Nuclear System^ I n c ^ p ^ l ^ a t ^ W d l M No|||B'er 2 4 , ^ 8 7 .

Supplement dated: iMefhber 24, 1 9 9 2 H v ^ . O

FOR THE U . S . K N U C L E A R REGULATORY COMMISSION

Charles E. MacDonald, ChiefTransportation BranchDivision of Safeguards and

Transportation, NMSS

Date:DEC 1 4 1992

2 6 8

jiti yti w w y*i MK jtt w w azNRC FORM 618(3-96)10 CFR 71








4Z. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth inTitle 10,Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."




Safety Analysis Report for the HN-190-1Radwaste Shipping Cask STD-R-02-006Revision 4.

c. DOCKET NUMBE?l~9086

4, CONDITIONS , . ;. " . •,-.

This certificate is conditional upon fulfilling the requirements of 10.CFR Part 71, as applicable; and the conditions specified below.

5,

(a) Packaging

(1)

(2)

Model No.: M

Description,;* < % ^ \ -/' ''iC-si

A steel erica'sed, leac|Shielêd ;c^^forfradiMctive material. The cask isa right circular cyltndef/82.5 Inchejs hH#t&yj|81.5 inches?in diameter. Thecask cavity is 74i>5 jWheis high-i>y^7-5.63/t^Ghes in diameter. The cask side

, , *J_J._ . , 'jV«i«-s.%.t'hirL innpv^^pSi chpl.l. a li£3/4-inr.h lead

wall. A steel f 1 aftsfe fs, welded!tjo: the§nner/and outer-steel shells of theside wall a%the tb 'p>^^^d^;a^î ich^tk ick steejp;plate which is

ng |,side wall at*the tb^/uTg^d5i§,;a^îiich^tstepped to mate> withHhe"%teeM^frigev Jhe :Viton or Buna-N/O-ring gasketlfâife^rbetweePositive lid closure is accomplMe¥ds by thir

k jp:cask closure is sealed by a

h l i d ^ d l flbetween the.lidyand steel flange.Positive lid closure is"accomplMeTds by thirty,^ 1-inch studs and nuts. Thelid contains a centrally located 4-inch stepped-^steel shield plug. Theshield plug is seated by/a Vi,ton or Buna-NJp-rfng gasket, and sixteen, 1/2-inch studs and nuts areused"to^rov^de positive closure.

Tie-down is accomplished by four-tie down lugs welded to the cask body.There are three cask lifting lugs, three lid lifting lugs, and one shieldplug lifting lug. The package gross weight is 50,000 pounds.

(3) Drawings

The packaging is constructed in accordance with Hittman Nuclear &Development Corporation Drawing Nos. STD-02-028, Revision 9;STD-02-029, Revision 6; and STD-02-030, Revision 5.

2 6 9

S

«S

5. (b) Contents


NRC FORM 618A CONDITIONS (continued) U . S . NUCLEAR REGULATORY COMMISSION(3-96)


Process solids either dewatered, solid or solidified, in secondarycontainers, and limited to the following:




0.3 millicurie of radionuclides for .which the Ag quantity inAppendix A of 10 CFR Part 71 is more than 1 curie.

(ii) Objects o^nonradtoactiye material externally contaminated withradioactivelinaterial;, provided that the radioactive material isnot read;i3y^ispersible and tlie^surface contamination, whenaveraged tfvdr an area of 1 square meter, does not exceedO.OOprfmillic^rie (220,00.0:disintegrations, per minute) persquare-pentimeter;of radionucTide;s);fQ;r which the A2 quantity inAppendix*^/of 10 CFR Part\7I is jn6i:more than 0.05 curie, or0.00r-"mi]Xicurie (2,200,0(10^.disintegrations per minute) persquare centimeter forJotHer radjonucl ides^

] X ( , , ^ gsquare cent-imeter for,JotHer radjonucl ides^

(2) Maximum quantity of mater^iTpeirJpackage ; ;;

270

s

ga •BBj*

Greater than Type A quantity of radioactive-material with the weight of gthe contents, secondary containers and. shoring not exceeding 14,500 zpounds except the weight of the contents in HN-100 Series 1, Unit 5 ™must not exceed 6,900 pounds. Internal decay heat must not exceed 7thermal watts.

JEJgJgj£U£J£U£U£J£U£Jik2£JSJSk2BJ!^^

^NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)



(1) The hydrogen generated must be limited to a molar quantity that wouldbe no more than 5% by volume (or equivalent limits for otherinflammable gases) of the secondary container gas void if present atSTP (i.e., no more than 0.063 g-moles/ft at 14.7 psia and 70° F); or

(2) The secondary container and cask cavity must be inerted with a diluentto assure that oxygen must be limited to 5% by volume in those portionsof the package which could have hydrogen greater than 5%.

For any package delivered to a carrier for transport, the secondarycontainer must"be prepared for shipment in the same manner in whichdetermination for gas generation is made. Shipment period begins whenthe package is prepared (sealed) and must be completed within twice theexpected shipment time.

(b) For any package shipped within 4O;days of preparation, or within 10 daysafter venting of drumsor other secondary^containers, the determination in(a) above need not be\macle, and the time restriction in (a) above does notapply. •_ <\'%* . '" ? zj

7. Except for close fitting'contenjts^ shoring must be placed between secondarycontainers and the cask cavity to/minimize movement during normal conditions oft r a n s p o r t . ., ''"^>.."-'-_- '•'/'-,• ' ;. '"' •'

8. The lid and shield plug lifting lugsmust not be Used for lifting the cask, andshall be covered in transit. '''<-'';':'V;.. >"'

9. In addition to the requirements of Subpart G of 10 CFR Part 7*1:

(a) Prior to each shipment; the packaging lid seals, if opened (or if securityseal is broken,), must be inspected. The seals must be replaced with newseals if inspection shows any defects or every twelve (12) months,whichever occurs first.

(b) Each packaging must meet the Acceptance Tests and Maintenance Program ofSection 8.0 of the application.

(c) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures of Section 7.0 of the application.

10. The package authorized by this certificate must be transported on a motorvehicle, railroad car, aircraft, inland watercraft, or hold on deck of a seagoingvessel assigned for the sole use of the licensee.

S 271

i


11




REFERENCES

Scientific Ecology Group, Inc. application dated May 18, 1993.

Supplement dated June 23, 1993.

.<*. ;•>..•• CFOR'TkEUvSi.NUCLEAR REGULATORY COMMISSION

)ate:

William D. Trayers^DifectorSpent Fuel Prpie^'OfficeOffice of NucJear Material Safety,'and:-S.afe.gu4rafv ><'''))

'-\

272





1?


1


- 4I. PREAMBLE




Scientific Ecology Group, Inc.P.O. Box 25301560 Bear Creek Rd.Oak Ridge, TN 37831-2530


Westinghouse Hittman Nuclear, Inc.Application dated October 28, 1988,as supplemented.

c. DOCKET NUMBER 71-qnaQ4. CONDITIONS . -/

This certificate is conditional upon fulfilling the requirements'of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model No.:

(2) Description• y,, -

, V » > . - - ' • • •

The cask is a steel afinuljui ;84-l/4'inch6f pgh;?by 81-5/8-inches in diameter.The cavity is 75-1/2 Itiih!es\h1gh^ty£75-§78|1)|^hes indiameter.5 The side/âl|^C£nsist of twVpljfsfof 1-1/2-iivch steel.The 3-inch; steel 5bj£'e is^|j{tegrally.weiye.d0t) the^ylinder. The lidis a 3-inch steel^1a£e,,,.1s€eppe^ of thecylinder. A centrally'Tocatld:Ishield:R1 ug isi s ijni1 arly constructed.The lid and "plug a?e4attacHe^;with;.'?'tU'd^(0^J-^nd nuts-^hd sealedwith Buna N 0-ring g'askets. A j iigged dfaiV^line and/oir optional vent/test inthe secondary 1 jd connection fH;|/ôîded. Four skewedlugs welded to the, outer she! 1"'are»^sed for t ie down. There arethree cask lifting/Tugs, three lid lifting lugSjând one shield plug liftinglug. The package gross weight is approximately^,000 pounds.

(3) Drawings

The packaging is fabricated in accordance with Westinghouse Hittman Nuclear,Inc. Drawing Nos.: STD-02-078, Rev. 1 and STD-02-079, Rev. 0.

273£L2SJ£J£^


•* Page 2 - Certificate No. 9089 - Revision No. 12 - Docket No. 71-9089

(b) Contents

(1) Type and form of material.

Process solids, either dewatered, solid or solidified, and limited to thefollowing:

(i) Materials in which the radioactivity is essentially uniformlydistributed and in which the estimated average concentration pergram of contents does not exceed:

te 0.0001 m i l l i c u r i e of radionucl ides for which the A2 quant i ty in2 qAppendix A of 10 £FR Part71 is not more than 0.05 curie;

| | ; ; 6 . % . / h c h t e A | q u a n t ^ ; f Appndx A f1(PCFR Bar^71?is^t:i more'i than 0.05:curie, jor 0.001 mi Hi curie(^2000bi5?;di^nt|g^atii6ns/pefe%ii^^ per square centimeter for

0.005 milTicur ie of radionucl ides for which the A2 quant i ty inAppendix A of 10 CFR Part 71 i s more than 0.05 c u r i e , but not morethan 1;cur ie ; or

te 0 .3 milTvteurie of r ad ionuc l ides for which t h e A2 q u a n t i t y in^ Appendix A>Of 1.0 CFR Par t 71 i s moreithatn 1 c u r i e .

* rradioactive||T|terial,/provided^ thTat|the radioactive material is notreadily .disp^B^Wve and^tM,surt|^?contamination, when averaged

:6ver an \l5eatpjf*l>;|quare meteji^b*eis not .exceed. 0.0001 mi Hi curie(220,000}cdjsih1^gr|ttonsn^e^ ofradionuc|lld6,% f6"r3whi ithe< Apqiiant/iSy/in Appendix A of

£ (2) Maximum quantity of materi-a(ltP'erxpackage, t V ^

Greater than Type ^.quantity of radioactive'material which may containfissile material proyided,vthe; fissile^material does not exceed thelimits in 10 CFR §71.53^4'Theeweight of the contents, secondarycontainers, and shoring must not exceed 17,000 pounds and the internaldecay heat load must not exceed 2 thermal watts.

274

'• •^r,:--i?^-"-..v:'

NRC FORM 618A(3-96)




(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP (i.e., nomore than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

(2) The secondary container and cask cavity must be inerted with a diluentto assure that oxygen: must be limited to 5% by volume in those portionsof the package which.'could have hydrogen greater than 5%.

For any package delivered to a carrier for,transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for gas generation is made. Shipment period begins when thepackage is prepared (sealed) and must be completed within twice the expectedshipment time.

(b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drums: or other secondary;containers, the determination in(a) above need not be-fiade, and the time restriction in (a) above does not

9.

10.

Except for close fitting contents,, shoring must be placed between the secondarycontainers and cask cavity-to minimize movement during normal conditions oftransport. •/"•'••

The lid and shield plug lifting lugs must not be used for lifting the cask, andshall be covered in transit.

Packagings without a drain line must be provided with the optional vent/testconnection in the cask secondary lid.

The drain line and optional vent/test connection must be appropriately plugged andsealed prior to transport.

11. Prior to each shipment, the packaging lid seals, if opened (or if the securityseal is broken), must be inspected. The seals must be replaced with new seals ifinspection shows any defects or every twelve months, whichever occurs first.

12. The packaging must be leak tested at least once evQry twelve months in accordancewith Leak Test Procedure STD-P-02-002, Rev. 3, dated August 18, 1989. Each caskwhich has been damaged or repaired in the area of a seal must also be tested priorto subsequent use; normal gasket maintenance does not require a subsequent test.

13. Packagings fabricated after November 30, 1983, must be constructed of A-516, Grade70 carbon steel.

275



14. The package authorized by this certificate must be transported on a motor vehicle,railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vesselassigned for the sole use of the license.

15. The packaging shall be prepared for shipment and operated in accordance with theOperating Procedures of Section 7.0 of the application.

16. Each package must meet the Acceptance Tests and Maintenance Program of Section 8.0of the application.

17. Packaging fabricated in accordance with Hittman Nuclear & Development CorporationDrawing Nos. C001-5-9128, Rev. 5 and C001-5-9129, Rev. 3 are not authorized afterApril 1989.

18. The package authorized by .this certificate is hereby approved for use under thegeneral license provisions"of 10 CFR §71.12.


"v^v; REFERENCES ,..-•../£/'' "'

Westinghouse Hittman Nuclear, ^D^ofated'Wppiicatiliri^iated October 28, 1988.

Supplements dated:

^NUCLEAR REGULATORY COMMISSION

William D. pavers , DirectorSpent Fuel Project OfficeOffice;olf Nuclear Material Safetyfand Safeguards

Date:

276

vs. as as ax as as a : as a* as as as a : as as as ax as as as a : ax T¥J: as as as as as as as as as as as a% as a* as as a* a* a* a* as ax

wNRC FORM 618(3-96)10CFR71





14c. PACKAGE UMBER d. PAGE NUMBERtUMB e. TOTAL NUMBER PAGES

4

2. PREAMBLE




Chem-Nuclear Systems,140 Stoneridge DriveColumbia, SC 29210

Inc.


Chem-Nuclear Systems, Inc. applicationdated Hay 1, 1985, as supplemented.


4. CONDITIONSThis certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable/and the conditions specified below.

(a) Packaging

(1)

(2)

Model No.: ,. CNS :14-195-H

Description!?

A steel encased leadv;sh£ilded cask fon tradioactive material,right circular cylincdirl83iy8^ch\dikme|fe^by 89-7/8T-inch with a 77-inchdiametervby 80-l/,87;ih'ipli..âyi^r^''tead/-shJisSingi4s 2-3/16-inch thick, and isencased in:an oKtefr sf^îhe^l^Z/A-mc^S^cînd an :in.ner steel shell 1/8-inch thick. ; P o ^ i y e ^ ^ s ^ r e i ^ ' t h e ^ ^ o n ^ i & B e r - S f e a a e d l id is providedby twelve, 1-1/4-iri'chVidiam' ^^^ /Aêcondary^lid with a Neopreneseal uses jeightee||>374t-10;'UNC bqitsSfpr ,clos1ire. Jpe, cask is welded to a96-inch square baspiftp,l;a'tef,' h;a^wo"ltft^TigVtrunnions^ three l id l i f t ringsand one secondary l id liftityg^rftjg^yPackage grossc':yfeight is 56,500 pounds.

The cask is

(3) Drawings

The packaging is fabricated,in accordance ,with Chem-Nuclear Systems, Inc.Drawing No. 1-189-101, Sheet 1 of>\,-'Rev'. A-G. The optional shield inserare fabricated in accordance with Chem-Nuclear Systems, Inc.Drawing No. C-119-B-0017, Rev. 3.

inserts

2775!^

ig^rwigSE^gÊrgnirwîg^ww^^^'siiîg^^c


Page 2 - Certificate No. 9094 - Revision 14 - Docket No. 71-9094

8983

B 5. (b) Contents


Process solids, either dewatered, solid or solidified, or solid reactorcomponents, in secondary containers, and limited to the following:



0.005 millicurie1 of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 0.05 curie, but notmore than 1 curie; or


(ii) Objectsôf nonradioactive material externally contaminated withradioactivetmaterâl^provide8-«that the radioactive material isnot rea8.i5Jyidtspers"ible andthejsurface contamination, whenaveragedj§ov?er; an area.of l.squjifk meter, does not exceed

; 0-0001 ni11JlûVie'"!^2a,'000;dis^Htegra.tions"'per minute) persquare!;cenîmeteriOfradipnlielside^for which the A, quantity in

than 0.05 curie, orintegrations per minute) per

foy, othervXadionuclideV.

(2) Maximum-quantity of!matej*.i^^%t.package /;>

Greater thapCType A quantity of radioactive.material with the weight ofthe contents, secondary containers, shield inserts and shoring notexceeding 17,700 pounds* ..>/

278




(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP (i-e.,more than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or no


For any package delivered to a carrier for transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for gas generation is made. Shipment period begins when thepackage is prepared (sealed) and must' be completed within twice the expectedshipment time. --.„.

(b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drums or other/ secondary containers, the determination in(a) above need not be-iria.de, and the time-restriction in (a) above does notapply. . ; ; ;r_

7. Shoring must be placed :between secondary containers (or activated components), andthe cask cavity to prevent,movement during normal conditions of transport.

8. The lid lifting lugs must not-be;used for lifting the cask and shall be covered intransit. ., . ; •_/,_. :

9. In addition to the requirements ofySubpsrt G of 10 CFR Part 71:

(a) Prior to each shipment the lid gaskets if opened (or if security seal isbroken), must be inspected. These gaskets shall be replaced if inspectionshows any defects or every twelve (12) months, whichever occurs first.

(b) The package shall be prepared for shipment and operated in accordance withSection 7.0, Operating Procedures, in the application dated May 1, 1985, andsupplements dated August 26, 1985 and August 23, 1990.

(c) The package must be maintained in accordance with Section 8.0, Test andMaintenance, in the application dated May 1, 1985.


11. The package authorized by this certificate must be transported on a motor vehicle,railroad car, aircraft, inland water craft, or hold or deck of a seagoing vesselassigned for sole use of the licensee.

279

11





REFERENCE

Chem-Nuclear Systems, Inc. application dated May 1, 1985.Supplements dated: August 26, 1985, August 23, 1990, December 4, 1992,September 29, 1995 and January 23, 1996.

"FOR THE U.S. NUCLEAJtREGULATORY COMMISSION

. \ , C

(>^;C xWilliam D. Trav,ets||b;irector^ V-Sp^entcFfe1> Prp3ecff|)f f i ce I ~>)| ^ , f Office&f' Nuc]e.afe^Material Safetyvf-S?-''-.' ;and .sa-fpniiavrlc *§,-•&* •'. • ''

Date: M

a 280

NRC FORM 618(3-96)10 CFR 71



!. a. CERTIFICATE NUMBER

9096

b. REVISION NUMBER




4l, PREAMBLE





Inc.


Chem-Nuclear Systems, Inc. applicationdated August 26, 1985.


4, CONDITIONS , . • ; •


5,

(a) Packaging ;,

(1) Model No:: _CNS 21-300

(2) Description % 6 § k \f

A steel encased$|ead shielded cask fqjâdioactive'material. Thecask is a r i g h & t c u l a r cylirfder\wi|h|^6-3/4-inGOD by 117-1/4-inch height,,. anBiiâv4tty

;^3^heh/!ipJ4f 109-1/4-inch height. The1-irich thicKl->leacf^snii|ld is suppqfcfe^^y>outer andlinner steelshells 3/4-inch ii^:/J^Hc^\î^^th^mCkr plates of the lid andbase are lamiri^jd steel plate^jlith a$piafl thickness of 1/2-inch.Positive cl6"|ure!f6f,t'hîsi3Tcone^^^ licl is provided bytwelvej^l-l/înc^d^mellg-âp^^^w^.^ A secondary lid with aNeoprene,seal uses ^.ightlln^tSy^t000 "diamete.fXb.6lts for closure.The cask is , welded to a^^rji^h^squate base.pâte and has twolifting trunnions, three'Ifd ftift rings and.one secondary lid l i f tring. Package)gross weight is 57,450 pounds.

(3) Drawings

The packaging is fabricated in accordance with Chem-NuclearSystems, Inc. Drawing Nos. 1-298-101, Rev. K, andC-114-D-0006, Rev. C.

281



5. (b) Contents


Process solids, either dewatered, solid, or solid reactorcomponents, in secondary containers, and limited to thefollowing:

(i) Materials in which the radioactivity is essentiallyuniformly distributed and in which the estimated averageconcentration per gram of contents does not exceed:

0.0001 millicurie of radionuclides for which the A2quantity .in Appendix A of 10 CFR Part 71 is not more than0.05 'curie';

0.005 millicurie of radionuclides for which the A2quantity in Appendix A of 10 CFR Part 71 is more than0.Q5 curie, but not more than 1 curie;.,or

0.3 miJ;lJcurie of radionuclides for which the A2 quantityin AppfndixtA of fQ CFR Parjt>71 is more than 1 curie.

\( ;ii) oyec||?Jo3Fnonraîpactive itfajferial externally contaminatedl-[ wiljh r^foactivematerjilyHpôvided that .the radioactive

... maêîafef^npt- readily*d|,sperstb2e. and the surface'- ' cpjitamjni^x)^; whenfayeraiged ovjlrân area.of 1 square

v ;, (ZiÔpo^d^nf^rîg^s^pBr,lR\hute) ger square centimeter•, >, ofr.adioh^cTideS;^ quantity in Appendix A"c ;.ôf 10 CFRtPar^|?\t^npt/mbre'than O,rO5' curie, or

•V/OU.001 millicurîl^lbb.OOO/disintegra^tions per minute)<per .square centiriiete^ for other ;r£d;ionuclides.


Greater than Type" A quantity of radioactive material with theweight of the contents, secondary containers, auxiliaryshield, and shoring not exceeding 27,250 pounds.

282

r LWWwwwwwwww^wwwwwwwww-iigatwwMto

NRC FORM 618A(3-96)



6. (a) For any package containing water and/or organic substances whichcould radiolytically generate combustible gases, determination mustbe made by tests and measurements or by analysis of arepresentative package such that the following criteria are metover a period of time that is twice the expected shipment time:

(1) The hydrogen generated must be limited to a molar quantitythat would be no more than 5% by volume (or equivalent limitsfor other inflammable gases) of the secondary container gasvoid if present at STP (i.e., no more than 0.063 g-moles/ftat 14.7 psia and 70'F); or

(2) The secondary container and cask cavity must be inerted with adiluent to assure that oxygen must be limited to 5% by volumein those portions of the package which could have hydrogengreater than 5%.

For any package delivered to a carrier for transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for gas generation is made... "Shipment period beginswhen the package is prepared (sealed) and must be completed withintwice the expected shipment.time.

(b) For any package?:S.hfjp))ed within 10 dayjs$of preparation, or within 10days after venting W drums or other?secondary containers, thedeterminat.ipji''!in(^)" above, need not\be}';made, and the timerestriction in;(a) aboye does not apply. '

.V-"'''''•/>' ~/ y

• • •'' " ' •• •'"'

7. Shoring must be placed'between secondary containers (or. activatedcomponents) 'auxiliary' shield', and the'cask^cavity to prevent movementduring normal-conditions of tr^nspdrt.

8. The auxiliary shield shown in Drawing No. C-114-ET0004, Rev. No. B, maybe used for shipment of solidified wastes and,sol id reactor components.

9. The lid lifting lugs must not be used for lifting the cask and shall becovered in transit.

10. Prior to each shipment the lid gaskets if opened (or if security sea> isbroken), must be inspected. The gaskets shall be replaced if inspectionshows any defects or every twelve (12) months, whichever occurs first.


(a) The package shall be prepared for shipment and operated inaccordance with Section 7.0, Operating Procedures, in theapplication dated August 26, 1985.

(b) The package must be maintained in accordance with Section 8.0,Tests and Maintenance, in the application dated August 26, 1985.

283

MK W W JE W a t a t W ac ytCyrf \t(M a t ytcyti. no.


Page 4 - Certificate No. 9096 - Revision No. 12 - Docket No. 71-9096f

!! 12. Fabrication of additional packagings is not authorized.

z deck of a seagoing vessel assigned for sole use of the licensee.

3

5

Date: 4

13. The package authorized by this certificate must be transported on amotor vehicle, railroad car, aircraft, inland water craft, or hold or



,. REFERENCE: ,

Chem-Nuclear Systemsj; Inc. application dated August 26, 1985.

Chem-Nuclear Systelite; Inc. supplements dated August 23, "1990, andAugust 28, 1995. , \;-.. .^, ' , ,

/%%- ;FO'R THE Uls:.'.NUCLEAR REGULATORY COMMISSION

"-&:\ •' Wi(l l;i 'aififi)?f raylrs^-'-'Di rector

yi • • Spent; Fuel Project' Office'Material Safety

284

NBC FORM «1S(M6) CERTIFICATE OF COMPLIANCE " » ""**" " " " " " " " e ° " " " ™ 0 "

FOR RADIOACTIVE MATERIALS PACKAGES1.«.CERTIFICATE NUMBER9098

b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER

U A 0 9USA/9098/B(d.PAQE NUMBER


3PREAMBLEa. This certificate is Issued to certify that the packaging and contents described in item 5 below, meets theappiicabiesafety standards set forth InTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATION "L ISSUED TO (Nsmt tnd Mdna) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Department of EnergyTransportation & Packaging

Safety Division, EH-33.2Washington, DC 20585

Cintichem Inc. application datedAugust 20, 1987, as supplemented.

c. DOCKET NUMBER

i T - '•" r

'1-90984. CONDITIONS - •


(a) Packaging

I

(1) Model Nos.: CI-20WC-2 and CI-20WC-2A

(2) Description

Steel encased, wooden outer protective jackets with/a uranium shieldedcask and inner steel containment vessel. The protective jackets areconstructed of disks And rings of plywood,'which are glued together andreinforced with steel rods. The protective jackets are contained withinan 18-gauge steel -drum. ."The shielded casks have depleted uranium shieldsencapsulated in steel with a gasketed and bolted flange closure with six,3/8"-16 UNC-2A x 3/4" long bolts. Iheinner containment vessel is a2.73" 0D x-5.56" long 416^stainless"steel, gasketed and threadedcontainer. :*The gross weight of the packages is about 400 pounds.

^Model No.

Protective jacketsoverall dims, in

U(D) thickness, in

Cavity dims, in

CI-20WC-2

24-1/4x22x28-3/4

2

3.1x6H

CI-20WC-2A

24-1/4x18x26-1/4

1.8

3.1x6H

285

(b)

CONDITIONS (continued) I

Certificate No. 9098 - Revision No. 7 - Docket No. 71-9098 j\i

(3) Drawings ii

The packagings are constructed in accordance with Cintichem Inc. Drawing 'Nos.: )

Model No. CI-20WC-2 !101259, Rev. C and 100964, Rev. G <

j

Model No. CI-20WC-2A 1101354, Rev. F and 101326, Rev. D 1

Inner Containment Vessel „., ... I101401, Rev. C ( , v., \-\ t% £[ : V f s s j

Contents <?%V"'' *';"*7 % f

(1) Type and "form of material ^J j

(i) „, Mo-99/Tc-99 in normal form as sol ids" or liquids.i "^ ~- ' -. ,' . _.. " i

* - . * ''><••", '

(ii)_J-131 in normal form as liquids. , !

(2) Maximum quantity of materral per package •',

(i},^ For contents "described in;5(b){l)(i): - 1,. 1,000 curies--'_- rt^-.-^r>.""•* "• . ':". >; ... 3

(ii) For contents described 4n"5(b)(l)(ii)':' . 2 0 0 c u r i . e s - . ; .--t!^ •..-..<•--'-•'~ - ' ' •".•'" 1

6. Contents must be contained within the inner containment vessel specified in5(a)(3). " ./. .•'. i',J' ' ; <?'%*'• H

7. In

! a.

b.

| c.

d.

\

addition to the requirements of Subpart G of 10 CFR Part 71: I

The package must be prepared for jshipment*arid operated in accordance with the 1operating procedures (PO-05 "arid P0-06) of the application. |

1The package must be maintained in accordance with the maintenance procedures i(P0-06) of the application. 8

9|

The inner containment vessel neoprene 0-ring seal must be replaced prior to 8each shipment. I

Prior to each shipment, the loaded inner containment vessel must show no 1leakage when tested to a sensitivity of at least 1x10 std-cm /sec. 1

The inner containment vessel must be leak tested within 12 months prior to juse in accordance with the leak test procedures (PO-07) of submittal dated IFebruary 3, 1993. The inner containment vessel must show no leakage greaterthan lxl0*r std-cm3/sec.

286 |



8. Structural parts of the packaging which could be used as tie-down devices must besecurely covered or locked during transport in such a manner as to prevent theiruse for that purpose.

9. The packages authorized by this certificate are hereby approved for use under thegeneral license provisions of 10 CFR §71.12.

10. Expiration date: February 28, 1998.

REFERENCES

Cintichem Inc. application dated August 20,, 1987.

Department of Energy supplements ^ated: July 15, September 18, and December 21, 1992;and February 3, 1993. r ,V "••••*/ s.

, %.? - />"", *O FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Charles E. MacDonaid, ChiefTransportation Branch'Division of Industrial and:•/Medical Nuclear Safety, NMSS

D a t e : b t b Z « » l 3 3 J -^

287

MIHWITI\ffl









2

. PREAMBLE



u ISSUED TO (Name and Address)



EG&G, ATR Fuel Element Shipping ContainerSafety Analysis, EGG-ATRO-7737 (Rev. 1),August 19, 1987, as supplemented.


4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10'GFR Part 71, as applicable:'and the conditions specified below.

(a) Packaging

(1)

(2)

Model N o . i v - A T R -•• ; .

Description NH>f^>},. - - ' ' ^^ '^ '"'. •''.

The inner contairi-ej^js a right^para^TeljepJ;ped, 69-7/1,6 inches x 26-13/16inches x 6-15/16 | lno|e.s | cdnss/tr'ucteclr0^.:;3^-inch plywood, covered with16-gauge s tee l . Meftop and^bottomWr=ep|ned with-high densitypolyethylene foam^|M!wj th : ^ pla^e.; Wood spacerscovered, .with^ponge}?^ tfirek cadmi urn pi ate

idvhinge pins provide

The inner container vi£ ep'tfosed^lthtn :sn overpack, 73-15/16 inches x31-3/4 inchedx 11-3/16 i"fi|fre|s^onstru.cted of;i-'inch plywood, framed bysteel angle me'iTibers and covered with 18-gauge\>teel. Aluminum, honeycombimpact limiter-sV-are fixed to the ends of the overpack. Positive closureof the overpack is provided by four hinge pins which are secured in placeusing 1/16-inch diameter cotter pinsiVThe package weight isapproximately 853 pounds.1 '"*

(3) Drawings

The packaging is fabricated in accordance with EG&G Idaho, Inc., DrawingNo. 445721, Sheets 1, 2, and 3; and EG&G Idaho, Inc., Drawing No. 445722,Sheets 1 and 2.

288

az ai;ai: a? at araxwwwaz WaTaraa. WWW:BE.ara7ac wwwataTWWaTaT atazwNRC FORM 618A(3-96)


5.


(b) Contents


Unirradiated ATR fuel elements. Each element contains 19 formedfuel plates, clad in Aluminum 6061. Each element contains amaximum of 1,100 grams of U-235 in uranium that is enriched to amaximum of 94 wt% in the U-235 isotope.


Up to four (4) unirradiated ATR fuel elements. Total U-235 contentnot to exceed 4,400 grams per package.



6.

7.

8.

9.

10.

The contents must be maintained within its compartment and the active fuellength must be completely within the region of the cadmium covered spacers-.Wood spacers may be used.;to accomplish this* /-

Each package must meet the Acceptance Tests and.Maintenance Program ofSection 8.0 of supplement-dated August 27, 1993;.

The package shall be prepared /for shipment andioperated in accordance with theOperating Procedures in Section 7.0 of supplement-dated August 27, 1993.

* '.' -The package authorizedby this certificate is_hereby approved for use under thegeneral license provisions.of 10 CFR §71.12.Expiration date: January 31, 1999. ;

REFERENCES

EG&G, ATR Fuel Element Shipping Container Safety Analysis, EGG-ATRO-7737 (Rev. 1),August 19, 1987.

Supplements dated: June 11 and August 27, 1993; and October 13, 1995.


Date: <-i


and Safeguards

289

su&guiusususiaLaLaysLMiiyi^

NHC FORM 618(MB)10 CFR 71







PREAMBLEa. This certificate is issued to certify that the packaging and contents described in item 5 below, meets the applicable safety standards set forth in Title 10, Code



a. ISSUED TO (Name and Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Neutron Products, Inc.22301 Mt. Ephraim RoadDickerson, MD 20842

A Av

Neutron Products, Inc., applicationdated August 31, 1977, as supplemented.

. DOCKET NUMBER

4. CONDITIONSCONDITIONS <v <\j? <£&! <sThis certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below

(a)3

Packaging

(1)

(2) Description

The Gxisk isshelled a .^,tube.^Positiyie)end coyefs at each -...^diameter^j.2 gauge steeheight madô! 3/4-inch

o>withii|.,a wooden overpack.inch-thick steel sphericalby?3/8-inch thick steel

israccomplished by bolted7 .^,.,r ...- ovejpack is a 48-inchfch V^boden^shefl 38-1/4 inches in

v -/ • «...-«. plywood sheet;s;glued together andreinforced by/16 steel t ie rods and 32 Tttg|screws. Positive clsoure ofthe overpack l i d j-sâccomplished byêqually spaced bracket assemblieswith attached chains arfd- held iogetheV with a 3/8-inch by 4-inch weldedring. The maximum package^gros^wei'ght is 6,000 pounds.

(3) Drawings

The Model No. NPI-20WC-6 packaging is constructed in accordance withNeutron Products, Inc. Drawing No. 240010, Rev. C. The overpack isconstructed in accordance with Neutron Products Inc. Drawing Nos.240160, Sheet 1, Rev. None, and 240160 Sheet 2, Rev. A.

2 9 0

^

i^^



5. (b) Contents


Cobalt 60, as sealed sources which meet the requirements ofspecial form radioactive material.


The maximum activity must not exceed 9,500 curies. The maximuminternal decay heat must not exceed 150 thermal watts.

6. The contents must be secured in^thejirum assembly (Item 11) so as to restrictmovement in any directiion|t|> lessStfan/0^25 inch by lead, steel or tungstenfull diameter plugsâpd'^pacers. J w /

7.

8.

The gross weighiKof the packaging must not exceed^, 000 pounds and the innershielded casj^shall be snug-fitting within the Wooden overpack.

In additionvtor*he requirements of Subpartôf^lO^CFR Part 71:

(a) TheipackageSn^^be, prepared for/Shjpeift and operated in accordancew i ^ t h e Operffcittg Procedure! i if theggippl ement Edited September 21,1QQ3 i -^S i ' r ? /-A I % ^ c ^ - * (C si

(b) The

9.

10.

The packagingthe ^ J

1 Ym--™packag;ermus|gfe§||the AccepJb;anC^'es>t//and M;Entenance-supplement tl%eMSeptembeif^l^993^w,<. ^_

Program in

Expiration^date: 'bctol^r 3 $ p

herebyâpproved for use under

^'

tS NJSS1'

A

REFERENCES V

Neutron Products, Incorporated' aBîc|tioâated> August 31, 1977.

Supplements dated: February 6, 1978; July 31, 1985; August 2 and September 7,1988, and September 21, 1993


A-

Dated:o 9

Cass R. Chappell, Section LeaderCask Certification SectionStorage and Transport Systems BranchDivision of Industrial and Medical

Nuclear Safety, NMSS

2 9 1

^

INRC FORM 618(8-8SI10 CFR 71



9107

b. REVISION NUMBER

5


IK A,

d. PAGE NUMBER

-Jr

o. TOTAL NUMBER PAGES

2 _

2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafetystandardsset forth in Title 10, Code



t

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJ3ESIGN OR APPLICATION 'a. ISSUED TO (Name anil Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


w ,>

Technical Operations, Inc. applicationdated December 30, 1982, as supplemented,

"c. DOCKET NUMBER 7T-iQ1 f|74. CONDITIONS <j ^p "V-<0/ ^


5.

(a) Packaging

(1) Model Nql-;7 771

(2) Descri

The ModfeUNo.storage^The capacityaccept ceîaindeemed to^njetChanger m e W

d i i

x uje,as a source changer,,w.»^«,yh&fpr radibgraphic sources.

n mtu Pfc?ffri e s W # b a l tS$P • The contai ner wi 11Ijm^nllefcdiogfafhic sources which have beenS l f / s m t ^ ^ m - The Model No. 771 Source

-••-•;:»-• •—^-«-—' — '">-MfJ ^ngljMMXinch.eslV/ide andv?0 inches high. Theradioactive\source assemblyW|fhp%d f « Z i r e a l t o r Titanium "S" tube.The "S" tube ^surrounded byldepJ-eted uranium .mefVl as shielding material.The depleted ura/nim shield assembly is encasetfîn a steel housing. The voidspace between theniep!.$ted uranium shield assembly and the inner container isfilled with a rigid poPjêthanjs foam,. <Tfie gross weight of the container is

5.

690 pounds.

(3) Drawings

>\(

The packaging is constructed in accordance with the Technical Operations, IncDrawing No. 77190, Sheets 1 through 6, Rev. 0.

(b) Contents


Cobalt 60 as sealed sources that meet the requirements of special formradioactive material.


110 curies

2 9 2

^

^" * N U C L E A R R E G U L A T 0 R Y COMMISSION

COND.T.ONS (continue*,


6. Source assemblies for use in this packaging are limited to those assemblies asidentified in Section 1-3 of Technical Operations, Inc. application datedDecember 30, 1982.

7. Nameplates shall be fabricated of materials capable of resisting the fire test of10 CFR Part 71 and maintaining their legibility.


(1) The package must be prepared for shipment and operated in accordance with theOperating Procedures in the supplements dated February 16, April 13, andApril 28, 1993; and, %$ O £"

(2) Each package must^be^.maintained and acceptance^feested in accordance tested inwith Chapter 8 of^he^supplements dated Februakyjl6, April 13, andApril 28, 1 9 9 3 \ " V

9. The packaging authorised by this certificate is herei)y^ap|V%ved for use under thegeneral license§rovisj8Tis,.j)f 10 CFR §71.12. .*<• j X t&,

10. Expiration date:*? May

*STechnical

Supplements dated

Operati oa"sT Inc,^(;;aBpl^B|oi|datecll041^^1^30^1982. ^

COMMISSION

Charles E. M cDorfald, ChiefTranspjoria^jon Branch

'D'TyJsfon^ of" Industri al and'Medical Nuclear Safety, NMSS

MAY 2 0 1993Date:

2 9 3

jftraTaTaTa7aTaTaTara£ a^aTaTaTaTac a^ aTaTataTaTaYata^ stLysniLsai ae az a<: aTaTaTaTataTatat at at at at ar at:




1. a. CERTIRCATE NUMBER





4I. PREAMBLE





Inc.


Chem-Nuclear Systems, Inc., applicationdated May 31, 1983, as supplemented.


«

«i


5.

(a) Packaging

(1) Model No.: CNS. 6-75

(2) Description ;;;"

The packaging is a.ssMel encasfd, leadshfilded right circular cylinderfor radioactive matehiii. The outside dimensions arq 62 inches indiameter'by 86-5/8^m9h;es%longWrid the £#|ty dimensions are 53 inches indiameter, by 74r>#2 in~eh!s;>1ong. Jhe:f3-l/:4-inch/annulus. between the outer3/4-1 nch and rr "-•-'--•- ---plate consistslead and'a 1/4-outer and a;l/.2-inchrt^iclc steelMnnercplate with 2^7/8 inches of leadshielding.' A secondary coye^,. plugging the 20-inch central opening in thecover, is constructed of a TU^h~outer plate, 1-1/2 inches of lead, a1/2-inch plated 1-3/4 inched'of lead and a 1/4-inch inner plate. Thecovers are Neoprene gasketed and secured by sixteen, 3/4-inch and eight,5/8-inch bolts, respectively. The cavity is vented through a 1/8-inchplugged tube through-the cover and drained through a 1/2-inch plugged tubeat the bottom. Three lug's on .the cask sides, cover ribs and secondarycover are provided for lifting. Four lugs on the cask shell are used fortie-down. Package gross weight is about 41,300 pounds.

(3) Drawing

The packaging is fabricated according to Chem-Nuclear Systems, Inc.,Drawing No. 1036-D-01, Sheets 1 and 2, Revision M.

294

«NRC FORM 618A(3-96)



(b) Contents

i


Dewatered or solidified waste, in secondary container, and limitedto the following:



0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71js more than 0.05 curie, but notmore than 1 curie; or

0.3 mi H i curie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 1 curie.

(ii) Objects of nonradioactive material externally contaminatedwith radioactive material, provided that the radioactivematerial is not readily dispersible and the surfacecontamination, when- averagedrover an area of 1 square meter,does not" exceed 0.0001 millicurie (220,000 disintegrations perminute) per square centimeter of radionuclides for which theA2 quantity-in Appendix A of 10 CFR Part 71 is not more than0.05 curie, or 0.001 millicurie (2,200,000 disintegrations perminute) per square centimeter for other radionuclides.


Greater than Type A quantity of radioactive material with the weightof the contents, secondary containers and shoring not exceeding10,300 pounds. The decay heat load shall not exceed 20 watts.

2 9 5

U&J&]&?&^^

:WWW^WWWWWWWWWWWWWW»65l

a

B

*

i

gg

i

8

m

*

aBM

jj (b) For any package sh||||di withfntdb/da^s^.of|p|>eparatioh, or within 10 daysp after venting of dftesf pjf othersecondar-yjdontainers, the determination in




(1) The hydrogen generated must be limited to a molar quantity thatwould be no more than 5% by volume (or equivalent limits for other

void if present atpsia and 70°F); or

inflammable gases) of the secondary container gasSTP (i.e., no more than 0.063 g-moles/ft3 at 14.7

(2) The secondary container and cask cavity must be inerted with adiluent to assure.that oxygen must be limited to 5% by volume inthose portions of,the package;with could have hydrogen greater than5%. ,-,v, \.»"" '•" '*'''/:,,..

For any package^delivered to a carrier for transport, the secondarycontainer imisi be prepared for shipment in the same manner in whichdetermination .for.gas generation is made. Shipment period begins when thepackage i$'prepar$dt(sealed) and must be completed within twice theexpected shipmentvti%je* //y^

(a) aboveneed /not %T£'^ge^--a'naê^tjnje.'^'estrjction in (a) above does not

apply--.;. ^Pj *Mff&\-~., -.-ftW9# ;;/'/7. Except for close fit^g'fdoTite^fsy!,sîdrin^'#ust be%laced between the secondary

containers and^the cas^'i^ty^t^^p^6ye'ht:^%yenleh>''during;•;normal conditions oftransport. \"4 ^W-^^^^îi^^^'^r'^C i"~':<

8. The cover lifting,lugs must not b'e}^s4p|fbr^Tifting of ihe cask and must beplugged or covered in transit. •""•^^ ,„

9. In addition to the requirements of Subpairt Gjof 10'CFR Part 71:

(a) Prior to each shipment, the packaging lid seals, if opened (or if securityseal is broken), must be inspected. The seals must be replaced with newseals if inspection shows any defects or every twelve months, whicheveroccurs first. A determination must be made that closure seal replacementis current with the seal replacement schedule. Cavity drain line and ventconnections must be sealed with appropriate sealant applied to the pipethreads.

(b) The packaging must be maintained in accordance with the MaintenanceProgram of Section 5.0 of the application, as supplemented. In addition,the cask must be leak tested at least once every twelve months inaccordance with Subsection 5.2.5 of the application.

(c) The package shall be prepared for shipment and operated in accordance withthe operating procedures of Section 4.0 of the application, assupplemented.

296



10. Fabrication of additional packaging after October 31, 1983 is not authorized.

11. The package authorized by this certificate must be transported on a motorvehicle, railroad car, aircraft, inland water craft, or hold or deck of aseagoing vessel assigned for sole use of the licensee.



REFERENCES

Chem-Nuclear Systems, Incorporated, application dated Hay 31, 1983.Supplements dated: September 9, 1983; January 27, 1984; August 26, 1988; andAugust 27, 1993.

s

' - '-I'- \ C;#//<:: ';' Will ;i ant*D> TraVef*s-, Director^:/'/:'/} ':>:--;:;.iS;pent*Fuel P j r ^c t Office-%-..:>',, .,;<'; Ofsf:|eg;of Nucleir Material Safety

Date: M \ ^V \ M V ^ . - ^%<;/';;=!" ;j; . f : " '

297





9111

b. REVISION NUMBER

14


USA/9111/A

d. PAGE NUMBER

1


42. PREAMBLE





Inc. Chem-Nuclear Systems, Inc., application datedJune 29, 1983, as supplemented.


4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10'CFR Part 71, as applicable; and the conditions specified below.

(a) Packaging .;V ;•••

(1) Model Nos.: CNS,:6-§0-2 and CNS 6-80-2A

(2) Description ":

A steel encased, 1 eadjp^ltel ded "ca ic for- so|.|||jfadioacti:v% material. Theoverall dimensions ot^f- 'cask are i$-VI£?£ti&fy diametevvby 78-5/8-inch height.The cask consistsj-pf €»o.l:QhcpniK#-^rb'o'n>\êl ^cylindrjcal shellssurroundings 4^1744,incfi''' h;i k lead_s^;etl)lkirThe/,^/8-incli thick inner shellhas a 59-inch ID;?and trie;fi^hcri;itKi;cîou^^ OD; thebase consists of x^b%înch%hjcfcjWefd|cf st^'ef';p1atesibf 60-inch diameter and70-1/2-inch diame:^^.a^d.ay%êpp!ediweiiêd 1 fd'>comprised of two, 4-inch thicksteel plates;constructioncavi ty i s 59- .c._.. -„ ,-,.,•,,,.„.,. -.accomplished b v e i a h t . 1-1/4-ihcf^bolts or studs and nu t s . Both l i d s on ModelNo. CNS 6-80-1 _redundant Neoprene seal.. : Both lids on Mode/1 No. CNS 6-80-2A are sealed usinga double 0-ring configuration .as'shownôh'sDrawing No. C-110-D-0020, Rev. A. Aplugged drain port is located at the cask bottom. The cask is lined with12 gauge stainless steel. Three lift lugs, located on the secondary lid areused for lifting both the cask and the primary lid. Four lugs, welded to theouter shell are used for tie-down. The package gross weight is approximately51,500 pounds.

(3) Drawing

The packaging is fabricated in accordance with Chem-Nuclear Systems,Incorporated Drawing No. C-110-D-0028, Sheets 1 and 2 of 2, Revision B oroptional lid seal configuration given in Drawing No. C-110-D-0020, Revision A,for the Model No. CNS 6-80-2A.

298

NRC FORM 618A(3-96)



5. (b) Contents


Greater than Type A quantity of byproduct material contained in solidsand solidified waste, in secondary containers, or activated solidcomponents, and limited to the following:


0.0001 millicurie of\ radionuclides for which the A2 quantity inAppendix A of 10 :CFR£Part> 71 is iiot more than 0.05 curie;

0.005 miilfcurie of radionuclides for Which the A2 quantity inAppendix/A of 10 CFR Part 71 is more than 0.05 curie, but not morethan-1 curie; or

0.3Jmililcurie of radionuclides for^which theA2 quantity inAppendix ANof:ao,CFR Part 71 is ,mo£e?'than 1 curie.

(i i) Objects of |i^rladi;bact1yevmateri.ai|ife}cternally contaminated with^rsadioactive?Craaterial,/provided,th'ajfjthe radioactive material is not<readily<;dfiisp^W|ble; and'^he-;siir|a;^con,tamination, when averaged,oyer aovêa^pf^/Jr^quare.,raet'eip^44es np*t/exceed.;0.0001 mi Hi curie(220,000j\dj,sintefpStionsipehfm^0u'te)^|e^: square, centimeter ofradionucîae%foy^]hichjtHe ^'ûant'tt^/in Appiendix A oflO GFR PaJ t %OjsZjfioi'•,mt^re\tjfan. 0,.05/curie, lor,0.001 millicurie

^rper-iinut-e) perMUare centimeter for

(2) Maximum quaifttty of materiai^per package *K>

Greater than Type Aûantity of radioactive material with the weight ofthe contents, secondary; containers/and-shoring not exceeding 7,500pounds. The decay heat load must not exceed 60 watts. The contents mayinclude fissile materials provided the mass limits of 10 CFR §71.53 arenot exceeded.

2 9 9

¥B NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONg (3-96)


6. (a) For any package containing water and/or organic substances which couldradiolytically generate combustible gases, determination must be made by testsand measurements or by analysis of a representative package such that thefollowing criteria are met over a period of time that is twice the expectedshipment time.

(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP (i.e., nomore than 0.063 g-moles/ft3 at 14.7 psia and 70° F); or

(2) The secondary container and cask cavity must be inerted with a diluent toassure that oxygen must be limited,to 5% by volume in those portions ofthe package which could have hydrogen greater than 5%.

For the package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in, which the determinationfor gas generation is made. Shipment period begins when the package isprepared (sealed) and must be completed within twice the expected shipmenttime. • * .-"•-< , „ ;.>>"''

(b) For any package shipped"within 40; days of preparation, or within 10 days after£ venting of drums or o|?Henjsecondarycontained the.determination in (a) abovea need not be made, and|Jthej;time r(Bstrictipn^W4(a) above does not apply.

£ 7. Except for close,fitt|ing^con|Wrrts^, shortng^must*be placed between secondaryZ rnntainprs anH thp raskiravitV'-fhi.nirouent mnuomfint, HrtKnnn nnvrmal rnnditinnscontainers and the cask^cayity^tp/preyenjt movfment^filririg normal conditions of

transport. ... V-V!'-4>j '"'vv ;'< ' !-vf!"v vM"/.'.> ~-~,

g 8. The cavity drain line mu$|yb4'^eaTe)lVwi;|{jt.'ippWd))r.i!lte sealant applied to the pipe gc plug threads prior to trahspori. ; ; v ^ r'- f -* 9. Packages must be leak tested initially^and at least price every 12 months, as: specified in Subsection 8;1.3 of the Safety Analysis Report as revised December 19,£ 1988. The cavity or volume between the double.Orring seals (Model No. CNS 6-80-2A)£ shall be pressurized to 14.0 psig. Seal acceptance must be based on no observable: leakage over a ten minute period using a pressure gauge with a maximum graduationc of two pounds and the pressure supply line disconnected from the cask and test^ fixture.

10. The package authorized by this certificate must be transported on a motor vehicle,r railroad car, aircraft, inland water craft, or hold on deck of a seagoing vessel* assigned for sole use of the licensee.

uy 11. Each package must meet the Acceptance Tests and Maintenance Program of Section 8.0? of the Safety Analysis Report of June 29, 1983, as revised September 19, 1983 andJ December 19, 1988.«

300^

B

gggggggggg

NRC FORM 618A(3-96)



12. The package shall be prepared for shipment and operated in accordance with theOperating Procedures of Section 7.0 of the current Safety Analysis Report ofJune 29, 1983, as revised September 19, 1983 and December 19, 1988.



REFERENCES

Chem-Nuclear Systems, Incorporated^application dated June 29, 1983.

Supplements dated: September^, 1983, December 19, 1988 and December 28, 1993.

'' FOR THE V.S. NUCLEAR REGULATORY COMMISSION

^•t^CL?; Wflliam/pfejTravers, DirectorSpents Fiief?Project Office!0^ce> ; iWu c l< e a r Matenai Safety

and:

Date: MU•A <y.

*V'• , . . <../•>

3 0 1I&J3^^

NRC FORM 618(MS)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.a.CEHTII IMBER b. REVISION NUMBER C.PACIKAGE IDENTIFICATION NU

USA/9126/B(U)d.PAGENUMBERENU e. TOTAL NUMBER PAGES

PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



a. ISSUED TO (Name and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation applicationdated March 9, 1989, as supplemented

c. DOCKET NUMBER

4. CONDITIONSThis certificate is conditional upon fu!filling;the requirements of 10 CFR Part 71, as applicable, and the'con'dijions specified below.

(a) Packaging , \r-~..

(1) Model' Nos.: 2O'^20A, 50 and 50A y

(2) Description

A.-steel -erfcasdd^rani

surrounded^depleted f^The void space betweei^^^^Wetej^pranium/^teld assembly andthe oujte'rf. container if/filpfc§with^polyur'eitn1ane foam. The grossweight ofj/|he containertiA325 pounds. ^ ^

oic device. The

inches"assembly is

ismaterial. The

in^a"steel housing,assembly and

(b)

(3) Drawings

The packaging is constructed )in accordance with Gamma IndustriesDrawing No. 821-1001-128, Rev. 2, Sheets 1 and 2.

Contents


(2)

Cobalt 60 as sealed sources that meet the requirements for specialform radioactive material.


Model No. Quantity

20 and 20A50 and 50A

20 curies50 curies

3 0 2

M^^



6. The source shall be secured in the shielded position of the packaging bythe safety plug assembly, source assembly, and lockbox assembly. Thecomponents used to secure the source must be fabricated of materialscapable of resisting a 1475 °F fire environment for one-half hour andmaintaining their positioning function. The ball stop of the sourceassembly must engage the locking device. The flexible cable of thesource assembly and safety plug assembly must be of sufficient lengthand diameter to provide positive positioning of the source in theshielded position.

7. The can and side plates must be a minimum of 1/4-inch thick carbonsteel. The can and side plates shall be joined by full penetrationwelds. All other welds shall be fillet welds having sufficient throatthickness to develop strength equal to or greater than the metals beingjoined.

8. The nameplates shall be fabricated of materials capable of resisting thefire test of 10 CFR Part 71 and maintaining their legibility.

9. In addition to the requirements of Subpart G of 10 CFR Part 71, thepackage must be operated and maintained in accordance with the operatingprocedures and maintenance program in Chapters 7 and 8 of supplementdated September 27, 1994.

10. Fabrication of new packages is not authorized.



REFERENCES

Amersham Corporation application dated March 9, 1989.

Supplement dated: August 21, 1989; and September 27, 1994.




0 8 1994

Date:

303

•xiu*ua^MGuaiuiii>iau»uau9M&j&ius!^^

KRC FORM 618

10 CFR 71



CERnHSME NUMBER ..REVIglION NUMBER c. PACKAGE IDENTIFICATION NUMBER.PACKAGE IDENTIFICATIOI

USA/9127/B(U)d. PAGE NUMBER e. TOTAL NUMBER PAGES

2

iiii

•it

iii£

\

i

ti

t

ii

i. PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theapplicablesafetystandardsset forth in Title 10, Code

of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material-"





Amersham Corporation application datedMarch 9, 1989 as supplemented

c. DOCKET NUMBER

4. CONDITIONSThis certificate is conditional upon fulfillingjhejrequirements of 10 CFR Part 71, as applicable, and the/conditions specified below.

(a) Packaging

(1) Model nuo.. ^

(2) Description^

A steel encased, UK,aniliiTcontainer'^ a p p ^ ^ a %

, 10QAjg|00. and 200A

high.or titanium^S" 1shielding materialsteel housingâssembly and\tfre outergross weight of/jthe containers;'fSQ'QvfJc

2l'dedi:Ta9Hpgtap|iLi^device. The shippingrr.^^.. ,e^.^>^_,,__ w i ( ^ n d 4 2 i n c h e s

a Z iâ l loyÊepletejd. uranium metal as"assemb*.|y is encased in a

u@i|ium shielda poûfethane foam. The

(3) Drawings

The packaging is constructed^âc.cordance^with Gamma Industries DrawingNos. 821-1001-128, Rev. 2; 3heetHl and 2:

(b) Contents


Cobalt 60 as sealed sources that meet the requirements of special formradioactive material.

3 0 4

^^

fJRC FORM 613A(6-83)



(2) Maximum quantity of. material per package

Model No. Quantity


100 and 100A200 and 200A

100 curies200 curies

The source shall be secured in the shielded position of the packaging by thesafety plug assembly, source assembly and lockbox assembly. The componentsused to secure the source must be fabricated of materials capable of resistinga 1475°F fire environment for one-half hour and maintaining their positioningfunction. The ball stop of the source assembly must engage the locking device.The flexible cable of the source aênjpysan.d^safety plug assembly must be ofsufficient length and diametefpQiôv-ide^bin-Mê^positioning of the source inthe shielded position. \ J v ^

7. The can and side p l a ^ must be a minimum of 1/4-inch €hiok carbon s tee l . Thecan and side p la tes^ha l l be joined by full penetration W l ^ s . All other weldsshall be f i l l e t wettls having sufficient throat thickness, tppdevelop strengthequal to or grea^R t f i ^ ^ h i m e t a l s being joined .<y^ jL

8. The nameplates iftVll be •fflllJated of_materia/s^pfble of rest ing the firetest of 10 CFRiPart 71

Part 7feithe packagerocedbfees in

9. In addition to the reqmust be operat|d3andSection 7 and Section

10. Fabrication of new^pac

11. The package autho'r i-zedgeneral license provisions

approved for use under the2?

12.. Expiration date: Oct%§=$l, 1999.

Gamma Industries application dated March 9, 1989.

Supplement dated: August 21, 1989; September 27, 1994.


Date:o i

Cass R. Chappell, Section LeaderCask Certification SectionStorage and Transport Systems BranchDivision of Industrial andMedical Nuclear Safety, NMSS

305A a i i 5 ^ ^

srnrFHtFUirwrnm

NRC FORM 618

am10CFR71






2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafetystandardsset forth in Title 10, Code





^

Amersham Corporation application datedMarch 9, 198S, as supplemented

> Jc. DOCKET NUMBER ^*J €^1-9128

4. CONDITIONS ^ \j) ^ " H ^ ? / /This certificate is conditional upon fulfilling the requirements of 10 CFFI Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1)

-?*•?/

A stee^,encased, |c|pUnf shfcontafiner is a'pDro .iniEite'>ly~4'26 inches higffiMp ?%0Mt msourceâ^semb^Mii? hîfff^""1

septum j t theê4%n or*beyond Bxe opt3Mmlfye3%||

Ided soutjcfeêxchanger. CThe shipping^ ^ W M g | % m e t e r , 13Cinches long and

i^^«^v,v.,+4^^ T .^ radioactiveir"S" tube. A. the source assembly

ie is^surrounded byfv&mi--'~*--i*-*«-<r\— TheXdepleted uraniumf |f»^ e eVMV s i n9- Ch'e"xvoid space between^s |^ ly%hj / the outet^ container is filledie^gross weight of^tne container is 500

shield a%mblyl i etoasediHthe depleted^ uranium sfiiM-with a polyu|ethane foam. n~pounds. ^/-^

(3) Drawings

The packaging is constructed .in accordance with Gamma IndustriesDrawing Nos. 821-1001-033, 180-01, 191, 821-1005-008D, 821-1001-117821-1001-128, 821-1001-129, 811-1001-212, 811-1001-111, and801-1001-159.

306



5. (b) Contents


Cobalt 60 as sealed sources that meet the requirements ofspecial form radioactive material.


200 curies

6. The source shall be secured fayth^sjMf-lijed position of the packaging bythe safety cap, source jiss^nibp^ atfd aibcidjoxâssembly. The components usedto secure the source^mus^lBe1 fabricated bfNnatepials capable of resistinga 1475°F fire environment for one-half hour and^maintaining theirpositioning functipnf The ball stop of the sourceâssembly must engagethe locking deytcel The flexible cable of the source-assembly must be ofsufficient lericjth and diameter to provide positive.Tpos;ftioning of thesource at the septumon the shielded position.^'y y '/

The cancan andshall be .equal to on^greater

8. The namepTates sh>p£be of-resisting the firetest of IOM:FR

9. Use of packaging fabj^M&d^^MJî3fa^Ûi^991 is not authorized.

10. In addition tG^the requi>en^n^b|fS|ib.pVtt,Gi|pf 10 CFR Part 71:

a

11

The package 4pa"J4 be prepared for shipmentcand-operated inaccordance v/fth' the Operating Procedures oKSection 7.0 of theMarch 9, 1989 applicatjonâs s^ppljemenil'd.

b. The package must be main'taS'neft in "accordance with the AcceptanceTests and Maintenance Program of Section 8.0 of the March 9, 1989,application as supplemented.

The package authorized by this certificate is hereby approved for use underthe general license provisions of 10 CFR §71.12.

12. Expiration date: February 28, 1996

307

tia!j&ua\i9MJWJW&MX>/a!s4&M^

<f^r^/&&&jF&fifl&i<f!RfrilS/^M^^



REFERENCES

Amersham Corporation application dated March 9, 1989.

Supplements dated: August 21, and September 23, 1989; February 8, andDecember 6, 1990; and January 29, 1991.


Date:

Charles E&MCDgnald, ChiefTransportation^BranchDivision of Safeguards and

Transportat i ori jJMSS

./•'

•4

308

jSTWWWWiig MWWWaE a£ W aSH aa :agNRC FORM 618(3-96)10CFR71






USA/9132/B(M)Fd. PAGE NUMBER


5

X. PREAMBLE



o. ISSUED TO (Name and Address)



Nuclear Packaging, Inc. applicationdated April 22, 1985, as supplemented


4 . C O N D I T I O N S . r •••','-This certificate is conditional upon fulfilling the requirementsfof 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No.: cT-3

(2) Description

A stainless steel and le^VîeldetDiwâdia'tedêl shipping* package (cask).The cask is a right circUfaf cylinder with .upfef and lower-steel encased rigidpolyurethane foam (2Q Ib||t3lf'imgabt.vWIniteYs^^The overall'dimensions are 213.2inches in length andf2f|inChes ;fri diameter.f '^fhfexask without^the impact limitersmeasures 177.2 inchWfit iengtând 26;.44'iinches ,i,n>d3ameterl

The outer cask shelT^Xcomprts^dof; a;i-inch thi^kr/stainless steel shelloverlayed with aulO gauge^tjainiUss;stieelvcoYer>,:"Between;:these two materials isa 0.08-inch diameter wrt'el%r£pT p/jîding in;:ai^gap forâdditional thermalprotection. V-;-% ' :- Z/;j$:s:i>b <;,...' ,/.'•

The inner shell (containment vesselV'is a standard seamless stainless steelSchedule 40 pipe having an o.utside diameter of 8.625 inches with a nominal wallthickness of 0.322 inch. The. annular space,-Between the inner and outer shellsis filled with lead having"a thickness; of./approximately 8 inches.

Both the inner and outer shells are welded at each end to heavy steel closureplates with conical surfaces to assist in positioning and sealing. Thecontainment vessel measures 147 inches in length by 7.981 inches in diameter.

The containment vessel is sealed at the bottom end with a 11.83-inch thickstainless steel plug with two Viton 0-ring seals. The top end of the containmentvessel is sealed with a 11.625-inch thick stainless steel plug with two Viton0-ring seals. The bottom plug is retained by a closure plate secured by eight,l/2"-13UNC x 2-1/4-inch ASTM A320, Grade L7 socket head cap screws. The topplug is secured in place utilizing 16, l/2"-13UNC x 1-3/4-inch ASTM A320, GradeL7 hex flange screws.

3 0 9dYV¥L7K&MM7&2&2SU£J&J£UEJ3UgJSU£J£U3U£U&7&



5.(a)(2)(continued)

No drain or vents penetrate directly into the containment vessel. A drain/ventline opens directly into the area between the two 0-ring seals at each end ofthe cask (end plugs). During shipment, the lines are sealed with Viton 0-ringsealed threaded fasteners.

The cask is provided with six trunions, four spaced 90 degrees apart at the topend and two spaced at 180 degrees apart at the bottom end of the cask. The caskis tied down at the forward and aft ends by means of a cradle and yoke assembly.The gross weight of the cask and contents is 38,200 pounds.

(3) Drawings

The packaging is constructed in accordance with Energy Research and DevelopmentAdministration (ERDA) Drawing No. H-4-66230, Sheets 1, 3, 5, and 6, Revision No.0, and Sheets 2 and 4, Revision No. 1. For payToads in spent fuel containers,the applicable drawings are DOE Drawing Nos. H-3-47474, Sheets 1 and 2,Revision No. 0, and H-4-66535, Revision No. 0, and Los Alamos Drawing No. 54Y-110854, Sheets 1 and 2, Revision No. B.

5.(b) Contents ;

Type, form, and. maximum .quantity of:material peKpackage

Irradiated, (a) mixed oxide^MOX) fuel pins ahd^issemblies; (b) reactor fuelcomprised of U-235 arid/orj?u>239 oxides, ;capj)tdes, nitrides-, or metallic alloys;and (c) structural components^': The minimum"otifbii/ig*;t'ime of each assembly androd must be 90 days ,v.and,,thVcask may contain 1 ,,40p^thermal watts. Prior toirradiat ion, the fueTVandCistructuraT,componentsimust have the followingspecifications.:- ~'\\.~ .--"'Y' > ' ,'. •.-'l**':-:.^:,...;''

Type

217-Pin DFAassembly

217-Pin MOXfuel pins

FuelDescription*

31% PuO2 - 69%U0, (natural U)

50% max PuO6 +^UOj -remaindernatural U0,

ArrayDescription

Hexagonal arrayw/pins at 0.26"center-to-center

Circular arraygroups of pinsin seven compart-ments in 5"Schedule 5 Pipe

HaiximumFissilePackageLoading

11.2 kg

27.5 kg

PinDimensions

0.23" dia36" activefuel length

0.23"-0.29"dia. 36"active fuellength

g

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&3 1 0

raninininininsninirwanirwwNRCFORM618A(3-96)

CONDITIONS (continued} U.S. NUCLEAR REGULATORY COMMISSION

SS


Type

109-Pin MOXfuel pins

55-Pin MOXfuel pins

37-Pin MOXfuel pins

42-Pin MOX

40-Pin MOXfuel pins

19-Pin MOXfuel pins

PU compoundsfuel pins(spent fuelcontainers)

LAMPREfuel pins(spent fuelcontainer)

FuelDescription*

35% PuO, -65%U02 (86% U-235)

35% PuO2 -65%U02 (86% U-235)

35% PuO, -65%UO, (86% U-235)

35% f.uO, -65%U02 (86&U-235)

35% f u02lr.65%U02 (86% Ur235)

35% PuO2 -65%U02 (86% U-235)

50% PUX max-UXX=C,N, or 0(94% U-235)

97.5% Pu max-XalloyX=Fe, Co or Cs

ArrayDescription

MaximumFissilePackage PinLoading Dimensions

Circular array 26.2 kgindividual pinscontained in 0.44"dia. tubes

Circular array 13.2 kgindividual pinscontained in 0.625"dia. tubes

Circular array 8.9 kgindividual pfnscontained in 0.75"dia. tubes

Circular array; 10.1 kgindividual pinscontained: in 0.625"dia. tubes'

Circular array 9.6 kgindividual-pins,contained in 0.625"dia. tubes

/Circular array 4.6 kg^individual pins .,contained in 0.88"dia. tubesUnrestricted array 8.0 kgindividual pinscontained in SS5-inch Schedule40 pipe

Circular array 8.0 kgindividual pinscontained in 0.625"or 0.75" dia.steel tubes







Containercavity5.047" dia.by 38.9"length

0.425" dia.38" activefuel length

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atWajWatWara ;NRC FORM 618A(3-96)



Type

Structuralcomponents(incl. controlassemblies)

24 max.Pins. U-Pucarbide fuelpins

18 max.Pins. Sodiumbonded (fuel-to-clad)

FuelDescription*

Dosimetry foils

85-94%(Pu-U)C -6to 15% (Pu-U2)C,.Max 23% Pu,uranium is not,enriched , ~\ '*;

iq%/Zr-20% Pu-max. Remainder^U (U enriched

ArrayDescription

MaximumFissilePackageLoading

1.0 kg

PinDimensions

Circular array; 3.0 kgindividual pinscontained inrQ.6,25-in. dia.£ubesfwithi(n 5-in.$cheduTe!'{4.b,;pipe

Circular array;; 1.9individual pins (•""')-contained in 0.625<-in. diam. tubes^^ -----within 5-irt.^-:/^Schedule 4.0^npe

kg

0.37" outerdia. 36"active fuellength

0.30" outerdia. 36"active fuellength

*A11 plutonium in tMVJu6^^|^ll)"thfi..(a>?phtaJ-ns at least 10% Pu-240; fueltype (9) has no liriif'jfor c^^py^&T!l^^o!ntd:X^fX least 6% PU-240.

5.(c) Transport Index,for CHt,i;ca1-i*y'GbntrQJ'-^^^'.-/

Minimum transport jndex to bV sh ow rqrf ,- •'<"••,label for nuclear criticality corifr,6}j^ 100

6. Content 5.(b)(l) shown in AEC Drawing No. H-4-21566, Rev. 9, and ERDA DrawingNo. H-4-66230, Sheet 5, RevV 0. l^ A „. ..-

Contents 5.(b)(2), (3), (4), and (5) must be contained within inner containerIdent 69 described by ERDA Drawing Nos. H-4-66160, Sheet 1, Rev. 0, and H-4-66230, Sheets 5 and 6, Rev. 0.

Contents 5.(b)(6), (7), (8), (12) and (13) must be contained within innercontainer Ident 1578 described by ERDA Drawing Nos. H-4-66160, Sheet 2, Rev. 0,and H-4-66230, Sheets 5 and 6, Rev. 0.

Contents 5.(b)(9) and (10) shown in DOE Drawing No. H-3-47474, Sheets 1 and 2,Revision No. 0, and Los Alamos Drawing No. 54Y-110854, Sheets 1 and 2, RevisionNo. B must be contained within the Ident 69 Liner shown in ERDA Drawing No. H-4-66230, Sheets 5 and 6, Revision No. 0, and DOE Drawing No. H-4-66535, RevisionNo. 0.

3127^

Sr rgJTBKWBK at WWmWWWWWWWWWWWWWWWgtWWSto

NRC FORM 618A(3-96)



7. The cask must be shipped dry (no water coolant in cask cavity). Shipment ofsodium wetted fuel rods (external) is authorized for up to 200 g of sodiumprovided the additional requirements of Section 7.4 of the application areadhered to.


(a) Each package must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application, as supplemented. The leak test to satisfyANSI N 14.5 and Regulatory Guide 7.4 in Section 8.1.3 of the applicationmust be a test having sufficient sensitivity to detect a leak rate (air atstandard temperature and pressure leaking to 10"2 atm) of 10- atm cc/sec.The results of these tests must be documented and retained for the life ofthe cask.

(b) Each package shall.be operated and prepared for shipment in accordancewith the Operating Procedures of Chapter 7 of the application, assupplemented.

9. Any repair to the trunnions because of out-of-roundness or weld failure mustbe authorized by NRC prior to returning the package-to service.

10. The containment closure bolts (as specified by,;N.6ie 9, Drawing No. H-4-66230,Sheet 1, Revision No. 0);must be torqued to 7Q;|M0 ft-lb.

11. The cask authorized by this-certificate, is hereby approved for use under thegeneral license provisjons^of 4.0 CFR §71.12.. '.":'•

12. Effective Date: April 4>; 1996'.• Expiration Date:/Mpril 1, 2001.

v '•"'•" iPREFERENCES -.->;' - ,Nuclear Packaging, Inc., application dated: April 22, 1985.

Supplements dated: October 8 and 31, 1985; February 4, 1986; March 21, 1986;May 24, 1988; September 11, 1990;,March 22, 1991; and February 21, 1996.



and Safeguards

Date:

313

NRC FORM 618(MB)10CFR71




USA/9137/B(U)d.PAGE NUMBER


2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicable safety standards set forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Technical Operations, Inc. applicationdated November 9, 1979.

•;c. DOCKET NUMBER 7 1 - 9 1 3 ' 7

4. CONDITIONS ^ \_£ " ~\ ^ -'This certificate Is conditional upon fulfilling the-requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

~ 3 K

(a) Packaging M* v

<-r' t(1) Model No ": 820

(2) Description

HI'm< cz. *-?

A s tee^ncasûran^^hjeOdedû^^hanger . Primary componentsconsis*-bf an ou$e.r ^ t ^ e s ; s ;s;teeKf^l,>t'pMurethane pottingmateriaûran^^êTdJêîgl|t:iTj|tari'ium "xlptftUbes,/iqurce stop, and toplud ^^K^^MM&^M^TîF^-I^Mfe^securely positioned withinthe J tjubes bê^n^f^ô^c'e^Kle 'r lTbcking de>ice. The packagehas an outside dfamet g of yf9f f /^ inch^nd outside length of 21-1/2inches. The maximum total&wfi|^h^pof'th|1package is approximately 222pounds.

(3) Drawing YThe packaging is constructed iiri accordance with Technical OperationsInc. Drawing No. 82090, Sheets 1 through 4. '

314

^

^



(b) Contents


Iridium 192 sources which meet the requirements of special formradioactive material.


1,000 curies with no more than 240 curies in a single source.

6. In addition to the requirements ofrSubpariUG,,,pf 10 CFR Part 71:

(a) The package shall be pripafed*for shipmen1:Mn.d operated in accordancewith the OperatingjfPr;6c'eciures of Section 7.0"of4t'heNapplication, assupplemented; and^,^ ""' S~l-

(b) The package mtr^meet the Acceptance Test and Maintenance Program of Section8.0 of the application, as supplemented. s^/ ^,<?

7. The package authorized by^|3Sêertificate is rer by 4ipproved:-;fpr use under thegeneral license5pjrovisions^y^^,pNC.FR^0i:*:€2. / f%%£$ "l™,

8. Expiration datef5.(November ?30#1995. h>..

hum^ ^PAA^^J^MUHIPI^ hum -<:Technical Operations, Inc. apj^citîon^da't^d1 November 9,|^79. ~ VAmersham Corporation sfuppleme1^sfdated|Aûgu1s't=!2'2y^89.ây 4, and-October 19, 1990.

t/.yffF0R-3)H^.p;|S. NUCLEAR^REGULATORY COMMISSION

NOV 0 B 1990

<C;har,lfs E'. MacDonald, Chief/''franlsportation Branch

Division of Safeguardsand Transportation, NMSS

Date:

315




L CERTIFICATE NUMBER

9139

b. REVISION NUMBER

8


USA/9139/A

d. PAGE NUMBER

1


42. PREAMBLE





General Electric Company application datedMarch 24, 1980, as supplemented.

c. DOCKET NUMBER 71-91394.CONDITIONS ' - , . '•'

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as'applicable; and the conditions specified below.

5.

(a) Packaging ^

(1) Model No.: .589

(2) Description/ N/2

A steel encased lea^b-ielded cask for;ra|}S?ittive material. The cask is aright circular cylin^xfwith 79îrich 0D; by2|0rinch height, and a cavity 74-inch ID by.J4-inehfiheliJtht;>^;The"lT5^nchJ$j|fck lead shield is supported byouter and.innerVâ^boh^fiei'-shells7G;^5-pc\.andÔ.375.-1 nch thick,respectively, tjfi jjip toiii rvise inch rfch^ck "1 eîd^shteldciiS supported byby outerand inner ea,rbon^||efi^pl atjes; 1 .Of-.ir ch and 0;p75înch Ithick, respectively.The 1.5-inch\,thick~ji^ o^ter and inner carbonsteel platescl-incnlâhd;^5"-ir|s:h .|'h>TckvL-'resp,!Bctiveli:.f:. Thecarbon steel,used is SA516, iGây^pv,, jHe lid is attached to the cask witheight (26,000Mix proof load %c.n|•'ftaCchet -type l.oad,binders and sealed with aBuna N 0-ring. ' Jhe cask is equipped with a 3/4î.nch drain line, sixteen-holdbolt-down flange'(l-înch bolts) and two 2-1/2-ihch diameter lifting lugs.The cask lid seal and lifting lugs are protected by a wooden sacrificialimpact limiter (about 8 ;x 10 inches thick). Gross weight of package andimpact limiter is 50,000 Ibsi

(3) Drawing

The packaging is constructed in accordance with PX Engineering Company, Inc.,Drawing No. 589-L, Sheets 1 through 3, Revision No. 0.

316

NRCFORM618A(3-96)



5. (b) Contents


Dewatered or solidified waste material in sealed secondary containers, orsolid irradiated hardware, and limited to the following:


0.0001 mi Hicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part)71 is not more than 0.05 curie;

0.005 milUcurieof radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more'than 0.05 curie, but not morethan 1 curie; or

0.3 milltcurie of radionuclides for which the A? quantity inAppendix A of .10 CFR Part 71 is more;;than 1 curie.

(ii) Objects ofnonTadi.oacW^-materiaiêXternally contaminated withradioactive:"mater,ial, provided tâtfrthe radioactive material is notreadily dispfe.riible and the sUrfaiêontami nation, when averagedover an areaîf/j/square'-meter,,. oj0> not exceed 0.0001 millicurie;(220,00O.!disihTijBgrations. periminyte) per square centimeter ofradionucrlides, for/Vwhich?;theÂ^fquantify*fin Appendix A of10 CFR Parti^'is'^btj'ni'or.e than 0.05/:ciitie, or; p. 001 mi H i curie(Z,ZOO,OO^\di^nt0^ti6hs''p'f^/^ûie)'/sii&r square centimeter forother radipriucl'^"^ '"''"~'y :'

(2) Maximum quantity of matenîljper^fpackage c:

Greater than type A quantity of radioactive^material with the weight ofthe contents, secondary containers and-.shofing not exceeding 20,150pounds. l-\"" '<'"'-- ,- -'•,, <• '• v "',--'••

3 1 7

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(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammable

H gases) of the secondary container gas void if present at STP (i.e., nomore than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

«(2) The secondary container and cask cavity must be inerted with a diluent

to assure that oxygen must be limited to 5% by volume in those portionsof the package which could have hydrogen greater than 5%.

For any package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination forgas generation is made. Shipment period begins when the package is prepared(sealed) and must be completed within.twice the expected shipment time.

(b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drums or other secondary containers, the determination in(a) above need not be;made, and the time restriction in (a) above does notapply. ... : ./.-

7. Shoring must be placed between secondary coritainers (or activated components) andthe cask cavity to prevent movement during jrormal conditions of transport.

8. The lid lifting lugs must not be used for, lifting the cask and must be covered intransit.

9. In addition to the requirements of. Subpar.t G of 10 CFR Part 71:

(a) Each package shall be operated and prepared for shipment in accordance withthe Operating Procedures in Tennessee Valley Authority supplement datedNovember 19, 1991; and

(b) The packaging acceptance tests and maintenance program must be in accordancewith Section 7.0 of the General Electric application, dated March 24, 1980,as supplemented, except:

(1) The lid 0-ring seal must be replaced if inspection prior to each shipmentshows any defects or every twelve (12) months, whichever occurs first.

(2) During inactive periods, the maintenance and testing frequency may bedisregarded provided that the packaging is brought into full complianceprior to the next use of the package.

10. The package authorized by this certificate must be transported on a motor vehicle,railroad car, aircraft, inland water craft, or hold or deck of a seagoing vessel

318

NRCFORM618A(3-96)





REFERENCES

General Electric Application dated March 24, 1980.

General Electric supplements dated: May 29, and July 11, 1980.

Tennessee Valley Authority supplements dated: May 16, 1990; and November 19, 1991.


Date: 4 I


. ' and Safeguards"

3 1 9

fc

NRC FORM 618(8-85)10 CFR 71







2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item S below, meets theapplicablesafetystandardsset forth InTitielO, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEXIESIGN OR APPLICATIONa. ISSUED TO (Name and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Amersha Corporation40 North AvenueBurlington, MA 01803

Technical Operations, Inc. applicationdated August 1, 1980,

c. DOCKET NUMBER 1^9143

4. CONDITIONS \ % ^ ^y *.This certificate is conditional upon fulfillingUhe requirements of 10 CFR Part 71, as applicable, and the/conditions specified below.

(a) Packaging

(1) Me

(2) Description

A sfainless steejshipping

(3)

\

radiogcaphic device. Theinche^ghigh and 5.3 inchesifisedd&side a tungsten'by depleted uranium metalassefnKIy is encased in a

etween^Bhe uranium shieldth a castable rigid

the cfn-fainer is 47.0 pounds.

The packaging is^p'onstructed in accordance with the following TechnicalOperations, Inc.^braWng^f(qs.^92O90^Sheets 1, 2, and 3 of 3, Rev. 0;90090, Sheets 3, andT* ofH, Rev. 0; and 90091, Sheet 1 of 1, Rev. A.

soufrcef o r Y 5staTfffessassemb-Ty Jr

polyur-fifkane foam.A

3 2 0

v*gihHP

ft&^

6.

618A

21 - Certification No. 9143 -.• j , U.S. NUCLEAR REGULATORY COMMISSION

r T ^ Docket No. 71-9143

5. (b) Contents


Iridium 192 as sealed sources which meet the requirements of specialform radioactive material.


240 curies (output)

Output curies are determined in accordance with American NationalStandard N432-1980, "RadiQ-^gâl safety for the Design and Constructionof Apparatus for Ga™mp£adjrQdj5p .|> »

The source shall be seamed in the shielded posvfcfon pf the packaging by thesource assembly. The^source assembly must be fabricated of materials capable ofresisting a 1475°£^feire environment for one-half hour|m)d maintaining theirpositioning func&pn. The source assembly must engage t;hj| locking device. Thesource assembly^jnustebaof sufficient length anddâjjj^ter'fo provide positivepositioning ofHS'e stfu&^wj'tnin t n e depletedii^^tn shiera assembly.

isisting the fireThe name platfe^hall betest of 10 CFH-Part 71

In addition to^the r<(I

a. The pacl&?ewith thesupplemen

\3t^ Wb. The package'lmyst meet

Section 8.0^f/the applicatT

jerateifin accordanceajgJTication, as

ire§Wand Mapplemented /=

irrtftnance Program of

9. The package authorizecl^ this certificate is here^âpproved for use under thegeneral license provisions .fl 10 pFR §71.12. K "

10. Expiration Date: January 31, 2001.

REFERENCES

Technical Operations, Inc. application dated August 1, 1980.

Amersham Corporation supplement dated November 12, 1990, and November 6, 1995.

FOR THE U.S . NUCLEAR REGULATORY COMMISSION

Date:


and Safeguards

321

^





9145

b. REVISION NUMBER

11


USA/9145/A

d. PAGE NUMBER

1


32. PREAMBLE



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OFTHE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


NUPAC Services Division, Inc. applicationdated February 21, 1991.


4. CONDITIONS s -•-„. . " ) '•'• ,;- s

This certificate is conditional upon fulfilling the requirements'qf 1QCFR Part 71, asapplicaBIejand the conditions specified below.

(a) Packaging • </;\>? ''''.^

(1) Model Nos.: NUPACJ0-1.5L, NUPAC 50-2.5L, NUPAC 5Q-3*t)L, and NUPAC 50-4.OL.

(2) Description^;,?' ^ M # v \ v - , <

A steel en'caêd lead |li|.e|:de|i ca^pôr fâdJBaJtive materjal. The casks areright circular cylindg^)@;th' a 4j8..5-|nch\i^î'e diameter.by 52.5-inch insidehigh cavity^ The ;wall^=Q%\the«ca^sônta|;n^r lead thickness ranging from1.25 to 3:7,5, inch^^n^î i i .3/8-1_nc^t^ |?>stefe> sheg^. The bottom and1.25 to 3:7,5, inch^^nd^^>li iv3/8-1_nc^t^c stefe,> shejfljs.. The bottom andtop covers;.of the^cask aê&ayejup!!ofn^wo^^teej^y,-ates^ran9in9 1° thicknessfrom 1.00 tpj.od^j^jl^"'•TKjeiipriimary^clsk l i P ^ i seci|r7e;d to the cylindricalcask body by^gh1^rv^h^^tK6^ ;

:Jb^tfe^. Â- efcondairyCcask lid is centeredin the primaryîdXn/Pit'^ l i d ^ i t h eight, 3/4-inchstuds and nut|.> Each:'"liclVis j>rîj^|4^Hh',:arNeoprert6;-gasket seal. The caskis provided wHh?,four equallyis^||oîiift'ihcj/tie dpw'n^devices. Cask gross

in the primary^!id"anydstuds and nut|.•> Eachis provided with^four equally Î.^._,weights range fronrl3,200 to 28>900^pounds.

(3) Drawing

The Model No. NUPAC 50 Series packagings are fabricated in accordance withNuclear Packaging, Inc. Drawing No. X-20-201D, Sheets 1 and 2, Revision C.

322

NRC FORM 618A(3-96)



(b) Contents


Dewatered, solid or solidified waste, in secondary containers, oractivated solid components, and limited to the following:


0.0001 mi H i curie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie;

0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 0.05 curie, but not morethan 1 curie; or

0.3 miilicurie of radionuclides for which'the A2 quantity inAppendix A of 10 CFR Part 71 is more than 1 curie.

(ii) Objects df-nqnradioactive material^exiternaTly contaminated withradioactive material, provided tha^the radioactive material is notreadily dispirsibl.e and. the surface^contamination, when averagedover an area|pf/.l square meter, !doj§: not exceed 0.0001 millicurie(220,000 dfstiTnfegratibns per minute)'per square centimeter ofradionuclsides^ffor/^/hich the ,A2 qiiantity in Appendix A of10, CFR' Part it 'is not more tItan^p .-05 /cur/i e, or 0.001 mi 11 i curi e(2,200,pOO/,disintegrations:p4KminuMj;per square centimeter forother radjonucl ides'. ;' '., : !:',;.. ?-':-/"'

(2) Maximum

Greater tharfType A quantity;' 6i radioactive material.

(a) For any package containing water and/or organic substances which couldradiolytically generate,.combustible gases,^determination must be made bytests and measurements or by analysis of a representative package such thatthe following criteria are met over a period of time that is twice theexpected shipment time:

(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP (i.e., nomore than 0.063 g-moles/ft3 at 14.7 psia and 70'F); or

(2) The secondary container and cask cavity must be inerted with a diluentto assure that oxygen must be limited to 5% by volume in those portionsof the package which could have a hydrogen concentration greater than 5%.

For any package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination forgas generation is made. Shipment period begins when the package is prepared(sealed) and must be completed within twice the expectedshipment time.

323^

nNRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


6. (b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drums or other secondary containers, the determination in(a) above need not be made, and the time restriction in (a) above does notapply.

m 7. Shoring must be placed between secondary containers (or activated components) andg the cask cavity to prevent movement during normal conditions of transport.s 8. In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) Prior to each shipment, the packaging lid seals must be inspected. The sealsmust be replaced with new seals if inspection shows any defects or every 12months, whichever occurs first.

(b) Each package must meet thevAcceptance Tests and Maintenance Program ofSection 8.0 of the application". "C ^ ^ U U I U I I u « v ui biic a(;pu>v;

(c) The package shall be prepared for shipment and operated in accordance withthe operating procedures in Section 7.0 of the application.

9. The package author izedfbyjh is certificate must be transported on a vehicle,railroad car, aircraft, piand water craft, or hollar deck of a seagoing vesselassigned for sole.use of tiiei-Ticensee. /,<•

10. Lid lifting devices must be|;dpvered prior to,,transport to prevent their use astie-down

11. The cask body and eacftiic&k"tfd^ accordance with 10 CFR §71.85(c).

12. The package authorizedSfpr}u|e byi^thisi-isertificate^ is-hereby"approved for use underthe general license pro>l ;6ri<s:;-&'f''-ip>CXft= lVl; f-''v-''

13. Expiration date: April 1, 1999;. • |Jn'iS|!y;ey.Wficate is npt'-Venewable.

Y , REFERENCES V

NUPAC Services Division, Inc. applicatioh\dated'-February 21, 1991.

Supplement dated: February 16, 1996.


William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand Safeguards

Date:

324

NRC FORM 618(845)

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.a.CERTIFICA- b. REVISION NUMBER




2Z PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafety standardsset forth inTitle 10, Codeof Federal Regulation's, Part 71, "Packaging and Transportation of Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DESIGN OR APPLICATIONa. ISSUED TO INmta and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


* \t

Technical Operations, Inc., application datedOctober 30, 1980, as supplemented.

> *"c. DOCKET NUMBER " 4 s i 71^91 '4 7

•*.'.. -•-.CONDITIONS ^ v \ ^ ; -\;'-^JThis certificate Is conditional upon fulfilling the_requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

w b

(a) Packaging

(b)

(1) ModeyNot 850

(2) Description

A statnless

(3)

•• — ~ — • """ "^" \ j i fy• TiT"^"*?^1*' «• aniuin^^>ii;ict(ued source changer. The

S l S ^ ^ 1 ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ ^ 9 " and 9 - ° incneswide. The mdjoaGtivegsou^ce assente ies fa,ppoused-inside titanium

f S l ^ d f S ^ 8 K 5 U W ^ ^ S U l T ^ by ^p l e t e d anium metaltiliS^i94^^^^tosffiMWSW assembly is encased in astainless-'steeT^ous^ng.^Mt^d^pae^betweenahe uranium shieldassembly^ stainless s « f % | | n g - f f i l l e d feith a castable rigidpolyurethane|foam. The g ig^g fgh t t ^ the container is 105.0 pounds.

Drawings' ^/ %%""'

package is constructed 4ri7accQrdance with Technical Operations,., Drawing No. 85090,^Sheet li&v. 0 (contained in supplement dauary 22 1987) sheets 2 through 5 R 0 D i N 90091

TheInc., Drawing No. 85090,^Sheet li&v. 0 (contained in supplement datedJanuary 22, 1987), sheets 2 through 5, Rev. 0; Drawing No. 90091, Rev.A; Drawing No. 85000, Rev. D; Drawing Nos. 85000-5, 85000-6, 85000-7Rev. -; and Drawing No. 91091, Rev. A.

Contents


Iridium-192 as sealed sources which meet the requirements of specialform radioactive material.


240 Curies.

325

^

\

ij

NRC FORP.1 S18A(6-83)



The sources must be secured in the shielded position of the packaging by thesource assemblies. The source assemblies must be fabricated of materialscapable of resisting a 1475°F fire environment for one-half hour andmaintaining their positioning function. The source assemblies must engage thelocking device. The source assemblies must be of sufficient length anddiameter to provide positive positioning of the sources within the depleteduranium shield assembly. Shielded shipping plugs shall be installed on sourcetubes during transport.

The name plate must be fabricated of materials capable of resisting the firetest of 10 CFR Part 71 and main^inlrldahtgr*legibility.

8. CFR Part 71:In addition to the reqfrpefnents of Subpart G of

(a) Each packageyjiust meet the Acceptance Tests afi&Waintenance Program ofSection 8 ^ n the application, as supplemented.^.

(b) Each pa<9(|gewith thXjb

.A

as supplemented.

The packagireauthorizethe general njicense/pro

Expiration djljle: N

9.

10.

Technical Operations,Mn

e operated andcedures of

shipment in accordancethe application,

iereby approved for use under

Amersham Corporation suppll%nents dated: January 22, 198^March 30, an1988; March 10, 1989; Octobef 19, a,nd November 16, 1-990; and August 15,

and November 3,1995.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION/

A'

SEP 1 3 1995

Cass R. Chappell, Section LeaderPackage Certification SectionSpent Fuel Project OfficeOffice of Nuclear Material Safety

And Safeguards

Date:

3 2 6

a ^ ^ ^

^NRC FORM 618(M5)

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.a.CERTIFICATE NUMBER b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER

USA/9148/B(U)d. PAGE NUMBER1MB 0. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate Is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10. Code



a. ISSUED TO (Name and Address!



Technical Operations, Inc. application datedMarch 24, 1981, as supplemented.

..--V-; " : '-• -.71^9148"c. DOCKET NUMBER ' <;,///

4. CONDITIONS ... ^ _ J <Ay;This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the'conditions specified below.

(a) Packaging ,«v>.

(1) Model No.: ^770

(2) Description-

A steel encased ufanium;^|.ie1:dedôurGe^c||iiri^5r for radiqgraphicsources i n - s p e c i l a i t ^ o r m ^ ^ 22f§inches long, 24inches wfde^ and-j2§tvt,ncHi^§s^ji]ghJi]/I'lThfe|^îi?ac^ê/ôurce^-"asseinbly is housed inZircal loy or%titan-'ti(m'ylS" •feiiDelJ;?;TH ;j S " tube/ffi^surrouficled by depleteduranium metal,,^shieî^Jêf^pêt^dlu||jîum^sfe%'ld asselfibly is encased in twosteel containers. ^^t^~Q^^f^^^^kiK^0A^^\€^^r^^\\x^ shield assemblyand the inner/container |^ f|j^¥ie^|^th cL-r^gid polyurethane foam. The grossweight of the\con,tainer is 8#'jppuhcis> '<%' ^'/

(3) Drawing ^7/ %^"^ '

The packaging is constructed>in.-accQi?clance-iwith Technical Operations, Inc.Drawing No. 77090 - Sheet l^throughlRev. 3.

(b) Contents


Cobalt 60 as sealed sources that meet requirements of special formradioactive material.


550 curies

327

' "-' " CONDITIONS (continued)


5. The source must be secured in the shielded position of the packaging by theshipping plug, source assembly, and locking device. The shipping plug,- sourceassembly used must be fabricated of materials capable of resisting a 1475°F fireenvironment for one-half hour and maintaining their positioning function. Theball stop of the source assembly must engage the locking device. The flexiblecable of the source assembly and shipping plug must be of sufficient length anddiameter to provide positive positioning of the source in the shielded position.

7. Name plates must be fabricated of materials capable of resisting the fire test of10 CFR Part 71 and maintaining their legibility.

8. The lifting eye bolts (2) must be removed prior to shipment and the holes coveredto prevent their use as a tie-down device during transport.

In addition to the requirements M S(fBpa2i((6\df? 10 CFR Part 71:"••Ax? V- *"•* * ™* **K.~*J //

(a) The package shallfbl>prepared for shipment a¥d|bperated in accordance with theoperating procedures in the application; and //%

(b) The package -sfVa-ll be maintained in accordance with <tfi"e maintenance program inin the application- ^ ^J

10. The packaging I j j ihorize^i^hds certificate/islfeMby approved for use under thegeneral 1 icen | fe j rovis ion |^o\CFR c §®|2 f J p | § ^ "general licensejirovisionl^

11. Expiration datf'f March

Technical

Supplements dated: January 'iMv^k April 16, 1992.


JUN 2 3 1992


and Transportation, NMSS

Date:

328

NRC FORM 618(3-96)10 CFR 71






USA/9150/B(U)-85d. PAGE NUMBER


3

2. PREAMBLE





PAT-2 (Plutonium Air-Transportable Model 2)Safety Analysis Report, SAND81-0001, printedJuly 1981, as supplemented.

c. DOCKET NUMBER

4. CONDITIONS


5.

(a) Packaging

(1) Model No.: :PAT-2

(2) Description

A superalloy primary containment vessel'- (TB-2) surrounded by a protectiveoverpack (AQ-2).:~^Tfie contents which;may be in canisters are containedwithin a capsuleV(:C-t)i within the TBrfe

The AQ-2 overpacjt isa;,right; circular cylinder, approximately 356 mm (14inches) high ,and;381 mm (15 inches) in diameter with protruding handlesattached to the cylinder outer walls,. .The outer shell is a doublewalled stainless steel structure with 'rounded end caps, riveted on thebottom and bolted at the\vtopV(,,An inner grain oriented maple woodprotective,.case houses tt>.e>/jBr2';'' it is surrounded by a titanium loadspreader which is further surrounded by a grain oriented redwoodprotective case.

The TB-2 containment vessel consists of (2) iron-base superalloysections, bolted together with (20) bolts, forming an 88 mm (3.46 inch)diameter sphere. A copper gasket held between knife-edge sealing beadson the matting hemispherical surfaces of the TB-2 provides a seal.

The C-l capsule is a stainless steel cylinder with a nominal 44 mm (1.80inch) diameter and a nominal 70 mm (2.76 inch) length; it has a screw toplid which is sealed with teflon tape.

Brass or aluminum canisters may be used in the C-l capsule to holdvarious radioactive contents. The canisters may have quartz or glassliners.

The package gross weight is approximately 73 pounds (33 kg).

3 2 9?¥£ 7K 7K 7K. VK BK 7K BK 7K BK BK BK BK BK BK BK BK BK BK BK 7K JtC,

!j of hydration.

ii

NRCFORM618A • CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


(3) Drawing and Specifications

The packaging is constructed in accordance with specifications anddrawings, as listed by document number, issue, and title in the List ofData LD-T67000-000, page 1, issue D and page 2, issue D (Chapter 9 ofSafety Analysis Report, SAND81-0001, printed July 1981).

(b) Contents


Plutonium, uranium, or mixtures of plutonium-uranium in various isotopiccompositions in solid form as: ( : ..

- - - ^ '•'•"• : = ' - ' ! - ' " -:-:• ^ >:• ,

(i) oxide powder,"sintered oxide pellets, .and metal;

(ii) plutonium sulfate tetrahydrate, Pu(S0;)^4H20 and plutonium nitratedihydrate, Pu(N0,)4 2H20. '.';..

(2) Maximum quantity of material per package^-;- ; V;

z (i) For the contents^descpibed in 5(b);(*)'(i): . .

Not to exceed^ ;1:5 grams fissile material, 120 fjg'iams mass, 2 wattsdecay heat,^6iru0.5. gram''water..'/$.'££;

(ii), For the^eontent^/descnb"ed;

Not to exceed.3 grams or ;0.5<.grams/water in addition to the waterof hydrationT," '' --/..a : f.-\~•'<'•./ '•"'-,/

6. Up to 9 grams of polyyinylchloride (P,y^;18 grams of quartz (S.iO2) or glass, 50grams of brass, and 16 grams of aluminum may be used Within the C-l capsule forpackaging of contents. Up to 0.3 gram of polytetra-fluoroethylene (PTFE) tape maybe used to seal the C-L.capsule.

7. The C-l capsule need not be leak tested, when the activity of plutonium contentsdoes not exceed 20 ci per package.

8. A maximum of 2.0 grams of aluminum foil may be used to shim the C-l within theTB-2 to avoid relative movement between the two.

9. Prior to first use, each package must meet the criteria for the acceptance testsspecified in section 8.1 of Chapter 8 of the Safety Analysis Report (SAND81-0001,printed July 1981).

10. Prior to each shipment, the package must meet the criteria for inspections andtests specified in section 8.2 of Chapter 8 of the Safety Analysis Report(SAND81-0001, printed July 1981).

330

WWWWWWWW.^ JfrQ WWW WWW 3*1 ^NRC FORM 618A(3-96)



11. Periodic testing and maintenance of the package must be in accordance with section8.3 of Chapter 8 of the Safety Analysis Report (SAND81-0001, printed July 1981).

12. Operating procedures must be in accordance with Chapter 7 of the Safety AnalysisReport (SAND81-0001, printed July 1981).

13. Through special arrangement with the carrier, the shipper shall ensure observanceof the following operational controls for each shipment of plutonium by air:

(a) The package(s) must be stowed aboard aircraft on the main deck in theaft-most location that is possible for cargo of its size and weight. Noother type of cargo may be stowed aft of the package(s).

(b) As an alternative to (a) 5 packages must be, stowed in the aft-most lowercargo compartment. No other type of cargo may be stowed aft of thepackages(s). .

(c) Package(s) must be secured and restrained to prevent shifting under normaltransport.

(d) Cargo which bears the;"EXPLOSIVE A" label may not be transported aboard anaircraft carrying a PAT-2 package(s). . V;

14. The package authorized for .use by this certificate-is hereby approved for use underthe general license provisions1 of 10 CFR §71.12.

: • • . ! ; • ! - ' * - = , . % , . : • ' • ' '

15. The package authorized by; this /certificate is Hereby approved for transportation ofplutonium by air. ; >, ". : : • ?/

16. Expiration datef July 31;,. 2001;'

REFERENCES

PAT-2 (Plutonium Air-Transportable Model 2) Safety Analysis Report, SANDIA Report No.SAND81-0001, July 1981.

DOE application dated April 19, 1983. Supplements dated August 3, 1983, July 15, 1986,July 16, 1991 and May 29, 1996.


Date: "7^/^


and Safeguards

331

»zflK:)iS^








4i. PREAMBLE




Scientific Ecology Group,1560 Bear Creek RoadOak Ridge, TN 37831

Inc.


Scientific Ecology Group, Inc. applicationdated September 21, 1992.

c. DOCKET NUMBER 71-91514. CONDITIONS

This certificate is conditional upon fulfilling the requirements" of 10 CFR Part 71, as applicable; and the conditions specified below.

(a) Packaging

(1) Model Nos.: # 4 0 0 Series 3 and LN 14-170 Series

(2) Description; ?,•>

Steel encased", lead sh^f|Hd*ca§k"l>fbr rjad.&ai||ive material. The casks areright circular cylinder^8l4/2 inches h;ighf|yt81-3/4 inches in diameter. Thecask cavities are 7,3r3^^^ches-'¥t^h*%yx7j5jfl^'inqhes in>djameter. The caskside walls "consist^! ^3;/^%np.bJ;M^^#i?l^ t^yshell :^'a 1-7/8-inch leadshell, andva;i7/8-% Ll

2-inch thickrsteel>integrally weldedsteel flange,ii WE „. , ...the top. The l-id is compiiisedô^two^ 2-incri thick (Steel plates, which arestepped and weldeU together tbr4m|tl™€hHhe/steel; âhge. The cask closureis sealed by a fteoprene gasket foUated between thfpid and steel flange,positive closure of the lid is accomplished byêtghi:, 1-3/4-inch ratchetbinders. The lid contains a centrally located shield plug comprised of two,2-inch thick steel plates and one, 1-ih.ch^hick steel plate stepped andwelded. The shield plug is sealed;>by a^Nebprene gasket, and eight, 3/4-inchstuds and nuts are used to provide positive closure. The packagings areconstructed of A-516, Grade 70 or A-537, Class 1, carbon steel. The outershell will have a minimum yield strength of 46,000 psi. Tie-down isaccomplished by four tie-down lugs welded to the cask body. There are fourcask lifting lugs, three lid lifting lugs, and one shield plug lifting lug.The package gross weight is approximately 53,000 pounds.

1$ey;tQget{ierto formâ 4inch thick baspt ami .oute^ste^>fiells of:the side wall. AeînftjeKianaût^ls^ sJietls of the side wall at

332

J^'^TSJ£J£JS^



5. (a) (3) Drawings

The Model No. HN-100 Series 3 packaging is fabricated in accordance withHittman Nuclear & Development Corp. Drawing Nos.: C001-5-9138, Rev. 13;C001-5-9139, Rev. 8; C001-5-9140, Rev. 9; C001-5-9141, Rev. 3;C001-5-9142, Rev. 1; C001-5-9143, Rev. 8; and C001-5-9144, Rev. 3.Optional stainless steel shielding insert in accordance with DrawingNos.: STD-02-035, Rev. A; STD-02-036, Rev. A; and STD-02-037, Rev. 2.

The Model No. LN 14-170 Series I packaging is fabricated in accordancewith LN Technologies Corporation Drawing Nos.: 8916 M 2001, Rev. 1;8916 M 2002, Rev. 0; 8916 M 2003, Rev. 0; 8916 M 2004, Rev. 0; -8916 M 2005, Rev. 0; and 8916 M 2006, Rev. 0.

•7

(b) Contents



(i) Materials rin, which the radioactivity; is essentially uniformlydistributed ;and in whicfi the estimacted average concentration pergram of contents -f does" not exceed:->;,'

,0.0001 millicurie ofradionuclidjesffor which the. A2 quantity inAppendixjA/ofVTlO'CFR Part. 71* :is\vnq.f more, than 0.05 curie;

0.005 milji'curie of radioriufelides fpr which the A2 quantity inAppendixiA of'40^C;FR Part-;71^iss more,*than 0.05,curie, but not morethan.,1 L ; v ' > : ' ^ f

Appendix/A of 10 CFR0.3 m)111icurie of rad4p!nuc1.ides for which the A2 quantity in

FR:Part:j71 is more than)! curie.

(ii) Objects of nonradioactiye material externally contaminated withradioactive material, provided that the radioactive material is notreadily dispersible and the surface contamination, when averagedover an area of 1 square meter, does not exceed 0.0001 millicurie(220,000 disintegrations per minute) per square centimeter ofradionuclides for which the A2 quantity in Appendix A of10 CFR Part 71 is not more than 0.05 curie, or 0.001 millicurie(2,200,000 disintegrations per minute) per square centimeter forother radionuclides.


Greater than Type A quantity of radioactive material which may containfissile material provided the fissile material does not exceed the limitsin 10 CFR §71.53. The weight of the contents, optional shield insert,and secondary containers shall not exceed 17,800 pounds. When the shieldinsert is not installed in the cask, the internal decay heat load shallnot exceed 7 watts. When the shield insert is installed in the cask, the

? internal decay heat load shall not exceed 28 watts.

L 3 3 3

^ 7& W- 7SU5UBJ3UEJSJ3U&J

be based on lead equivalence for lead and steel with allreadings within 2.3 inches ± 10% on a 4-inch grid.

«



fi 6. (a) For any package containing water and/or organic substances which could

radiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package such thatthe following criteria are met over a period of time that is twice theexpected shipment time:

(1) The hydrogen generated must be limited to a molar quantity that wouldbe no more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP(i.e., no more than 0.063 g-moles/ft at 14.7 psia and 70'F);or


For any package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination forgas generation is made. Shipment period begins when the packageis prepared (sealed) and must be completed within twice the expected shipmenttime.

(b) For any package shipped. Within 10 days of,preparation; or within 10 daysafter venting of drunis^.or,other secondary'containers, the;; determination in(a) above need not bejmade, and the time restriction in (a) above does notapply. " :i ~; ' , \~'"l2-ii

7. In addition to the requfHemeritsôf Subpart G ^ t | W CFR Part 71:

(a) Prior to each shiprêî,\tneâckagin'gjjTAdv'seal^;if opened (or if

jp security seal is broken).*',must be inspected.,/The seaTs\must be replaced with£ new seals if inspection shows 'an^:êfecVsCor,^Very 12: months, whichever occurs£ f i r s t . * ' i\ ,;..••'/!..'•*••v ..••:"-•' '': ,'

(b) Each package must meet the Acceptance Tests and Maintenance Program of:

Model No. HN-100 Series 3 N-,

£ Section 7.0 of the application. .Gamma scan for the shielding acceptance may

Model No. LN 14-170 Series I

LN Technologies Corporation Procedures WM-011, Rev. H; WM-012, Rev. H; WM-013,Rev. F.

P

* 334

(3-96)

7.



(c) The package shall be prepared for shipment and operated inaccordance with the Operating Procedures of:

Model No. HN-1OO Series 3

Section 6.0 of the application.

Model No. LN 14-170 Series I

LN Technologies Corporation Procedure WM-014, Rev. L.

8. Torque requirements for closure fasteners:

(a) Primary lid ratchet binders must be torqued to 175-200 ft-lbs.

(b) Secondary lid bolts must be torqued to 120 ± 10 ft-lbs.

9. Seals which show any visual defects (cracking, gouging, tearing, etc.) must berepaired in accordance with:

Model Nos. HN-100 Series 3

Note No. 3 on Hittman Drawing No. C001-5-9138, Rev. 13; or, replaced with a newseal.

Model No. LN 14-170 Series?!;. V '•.;".

LN Technologies Corporation "ProcedurevWM-012> Revi H, Section 7.1 (joint angle mustbe approximately 45'); or4: replaced with anew seal.

10. The package authorized by this certificate must be transported on a motor vehicle,railroad car, aircraft, inland[;watercr,aft, oHhold or deck of a seagoing vesselassigned for the sole use of the ljcens.ee.



REFERENCES

Scientific Ecology Group, Inc. application dated September 21, 1992.



Date: AP r i l 4' 1996 3 3 5

NRC FORM 618(3-96)10 CFR 71


9152



b. REVISION NUMBER

12




4— — — __, .—_2. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forttun Title 10,Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."


5

a. ISSUED TO (Atone and Address)



U.S. Department of Energy applicationdated February 26, 1988, as supplemented.

. DOCKETNUMBER 7 1 — 9 1 5 2

4. CONDITIONS


3

(a) Packaging

(1) Model Nb.r^CNS 1-13C II

(2) Descri pt i on \~ ^ ;(

A shipping c a t i o n radioactive :waSfci?J|? The packaging consists of a

leadsurrbunds-the cehfrVal,cavity.' l.o?sVre; ;sfa'ccompl.ished by a steel,plug type3jVa^\fiiT6d!coyer'-secured B ^ e l v e (12), 1-1/4" bolts andseal provided b^-a,fMp sHticofejrubber/igasket<aVd a silicone rubber0-ri ng wi th 'a> seapd- 3/8^ ; t^st^brt between th%. gaskets.Approximately^" *df; lead^alre^in the base and'cpver. The cask isequipped w.ith a cavityrdnaitefne sealed withH 3/8" cap screw andgasket, a steel lifting''habit for the" cover,;;and top and bottom impactlimiters filled with 16.5 lb/ft3 rigid ppl.yurethane foam clad insteel. The impact limiters are attached to the cask by six (6), 1"ratchet binders. .The overall djmens-ions with impact limiters is 60"in diameter and 99-5/8" high.: The package gross weight isapproximately 27,000 lbs.

(3) Drawing

The packaging is constructed in accordance with Chem-Nuclear Systems,Inc., Drawing No. E-l-436-111, Sheets 1 and 2, Rev. D.

336

^JSJSUSJ&Mk^MLM^^7K\7^7fRJSJ&MJ&SU&2SJK.

NRC FORM 618A(3-96)



(b)

a

Contents


(i) Greater than Type A quantity of nonfissile radioactive materialas solidified or dewatered process solids (resins) within asealed secondary container; or

(ii) Greater than Type A quantity of irradiated solid reactorcomponents within a sealed secondary container.

(iii) Greater than Type A quantity of irradiated fuel (dewatered)within secondary containers described in Chem-Nuclear Systems,Inc. application dated July 16, 1985.


For the contents described in 5(b)(1)(i), (ii), and (iii):

Not to exceed-a decay heat generation, of 800 watts and 3,000 poundsincluding weightôf; the contents and secondary container; and

For the contents-described; in,5(b)(1){%):

(2)

Residual water tivihe secondary conta-\ner not to exceed the activitystated i n> Table "4£5,;'2 i- of -the applfcation.-

For the cont^nfe/described in 5(b)(l)(,iii):• - ; - • . %

The maximum U^235t;enric]iment of the uranium oxide fuel material mustnot exceed 3 w/o. The/fav^geburnup of the fuel material must notexceed % 165 HWD/MTU anWMîiê cooled for at least 6.0 years.Fissile contents not to exceed 400 grams.U-235 prior to irradiation.



For contents described in 5(b)(l)(iii): 100

6. As needed, appropriate shoring must be used in the cask cavity to limit movementof the secondary container during accident condition of transport.

7. The cask cover must be secured by 12, SA-354, Type BD, l-l/4"-7UNC x 2-1/4" longbolts torqued to 270 ft-lbs ± 10% (lubricated) or 360 ft-lbs ± 10% (dry).

8. Prior to each shipment, the leak test described in Appendix 8B of the applicationmust be performed. No package is to be delivered to a carrier for transport witha detectable leak using the method of Appendix 8B.

337

^£

5

M

P

SP

s

10. In addition to the-requiênts-.^Subâr^'^p^lXI^CFR Part 71:




(i) The hydrogen generated must be limited a to a molar quantity thatwould be no more than 5% by volume (or equivalent limits for otherinflammable gases) of the secondary container gas void if present atSTP (i.e., no more than 0.063 g-moles/ft at 14.7 psia and 70*F); or

(ii) The secondary container and cask cavity must be inerted with adiluent to assure thatroxygen>~must be limited to 5% by volume inthose portions of the package1 whichycibuld have hydrogen greater than5 % . •" "- " *'••'•''. , .

determination Ton-gas generation is made. Shipment'period begins when thepackage is prepared^sealed) and must be cojnp:Tete'd within twice theexpected shipment ti|ie>^;% >/,l0'&?

(b) For any package containing matenials with£r;|d;ioactivity concentration notexceeding that for l&^specific;.activity ftaferial, and shipped within 10days after ventingfof<$ru|s.:; or 'other "se'GjQWd.ary cqntainens, thedetermination irt^Wi abo'vj n'eed: not be^ra|de^' and^tfie time restriction in( a ) a b o v e d o e s "n^'anni** /^''' /-"^'' >!•••'*; S-.A-^S;-- ;•/-•'.--'/',-

(i) Each package must meet the aê^tan^tests;and be'maintained in accordancewith the Maintenance Program o^S^ffon 8 of the^pTicationwith the Maintenance Program o^Segîon 8 of the,capplication.

The leak tests described in Appendixes 8-A and 8 -B of the application maybe performed in accordance with EG&G JdaKo, Inc. letter dated December 20,1982 which was submittedwithPthe Department of Energy consolidatedapplication dated February 26, 1988. Maintenance and repair records shallbe furnished to the packaging owner.

(ii) The 0-ring must be replaced quarterly with new seals. The flat lid gasketmust be replaced annually. The test port and drain line seals must bereplaced before each loaded shipment.

338

m^m^;^

« "i

i

s

s

aSS

fa

s

M

B

NRC FORM 618A(3-9B)



11. The package authorized by this certificate in hereby approved for use under thegeneral license provisions of 10 CFR §71.12.

12. Expiration date: Hay 31, 1999.

REFERENCES

Department of Energy consolidated application dated: February 26, 1988.

Department of Energy supplements dated: May 12, 1989; and April 11. 1994.


^>^,.>-

Date:

S

S

William D. Travers, DirectorSpent Fuel Project Office

., " .;,-. Office of Nuclear Materjal. Safetyy- ' ^vi^x-- and Safeguards .;;".

' ^ 2 "

339

^^^^^^ffi3K^^i!iy3K2SL^(^

NRC FORM 618(8-S5)10 CFR 71

CERTIF.CATE OF COMRUANCE » • " « » " « * " * " » " » - « « »FOR RADIOACTIVE MATERIALS PACKAGES

1.U.CERTIFICATE NUMBER




I PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafetystandardsset forth inTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORTOF THE PACKAGEJ3ESIGN OR APPLICATION 'a. ISSUED TO Warns and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Industrial Nuclear Company2515 Williams StreetSan Leandro, CA 94577

Industrial'Nuclear Company applicationdated December 23, 1981, as supplemented.

c. DOCKET NUMBER """' 71^915 6

4. CONDITIONS .-. .- / • - '<-%?:This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the'conditions specified below.

(a) Packaging

(1) Model No.j^'lR-50

(2) Description

The " " ~"'~changer,radiograph]cmeasures

iveôur^^^mbJ^^JjhdiiVel^j^^fliloy or>:titaniunf "S" tube.The "S" tube* is surrounded ByêpJ^te'dû^ûm metatâ's shieldingmaterial. 1jli'e^.depleted"arat0^fVKj^lclâ^|nibly is&encased in a stainlesssteel housingv^Jhe void spaiie^betwên thefdepletld/'uranium shieldassembly and t'Ke^rgner container is filled witâ| ;rigid polyurethanefoam. The 45 pound source changer is centered^by plywood supports withina 10 gallon (min 20 gauge)^stee] drum with a i'2-gauge steel closure ring.The gross weight of the" squtce\fehangfey lino; overpack is 70 pounds.

(3) Drawings

The packaging is constructed in accordance with Industrial NuclearCompany Drawing Nos.: 2A, Rev. 1, dated November 4, 1992; 2B, Rev. 1,dated August 31, 1992; 50-4, Rev. 2, dated November 4, 1992; and 50-4(A),Rev. 2, dated August 31, 1992.

340

' CONDITIONS (continued)


(b) Contents




120 curies

6. The sources must be secured in the shielded position of the packaging of theieldesource

1475°F

e p p g gshipping plug, source assembly;. fgcl iJ^l^Kigêv^ce. The shipping plug,assembly used must be fabri;cafe%dlof mafeViaslsifeap;able of resisting a 14fire environment for one-hîffhour and maintaining-<t'fiejr positioning function.The ball stop of the^s{b.urce assembly must engage theôeking device. Theflexible cable of theJsource assembly and shipping plugûst be of sufficientlength and diamet&feito provide positive positioning of tfie\source in theshielded position?^ o P

7. The name plate|on? overp%k^ps^ be fabricated/ofMaferials capableof resisting t ^ f i r e tes%|ffl;rQ. CFfc sr,fc 7l/anfl|ifa.intainings Its legibility.The two vent HoTes in theSsê-/Ojf theVroverp4cl< ||!|§ be covemJclwith tape orrubber (piastii^T plugs tofpjfgsissvt Q$g$J$$ rM)j||fo|ier. ^T-,

8. In addition tolfhe requêmeTO^TOubpapjWGî^t) ,CBR/Part 713, each packagemust meet the Caaceptafjceytest^nq i|ria|n1}epI%§ 'rodMm 'andcsF)all be operated

nUCcPjUallUc I c o L 9 aliU

1992 *<?

and prepared for shipiiapplication documentMaintenance Program," Re|§|(f<

The packaging autnQ'rl-zed by thisthe general license^ffiyisions of

m e fs^herebyâpproved for use underW*§71.12. ^ U

10. Expiration date: JanuaV/31^1998. j^-fH RBFEREIC'ES ^

Industrial Nuclear Company application dated December 23, 1981.

Supplements dated: May 28, 1982; October 13, 1983; and March 20, June 25,September 4, and November 4, 1992.


JAN 7 1393Date:

Charles E. MacDonald, ChiefTransportation BranchDivision of Safeguards andTransportation, NMSS

3 4 1

ftw^YS!M&>/e&isM&^M^

NRC FORM 61S

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESLa. CERTIFICATE NUMBER





2>_ PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theappiicabie safety standards set forth in Title 10, Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."




Industrial Nuclear Company Applicationdated December 23, 1981, as supplemented.

• c. DOCKET NUMBER 71-91574. CONDITIONS <-, '-^JJ ''<Ki< ^


(a) Packaging

(1) Model* No.:

(2) Description

..a.r...r. - r - . ^ - . . ^ ^ ^ „,=....._ exposureradiographic

r_. exposure device measures8.875"inches>l"6rjciP 4. 5 .1 ndhfes; -wid|^ and .flînches|high. The radioactive

oifeed 13 n j-.'Zn;riy*El oyri,6'P'/-4.-J;....— ,»—J..1 --^sjjrieicimg material.

Jj:stainless steelhousing.'^jpe void space^j^^lln^the'êplete/^jriinium shield assembly andthe inner container is fiTled^with a rigid,pôjyurethane foam. The grossweight of the exposure device is 53 pounds^

The

(3) Drawingsf

'Vs*The packaging is constructed in accordance with Industrial Nuclear CompanyDrawing No. 1A, Rev. 2, dated November 4, 1992 and IB, Rev. 1, datedJune 15, 1992.

^3 4 2

iI CONDITIONS (continued)

Page 2 - Certificate No. 9157 - Revision No. 6 - Docket No. 71-9157irit

I (1) Type and form of materialI| Iridium 192 as sealed sources that meet the requirements of special form\ radioactive material.E

i

(b) Contents


m 120 curiesit 6. The source must be secured in the shielded position of the packaging by the

shipping plug, source assembly, and locking device. The shipping plug, sourceassembly used must be fabricated;of materials capable of resisting a 1475°Ffire environment for orfa-fialf hour arid maintaining their positioningfunction. The ball?stppôf the source assembly-must engage the lockingdevice. The flexible'cable of the source assembly;1 and shipping plug must beof sufficient length and diameter to provide positive positioning of thesource in the-shielded position.

7. The name piat§ on^theêxposure device must be-jabricated of materials capableof resisting'"the fff;eft¥st of 10 CFR Part/7iâ1idxmaintaining its legibility.

8. In addition to the r^mfe^pts^ of S(ibpirif-%S6$ 10 CFR Part 71, each packagemust meet-the acceptance|i'e|;ts a'n.d maintenjyfcel program, and shall be operatedand prepared for sjjipmerîfrâecofdanbe^^^lj^he operating procedures in theappi icati oh document en&i^!efl;^ Acceptance Test, andMaintenancjef;Progfantff ReW$fqn 11,rdated!NQVe:mbe;r-'.&'/1992, "as supplementedDecember ^5/ 1 9 9 2 ^ ^ ^ ^ h j ! ] < - \ ^ ^ "i'fc "

9. The packagihgtauthoHrel^b^th'T^ce^Tf^^ hereby approved for use underthe general license p1-bv"fsôns^;iO\C^R §7#$l2.

10. Expiration datef/.fJanuary 31, r998/JN'< / ' / . . . j REFERENCES?..- '"

Industrial Nuclear Company applicationldated December 23, 1981.

Supplements dated: May 28, 1982; October 13, 1983 (two l e t t e r s ) ; November 26,1990; February 22, and April 26, 1991; and March 20, June 25, September 4,November 4, and December 15, 1992.




Date:

343

^

NRC FORM 618(3-96)10 CFR 71




9159

b. REVISION NUMBER

7


USA/9159/A

d. PAGE NUMBER

1


52. PREAMBLE




VECTRA Technologies, Inc.Brookside Office ParkOne Harbison Way, Suite 209Columbia, SC 29212


NUPAC application dated February 29, 1988,as supplemented.


4.CONDITIONS . f " .-• •]-•.•-This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as'applicable} and the conditions specified below.

'-;-• J'I

(a) Packaging

(1) Model Nos.: NUPAC. 14/190L, NUPAC 14/190M,A.LN i4rT70W» and LN 14-170H

(2) Description

, LN 14-170L,

v, okSteel encased lead ^fi^^ldjed casksjforV^cftafotctive material. The casks are

right circular cylJn^^^jbH^^^S.-j iffeiipp) by 73.38r:fjnch IH cavity. Thewalls of the caSI& cftfft^^ fr'ojn 1.25 to 2.63 inchesencased iri 0-38î;nGfiLtK^d^^nHenl;s]t'e^^Hell}>|an®'0.88î-nch thick outer steelshel l . The top^cpê^n'^Msk'Bb^toiâre maaeûp of<;two steel plates rangingin thickriess fr^Ô'^jijBppiindhi^^Jh^pt^î'y c,a>k l id is secured to thecylindrical cask' 'b%dy.^ve^h^S(ft^^7^îi-#achet binders. An optionalsecondary l id is centered tn^|Ke:^p^mary^' l';fd and ^ s e c u r e d to the primaryl id with eighty 3/4-inch stadsiaHînuts':''%'Each,JLiJd?''is provided with aNeoprene gasket seal . The casksrX:niay be provided^with an optional 12-gaugestainless steel l iner (seal welded along allêdges), an optional l id ventline with pipe pliig, and an. optional 3/4închcdrain line and pipe plug. Thecasks are provided with f<?uVegu.alTy?spaced lifting/tie-down devices. Theprimary l id is provided with three l i f t ing lugs and the optional secondaryl id is provided with one l i f t ing lug. The casks gross weights range from49,200 to 65,200 pounds.

Model 0D,Number inches

NUPAC 14/190L, LN 14-170L 80.5NUPAC 14/190M, LN 14-170M 81.5NUPAC 14/190H, LN 14-170H 83.25

Lead Tk,inches

1.251.752.63

Top Tk,inches

4.04.05.0

Bottom Tk, Gross Wt,inches pounds

4.04.05.0

49,20053,50065,200

344j&2gJgJW^{7&J&J55U5SJ£kI£kJ£U5&J^

P

NRCFORM618A(3-96)



5. (a) (3) Drawings

Model Nos. NUPAC 14/190L. NUPAC 14/190M. and NUPAC 14/190H

The packages are fabricated in accordance with Nuclear Packaging, Inc.Drawing No. X-20-307-SNP, Sheets 1, 2 and 3, Revision No. A.

Model Nos. LN 14-170L. LN 14-170M, and LN 14-170H

The packages are fabricated in accordance with LN TechnologiesCorporation Drawing No. 5025-M-2005: Sheets 1 and 2, Revision No. 0.

(b) Contents

(1) Type and form,of material

Dewatered, solid, or solidified waste, or activated solid components, insecondary containers, and limited to the following:

(i) .Materials in which the radioactivity is essentially uniformlydistributed; and in which the es.Mjnated average concentration per"gram of contents does^not e/c.eeg*^'

0.0001 mil£ltcurie of radionuefides for which the A2 quantity inAppendix Aldf 10 CFR PaYt /risfnot more than 0.05 curie;

0.0051 mijlicurte of r:adio|iuejides;/|gr;. which the A2 quantity inAppendjix %;pfr 1Q!CFR Part 71 is nio'rfe than 0.05 curie, but notmore than /%cur]e; or ' 'ijv'- ,-J '•'"''

0.3 millicurie of: rac(ipnuclidesrfor which the A2 quantity inAppendix A of 10 F-R!pa|'t'"71 is.' more... than 1 curie.

(ii) Objects of nonradioactive material externally contaminated withradioactive material, provided*that the radioactive material isnot readily dispersible and "the surface contamination, whenaveraged over anarea^of-lsquare meter, does not exceed0.0001 millicurie (220,000 disintegrations per minute) per squarecentimeter of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie, or0.001 millicurie (2,200,000 disintegrations per minute) persquare centimeter for other radionuclides.


Greater than Type A quantity of radioactive material which may containfissile material provided the fissile material does not exceed the limitsin 10 CFR §71.53. The decay heat load is limited to 7 watts for theModel Nos. NUPAC 14/190L, NUPAC 14/190M, LN 14-170L, and LN 14-170M; and25 watts for the Model Nos. NUPAC 14/190H and LN 14-170H casks.

345

waEr^ ^

i

i

iH

NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION( 9 6 )(3-96)

HPage 3 - Certificate No. 9159 - Revision No. 7 - Docket No. 71-9159

(a) For any package containing water and/or organic substances which couldradiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package such thatthe following criteria are met over a period of time that is twice theexpected shipment time:

(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP ( i . e . , nomore than 0.063 q-moles/ft at 14.7 psia and 70°F): or

(2) The secondary container and cask cavity must be inerted with a diluent toassure that oxygen must be Limited.,to S% by volume in those portions ofthe package which pquld have hydrogen greater than 5%.

For any package .delivered to a carrier for transport, the secondary containermust be prepared for shipment in,the same manner;in.which determination forgas generationals made. Shipment period begins when the package is prepared(sealed) and mustjbe completed within twice the^expected shipment time.

(b) For any package ship|ed^within 10 days of/'prelpal'ation, or within 10 daysafter venting of drums%r other -sexcondaryco|itainers, the determination in(a) above heed not be^ade,-andTthe,time restriction in .(a) above does notapply.

7. Maximum gross weight oi'jlhe^cbatehts, secondary^ntainers, and shoring is limitedto 20,000 pounds':1 ^ i ^ ; ^ ^ ^ ' . - ' : ^ - ' " ' ^ ^ $M' '•

8. Except for closetf^ttirig^^^^ be''placed between secondarycontainers and the^cask ql^tfeto-mini^tze.'movenfelit' during normal conditions oft r a n s p o r t . "; •> • ~\\ '/.'#•?$&$<. ••• ''•' <>^'

9. The lid and the shield>plug lifting Tugs must not be,used for lifting the cask, andmust be covered in transit. v.

10. The cask must be provided with; either,(or botfij/a drain line or a lid vent line asshown in the drawing in order to provide a method to leak test the package.

3 4 6

^Ws7&tt

NRC FORM 618A(3-96)




(a) Prior to each shipment, the packaging Neoprene lid seals if opened (or ifsecurity seal is broken), must be inspected. The seals must be replaced withnew seals if inspection shows any defects or every twelve (12) months, whichever occurs first. Cavity drain and vent lines must be sealed withappropriate sealant applied to the pipe plug threads.

(b)

(c)

Each packaging must meet the Acceptance Tests and Maintenance Program of:

Model Nos. NUPAC 14/190L. NUPAC 14/190H and NUPAC 14/190H


Model Nos. LN 14-170L. LN 14-170M and LN 14^17OH

LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; andWM-013, Rev. F.

The package shall be.prepared for shipment arid-operated in accordance withthe Operating Procedures of: v V ;

Model Nos. NUPAC 14/J90L'- NUPAC:h47i90MandaiUPAC 14/190H

Section 7.0 of the,application. ^

Model Nos. LN 147170L. tflI 14-170H and LN: 14-170H

LN Technologies Cdjppbr%to^>Prqcedures WM-025, Rev. C.

12. The ratchet binders, on the cask 1id; mustobe torqued to 100+10 ft-lb.

13. The cask body and each;cask lid must'be marked in accordance with 10 CFR §71.85(c).

14. The packages authorized by this certificate must-be transported on a motor vehicle,railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vesselassigned for the sole use of the licensee.



347ffiffiW

CONDITIONS (continued)NRC FORM 618A(3-96)


REFERENCES

Nuclear Packaging, Inc., application dated February 29, 1988.

Supplements dated: April 19, 1988; and February 16, 1993.

NUS supplement dated: November 22, 1985.

LN Technologies Corporation supplement dated: February 16, 1988.

Scientific Ecology Group, Inc., supplement dated: April 30, 1993


Date: Vti

FOR THE U:s. NUCLEAR REGULATORY COMMISSION

William D. Tracers, DirectorSpent Fuel Prbjfect OfficeOffXce of Nuclear Material Safetyand Safeguards

15

348

p^ E

NRC FORM 618(M6)

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESi.a.CERTIFICATE NUMBER





22. PREAMBLE

a. This certificate Is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code

of Federal Regulations, Part 71 , "Packaging and Transportation of Radioactive Material."


3, THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATIONa. ISSUED TO (Name end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Amersham Corporation application datedAugust 4, 1995, as supplemented.

"c. DOCKET NUMBERUni^&i,4. CONDITIONS < %J <^l

This certificate is conditional upon/ulfilllng-the;requirements of 10 CFR Part 71 , as applicable, and the. conditions specified below.

5.

(a) Packaging

(1) Model No . ^ 8 5 5

Primary components consistpott^igg material, uraniumand^bpttom support plates

x 5/8" long hexthe "J" tubes by

^./#ppackagj^has an outside diametersicf^fieight df^lpproximately 14.75 inchesmaximum t o t ® weight of the package is

(2) Description

A steel gjfgasedof an outer carshield, e|gj)t Tiand a gaskete.d 1head bolts-J^Themeans of a srffncce cableof approximate^ 11.25 inchewhich includes t-h^lid eyebolt^approximately 195 jrounds.

(3) Drawing

The packaging is constructed in accordance with Amersham Corporation DrawingNo. R85590, Rev. B, Sheet No. 1 to Sheet No. 5.

(b) Contents


Iridium-192 sources which meet the requirements of special form radioactivematerial.


1,000 curies (output) with no more than 240 curies in a single source.

Output curies are determined in accordance with American National StandardN432-1980, "Radiological Safety for The Design and Construction of Apparatusfor Gamma Radiography."

349

^^

w«w«sh!«w«w«w^<ig^^

*iii

I

iit

E

iit

I

t

E

t

iii

NRCF0RM618A(643)



J. The cover bolts shall be provided with tamperproof seal in accordance with10 CFR §71.43(b).

7. The two (2), 1/4-inch diameter vent holes in the side of the packaging shall beprovided with tight fitting rubber or plastic plugs to preclude the entry of rainwater into the packaging.

8. The name plate shall be fabricated of material capable of resisting the fire testof 10 CFR Part 71 and maintaining its legibility.


(a) Each packaging must meeSection 8 of the a t m "

heB Tests and Maintenance Program inted.

(b) The package stfcTljrbe prepared for shipmentindhpperated in accordancewith the Op^ting Procedures in Section 7 or ^ application, assupplement

10. The package authogeneral license

11. Expiration dater^ecember

Amersham Corporation^ppli

Supplements dated:

rove^ufor use under the

Ocertificate is her

CFR §71.12.

AR REGULATORY COMMISSION


Date:

350

*&/&K&<afll8fi$ffl?i&FiW>®?$tf^^







1e. TOTAL NUMBER PASES

i PREAMBLEa. This certificate is Issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



3, THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEUESIGN OR APPLICATION 'a. ISSUED TO Warns and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Technical Operations, Inc. application datedJuly 15, 1982, as supplemented.

c. DOCKET NUMBER 71^9166A, CONDITIONS

This certificate Is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

Model No.?'%864

on(1)

(2) Description

The Model' No. 86/kj)nips)j^^c6îAner~%s.:^dî^hBd useless a source changer,d in

and

(b)

storage cbntainer^t:and |ype>B7shipping^cbnâineK-fpr ratfiographic sources inspecial form. Thlf^6d,e.l^Q4^8J54,;source;}dKang/Bjr' ''-'6.0/Jj-n,ches in diameter an9.56 inchedîghi^thei;packa'g^ incorporates ^^TOndlesiiwhich protrude fromthe side of the pa^k;asge>X.^lv!ijji'ches:

y^ point). Three radioactivesource assemblies a:'reiWu^d^^JbâisÛê^tubes.^CTlJe source tubes aresurrounded byfuranium meial iswe;ifdxihg\(4.3^t)s). Thfturanium shield assemblyis encased in4^carbon steel %ms\ngîth^vbid space,.'"filled with a castablerigid polyureth'ari^foam. A dec'Icijtate above the^sfiield contains three sourcelatching assemblfeVand a shipping cover protecting the latching assembliesduring shipment, the grbss^weight of the container is 67 pounds.

(3) Drawing ' ' :":'

The packaging is constructed in accordance with Technical OperationsInc. Drawing No. 86490, Sheets No. 1, through 6, Rev. 1; and 86491, SheetNo. 1, Rev. 1.

Contents


Iridium 192 as sealed sources that meet the requirements of special formradioactive material.


360 curies

3 5 1

i ^ ^


Page 2 - Certificate No. 9166 -Revision No. 3 - Docket No. 71-9166

o.

7.

The source attached to the source assembly must be secured Mn the shielded positionof the packaging by the source latching assembly with the latch bars in the engagedposition. The safety pins shall be operational and the shipping cover shall be inplace and secured.

The two (2), 1/4-inch diameter vent holes in the sides of the package shall becovered with tape or rubber (plastic) plugs to preclude the entry of rain waterinto the packaging.

The name plate shall be fabricated of material capable of resisting the fire testof 10 CFR Part 71 and maintaining its legibility.

In addition to the requirements of Subpar>t=>G,.of 10 CFR Part 71:

(a) The package shall be^prepared" for shipmentând operated in accordance with theOperating Procedure'sôf vSection 7.0 of the application; and

/(b) The package must^meet the Acceptance Test and Maintenance Program of Section

8.0 of the application.

10. The package authp'Kiiedgeneral license^;

for use under the

11. Expiration date":,. January

Technical OperationsVÎnc.

Supplement dated: November

certificate is§71.12.

^98|fe

ftNUCLEAWREGULATORY COMMISSION

pj ET MacDonald, Chief^transportation BranchDivision of Safeguards


Date:

352

NBC FORM 618(846)10 CFR 71



1.B. CERTIFICATE NUMBER




1 PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicable safety standards set forth in Title 10, Code






Amersham Corporation application datedAugust 25, 1982, as supplemented.

C. DOCKET NUMBER 71—91674. CONDITIONS

This certificate Is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model Nos.: 3206f,V,3227B, and 3218

(2) Description , vj---> ( !-. ' ;

Thej.KEG conâiners^/are designed-as ;Type B /shippingcontainers for neutronsources in special formi/>Th£ containers,/^^constructed of stainlesssteelând the^dim^siqnlarfeUâ'inchesiln^diameter by 20.4 inches high.The containeâre^tiTled with; water extended polyester (WEP) whichprov ide r ad iitjohOafrd'fê^mal^prBt^ to the/contents. The Model No3206B and |227B cont'ainei*sfpakh. have'*one receptacle for the source(2-inch Uiaineter and 3-inchj diameter'receptacles, respectively). TheModel No. ^18,container Ws ilwo (2) receptacles for the sources (2-inchdiameter andn^-inch diameter receptacles):/ The smaller receptacle willbe used only for a^reference or calibration source. A stainless steelencased WEP plug will b%. inserted/into, the receptacle and held in placeby a knurled stainless steel screw cap. A stainless steel latch bar islocked in place over the screw cap with a key operated padlock. Thegross weight of each container is 165 pounds.

3 5 3



5. (a) (3) Drawings

The packagings are constructed in accordance with Amersham CorporationDrawing Nos.:

Model No. 3206B Model No. 3227B Model No. 3218

0A22413, Rev. D1A22299, Rev. G3A22297, Rev. C3A22420, Rev. B2A22442, Rev. A2A22385, Rev. B2A22419,

^NOTESi

0A22527, Rev.1A22299, Rev.3A22297, Rev.3A22416, Rev.2A22528, Rev.

DGCAAA

SQ\V

0A22440, Rev.1A22299, Rev.2A22441, Rev.2A22442, Rev.3A22302, Rev.3A22439, Rev.3A22443, Rev.3A22444, Rev.

^3A22321, Rev.

DGAACAAAC

and the NOTES ON DRAWINGS" given on pp 1-34 an'dx 1-35 of theapplication^ (01/17/83). ^ >

(b) Contents /?*?

(1) Type~-and form

,

oAm-2 1/Be neutrt^sources^hat^meetiflfefrequiremen^s-of special forma d J o a t i v f i t r - ^ ^ ^ i-****& H? < •--

(2) Maximtfm qi

25 curies

§

Venting of the source receptacle(l^/jn\|V|jvt wfpecompjss^tnon of the WEPshielding plug due*<to^t,he accident ^bi$i#ions of transport, shall be provi<by drilling a 1/4-inW^o.le in the top surface of theVscrew cap(s). The hole. . . . . . . . . ... ^ L . .. . v . . .

shielding plug due*<to^the accident ^Qniiibions of transport, shall be provided fornH^hole in the top surface of theVscrew cap(s). The hole

shall be filled with pfajstic, rubber, or low temperature melt alloy to precludeentry of rain water during njblrmal /cond/itions-ofytransport.

7. Name plates on the container must be fabricated of materials capable of resistingthe fire test of 10 CFR Part 71 and maintaining their legibility.


(a) Each package shall be prepared for shipment and operated in accordancewith the Operating Procedures in Section 7 of the application, assupplemented; and

(b) Each package shall be acceptance tested and maintained in accordance withthe Acceptance Tests and Maintenance Program of Section 8 of theapplication, as supplemented.

354

^^B^«^»l»mjBMSM«MBS.«^

fr&F^Af<ti^

' NRC FORM 818A U.S. NUCLEAR REGULATORY COMMISSIONi (6-83) CONDITIONS (continued)

• Page 3 - Certificate No. 9167 - Revision No. 4 - Docket No. 71-9167

\ The packaging authorized by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12.

i

\ 10. Expiration date: December 31, 1998.I*

I REFERENCES

Amersham Corporation application dated August 25, 1982.

Amersham Corporation supplements^atfed:^ January^;: |?83; March 1, 1988; August 1 andSeptember 19, 1991; and February^!? and October 29, 1993..^

FOR THE U.S. NUCLEAR REGULAtQRY COMMISSION

Systems Branch

355

NRC FORM 618(&«5>10 CFH 71



•.CERTIFICATE NUMBER




3 _2. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standardsset forth in Title 10, Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."




Chem-Nuclear Systems, Inc. applicationdated February 26, 1990, as supplemented.

'c. DOCKET NUMBER§7h?1

4. CONDITIONSCONDITIONS <^ V ^ <^->'! „This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the'concMions specified below.

(a) Packaging

(1) Model No^f CNS §

(2)

steel jacket^ The bottoml£|dj|ip is'maHe of ,£v«C'3-l/4-ihsteel plates.^J^.e primary Turfs sealed with^&Aiouble sil-'

11 jfVxxv^i&y.

ies ene#e"d in 0^5-inch thick inner^ t g ^ s h e l l ^ T h e exposed sides ofHb^ r ie r con|<i sting of a 5/32-inch

covered5|ith a 3/16-inch thickthick carbon

20 equally spacfetf 2-inch diameter bolts. Th;e\>29-inch diameter centeredsecondary l i d is seaj-ed with a double >Wicone 0-ring and twelve equallyspaced 2-inch diameter bQT^^The'yptHorial drain line is sealed with a 3/4-inch diameter cap screw and a^silitone 0-ring. The l i d sealing surfaces arestainless steel and the space between the double 0-ring seals is providedwith a test port for leak testing.

The top and bottom of the cask are provided with steel encased, r igidpolyurethane foam impact l imiters. The impact limiters are secured to eachother about the cask with eight 1-inch diameter ratchet binders. The impactlimiters are 102 inches in diameter and the overall height of the packagewith the'impact limiters attached is 132 inches.

The package is provided with four tie-down and two removable l i f t i n gdevices. Each l i d is provided with three l i f t i ng lugs. The gross weight ofthe packaging and contents is approximately 74,000 pounds.

3 5 6

NRC FORM 618A(6-83)





(3) Drawings

The packaging is constructed in accordance with Chem-Nuclear Systems, Inc.Drawing No. C-110-E-0007, Sheets 1, 2, and 3, Revision No. H.

(b) Contents


(i) Byproduct material in th.e form of dewatered resins, solids, orsolidified waste conta4nednwi$hirksecondary containers; or

(2)

( i i ) Radioactive jn^te^ral in the form or^4$Jâted reactor components.

Maximum quantiiyôf material per package f\

Type B quantify of radioactive material, not toje*cee& 2,000 times a Type Aquantity, MO thlâ^lwatts, and 14,680 pouj^s^rrcl udjifg weight of thecontents, aserondair^îtainers, and shorifissile materials imalêUthejnas&Jirexceeded<

be pi acetlgbetween thee/pask ccalstity to prevent

jfg ge contents may include

0 CFR §7tl53 are not

©secondary lid by twelve,torched to 500 ft-lbs ± 50

6. Except for closedfittisecondary contfriners,movement duringaccid

7. The cask pr imary^d2"-8UNC-2A x 4" %o%ft-lbs (lubricateid})?

8. Prior to each shipmeift^(except for 't/hf^rfE'ents mêting^lTe requirements for lowspecific act ivi ty ma t^4^ \ which is transported by exBîisive use vehicle), thepackaging must be leak t ^ t e d in accordance withSedfNon 8.2.2.2 of theappl i cati on. }^ ^ A Jy V

9. In addition to the requirements ofSubpart G of 10 CFR Part 71:

(i) Each package must meet the acceptance tests and be maintained in accordancewith the Acceptance Tests and Maintenance Program of Section 8.0 of theapplication, as supplemented February 22, 1994,

(ii) The seals must be replaced with new seals if inspection shows any defects orevery 12 months, whichever occurs first. The tests ports and optional drainline must be appropriately plugged and sealed prior to transport, and

(iii) The package must be prepared for shipment and operated in accordance withthe operating procedures of Section 7.0 of the application.

357

NRC FORM 618A CONDITIONS (continued)


U.S. NUCLEAR REGULATORY COR/MISSION

10. (a) For any package containing water or organic substances which couldradiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package such thatthe following criteria are met over a period of time that is twice theexpected shipment time:

(i) The hydrogen generated must be limited to a molar quantity that wouldbe no more than 5% by volume (or equivalent limits for otherinflammable gases) of the secondary container gas void if present atSTP (i.e., no more than 0.063 g-moles/ft3 at 14.7 psia and 70*F); or

(ii) The secondary container and) easjfc cavity must be inerted with a diluentto assure that oxyî^musOjKl^lpiêtl^to 5% by volume in thoseportions of the fjafckage which coulcrhive^hydrogen greater than 5%.

(b)

For any package\defivered to a carrier for transp£is±, the secondarycontainer must^Ve prepared for shipment in the saiie/rnpiner in whichdeterminatioRJffor gas generation is made,. Shigment^^riod begins when thepackage isfyprep$fe;ek.(sealed) and must be coj^êd w'ttfgn twice the expectedshipment tjm'e. ^ "*"•"

For any package conexceeding^that fordays of Reparation

dioactivvty concentration notial, andQnipped within 10

venting ofpdrums or otherneed not be made, and

the time«restri^vK

11. The package authori zed^^general licenseIprovisiioff

12. Expiration date: \June 30

herepyâpproved-afor use under the

26, 1990.Chem-Nuclear Systems, Inc., application dated

Supplement dated: February 22, 1994.


f\- £*Cass R. Chappell, Section LeaderCask Certification SectionSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

Date* ûne

358

^NBC FORM 618(3-96)10CFR71



1. a, CERTIFICATE NUMBER


13c. PACKAGE ID BER d. PAGE NUMBER e. TOTAL NUMBER PAGES

0

2. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10,






c. DOCKET NUMBER 71-91764. CONDITIONS . >

This certificate is conditional upon fulfilling the requirements'of 10 CFR Part 71, as Applicable; and the conditions specified below.

5.

(a) Packaging ,. <

(1) Model Nos.: NUPACa4/210L, NUPAC 14/210H, CNSI L4.-215H Ser ies A, LN 14-195L,^nd LN::.!'

(2) Description;

Steel encased lead s$%fded casks,,for radia t ive material. The casks areright circular cyLindefcs with'a"77:y25,-i;npfi®P by 80.25-inch IH cavity. Thewalls of the cdL^ôi^f^îîj^m^'rî^ from. 1.25 to 1.88 inchesencased in 0.38-3ricfi; Jh'i'icîhner stê1#helLMd^'6.88-inch thick outer steelshell. The,top-cov^V^hd Jcask bqtip#;are majfenup of two steel plates with

«- •„£' o r\•"Aî-û^î '~x\Hn''r.vi''iiwov<\f»>^cir i•?A"A f OQÎIV?QH TQ t h e c y l i n d r i C c

secondary l i d i sthickness W~2.0*^he5wjJn?:P1^Waj^?!as^fi.d:'*h secured to the cylindricalcask body by.;eight,^l/;4-incJ)âghet: binders. An optional :centered in'jthe primary lids/a1)<|^|s;ecured to the primary lid with eight,3/4-inch studs-and nuts. Ea'dJ$/Tf$$5s provjded with, a Neoprene gasket seal.The casks may be'provided witficanAoptional 12 gauge stainless steel liner(seal welded along/all edges), an optional lid^vent line with pipe plug, andan optional 3/4-inch drain line with pipe plug. The casks are provided withfour equally spaced Iffti'ng/tie-down devices. The primary lid is providedwith three lifting lugs and the; optional secondary lid is provided with onelifting lug. The casks gross weights range from 51,600 to 58,400 pounds.


NUPAC 14/210L, LN 14-195L 82.25NUPAC 14/210H, LN 14-195H 83.5CNSI 14-215H Series A 83.8

Lead Tk,inches

1.251.881.85

Top Tk,inches

4.04.04.0

Bottom Tk,inches

4.04.04.0

Gross Wt,pounds

51,60058,40058,400

3 5 9


* Page 2 - Certificate No. 9176 - Revision No. 13 - Docket No. 71-9176sM

Si

S 5. (a) (3) Drawing* Model Nos. NUPAC 14/210L and NUPAC 14/210Hg* The packages are fabricated in accordance with Nuclear Packaging, Inc.,S Drawing No. X-20-306-SNP, Sheets 1, 2 and 3, Revision No. A.3 The packages may include an optional removable shield insert fabricated3 in accordance with Pacific Nuclear Drawing Nos. PS-121892-1 and PS-121892S submitted on December 21, 1992.SS Model No. CNSI 14-215H Series A* „ " ^ : ^ ••" * ;• ,

The package is fabfeijcated in aceorda^nce/.with Chem-Nucl ear Systems, Inc.,S Drawing Nos. 24500-08, Sheets 1 and 2^:Rev> D, and 24500-5, Rev. 2.S . •:--> 'S The package may include an optional removablepshield insert fabricated ing accordance"with Chem-Nuclear Systems, Inc., Drawing No. C-119-B-0017,« Rev. 3^..,^ < ^ ^ x ^.^ <;>',i Model•••Wb's. LN%6f9x5L and LN 14

i The packages areâBritateE^n/accpriafiS with LNfTechnologiesCorpbnation Drawg^No. SO^MkOO^'Isêts 1 and 2^ Rev. 0.

•^M^^î f^f 5 <,L/L

H

H

«

S

i

3 6 0?lL2^^

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gs

Sskj

«

£

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£k

kj

£k

kj

k

NRC FORM 618A(3-96)



5. (b) Contents







(ii) Objects o.f^nonradipactive material externally contaminated withradioactive:-material, provided that the radioactive material isnot readily? dispersible and the surface contamination, whenaveraged oveir an area of 1 square meter, does not exceedO.OdOl'mrTlicUrie. (220,000, disintegrations-per minute) per squarecentimeter of;radionuciides/for which the A2 quantity in,Appendix.A)of ,10 CFR Part 71 is/riot more than 0.05 curie, orO.OOFinil-Hcur.ie (2,200,000.disintegrations per minute) persquare'.centimeter ifor-othef ra'dionuolides.


Greater than Type A quantity of radioactive material which may containfissile material provided the fissile material does not exceed the limitsin 10 CFR §71.53. The/decay heat load is limited to 9 watts.

3 6 1

Prgggg

ininir^^

&



(a) For any package containing water and/or organic substances which couldradiolytically generate combustible gases, determination must be made bytests and measurements or by analysis of a representative package such thatthe following criteria are met over a period of time that is twice theexpected shipment time:


(2) The secondary container and cask cavity must be inerted with a diluent toassure that hydrogen must be-slimited.to 5%.by volume in those portions ofthe package which could Have hydro^n'greater than 5%.

For any package .delivered to a carrier for transport, the secondary containermust be prepared/for shipment in the same manner ,in. which determination forgas generation is made. Shipment period begins when,the package is prepared(sealed) and muftk.be completed within twice tjhi^xp^ected shipment time.

(b) For any package sh-igped\within 10 days jrf^ff&ratioV'or within 10 daysafter venting of dram|t^r\oth.ergseeondar^y)%ontainers/ft|ie determination in(a) above need not betntade;, ahcT?the tfme^gslriction ;inx(a) above does not

and optional

Except for closer -fittitilQoni^ secondarycontainers and the^casic 'bi$'A$jf to^m^imjze moverferit durijngtriormal conditions oftransport. •'..;-'> ' ^ £ ) $ $ $ & f\ "J J'&ji

The lid and the shieid'-'pjug lifting lugs must not besused for lifting the cask, andpgmust be covered in trarisrt.

1 0 . T h e c a s k m u s t b e p r o v i d e d w i t h ^ i t . h e r ^ o K b p t h T ' a d r a i n l i n e o r a l i d v e n t l i n e a sshown in the drawing in order to provide a"method to leak test the package.

gg

g

agggi

gg

3622E2E2IC




(a) Prior to each shipment, the packaging Neoprene lid seals if opened (or ifsecurity seal is broken), must be inspected. The seals must be replaced withnew seals if inspection shows any defects or every twelve (12) months, whichever occur first. Cavity drain and vent lines must be sealed withappropriate sealant applied to the pipe plug threads.

(b) Each packaging must meet the Acceptance Tests and Maintenance Program of:

Model Nos. NUPAC 14/210L and NUPAC 14/210H


Model No. CNSI 14-215H Series A

Chem-Nuclear Systems, Inc., Document No. CNSI 9176-S1, Rev. 1, Section 4.0.

Model Nos.LN 14-195L and LN 14-195H

LN Technologies Corporation Procedures WMrO3j3/Rev. A: WM-026, Rev. B: andWM-013, Rev. F. >*;\. \ ,-.;•-.;:,• " '£<%[

(c) The package shall b^pr~ep.ared/;for,,shipme|rt|^nd operated in accordance withthe Operating Pr:qcedU£e&;6f: ;-~;Vg

Model Nos? NUPAC 14/21^%hd NUPAd 14/2loff 'j&'/y

Section 7J)',of tfeapjriic^ioji:;;j ''}'i^'^jr, /"

Model No. CNSI 14-215H"leriei^j{^', :''.f\ :-'.-

Chem-Nuclear Systems, Inc., Document No. CNSI>;9i'76-Sl, Rev. 1, Section 3.0.

Model Nos. LN 14-195L .and LN 147195H . ?

LN Technologies Corporation Procedures WM-025, Rev. C.

12. The ratchet binders on the cask lid must be torqued to 100±10 ft-lb.


14. The packages authorized by this certificate must be transported on a motor vehicle,railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vesselassigned for the sole use of the licensee.



3 6 3



REFERENCES


Supplements dated: April 19, 1988; and March 1, 1993.

Pacific Nuclear supplements dated: October 23 and December 2 and 21, 1992.

Chem-Nuclear Systems, Inc., supplements dated: February 19 and April 21, 1988;January 18, and April 29, 1993; and January 29, 1996.

NUS supplement dated: November 22, .1985. ":;=,./; .,

LN Technologies Corporation supplement dated: February...16, 1988.

Scientific Ecology Group.,\]nc, supplement dated: April 30,^1993.

'SREGULATORY COMMISSION

Date:

OfficeVpf NucJ'ea^Material Safety

•n

NRC FORM 618(3-96)10CFH71




9177

b. REVISION NUMBER

7


USA/9177/A

d. PAGE NUMBER

1


2, PREAMBLE


b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any .country through or into which the package will be transported.






4.CONDITIONS ;, . " 'This certificate is conditional upon fulfilling the requirements" of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1)

(2)

Model Nos.: NUPAC 10/140 and LN 10-135A

Descri pti op'-f > s ^ y > , .

Steel encased lead shielded, ca5ks>;for radioactive material. The casks areright circular cylinaeMVi.th 'a}356'..Ci-ihcli IjEfe.by 73.0-inch IH cavity. Thewalls of the casks cfntf.in; a l,ead,.thickn^#gbf 2.75 inch- J -'- " Cft

inch thickAnnertsp&^^1i^firi^?'f:i3,-in£fi;||n" i ck- outer;Jinches encased in 0.50-

:s"teel shell. The top

centered in the3/4-inch stitdsThe casks may;(seal welded "along all edges}^f|fj?optiorial;lid vent;.line with pipe plug, andan optional 3/4-fhch drain line^and pipe plug. The casks are provided withfour equally spacecj/lifting/tie-down devices.^the primary lid is providedwith three lifting lugsxand the optional-secondary lid is provided with onelifting lug. Each cask^hasTVgross weight'of 56,500 pounds.

(3) Drawings

Model No. NUPAC 10/140

The package is fabricated in accordance with Nuclear Packaging, Inc.,Drawing No. X-20-308-SNP, Sheets 1, 2, and 3, Rev. A.

Model No. LN 10-135A

The package is fabricated in accordance with LN Technologies CorporationDrawing No. 5025-M-2005: Sheets 1 and 2, Rev. 0.

3 6 5

5

C&&2&2£J&2&2&J&7K7K7KM7K7*U!U£U£U&7&7&,2&

L W w ^



5. (b) Contents





0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 0.05 curie, but notmore than 1 curie; or x

0.3 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 ismoris: than 1 curie.

(ii) . Objects Q^^qnradioactiye material 7externally contaminated with, radioactive material/, -provided; .tfiat the radioactive material isnot readti^dispersible and tfijessurface contamination, whenaveraged pyei^ an are«l of 1 square meter, does., not exceed0.000|%ill;i;cur,ie .(220,00p/d^s4;ntegip^tions per minute) per squarecentimeter bf:vradiohUclide^;fdr which',the A2 quantity inAppen\d3xC^.:pf ipCFRiNrt 7r'is not-more than 0.05 curie, or.0.001#11ticuri^ minute) persquare ,cjenti.metef fp'r/other^r'adionucl ides,;

(2) Maximum quantity of mater^iai^peiSpackage , \.

Greater than Type A quantity of radioactive: material which may contain infissile material provided the fissile material does not exceed the limitsin 10 CFR §71.53. The decay heat load is limited to 24 watts.

366

IWaf araTaTaTaTaTaYw at W W M aniniraTaTaTaTaraz axa7aYaz at az ax w w at w at a>: at at war at at war atat aCONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONNRC FORM 618A

(3-96)




(2) The secondary container and cask cavity must be inerted with a diluent toassure that oxygen must be limited to 5% by volume in those portions ofthe package which could have hydrogen greater than 5%.

For any package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination forgas generation is; made. Shipment period begins when the package is prepared(sealed) and must be completed within twice the expected shipment time.

(b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drumsor other secondary containers, the determination in(a) above need not be made, and the time restriction in (a) above does notapply. X '-v

7.

8.

9.

10.

Maximum gross weight of thercdntents, secondary containers, and shoring is limitedto 15,000 pounds. •%. :"-•'/'• •>/

Except for close fitting contents; shoring must be placed between secondarycontainers and the casktcayity.tx)'minimize movement during normal conditions oft r a n s p o r t . - V - '('.I'-^'c'"'''" '•'"» ••-• ''''"

The lid and the shield plug liftirig(/lugs\must not be used for lifting the cask, andmust be covered in transit.

The cask must be provided with either (or both) a drain line or a lid vent line asshown in the drawing in order to "provide a method to leak test the package.

367

NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONs. (3-96)

3 Page 4 - Certificate No. 9177 - Revision No. 7 - Docket No. 71-9177


3

3?M

3

* Model No. NUPAC 10/140

(a) Prior to each shipment, the packaging Neoprene lid seals if opened (or ifsecurity seal is broken), must be inspected. The seals must be replaced withnew seals if inspection shows any defects or every twelve (12) months,-whichever occurs first. Cavity drain and vent lines must be sealed withappropriate sealant applied to the pipe plug threads.



Model No. LN 10-135A • -.. ' .

LN Technologies,Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; andWM-013, Rev. F.v) V',. .

(c) The package shal-ljbe prepared for shipment and operated in accordance withthe Operating Procedures of: r^ "* '

Section 7.0 of the appiifcationi

Model No. LN 10-135A •..""•:.;

LN Technol qgi es %f;jf/c(r:;ati on^Prbcedures WM-02E»rvRev. C,<;

368

Model No. NUPAC 10 /140^ . v ? r jf.%? > g

r12. The ratchet binders on tb^^k'i'Vd.^^^drq'iied'to 100M0 ft-lb. 613. The cask body and eadKcask lid musi^M^arked in accqrda'rice with 10 CFR §71.85(c). E

14. The packages authorized by this certificate must be?transported on a motor vehicle, ^railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vessel |assigned for the sole use o f the licensee, y % *

15. The packages authorized by this certificate are hereby approved for use under the *general license provisions of 10 CFR §71.12. «

16. Expiration date: April 1, 1999. This certificate is not renewable. j*



REFERENCES

Nuclear Packaging, Inc. application dated February 29, 1988.




Scientific Ecology Group, Inc., supplement dated: April 30, 1993.


William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety;afaSafeguards

> Date. _ ...,„„. .„. .......

369

5

£gM

3ggM

i3

g

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M

g









2. PREAMBLE







c. DOCKET NUMBER J J _ g \ JQ

4. CONDITIONS

This certificate is conditional upon fulfilling the requirementsjbf 1CTGFR Part 71, aVapplicableând the conditions specified below.

(a) Packaging < \ >

(1) Model Nos. NlTPAI Z/lOO and LN 7-100

(2) Description.-

Steel encased lead sWefxJed casksvfpr jraq|;4fc;tive matep-ial. The casks areright circular cy l i n l ^ l iw i t h .a^v.j§-inch|'pfby 40.75-%^ IH cavity. Thewalls ofi'the casl^c6^^^n'e%dx>t1fi-c;k'ê%@bf 3f«.00 injpKes encased in 0.38-inch th iek^nneY^ fee l ^ 'h^ shell. The topcover and''cask 6oj£q%a¥e¥^ in thicknessfrom 2.0 tp>3.5 ^"ch.6s^ tjr&ipjrjraaryjcask I r a ^ j f secured to the cylindricalcask body byêigh%?iMy4^fcchMrache^ optional secondary l i d iscentered iri./the prftjaHcfftdr^dîi^s^cufeS^tB the pîipary l i d with eight,3/4-inch studs,and nuts.& Each#,f|I^^ provided witfiâ Neoprene gasket seal.The casks maycb|pprovided witft|4|^ptionaT/12-gaugWstainless steel l iner(seal welded alpngâll edges), an optional lijdênH; line with pipe plug, andan optional 3/4-incn drain line and pipe plug^The casks are provided withfour equally spaced 1 ffting/tie-down; devices. The primary l i d is providedwith three l i f t i ng lug'sVand., the/optional /secondary l i d is provided with onel i f t i n g lug. Each cask has a gross weight of 48,900 pounds.

(b) Drawings


The package is fabricated in accordance with Nuclear Packaging, Inc.,Drawing No. X-20-309-SNP, Sheets 1, 2, and 3, Revision No. A.

Model No. LN 7-100

The package is fabricated in accordance with LN Technologies CorporationDrawing No. 5025-M-2005, Sheets 1 and 2, Revision No. 0.

370

az at az : az az at a/:at a£ araTar az az at a< az at a? agac 3atc az c at at w at w at a? WaT. warNRC FORM 618A(3-96)



5. (c) Contents'


Dewatered, solid, or solidified wastes, or activated solid components, insecondary containers, and limited to the following:

(i)

(ii)

Materials in which the radioactivity is essentially uniformlydistributed and in which the estimated average concentration pergram of contents does not exceed:


0.005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more>than 0.05 curie, but notmore/than 1 curie; or

,, 0.3:-ml\licurie of radionuclides forrwhich the A2 quantity in-Appendix A of 10 CFR Part 71 is more than 1 curie.

., Objectsvof jnohradixo'active .material externally contaminated with

... radioactive material, providetl|that the radioactive material isnot readily; djsperslble and ,§h|: surface contamination, whenaveragedib/er- an!area' of 1 square meter, does not exceed

;.\ O.OOjO^fmlWlc^ per minute) per squarecentimeter "of^.âdionuclidesV for; which the A2 quantity in

-•--<,Appe^.txtôfv^''C|:Rll>art.71 isr'npt more than 0.05 curie, or.,'^^.OOfTînil^G^ji.^l^^.^ppy^^dJ^sijntegratibris per minute) per: .sauare ceritiriieter,- for mother raUionucl ides..( ^ p p ^\ys^n^riy{cQiMMtQT;.0f;:pVc\eT radi

(2) Maximum quantity of mateifiil\ per package

Greater than'Type A,quantity of radioactive material which may containfissile material provided the fissile material does not exceed the limitsof 10 CFR §71.53. -The:;defcay heat: load' is limited to 17 watts.

371

B8 NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONg (3-96)

* Page 3 - Certificate No. 9178 - Revision No. 7 - Docket No. 71-9178

h* 6. (a) For any package containing water and/or organic substances which could* radiolytically generate combustible gases, determination must be made by* tests and measurements or by analysis of a representative package such that

the following criteria are met over a period of time that is twice theexpected shipment time:

% (1) The hydrogen generated must be limited to a molar quantity that would be8 no more than 5% by volume (or equivalent limits for other inflammable3 gases) of the secondary container gas void if present at STP (i.e., noS more than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

S (2) The secondary container and cask cavity must be inerted with a diluent toS assure that oxygen is limited to .5% by volume in those portions of theS package which could have hydrogen greater than 5%.S • • '

S For any package delivered to a carrier for transport, the secondary containerg must be prepared for shipment in the same manner in which determination forS gas generation is made. Shipment period begins when the package is prepared£ (sealed) and must be completed within twice the-expected shipment time.H

g (b) For any package shipped within 10 days of preparation, or within 10 daysg after venting of driims ,or other'secondary/cbntainers, the determination inH (a) above need not be^made, and>the timeirestriction in (a) above does not

apply. . " . •" ' ,: • -T-W« V * - */.-;- ' •"• .•.y X ;#' f

7. Maximum gross weight5:of,,the.contents, secondaryTcontaiiners, and shoring is limitedto 13,000 pounds. -VV,;. ^V:::-.-1 ''.^>V ' y " "':

8. Except for close fitting c.ontenis",,; shoring "mi(st/b!e placed between secondarycontainers and the cask'eaVity, to minimize 'movement during^normal conditions oftransport. ; -'Vi i K

9. The lid and the shield plug lifting lugs must not be used for lifting the cask, andmust be covered in transit. ;

10. The cask must be provided with either (or both) a drain line or a lid vent line asshown in the drawing in order to provide a method to leak test the package.

S•3

3 372








Model No. LN 7-100 :.%'•?.'••' '' '•• '\') \J :

LN Technologies Corporation Procedures WM-036 Rev. A; WM-026, Rev. B: andWM-013, Rev.,F.;>; <-' '•<•-,

(c) The packageJhaTrKbe prepared for shipment and operated in accordance withthe Operating Procedures of: .••;.'s"'.-/ ';/f~-

Model No, NUPAC 7 / l t T q S ^ \ C^'t / /%W :' "

Section 74) of the Implici t i

Model N6.:LN 7»'**

LN Technologi

12. The ratchet binders on inecasK ilagmustvpeôrqued to ioo±io f t - l b s . tfj

13. The cask body and'e,ajjf) cask l id mils^/ê||arkecIAlfn accordance with 10 CFR §71.85(c).

14. The packages a u t h o r i z e d ^ th i s ce r t i f i ca t e must bel^ransported on a motor vehicle,rai l road car, a i r c ra f t , in lan^watercraf t^ oryhdld or deck of a seagoing vesselassigned for the sole use of vthf;itceTisee.,;{ V^

15. The packages authorized by th i s ce r t i f i ca t e are hereby approved for use under thegeneral l icense provisions of 10 CFR §71.12. a

16. Expiration date: April 1, 1999. This ce r t i f i ca t e is not renewable.

nologi e s ^ r ^ f a t i opv Prclceûres^ WM-025^Rev. G?'1

inders on lî^casTk"iidl5must^be%oraii^ to lObilO

373

NRC FORM 618A(3-96)



REFERENCES






Date:

FOR THE U.S..NUCLEAR REGULATORY COMMISSION

William D. Trovers, DirectorSpent Fuel-Project Office1

Office of-Nuclear Material Safetyand,Safeguards * '

' • / <

J '"* * - }"'•'

374

waott a? ag




I, a. CERTIFICATE NUMBER

9179

b. REVISION NUMBER

7


USA/9179/A

d. PAGE NUMBER

1


52. PREAMBLE









(a) Packaging

(1) Model Nos.: NUPAC 6/100L, NUPAC 6/100H, LN 6-80L, and LN 6-80H

(2) Description * ^ .

Steel encased lead shielded casks for radioactive material. The casks areright circular cylinders; with a;-61.p-inch.~ip by 62.0-inch IH cavity. Thewalls of the casks contain a lead.thicknessi5r"anging from 2.43 to 3.56 inchesencased in 0.50-inch^hic;k'-inneV steel shells and 1.13-inch thick outer steelshell. The top .covpranrf'cask bottom are fnade, up of two steel plates rangingin thickness from '.2.0, to-fyO inches. ; .Tire primary cask lid is secured to thecylindrical cask bpdyi^y eight, 1-1/4-inch ifachet binders. An optionalsecondary lid is Centered;in the primaVy I/id arid is secured to the primarylid with eight, 3/4-inchNstuds-amk"nuts! ~ Each lid is provided with aNeoprene gasket seal. the caj>ksjj% be provided with an optional 12-gaugestainless steel liner (seal weWed;;;aTong all edges), an optional lid ventline with pipe plug, and an optional 3/4-inch drain line and pipe plug. Thecasks are provided.with four equally spaced lifting/tie-down devices. Theprimary lid is provided with, three lifting lugs and the optional secondarylid is provided with one lifting'lug. The casks gross weights range from42,900 to 53,900 pounds.


NUPAC 6/100L, LN 6-80L 69.11NUPAC 6/100H, LN 6-80H 71.37

Lead Tk,inches

2.433.56

Top Tk,inches

4.56.0

Bottom Tk,inches

4.56.0

Gross Wt,pounds

42,90053,900

375

wwwwwW-rawwwwaigEag^wwwaEC


3

rie oj 'isfadil- islides for which) the Ag quantity inj. Appendix A of lO^CER? Part?71'i-symore-thari^ 1 curie.

* (ii) Objects,;of nonradioactive material} externally contaminated withradioactive, material, prqyided^that the radioactive material is



5. (a) (3) Drawings

The packages are fabricated in accordance with Nuclear Packaging, Inc.,Drawing No. X-20-310-SNP, Sheets 1 and 2, Revision No. A.

Model Nos. LN 6-80L and LN 6-80H

The packages are fabricated in accordance with LN TechnologiesCorporation Drawing No. 5025-M-2005, Sheets 1 and 2, Revision No. 0.

(b) Contents

(1) Type and form of material <

Dewatered, solid, or solidified wastes, or activated solid components,in secondary containers, and limited to the following:

(i) Materials in which the radioactiy^tyîs essentially uniformlydistributee},and in which the estimated average concentration pergram of conterits does-no^ exce.e%|-/ <•-"•

0.0001 m|3|f%urie of" raîonuc%iq'is for which;the A2 quantity inAppendix cA2p'£30-CFRvPaYt 71 li'spnot more than; 0.05 curie;

\ J(>; *** " C ' • '•/ ~ ' \.s>" v ^ "' ' ''' ••

g 0.005 miXIivbfAjk. of radiohuc1tTdes^6i0'which the A2 quantity inAppeh j AVof JO; CFR Rayit'^ris more than ^0.05 curie, but not

„ ... m o r e "tfiiari • l . ' c u r j . e ; ! o r t! sÔ^.. , . . ' / - ' •••-'

g 0 . ; 3 mi H i c u r i e

, p qnot readily dispersible-and thev surface contamination, whenaveraged over ansareavof 1*square meter, does not exceed0.0001 millicurie (220,000 disintegrations per minute) per squarecentimeter of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie, or0.001 millicurie (2,200,000 disintegrations per minute) per

i h d i l i d

iH

i5 square centimeter for other radionuclides.

* (2) Maximum quantity of material per package

Greater than Type A quantity of radioactive material which may containfissile material provided the fissile material does not exceed the limitsof 10 CFR §71.53. The decay heat load is limited to 9 watts for theModel Nos. NUPAC 6/100L and LN 6-80L casks and 61 watts for the ModelNos. NUPAC 6/100H and LN 6-80H casks.

n

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NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96).




(2) The secondary container and cask cavity must be inerted with a diluent toassure that oxygen is limited to 5% by volume in those portions of thepackage which could have hydrogen greater than 5%.

For any package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination forgas generation is made. Shipment period begins when the package is prepared(sealed) and must be completed within twice the expected shipment time.

(b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drums; or other secondary containers, the determination in(a) above need not be xmade, and the time restriction in (a) above does notapply. ;•--.="-' 7 x-; ••

7. Maximum gross weight of .tlje contents, secondaryxohtainers, arid shoring is limitedto 15,000 pounds. '; • ; • t'

8. Except for close fitting-consents,: shoring must be'placed between secondarycontainers and the cask cavity,tominijnize movement during normal conditions oftransport.

9. The lid and the shield plug lifting lugs must not be used for lifting the cask, andmust be covered in transit.

10. The cask must be provided with either (or both) a drain line or a lid vent line asshown in the drawing in order to provide a method to leak test the package.

377?M.2&2BJ&2B.MJ&.2&JSJ&J&J&J&J£U£J&?WWW7K?W7K7&J^^





LN

12. The ratchet binders>on t^^^'^ftf'^tvjbe^tfiipiife^to lOOllp ft-lbs.

13. The cask body and each cask lid" mu^b!e\ftarked -in[.accordance with 10 CFR §71.85(c).

14. The packages authorized by? this certificate must be'transported on a motor vehicle,




Model Nos. LN 6-80L and 6^80H

LN Technologies Corporation Procedures WM-036, Rev. A; WM-026, Rev. B; andWM-013, Rev. F / v V " *''<',

(c) The package shallJbe prepared for shipment and operated in accordance withthe Operating Procedures of: .-;•;.'••";/"'

\ Model Nos. NUPAC 6/i0QMnd^NUPAC-r6A100H'

Section 7.0 of the application.:

Model Nos:. LN 6-rl

railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vesselassigned for the sole use of-the Ticensee.; \ ,/*"-



3

* 378

NRCFORM618A(3-96)



REFERENCES


Supplements dated: April 19 and 26, 1988; and February 16, 1993.





William D. freivers, DirectorSpent Fuel Project OfficeOffice* of NtfcTear Material Safety

/ and Safeguard

Date: i •' --'

, ' • / -

C :•/

379

^NRC FORM 618(3-96)10 CFR 71




9183

b. REVISION NUMBER

12




41. PREAMBLE




Nuclear Assurance Corporation655 Engineering DriveSuite 200Norcross, Georgia 30092

Nuclear Assurance Corporation applicationdated May 26, 1989, as supplemented


3

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(a) Packaging

(1) Model No.: NAC-1

(2) Description ~ V ^ > '>&''

A steel-arid lead s|l#l^d'shipping caskS ^he cask is a right circularcylinder with uppejpMgfr'lower steel encasexJVbalsa impact limiters. Theoverall dimensionsvlcet214 inchestin.lerig|h and 50 inches in diameter.The gross weighfeipf^the'-cask is approx$inta$ely ,49,000.pounds. The innercavity is" 178 irtches long/ahd"13".5 inched in/id^ameter.r The thickness ofthe inner shetll is.'S/161 Inch, and tH^thickni%y of the outer shell is1-1/4 inches. TihVtVfp stainless steel shelWare welded to a 2-inch thickstainless steel shieid;disc at :the bottom. .'The anriulus between the innerand outer shells is filled with* |^ad (lead thickness: 6-5/8 inchesmaximum, 5 inches minimum). '/;jV;;; '' "••' "}j

The stainless ste§l lid is a frustum of a cone 7.5 inches thick. The lidis secured to thecayity flange by six,. ASTM-A320, Grade L43, 1-1/4-inchdiameter bolts. The seal is .provided by.two polytetrafluoroethylene0-rings. Four trunnions, two located oh either side of the upper or lowerimpact limiter, are provided. Other cask features include two drainvalves located in the bottom shield disc, vent valve, head closure gasketleak check valve, and rupture disc - pressure relief valve system locatedin the cavity flange. For transport, the cask may be enclosed in anexpanded metal cage or closed shipping container.

380^lf\JK,lf\/K TfyjS. , 7SJSUSJSUSUSJSUSUSUEJSUSJBJSUSJSUSUSUKJSJSJSZ

NRC FORM 618A(3-96)

Page 2 - Certificate No. 9183

5.(a) (Continued)


Revision No. 12 - Docket No. 71-9183

(3) Drawings

The Model No. NAC-1 shipping cask is constructed in accordance withNuclear Fuel Services, Inc., Drawing No. E 10080, Sheets 1 through 4,Rev. 22.

(b) Contents

(c)


(i) Clad, irradiated, metallic natural uranium fuel rods,

(ii) Solid, non-fissile, irradiated; hardware.

(2) Maximum quantity-of,,material per package .

The cavity content must not exceed a thermal decay heat load of 750 wattsand a weight of 3,700 lbs., including weight of component spacers (or fuelbasket) used in. the cask cavity to limit movement of contents duringshipment; Fuel rods ,are additionally limited; EIS follows:

(i) 21 intact roq\s"Jijr 6 encapsulated (defective) rods. Each defectiverod will beêncapsulated:in/either; a>2.75-inch i.D. failed fuel rodcan, as showriton 'Nuclear Assurante^Gtfrporation Drawing No. 340-108-D2, Rev. 9, brâ^4:0.0-inch'I.D. fauifed fuel rod can, as shown onNuclean AssWanqe^Cqrporati on/DraWing No. 340-108-D1, Rev. 9.Defectiye r^ds*encapsulated in fhe 2.75/inch I.p.. failed fuel rodcans wiil.b.e<sjiipped,.iris!ai; six-rod capacity liner, as shown onNuclear Afsurance/Cwporatibri^Draw^ng No. 491-001, Rev. 0., anddefective rods encapsulated:ih'thê 4'.00-inch I.D. failed fuel rodcans will be shipped^riia^three rod capacity- liner, as shown onNuclear Assurance Cdrp^faîbn Drawing No. 347-211-F19, Rev. 5.

(ii) 1,600 MWD/MTU average burn-up. *

(iii) Minimum 365-day cooling time after irradiation.

Transport Index for Criticality Control


381

i

wwwaraYWWWWWWWWWWwwwwwww)

Hydro test to 30 psigReplace seats and seals g

£ " ' . . V '"'". : ' • • • - • • • • ' • v J

Test to 30 psig\Test to 100 psig*



8. The cask may be shipped in a closed shipping container provided that the closedcontainer, the cask tie-down and support system, and the transport vehicle(trailer) meet the applicable requirements of the Department of Transportation.Tie-down devices which are a structural part of the package must comply with10 CFR §71.45.

83

H

££ 9. When the cask is shipped in a closed shipping container, the center of gravity£ of the combined cask, closed shipping,container, and trailer must not exceed 75wJj

£ 10. When the cask is shipped in a closed shipping container, the internal heat load£ must not exceed 750 watts.

11. In lieu of the requirements of 10 CFR §71.87.(e), the licensee must performperiodic maintenance/Shd,testing of 0-rings, drain;afrid vent ball valves, reliefvalves, and rupture discs;of the cask as indicated;in the table given below.

,- inches.

H

M

88

Test /Action

, p gDuring inactive periods^ $he maintenance and testing frequency may bedisregarded provided thatHhe package is brought.into full compliance prior tothe next use ..of the package: * . ' ? |: '

Cask Component

Ball Valve ", •Ball Valve ' v; '

0-rings0-rings

Inner Containment Vessel

Cavity Relief Valve

Cavity Rupture Disc

Neutron Shield TankRupture Disc

Impact Limiters

;;'%, -Period ' -,..;V:

'••' '''?•.> l < ":V-Y,'/;\vt : Each Shipment

/Annually ; ,

' \ , Eae|i ,.Sh*i pment^AnnuaTTy -;

Annually

Apnually

Annually

Annually

Annually

8

8H

8

8Test to 5 psig

£

5

6. The cask cavity must be dry (no free water) when delivered to a carrier for g» transport.

7. As needed, appropriate component spacers (fuel basket and axial spacers forshipment of fuel rods) must be used in the cask cavity to limit movement ofcontents during accident conditions of transport. g

£

Test to 100 psig* g

Test at set point

Replace

Replace

There must be no visual (pressure gauge) indications of pressure drop for thecomponent under test during a 10-minute test period. Otherwise, correctiveaction must be taken and the test repeated until such time as the componentmeets the specified tests. (Test to pressures equal to or greater than thoseindicated.)

g

382

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NRCFORM618A(3-96)



12. The package shall be prepared for shipment and operated in accordance with theoperating procedures in Chapter 7 of the application, as supplemented.

13. Each package must be maintained in accordance with the maintenance program inChapter 8 of the application.



REFERENCES

Nuclear Assurance Corporation application dated May 26, 1989.

Supplements dated January 29 and March 20, 1990; and August 4, 1994.


Date:

William D. Trayers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety. and Safeguards : { :

383

NRC FORM 618(MS)10 era 71


FOR RADIOACTIVE MATERIALS PACKAGES1 a. CERTIFICATE NUMBER


3


USA/91fif/B(U)d. PAGE NUMBER 0. TOTAL NUMBER PAGES




3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DES1GN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Nuclear Packaging, Inc. consolidated applicationdated March 31, 1989, as supplemented.

Ir9;184"c. DOCKET NUMBER

4. CONDITIONS < x %^p Qt v

This certificate is conditional upon fulfilling j h t f requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

feP^MW^i"

(1) Model|No.:

(2) Description

The p|ckaging\igpOH) efi&osecNtrl(32.5" OD xa undeCyjedand fou r^ fsample cask.to absor*"'

„ 'Vvessrel; (20.5" OD x 23.4"|mcJ radiation shield

is contained withiniodinirjeol lection cartridgesthe f oanT'shoring above the

L%"the waterthe secondly^containment'

-^m- the pepi'meter of the sample caskegk|ge occurJ^Completely surrounding

nd radiation^hield is a foam filledsteel encased^erpack (48.6"" OD x 66.0" QH^Wich provides impact andthermal protectionv., v ^

The primary containmentXv#sl£r, Irthfch is constructed of 304 stainlesssteel varying in thickness from 3/4" to 1.25", is provided with doubleViton 0-ring seals and a sealed test port between the seals for leaktesting. The assembly is secured with eight, 3/8"-16 UNC x 8" long screws.

The secondary containment vessel and radiation shield provides 0.75" thicksteel and 5.1" thick lead shielding in the radial direction, 2.0" thicksteel and 5.1" thick lead shielding on the bottom, and 3.5" thick steeland 4.8" thick lead shielding on the top. The lid is secured with eight,1.0"-8 UNC x 3.0 long bolts. The lid is sealed with two Viton 0-ringswith a sealed test port between the seals for leak testing.

The overpack provides about 7.25" thick foam on the sides and about 13" onthe top and bottom. The two halves of the overpack are held together byeight, 3/4"-10 UNC x 1.5" long bolts. A Neoprene gasket prevents rainwater from entering the overpack.

The weight of the package including a maximum sample cask weight of 1,375pounds, is about 12,800 pounds.

384J^^

^

NRC FORM E18A(6-83)

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itt

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Page 2 - Certificate No. 9184 -

5.(a)(3) Drawings




(b)

The package is constructed in accordance with Nuclear Packaging, Inc.Drawing No. X-20-218D, Sheets 1 and 2, Rev. C.

Contents


(i) Radioactive material in form of liquid or gaseous samples in samplecasks, cartridges and v ia ls .

( i i ) Byproduct andresins,containers..

(2)

as solids and process solids orolidified in secondary

Maximum quanimjy of material per package

50 Ci of m<fxt'd_ fission and activation products^lSfnHlli l i ters of liquid,one sampjB^ca

In addition to^the reqprior to firsi?=use mustSection 8.1>(|mast be mafprepared for shipmentîrfsupplement d'ated Jul

The packagegeneral l

I Ul I dMU dLLIVflLIUII (J[ uuui-i.i^niu;iiii I I I M L C I O UI I II_|U I U ,

secondary container and^fodr carct*lidges and four vials.

CFR Parf^l, each packageand criteria specified inSection w-2, and must be.Oôf the=application, and the

8. Expiration date^^July

for use under the

Nuclear Packaging, Inc. consolidated application daêd Ma¥ch 31, 1989.

Supplement dated: April 7, 1 9 8 9 . ^

VECTRA Technologies, Inc. supplement dated: July 8, 1994.


K. ^

tJUL 2 7 1S94

Cass R. Chappell, Section LeaderCask Certification SectionStorage and Transport Systems BranchDivision of Industrial andMedical Nuclear Safety, NMSS

Date:

385

^

NRC FORM 618

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES9 1.H.CERTIFICATE NUMBER

9185b. REVISION NUMBER C. PACKAGE IDENTIFICATION NUMBER



2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theappiicabiesafety standards set forth inTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DESIGN OR APPLICATION 'a. ISSUED TO Warns and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


X >

Industrial Nuclear Company applicationdated October 13, 1983.

71-9185-C. DOCKET NUMBER

4. CONDITIONS ^ '%J "" "'^<^/i <.This certificate is conditional upon fulfilling^he'Tequirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.(a) Packaging

(1) Model No

(2) Description

ProtectijVjT overpgck %6§.consistsrofhaving ^cl amp-ri ng" type^|^ic|/(:|6rsu^i( l\ J|^j

device./ The overpacksteel drum

a 12-gaugedeyjce is centered

the exposure

(3) Drawings

The overpack i^constructed in accordance with. Industrial Nuclear CompanyDrawing Nos.: 10Q.-4, Rev. 2, dated NovemberN4^»t992; and 100-4(A),Rev. 2, dated August 3IL1992. j-~?

3 8 6

^



(b) Contents




120 curies

6. The sources must be contained withinr,the»-.Mpdel No. IR-100 packaging inaccordance wi th Certi fi cate of Colripl fane! &f. ,#157.

7. The name plate on the pyiVpack must be fabricatecN)?/ materials capableof resisting the fireOte'st of 10 CFR Part 71 and maiatajning its legibility.The two vent holes^'nHhe side of the overpack must befcpvered with tape orrubber (plastic) plugs to prevent entry of rain water.,,~'-'v;

8. In addition tojthje reqlkr.e.me.rvts of Subpart G o£4iQ^JFR Part"71, each packagemust meet the a.cceptance^t^tsv.and maintenancefiffij&jram, andvshall be operatedand prepared for shipment^jtilacGordJuvc^viiith ttfe^gerating procedures in theapplication document entiîête/'OperatîîgiProce^ês, Acceptance Test, andMaintenance Program," Rev|s~ipn 1, dltedôveifib'eil^l 1992, as-~suppl ementedDecember 15, 1?§2. *• «~* N v ^ - — * — i - * - ^ * ^ ,

9 Thethe

itenance Program," Rev s~ion 1, dlted^Noveiribeife^ 1992, as^supplementedimber 15, |9§2. A '^&^>~~^J^0 f / / S

packaging %uthori^|dvpy. tVgX^rtjifiida^ffs he^p>âpprpy.^ for use undergeneral license prpvWplis pfJi;d!aW:§Mxl2. i$W ^ '

ration date:..^3anuar^lT^998^^|^îxv '^fi* e,-.'10. Expiration date:.,>j

Industrial Nuclear Companyâptflication dated December 23X"1981.*

Supplements dated: May 28, 1982*; \6ctj&eryI3-, 1983 \tvio letters)*; April 26, 1991;and March 20, June 25, September 4, November*4, Kahd December 15, 1992.

*See Docket No. 71-9157.


JAN i 1393Date:

Charles E. MacDonald, ChiefTransportation BranchDivision of Safeguards andTransportation, NMSS

387

? ^

I

i\iii

iI\i

i

ii

;i

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I

!

NRC FORM 618

10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES\ a . CERTIFICATE NUMBER



USA/9186/BMFd. PAGE NUMBER

1a. TOTAL NUMBER PAGES






Safety Analysis for Shipping S8G Power Units inthe S-6213 Container, Rev. 7, datedJune 16, 1975,as supplemented; and Safety Analysis for Shipment^ ^ b Power Units in the Model 2

c. DOCKET NUMBER J ] Jg. ] ' ;

4. CONDITIONS ~ %$ ~" <^; ^This certificate is conditional upon fulfilling,th»requirements of 10 CFR Part 71, as applicable, and the/conditions specified below.

(a) Packaging

(1) Model No^f Mode^^Sr6213 Power Unit^

Model J1&6213 S^r) Ur

(2) Descr

Jf-7a power unitmecRanisms installed.complete~with

The Models Sapproximately 9-rJ/4""fdetincluding^nemj spheric^,outside diame'ter central

fer by 3j4V2 feet long,limiters^with 10-3/4-foot

.._.„_ „_ „ the barrel and cover halves.The Model 2 S ^ 1 3 PUSC is of the same designVs the Model 1, except thatthe primary contiiner^ material is HY-80 stlfr. A power unit is supportedin the PUSC by a ceiEr-alty 1 oeatedj;h4fe| circular steel plate (PU head)which is clamped betweerr-^e^c^n^cCI nrafing flanges of the PUSC andfastened by 94, 2-inch diameter high strength studs. The upper and lowerextremities of the power unit cantilever into the barrel and cover halveswithout additional support except for the longest control rod drivemechanisms (S8G Power Unit Type B only). A lower support adapter isinstalled in the barrel end of the container during shipment of the S6Wprototype power unit and the S6W shipboard power unit.

The PUSC is shipped in the horizontal position on a support frame whichis secured to a specially built flatbed rail car. The PUSC, includingframe and contents, weighs approximately 490,000 pounds for shipments ofType A and B, S8G power units.

The weight of the PUSC, including frame and contents is approximately438,900 pounds for shipment of the S6W prototype power unit and 429,900pounds for shipment of the S6W shipboard power unit.

3 8 8

}li9AMiW&l*&Wifytfiafii®^^

NRC FORM 618A(B-83)



5.(a) Packaging (Continued)

(3) Drawings

The Model 1 and Model 2 S-6213 PUSC are constructed in accordance withthe Drawings included in the applications (see references, below).

(b) Contents


(i) Unirradiated Naval Reactors Type A or B S8G power unit as describedin Chapter 5 of the application and containing uranium enriched inthe U-235 isot^p^ HEG(j

(ii) Unirradia£sd\,S6"t? advanced fleet rea&Mf prototype power unit orunirrad*a%eS S6W advanced fleet reactor* mpboard power unit asdescr^foyf in Chapter 6 of "S6W Prototype i@er Unit in S-6213 PowerUni t a p p i n g Container Safety Analysis Repoj^" WAPD-REO(c)1219,

(iii)a O e s c r i befiD-6213 P

:kaging,"jnium &

(2) Maximuifts/quant

For the Cfoel

containing uranium

performan

Sh

p g ^ ()d 4-n^the U-235 isotope.

core sb#oboard power unit,of "S6W Shipboard Power Unitr Safety tlysis Report For

containing

One Type ATJ8G PoW§r Urtit,(One Type B^fae.Power Unit,One S6W A d v a n ^ Fl eet Reactor'Wototype PowervWit, orOne S6W AdvanceVpeet Reactor Shipboard Powi^Unit, orOne S6W High Performaneie Fl,eet Core.Shiifapard Power Unit.

For the Model 2 S-6213 PUSC!

One S6W Advanced Fleet Reactor Shipboard Power Unit, orOne S6W High Performance Fleet Core Shipboard Power Unit.



The Model 1 S-6213 PUSC shall be designated as B( )F. Use of Model 1 S-6213PUSC packaging fabricated after August 31, 1986, is not authorized.

All control rods shall be restrained in the power unit fuel cells by thecontrol rod holddown latches.

3 8 9

Kiif&jaMjrijg&zigjtKiiRimimJl&jBM&JsXBMir&iw&i^



8.



For the Model 1 S-6213 PUSC, in addition to the requirements of Subpart G of 10CFR Part 71, a determination shall be made, for each shipment, of the "g"forces that the package or packaging has been subjected to during transport.

(a)

(b)

A nondestructive examination of the entire length of both inner and outersurfaces of the four tie-down support bracket-to-container wall buttwelds shall be conducted:

(1) if the packaging (with or without contents) has been subjected to"g" forces in excess of 2 g's in any direction through the centerof gravity of the package since the last inspection, and

(2)

(3)

following the fourth shipment , and

after every %c&fiyBshipment T o U ^ n g the fourth shipment.

The nondestr%c%rVe examination in accordance Jfy]\ a written procedure maybe by eitF

«^

penetrant method in accoj:

^Section V, AS)

(ii)

(iii)

esting Requirements for1973, or-

ection 12.5

(YokerPechnique; Dry Particle

p y 4.3.1 (General) andO (coatings), 4.3.3 (Dry Powtflr), 4.3.3.3.6 (Continuous),

and^.3.^3 (Procedure) as^cepted by using direct orrectifie^cu^nt^4.-^.3*«"(Yoke Technique), 4.3.2.5(sensitivity eSid trearfing), and 4.3.1.3 (smoothness), or

NAVSHIPS 250-1500-1, Section 12.4, 12.4.1 (General), 12.4.3(Dry powder), 12.4.3.3.2.1 (Yoke Technique)using direct orrectified current.

This requirement shall not be construed to require an inspectionif the previous shipment had been inspected in accordance with(8(a)(l)) above.

390.)j3^^ ^

^^

NRC FORM 618A(6-83)



8.(c) If any indications, as defined in accordance with either:

(1) Paragraph UA-93(a), Appendix VIII, Division 1, Section VIII, ASHE Code(with 7(b)(2)(i), above), or

(2) Paragraphs UA-72 and UA-73, Appendix VI, Division 1, Section VIII, ASMECode (with 7(b)(2)(i), above), or

(3) Class 1 acceptance criteria of NAVSEA 0900-LP-003-8000, "SurfaceInspection Acceptance Standards for Metal," with Change 2, July 1, 1974(with 7(b)(l)(ii) or 7(b)(2)(ii), above), or

NAVSHIPS 2 5 0 - 1 5 0 0 - 1 , S e c t i o n 1 0 . 3 * 2 ( w i t h 7 ( b ) ( l ) ( i i i ) o r 7 ( b ) ( 2 ) ( i i i ) ,above), as noted, . a U HtQ I s .

(4)

are detected, the pafkaVn^ shall be repaired fhd</e4nspected prior to use andshall be inspected<$H6V to each shipment thereaft^pfM\ny defects shall bereported in accorjkate with 10 CFR §71.95.

9. Expiration date:

For the Model 1 S-^13 PUSC

U.S. Naval Reactorslappl

Supplements dated: jluneG#C89-2838, dated Y & l lSeptember 5, 1990; NayjtlReactors letter G#C92^02714

For the Model 2 S-6213

ttorsjftter, dated7, 1992; and Naval

U.S. Naval Reactors application GJCJ1-41165, datedjtecember 19, 1991.

Supplements dated: Naval Reactors le'Ser^92^03563, dated June 17, 1992; and NavalReactors letter G#C92-03714, dated October 2, 1992.


- . /'William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

Date: <\\>

391

^

88

M

£

£





9187

b. REVISION NUMBER

3


USA/9187/B(U)

d. PAGE NUMBER

1


22. PREAMBLE






-Tech/Ops application dated December 27, 1983,as supplemented.


4. CONDITIONS .. ,N r-; : V j ) '{' sr-;.,This certificate is conditional upon fulfilling the requirements pf lO^GFR P-art 7i, as applicable/and the conditions specified below.

(a) Packaging ^ 3

(1) Model /No. :-.J65

(2) Description

//;„.

<~?, r>>-

iflA steel encase1i^r(aniu£^h-ieilde'drrSd^:p3raphic exposure device 5"0D;xCl2.25" 1 olg%fThe deyic^ is\priî|ed with d:l88" OD x 9.25"1 ong, hand! 4 anfftwoClv38ll"«v5-l!'"lb1rigftri angul ar35haped 1 egs.

im ry c^pbjnen^ôj^jLst,..pf.,a^6itpf sstee| sheilij internalbracing, o!ep|:eted ' anium|;sHi'e1 | a'rid a^jo^rce tube. The coPrimarybracing, êpIfetedffiâniumjJsHielJll^l^d «^j8yrce tube. The contentsare secure^^p.p,s4'ti ofi'e'dj H ri jjljh sSurce |iuBe^ by a'jsource hoi derasseinBly an^îcjuaj^|<aih!d' :i'ock|ftg^ assembly. Tamper-indi cati ngsealsva're p1J%^4)|^n^H|^)a^lcagx4iig^n1l a 0.122i.:nch thick steelouter%cpver is bc^êd^êrl^n^souirceâctuatdrând locking assemblyfor additional protecta^|a^^ng vtransport^\\Tne total weight ofthe packa|e!,is approximately59 pounds. ^Q-

(3) DrawingsV-

The packaging is constructed ifT'accordance with the followingTech/Ops Drawing Nos.: 86590, Sheets 1 through 5, Rev. 1; 86500-10, Rev. 0; and Amershan Corporation Drawing No. R86591, Rev. A.

392

NRC FORM 618A(3-96)



(b) Contents


Iridium-192 as sealed source must meet the requirements of specialform radioactive material.


240 curies (output)

Output curies are determined in accordance with American NationalStandard N432-1980, "Radiological Safety for the Design andConstruction of Apparftusr;f;or "Gamma Radiography."

6. In addition toNthe requirements of Subpart Gxbf>10 CFR Part 71:-^ ' , 'v "A

(a) Each packaging must meet the Acceptance Tests.-and MaintenanceProgram Hn^Section 8, of the October 29.,^93psupplement.

(b) The" ;p>ckagex"lh>^be prepared fo^shf|ment and'operated inaccordance wi|h^he\ppe^*i"ng Proced#es in Section 7, of theOctober 29, l ^ l ^ i fpp l eminent/ I T^ff >•%

7.

8.

Tech/Ops application dated

Supplements dated: March 15, 1984, November 8, 1§88\ and August 16, andOctober 29, 1993, and November.2,0, 1995., N"

8



Date:

3932£J£J£USL2&7W7W2&2Si79{7!R7Wffl2$S7&7f{J£L23&2&7W

i









2

2. PREAMBLE



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION

a, uoucu IU (jva/ne unit siuuttm/

VECTRA Technologies, Inc.6203 San Ignacio Ave.Suite 100San Jose, CA 95119

o. 11 IL,C rti>L» IUDI^ i ini,Ai ivn vr wiruni ui\nri

VECTRA Technologies, Inc.dated December 21, 1994,


applicationas supplemented.

^CONDITIONS ' ^ ~-r '{"•>: {i:: .y-This certificate is conditional upon fulfilling the requirements of 10 GFR Part 71, as applicable;'and the conditions specified below.

(a)

(b)

'-•-9!Packaging , %x r

(1) Model No.:4;UX-30

(2) Description

Overpacb for SO-iljsfilîWh'^^

''&!

inders. Thelack is a rigp^pteular^cyljnderô^tructed qf-'two stainless steels with th.e vf lmfe ietwe1enw|he s*hpl#filled with'6-inch thick foam•>-.A n nnftx ^|êjêd"and~gli§efed|hori.zpntalc:q.oint permits the top

*wi Â i '>v»-rtivi'rt«»/vi4.'*AP\rt'rtmT£+tirr,ifv-^r* T h e DackaQe " h a l v e s "

pins. The

overpackshells(7.8 --9.8halfare

(3)

The Model No. JJXT30 packagingîs fabricatedînâccordance with VECTRATechnologies, incorporated, Drawing No. X-2dfe235D, Sheets 1 through 3,

Rev. K. ;•;> N v ,..; ; v t t

Contents


UF6 enriched in the U-235 isotope.(2) Maximum quantity of material per package

(i) Model No. 30A cylinder: 4,950 pounds UF6 enriched to not more than5 w/o in the U-235 isotope.

(ii) Model No. 30B cylinder: 5,020 pounds UF6 enriched to not more than5 w/o in the U-235 isotope.

394*^

NRC FORM 618A(3-96)

CONDITIONS {continued) U.S. NUCLEAR REGULATORY COMMISSION




6.

7.

8.

The 30-inch diameter UF6 cylinder must be fabricated, inspected, tested andmaintained in accordance with American National Standard N14.1 (1990 edition).Cylinders must be fabricated in accordance with Section VIII, Division I, ofthe ASME (American Society of Mechanical Engineers) Boiler and Pressure VesselCode and be ASME Code stamped.

When the optional 4 lid lifting clips are used instead of the top lugs, the toplid (cover) must be lifted with a spreader bar (saddle).

In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) Prior to each.shipment, the overpack gaskets must be inspected. Thesegaskets must be replaced if inspection shows any defects or every 12months, whichever occurs first.

(b) Each packaging must meet the AcceptanceiTjests and Maintenance Program ofChapter 8 of the.app;licationf<as supplemented.

(c) The package shalj\fcel prepared for shipment and operated in accordancewith the 0perayni^^pcedure^<'of--ChaRtefi7 of the application, assupplemented..^ ^ " H ; - . - ^ - ^ ;,-,/

(d) Prior to eachishipent^the^stain.less st^'el'components of the packagingmust be .yisual;fi?, inspected.. Packagings 4n;which stainless steelcomponents shdwjpittf^^coxij^sib'nlicrlcjcing, or pinholes are notauthorized-;for t ' t ^ ^ ^ '"v < '

9. The package authorized by this certificate is hereby:approved for use under thegeneral license provisions of 10 CFR §71.12. ^v,

10. Expiration date: February ,28,. 20A1.*. . ~~'~/"-

REFERENCES

VECTRA Technologies, Inc. application dated December 21, 1994.

Supplements dated: February 24, May 24, September 21, and October 31, 1995; andJanuary 12, and March 26, 1996.


Date: May 4. 1996

ililliam D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

395- '^l&2SiI&M7KlKM7&M.m2SU3&3&SU5USU&J£U&J^^





9200

b. REVISION NUMBER

9


USA/9200/B(H)Fd. PAGE NUMBER


52. PREAMBLE






Nuclear. Packaging, Inc., application datedApril 6, 1991, as supplemented.

c. DOCKET NUMBER 71-92004. CONDITIONS C-V. ; V; '' ' . ; -

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable/and the conditions specified below.

5.

(a) Packaging

(1)

(2)

Model No.:;

Description

A stainless steel ^ndiiead shielded shJppinig cask. The contents areshipped dewatered.^hexcaskii'Si;ai,rjgh|?c|-rcular cylinder, 65.5-inch outerdiameter ;'by 2P7V5-inc)1 l;ength. Theâ|ify dimensions "are 51.25-inchdiameter by 192l^5Mricfp3£^ stainless steel innershell, 3.88-ih;cii;th1ek1¥a'd.annulusian'd 2.îlich thick stainless steelouter shell, an0^.Ô,-inchthick! gelded st'ainfess steel bottom plate makeup the cask. bodyVVfA^m%augej.sJ'a1-QJ|:iss?sêel thermal shield surroundsthe cask outer shVifw^th sâriSM^prpyiide'd by a,;wire wrap on a 3.3-inchpitch spacing. The outer i4^fife7^0-inch thicks-stainless steel equippedwith a 300 psig rupture disc'ik/the seal is provided by 2 Neoprene 0-ringssecured by 32, 1-1/2-6 UNC closure bolts. <-/£test port is provided betweenthe 0-rings. The lid is also providedKwitlra vent port. Protrusions fromthe outer cask external cylindrical sur/ace include 2 lifting and 4 t ie-down trunnions, 1 shear block for fi t t ing to the shipping skid, and 16impact limiter attachment lugs (8 at each end of the cask). The impactlimiters are 120 inches in diameter by 75 inches long fabricated from 1/4-inch thick stainless steel and filled with closed-cell polyurethane foam.Each impact limiter is secured to the cask by 8, 1-1/4-7 UNC bolts neckeddown to 1 inch. Plastic pipe plugs are provided in each impact limiter.The overall dimensions of the cask with upper and lower impact limitersare 120-inch outer diameter by 279.5-inch length.

396V^

{•

W W W W W W W W W W W W W W W W W W W W W W J I C

NRCFORM618A(3-96)




A separate inner vessel (fuel/canister basket) is positioned within thecask cavity. The inner vessel consists of 7, 14.5-inch ID by 0.38-inchwall pipes with a welded bottom plate and top end fixture plate whichprovides a 151-inch long cavity for the canisters. The pipe assembly ispositioned within a 50.25-inch OD by 1.0-inch thick steel shell with a2.0-inch thick welded bottom plate. The space between the pipes and steelshell contain stainless steel structural members and solid neutronmoderator and absorber. The top of each tube is shielded by a 10-inchthick stainless steel plug. The inner lid is 5.0-inch thick stainlesssteel equipped with 2, 300 psig rupture discs in series. The lid has 2Neoprene 0-rings and is secured to the inner vessel by 24, 3/4-10 UNCclosure bolts. A test port is provided between the 0-rings. The lid isalso provided with a,.vent (port. : ./

A fuel, filter,:<6r::kri5ockout canister is positioned within the inner vesselwith canister; impact limiters and a top lO.Oînch thick stainless steelshield plugf> Each canister is 14.0-inch OD byl5O.0-inch long by 0.25-inch wall and contains Bora! sheets or B,C rods. ;;Canister containment isnot required with .closure provided by welded-or;;bolted plate with 2 or 4fittings;,'^ ^ - X > ^ ••'••-"'••

The weight of the £as]^( 100,-5pO "pounds)yJiripact limiters (11,700 poundseach), inner vessei^d^pOO pounds), ,.cajfij£ers (1,046-to 1,440 poundseach),, and canlste'ôntents'cUvÔ to |gJ9"4 pounds each) is approximately181,500 poundsti;,^ ^ § ^ > ^ " '"" ;,: / W - . ~:'

(3) Drawings'""' '^".^/^''^MA

( i) The.:packa§|,ng^fSr^6hstitucted-lâpcordance with' Nuclear PackagingIncv, Drawing 'Noy"X-Ô^X^^Sheetsil' throughV7, Rev. T.

( i i ) The canisters are cortst^ycêd in accordance with Babcock and WiicoxCompany(Dfawing Nos.: "ll61299D, Rev. 1;-1161300D, Rev. Bl; and1161301D, Rev. 1,.

(b) Contents


(i) Byproduct and special nuclear material in the form of irradiatedfuel particles, partial fuel rods, partial assemblies, and coredebris. The maximum pre-irradiation U-235 enrichment must notexceed 2.98 weight percent. The average burnup of the fuel materialmust not exceed 3,165 MWD/MTU and be cooled for at least 6.0 years.

3 9 7 5

wWWW w 3E>g>Kat)E>EMB:SiC3E.BB.aKiBicg!C jE.aB.SK W W W W W W W W w W W W W W W W W W W WWWWWWWj

a NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)

i Page 3 - Certificate No. 9200 - Revision No. 9 - Docket No. 71-9200

5.(b)(l) (continued)

(ii) Irradiated core structural components, contaminated defuelings equipment, and filter-aid materials.M

£ Except for close fitting contents, dunnage must be provided ins the shipping cask cavity sufficient to prevent significant movement

of the contents and secondary containers relative to the outera packaging under accident conditions.

a (iii) Byproduct and special nuclear material in the form of internalcontamination inside the inner vessel. Internal contamination shallnot exceed the limits for low specific activity material as definedin 10 CFR §71.4.


Seven fuel, knockout, or filter canisters or any combination thereofwithin the inner vessel. The radioactive decay heat load must not exceed100 watts in each canister. The gross weight of each canister must notexceed 2,940 pounds. ---^7

^ (c) Transport Index for Critical ity Control /'•••;•'

Minimum transport index-tg be shown on \ V'J£>" label for nuclear criticaTity control: r ?*%•'*' 100

* 6. The cask cavity and inner vessel must be d^,when/delivered to a carrier for3 transport, except for free water which may-;be present following drip drying of

the canisters for a minimum of 2 minutes after removal from the storage pool.The canisters must be'lpaded .and dewatered;:inaccordance .with Section 7.1.1 ofthe application which includes approximately 2 atm of argon, nitrogen, or heliumcover gas. The cask cavity and injief,vessel,must be filled with argon,nitrogen, or helium.at 1.0 atm pressure. ' :


3 (a) Prior to each shipment, the inner and outer lid seals must be inspected.3 The seals must be replaced with new seals if inspection shows any defects3 or every 12 months, whichever occurs first; andM3 (b) Each package must meet the Acceptance Tests and Maintenance Program ofg Section 8.0 of the application.

£ (c) The package must be prepared for shipment and operated in accordance with£ Section 7.0 of the application.

B 8. For any canister containing water and/or organic substances which could radio-g lytically generate combustible gases, a determination must be made by tests and£ measurements or by analysis of a representative canister that the following3 criteria are met over a period of time that is twice the expected shipment time:i

s3

* 398a

NRC FORM 618A(3-96)



8. (continued)

The hydrogen generated must be limited to a molar quantity that would be no morethan 5% by volume (or equivalent limits for other inflammable gases) of thecanister gas void if present at STP (i.e., no more than 0.063 g-moles/fr at14.7 psia and 70"F); or that oxygen is limited to 5% by volume in those portionsof the canister which could have hydrogen greater than 5%.

For any package delivered to a carrier for transport, the canister must beprepared for shipment in the same manner in which determination for gasgeneration is made. Shipment period begins when the canister is closed and mustbe completed within twice the expected shipment time.

9. BoK torque:

The outer cask lid must be secured by 32, ASTM A320, Grade L43 (Cadmium plated),1-1/2-6 UNC-2A x 5.5 long bolts torqued to 780-945 ft-lbs (lubricated).

The inner vessel lid must be secured by 24, ASTM A320, Grade L43 (Cadmiumplated), 3/4-10 UNC-2A x 2.25 long bolts torqued to 130-158 ft-lbs (lubricated).

The upper and lower overpaok limiters must each be secured by 8, ASTM A320,Grade L43 (Cadmium platedK 1-1/4-7 UNC-2A x 41.75 long bolts torqued to 225-270ft-lbs (lubricated). .; j .- ''

10. Except for the contents specified in 5.(b)(l)(iji), prior to each shipment, thelicensee must confirm,;thatUhe cask and inner vessel are properly sealed bytests as specified tn1 Appendix^. 4 or Section 8.2.2 of the application. Thetest is satisfied if.no leakage.is detected using'a test with a minimumsensitivity of lxlO"3:jatm-'em3/s.,

11. The neoprene 0-ring seals5 used in. the containment vessel closure must be fabri-cated from neoprene material specified as. Cascade Gaskets compound numberCG 100-111-60.

12. The licensee may use a/tarpaulin to cover the cask during time of transport.

13. The package authorized by the certificate is hereby approved for use under thegeneral provisions of 10 CFR §71.12.

14. Effective date: April 1, 1996. Expiration date: April 1, 2001.

399



REFERENCES

Nuclear Packaging, Inc. application dated April 6, 1991.

Supplements dated: April 9 and 15, 1991; and February 21, 1996.


U\

William D. Travers, DirectorSpent Fuel Project OfficeOffice; of Nuclear Material Safety: and "Safeguards/ ;

Date > yyy- \ ^ vo . - <

<•<:'• •

400I2IS.7IC

jjtnsrwsrsnsnifwNRC FORM 618(3-96)10CFR71



1, a. CERTIFICATE NUMBER

9202

b. REVISION NUMBER




41. PREAMBLE






Transnuclear, Inc. applicationdated January 19, 1989, as supplemented.


4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No.: TN-BRP-.

(2) Description V., .--. •

The TN-BRP is a rigntlcircular cylindrical-xask designed for shipment ofup to 44 BWR spent-fjjei assemblies. The|total weight .of the package isapproximately 215,000; boiinds. This.:lncXddes the payload capacity of41,250 pounds. -Vine oveWTl dimerisipris-;Of the/package, with impactlimiters,are 244^5iincHes long b^,131- inches^diameter. The cask body is190.5 inches loog;b^.'83.'25 inches^in.diame'ter. The cask has a cylindricalpayload cavity which is"171 'inchesTorig and 64 inches in diameter. Thevolume of the cavity is,r aRpiri^iinately ,185:

Jcubic feet.

The containment vessel consistsvrif a 9.62-inch thick forged steel (ASMESA-350; Grade LF3) cylindrical shell, with bottom plate and lid. Thebottom plate and lid,are made from 9.75-inch thick steel (ASME SA-350,Grade LF3). The 74.7E>-inch,diameter lid.is bolted to the cask with forty-eight, 1-5/8-inch diameter;steel (ASME SA 540 Grade B24, Class 1) bolts.The cask is sealed with a viton 0-ring mounted in a groove machined in theunderside of the lid. The containment vessel is provided with access andvent ports in the lid, and two gas sampling ports and a researchinstrumentation port in the cask body.

The spent fuel assemblies are housed in a specially designed 44 compart-ment fuel basket. Each compartment can accommodate two BRP fuel assem-blies stacked end-to-end. During transport, one-half the compartments areloaded with, spent fuel and the remaining with stainless steel inserts.Peripheral inserts fabricated from an aluminum alloy are positioned be-tween the fuel basket and cask cavity wall.

401





The cask is provided with steel encased balsa-red wood impact limiters.The limiters have an outer diameter of 131 inches, an inner diameter of 91inches, and a thickness of 20 to 26 inches. Each impact limiter isattached to the cask by four equally spaced 2.25-inch diameter bolts. Theimpact limiters are also connected to each other with fourteen 1.50-inchdiameter tie rods.

The cask has four lifting lugs welded to the lid, and four lifting/tiedown trunnions bolted to the cask body.

(3) Drawings ., — - ....

(i) The packaging ^'constructed in ac'c^dance with the followingTransnuclear, Inc. Drawings: "sv •>

3024r150-l, Rev. 2 Longitudinal Section ,3024-150?2^ Rev. 4 Transverse Section •'<•"-.3024fl50^J^gej/. 2 Shell and Bottom^ 'y3024>150-%Rey>v2 Lid .-*''%&?

jj MujT-iJu-iv.,.:\xc^,^:$,p\; •;ImD'a;G,te;;L\mjitej*''Spacer~s~::,~ inoAicn i"n:«n-'---^o-"; \l^r^er'6ds^&^Tierod Bracket

30.2,4-150-6, JRS/^430241507 $i0'3/

, J p ; } p j f |3024-150-7, $i0'3/ f*. Rear Impaeifijfimiter3024-150^11 - ^ ^ > vPaekagfng?genetrati

•3024-150^11,^13024 ' *3024

3024-150-26if Revv, 0

3024-150-27., Rev. 0

l iTJ^niofr ShqulSer Bolt;i ^ e

:?Mf|l?!$ Impact Limiter;/& Tierod Bracket/.;/*! «mss"emfeTy.v '' -""'^ Re'ar Impact Li miter & Tierod Bracket

Assembly C<>3024-150-31, Rev'. 0 Attachment/Bolt3024-150-32, Reyf 0 "v V-Dtsc*Sprang

(ii) The fuel assembly basket is constructed in accordance with thefollowing Transnuclear, Inc. Drawings:

3024-150-8, Rev. 1 Basket General Arrangement3024-150-9, Rev. 0 Basket Cross Section3024-150-10, Rev. 1 Basket Plane View3024-150-15, Rev. 0 Type A and B Spacers3024-150-17, Rev. 2 Basket Peripheral Inserts3042-150-18, Rev. 2 Fuel Replacement Inserts

5.(b) Contents


«

»

K

402

W7^7SJQ7W7W7W7W2£!j!U£JW71K7W7ft7W7f!U£i2ikJ^^

:wwwwwwwwww.atwwsK:at»£:NRC FORM 618A(3-96)



(i) Irradiated BWR uranium oxide fuel assemblies as described in theapplication and including the following specifications:

AssemblyType

BCDDEFD(EG)EP

Array

11x1111x117x78x89x99x99x99x9

Pelletdia. fin.)

0.275/0.3730.275/0.3730.6200.5000.4710.4710.4710.471 . ,

CladThickness

0.0340.0340.0400.0350.0400.0400.040^0.040

Rod0D fin.)

0.344/0.4490.344/0.4490.700Q.5700.5620.5620.5620.562

0.5770.5770.9210.8070.7070.7070.7070.707

MassfU) Kg

132121133113141137136118

The BWR fuel assemblies/have a maximum burnup of25,000 MWD/MTU.The minimum cool ing time for any assembly is fourteen years.


(i) Forty-four{BWR;assembl ies. "?.•:. „-•

pa

6.

7.

(ii) Maximum decay^heat per package nq|^|p: exceed 3.1 kilowatts.Maximum 103 $at.fs per BWR assemb1yj|\

(iii) Above fwei\ass^mji4,es to be positioned in the fuel baskets asshown i !T-tK'e, drawings' referenced;^ n £ (a) (3) (i i).

(c) Transport Index:for Cptie%lJ.tyf.Cbrjtrbi ••> '.;-"'•• --> '^;K^C"~ ',• h;v-\: '^•<-:~'/. r

Minimum transportsndex to bs% shxbWn.'b,n;~ .

label for nuclear.cKiticality cbh|fojl\f;y? ' 100

Shipments must be completed between April 1 and October 31.

In addition to the requirements of Subpart- G,of 10 CFR Part 71:a. The packaging must be prepared for shipment and operated in accordance

with the Operating Procedures of Chapter 7 of the application.

b. The packaging must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application.

c. The packaging must be loaded in accordance with Section 7.1.2.19 andChapter 1 of the application.

8.

9.


Expiration Date: June 30, 1999.

403

NRC FORM 618A(3-96)



REFERENCES

Transnuclear Inc. application dated January 19, 1989.

Supplements dated: March 22, 1989; December 19, 1990; March 4 and October 3, 1991;and April 21 and November 7, 1994.


I{JAMMA*\\(*

Date yj? Ut [iL


and Safeguards

. - > ' • • * / • : : • - , •

'. a

404tt7K7KMJK7K7KM7K7K7Kffl,ffl,7*USU£U3U&J&7¥L7&7!^^




1. o. CERTIFICATE NUMBER





3IEAMBLE




Framatome Cogema FuelsP.O. Box 11646Lynchburg, VA 24506-1646


Framatome Cogema Fuels applicationdated May 31, 1996, as supplemented.


4.CONDITIONS , ^ :£) \Cj >,r~ ,y ,This certificate is conditional upon fulfilling the requirementspf 10f,CFR Part 71, as applicable, and the conditions specified below.

8!

(a) Packaging ,:

(1) Model No5;^

(2) Description

The9top flange c]dj;iicontainment ~'-:-'-industrial

('*$*" i

lp Thea steel drum by

Closurecarbon steel lid^andvly8-i;n'eprtfi4Gk siTic6ne rubber'gasket secured witheight, 3/8^16NC by l~r/2 e1o|if j^p&oHs.-.and nuts;^ The 16-gauge steelouter drum^/approximately^SW'Mches high and^22.5 inches in diameter.The drum closur%is a 16-gauge l id with a «12Vgauge bolt locking ring withdrop forged lugs, one^of which is threaded^ having a 5/8-inch diameterbolt and lock nut. <='</'" '•"'--> , ;

z -J*~r ,,

The gross weight of the packaging and contents is 490 pounds.

(3) Drawings

The packaging is constructed and assembled in accordance with FramatomeCogema Fuels Drawing Nos. 1249874E, Rev. 1; 1259100C, Rev. 0; 1259101C,Rev. 0; and B&W Fuel Company Drawing No. 1215600D, Rev. 3.

405

w

gggggM

* Max. Enrichment Max. U02 . Max. U-235 Max. Number

a (wt % U-235) mass (kg) mass (kg) Pellet Boxes


gggg

5.(b) Contents


(1) Type and form of materialgg

Dry uranium oxide solid pellets, annular pellets, or scrap, packagedeither on trays or bagged, as shown in B&W Fuel Company Drawing 1215600D,Rev. 3.

(i) Solid pellets on stainless steel trays. The minimum pelletdiameter is 0.315 inch and the maximum pellet diameter is 0.375inch.

(ii) Bagged solid pellets or scrap, or any combination. The maximumpellet diameter is 0.375 inch.

(iii) Bagged annular pellets. The minimum pellet diameter is 0.291 inchand the. maximum pellet diameter is 0.304 inch, with an annulus from0.045 to 0.065 inch in diameter.

(2) Maximum quantity, of material per package .. ,

The maximum weight of contents and all packaging materials within theinner container is 275 lbs. The maximum Quantity of polyethylene is149 grams per pellet .box. "; /

(i) For the content^ described in Item-:5(b)(l)(i), enrichment andfissile qu'antities are limited 3s follows.:

Max. Enrichment Max. U0z " Max. ,uV235 Max. Number(wt % U-235) . mass (kg) .mass (kg) Pellet Boxes

5.0 112! - 4.83 4

(ii) For the contents described in Item 5(b)(l)(ii), enrichment andfissile quantities are limited as follows:

5.0 84 3.62 33.85 112 3.72 4

H

gm

* (iii) For the contents described in Item 5(b)(l)(iii), enrichment and

gggm»

g

f i s s i l e quantities are limited as follows:

Max. Enrichment Max. U0z Max. U-235 Max. Number(wt % U-235) mass (kg) mass (kg) Pellet Boxes

5.0 84 3.55 33.75 112 3.55 4

406

2 12. Expiration date: January 31, 2001.5





6. Each package must have a stainless steel plate (spacer) positioned betweenpellet boxes, as shown on Framatome Cogema Fuels Drawing No. 1249874E, Rev. 1.

7. For packages containing fewer than four loaded pellet boxes, solid aluminumspacer blocks, as shown on Framatome Cogema Fuels Drawing No. 1259100C, Rev. 0,must be substituted for all missing boxes.

8. For contents described in Item 5(b)(l)(i) and limited in Item 5(b)(2)(i),stainless steel trays must be positioned between each layer of pellets, and onthe top and bottom of the pellet stack. Spacers or additional trays must beinserted in partially filled pellet boxes to provide a snug fit.


(a) The package must be prepared for shipment and operated in accordance withthe Operating Procedures of Chapter 7 of the application.

Chapter 8 of the application.

10. The eight, 3/8-inch,containment vessel bolts must be torqued to 35 ft-lbs ± 10%and the 5/8-inch closure ring bolt and lock nut must be torqued to 70 ft-lbs ±10%. Immediately following each loading of a package, the closure ring must beinspected to assure it is fully seated (engaged).


REFERENCES

Framatome Cogema Fuels application dated May 31, 1996.

Supplements dated: August 15, and September 9 and 10, 1996.


Date:


and Safeguards

407j&J&2&M.&2S&MJ£J3k?2&MJ&JB,MJMJ5U&2iVMJi^

i

!t

iiiiiiE(i

Iii

NBC FORM 618(MS)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1-a.CERTIl UMBER b. REVISION NUMBER IBER d.PAGE NUMBER a. TOTAL NIWBER PAGESNUMB NUMB

'REAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEHESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Chem-Nuclear Systems, Incorporated220 Stoneridge DriveColumbia, SC 29210

V

Chem-Nuclear Systems, Incorporated,application dated June 16, 1986,as supplemented.

ir2>. ""lc. DOCKET NUMBER ~' %Jf //

4. CONDITIONSThis certificate is conditional upon fulfilling<tfieyequirements of 10 CFR Part 71, as applicable, and the/conditions specified below.

(a) Packaging

(1) Model No.%CNSIT 5 * '

(2) DescriptJ,ojiA cyli ndgjcal.cavbotranspo^t^radi"posi t ioned ilimiters op the!shieldingând

ândâ^^Lsb'ie;4dedfshipping cjsk, designed to^.fhêasKîs transported in the uprightnâ|ed, ^mixi pol^Srethane foam impactL. i'i__-<.._///-/<—-s=^- *.. dimensions,

Cask gCask outBr diameteCask cafi^fWheight.Cask cavify/SMameterOverall package height, with impactOverall package J^âmeter, withîmpiLead shielding t h i c k r i e f s ^ ^jXGross weight

(packaging and contents)Maximum weight of contents,

shoring, and secondary containers

l imiters

^7 88 inches£8-1/2 inches

77 inches68 inches130 inches102 inches

1-7/8 inches

72,000 lbs

18,000 lbsThe cask body consists of a 1-1/8-inch thick carbon steel (A-516) inner shell,a 1-7/8-inch thick lead gamma shield, and a 2-inch thick carbon steel outershell. The inner and outer shells are welded to a5-1/2-inch thick carbon steel bottom plate. The cask cavity has an optional12-gage stainless steel liner. A 12-gage stainlesssteel thermal shield surrounds the cask outer shell in theregion between the impact limiters. The impact limiters aresecured to each other around the cask by eight ratchet binders.

4 0 8

^

NRC FORM 618A(6-83)



The cask l id is a 5-1/2-inch thick carbon steel plate , and has a31-inch diameter opening equipped with a secondary l i d . The primary l id is.sealed with a double silicone 0-ring and 24 equally spaced 1-3/4-inch diameterbolts . The secondary l id i s 46 inches in diameter, i s centered within theprimary l id , and is sealed to the primary l id by a double silicone 0-ring and12 equally spaced 1-3/4-inch diameter bol ts .The space between the double 0-ring seals is provided with a t e s tport for leak test ing the primary and secondary l id seals .

The optional cask drain and vent ports are sealed with a plug and a silicone0-ring seal .

The package is equipped withrfourpf£-dowrL lugs welded to the cask outershel l , and two liftingdugXwfficH' ar"e- rJmoved;during transport. The- . ^ . « - - *** covered by thelid is equipped witii\th^e"e l i f t ing lugstop impact l imi te^ncTra in cover during

(3) Drawings

The packagii^Qisfollowing

rdanpCwith the'awings:

(b) Contentsx &

(1) Type and form fff/faterial

ucted and assembledterns, Incorpora

C-11O03-29OO3-O1CC-llD^-29005r01C-lltj2D-29O03ldl2C-11GJV290C-1KFA-290

(i) Byproduct mater/al in the form of solute, dewatered resins orprocess solids, or^lidWiedvwast^,-^itained within secondarycontainers; or s<

(ii) Radioactive material in the form of activated reactor components.


Type B quantity of radioactive material, not to exceed 2,000 times aType A quantity. Decay heat not to exceed 100 watts. Weight of contents,secondary containers, and shoring not to exceed 18,000pounds. Contents may include fissile materials provided the masslimits of 10 CFR §71.53 are not exceeded.

4 0 9

NRC FORM 618A(6-83)



Except for close fitting contents, shoring must be placed between the secondarycontainers or activated components and the cask cavity to prevent movement duringaccident conditions of transport.

' The cask primary lid must be secured by 24, and the secondary lid by 12, l-3/4"-8UNCx 5-3/8" long hex cap screws with a flat washer, torqued to 300 ft-lbs ±30 ft-lbs (lubricated). The optional drain and vent ports must be pluggedand sealed prior to transport.

5. Lift lugs must be removed from the cask body prior to transport.

In addition to the requirements of Subpart Gj>f 10 CFR Part 71:

fMaintenance Program of Chapter(a) Each packaging must meet the8 of the application; an'd v

(b) The package must bOperating Procedu,'

•epared for shipment and operat°of Chapter 7 of the application;

accordance with the

(c) The primary lid&secreplaced with |i£tir sealwhichever occurs^first.

10. The package must <b«f leak tes

(a) Prior to eachfStiipnnof low specif|0acti'use vehicle, tne pacSection 8.2.2.3^ tK

11. (a) For any package containing

lid, and the optiona]pection shows

inpana^d£ain seals must berets or every 12 months,

requirementsexclusive

ance

(b) The packaging c6nrainmei.Y j nwith Section S.l.^fof the appHc•packaging, after tb&fthird use,prior to each use, aiK^after seal replacement.

ed infrst

twelve mow

;ordanceany

^period

For any p g g g#er_and/or ongan*|£substances which couldradiolytically generate combustijile g^es">Sa determination must be made by testsand measurements or by analysis of a representative package that thefollowing criteria are met over a period of time that is twice the expectedshipment time:

(1) The hydrogen generated must be limited to a molar quantity that would be nomore than 5% by volume (or equivalent limits for other inflammable gases) ofthe secondary container gas void if present at STP (i.e., no more than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

(2) The secondary container and cask cavity must be inerted with a diluentto assure that oxygen is limited to 5% by volume in those portionsof the package which could have hydrogen greater than 5%.

410ta>>£8&tas^!j&!>ts!JXdai!>#>Maiit!K^^

^

NRC FORM 618A(6-83)




For any package delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination for gasgeneration is made. Shipment period begins when the package is prepared (sealed)and must be completed within twice the expected shipment time.

(b) For any package containing materials with a radioactivity concentration notexceeding that for low specific activity material, and shipped within 10 days ofpreparation, or within 10 days after venting of drums or other secondarycontainers, the determination in (a) above need not be made, and the timerestriction in (a) above does not apply.

12. The package authorized by this certificate is hereby approved for use under thegeneral license provisions

13. Expiration date: OctoberG

Chem-Nuclear Systems ^M

Supplements dated: /August 27^and April 17, June fifSeptembe

Date:

REFERENCES

ication dated

28 and ^klvember 29, 1989,1995.

'COMMISSION

irectotffice

ateria^Safety

4 1 1

&

rar^NRC FORM 618(3-96)10CFR71








4

2. PREAMBLE




U. S. Department of EnergyWashington, DC 20585


Transnuclear, Inc. application datedSeptember 1, 1989, as supplemented


4. CONDITIONS ; ,This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model No.: TN-REG

(2) Description x

The TNrREG package^feâ cylindrical ste|V|.Qask designed for shipment of upto 20 PWR spent fue%,ass;embli.es.._ The- p^cfage, with impact limitersattached, is apôx^Stfly,; 234 inchesvlorfgând 131 inches in diameter. Thetotal weight b#\fheYap.kagie is sabputr;225?;00.0:/ppijnds. The maximum weight ofthe contents,'^cl/udfngtê fueif!b:a.?k>;t "assembly, is\approximately 50,500pounds. The c5s]c;ii^ranspo»?ted;inâ horizontal orientation on a speciallydesigned shipping? firaniey^-1 , . : ;.^! .. /

The containment vessel corispisits^f;, a 9.25-inch thick forged steel(ASHE SA-350)-cylindrical sbelV.and l i d . ' The l i d is approximately 82.25inches in diameter and has a maximum thickness of 8.5 inches. The l i d isbolted to the cask with forty-eight 1-5/8 inch steel (ASME SA-540, GradeB24, Class 1) bolts. The cask is sealed with a Viton 0-ring mounted in agroove machined in the underside of the l i d . A second metallic 0-ring isprovided to leak test the Viton 0-ring. The cask is provided with accessand vent ports in the l i d , and two gas sampling ports and a researchinstrumentation port in the cask body. All five of these penetrations aresealed using Viton 0-rings.

The spent fuel assemblies are positioned within a 40 compartment fuelbasket. Each compartment can accommodate a single PWR assembly. Duringtransport, one-half of the compartments are loaded with spent fuel and theremaining with stainless steel inserts. Peripheral inserts fabricated froman aluminum alloy are positioned between the fuel basket and cask cavitywall.

4 1 2

NRCFORM618A(3-96)



5.(a)(2) Continued

The cask is equipped with impact limiters made of balsa and redwood encasedin carbon steel shells. The impact limiters have an outer diameter of 131-inches, an inner diameter of 91 inches, and a thickness ranging from 20 to26 inches. Each impact limiter is attached to the cask by four 2.25-inchdiameter bolts. The impact limiters are also connected to each other withfourteen 1.5-inch diameter tie rods.

The cask has four lifting lugs welded to the lid, and four lifting/tiedowntrunnions bolted to the cask body.

(3) Drawings

(i) The packaging is constructed.in accordance with the followingTransnuclear, Inc^Djpawirigs:

3024-1503024-1503024-1503024-1503024fl503024rl503024-1503024-1503024-1503024-1503024-150

-6;,' RevT 4-7, Rev. 3^11, Rev. 2-12, Rev. 3^19,-Rev. 0-21v Revx. 1-22,\Rey.<2-23,>Reyv:. I-24,iRefel-25,iR|vl 1

Front Impact LimiterRear Impact L MiterPackaging PenetrationsLid Bolt ' v-Tie Rods andJie^Road BracketsLongitudinapSe/tion.Transverse^Sections --Shell andMttomaid' " V£g<' '

-m3024-150-27%R^y.f1>:

3024-150-©;, fleÔV3024-150-32rRevVK03024-J50-33, Rev. 13024-150^34, Rev. 03024-150-36,; Rev. 0

; Trunnion f^Front,;Irnp'act'Limiter and Tie Rod; B | i p V 6 i; ;;Brag|epVssej!i6iy

'•: :. Rfeari inipact t/ifnTter anclr.Tie Rod• «:is BracRet Assembly ..:";^'.;4mpac'tsl|imfter Attachment BoltîCpi svcXNSpr i ng . at Impact/ L imi t e r

^Lit; :;'RodBiC¥oison Rod , :

Impact LimiterFrbht Spacer

(ii) The fuel basket ..assemblyAis.constructed in accordance with thefollowing Transnuclear Drawihcfs:

3024-150-28, Rev. 03024-150-29, Rev. 03024-150-30, Rev. 03024-150-37, Rev. 13024-150-38, Rev. 0

Basket-General ArrangementBasket-Cross SectionBasket-Plan ViewPeripheral InsertFuel Replacement Insert

4 1 3

2SÛSU^7¥^7^2SJf^W\7^JSUSJ&^7^7K7¥.7^7^7^7^7^2S,^^^JSJSJ£.

jag ag aETagaz ag a g w agag ag aEcag SIOKJBECSK SK JJKSK sg cWaETaEL^KlgaEnjEitii: ag-Sj? W W a g ag ajc^g; .56. w w a? a?:5 NRC FORM 6 1 8 A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION

(3-96)


5.(b) Contents


(i) Irradiated PWR uranium oxide fuel assemblies as described in theapplication and including the following specifications:

Fuel formNominal pellet diameterCladding materialCladding thicknessMaximum fuel rod lengthMaximum active fuel rod lengthAssembly arrayMaximum initial fuel pin

pressure at 70°F; . vMaximum initial U2^ enrichmentInitial uranium loading ^

U02 pellets0.367 inchZircalloy0.024 inch162 inches144 inches14 x 14

1 atm3.5% w/o383 kg

( i ) Maximum of twenty'PWR fufel | ^( i i ) Maximum decay^lfea| per package jibt|"|o.êxceed 2.7 kilowatts.

M i 1 3 $ % PW b l C /

3i

£•* The PWR>fu'el assemblies have a maximum burrtup of 15,000 MWD/MTU. Thec minimum cooling time for any assembly is 17,years.

i* (2) Maximum quantity dfîiiterial per. package£ r ± \ u_.--j' _J? J.. t i>j.rt~*

V

;

5

SS

!5

y | p p g | | .Maximum ,13$;jwatts%er PWR assemblC.^ , / .

Above fueâ^sembTies to be positioned'xinpt(iii) Above fueâ^sembTies to be positioned.'xihpthe fuel baskets asshown in thexdâiwings referenced in 5(a){3)(i 1).

(3) Transport Index for Cfiiticali^Cpntrol" , -y ,>•.:'

Minimum transport index to b¥isji6^n

on label for nuclear criticality control: <,-u 100

6. Shipments must be completed between April 1,, and October 31.

7. Bolt torques:

(a) The cask lid bolts must be torqued to 1120 ft-lbs.(b) The bolts used to secure the vent and drain port covers must be torqued to

50 ft-lbs.

(c) The bolts used to secure the upper gas sampling port transport plugmust be torqued to 30 ft-lbs.

(d) The bolts used to secure the lower gas sampling port cover and porttransport plug must be torqued to 15 ft-lbs.

8. Known or suspected failed fuel assemblies (rods) and fuel with cladding defectsgreater than hairline cracks are not authorized.

414

NRC FORM 618A(3-96)




(a) Each packaging must be prepared for shipment and operated in accordancewith the operating procedures in Chapter 7 of the application. Afterloading, the cask must be vacuum dried and backfilled with nitrogen at oneatmosphere as described in Chapter 7 of the application.

(b) Each packaging must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application.

(c) The packaging must be loaded in accordance with Section 7.1.2.19 of theapplication.


11. Expiration Date: May 31, 2000.

REFERENCES

Transnuclear, Inc. application dated September 1, 1989.

Supplements dated: March 7 and October 22, 1990; January 7 and February 11, 1991;November 7, 1994; and March 2 and 15, 199,5.

:: 7 FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Date

'William D. Tfaversy DirectorSpent Fuel Project Office•Office of Nuclear? Material Safety

and'Safeguards

415W7$U£^









3

2. PREAMBLE






NuPac Services, Inc., applicationdated April 17, 1991, as supplemented.

c. DOCKET NUMBER 71-92084 . C O N D I T I O N S - - - •;"-:, '.''_• -

This certificate is conditional upon fulfilling the requirements of 10,dFR Part 71, as applicable/and the conditions specified below.

5.

< K X $ -

(a) Packaging

(1) Model No.: 10-142?

(2) Description

Steel encased, lead s ^ i d e d cask''for sq,Tjff;îoactive/material. Theoverall dimension%qf^|^!c^k.,|hcl>.#P5Fc:tA.|ift5;ters are 112-inch diameter by130-inch height., \^|e G^§ll^|insists of-iy/jôncentnic carbon steelcyl indrica'T vshellifcsirrou^ shield. The 1/2-inch. . , .. _._.._-,: i- . , . . , ,^^^. ^^,A._i.-,« :>.i>Jx.iti«*- ^ ^ t h thick; outer shell has athick76-inch 0Dand 74-inchA steppedcomprised of tyio,, 3-inch thic^ê^plates'xontaincing an opening for asecondary lid of similar const"r'u.cjit.oTVwith one additional 1-inch thick upperplate Within the'primary lid there is a 16incH'-"6r 29inch centered

y jplate. Within the'primary lid there is a 16-isncH'-"6r 29-inch centeredsecondary lid. The 16-inch lid is secured by Si 7/8-inch studs and nuts andthe 29-inch lid is secured by.16, 1-1/4-inch studs and nuts. The lids aresealed with a solid silicone flat cjaVket. The containment cavity is 66inches in diameter by 72 inches high. A plugged drain port is located at thecask bottom and the lid is provided with a plugged test port. Toroidalimpact limiters are located at the top and bottom of the cask. The impactlimiters are 10-gauge steel sheets filled with rigid polyurethane and areequipped with plastic plugs. As an option, interior and exterior surfaces ofthe cask body and interior surfaces of the upper lid may be covered with 12-gauge 304 stainless steel cladding and seal welded.

All exposed side walls are covered with a stainless steel thermal barrier.Four skewed lugs, welded to the outer shell are used for tie-down. Thepackage gross weight is approximately 68,000 pounds.

(3) Drawing

The Model No. 10-142 packaging is fabricated in accordance with NuclearPackaging, Inc., Drawing No. X-103-110-SP, Sheets 1 through 5, Rev. H.

4 1 6

3S? w ra wwwwwwwwwwwwwww ng ww w w wNRCFORM618A(3-96)



(b) Contents


(i) Dewatered, solid, or solidified waste which may be in secondarycontainers;

(ii) Activated components which may be in secondary containers; or

(iii) Dewatered, solid or solidified material, meeting the requirementsfor low specific activity material, which may be in secondarycontainers.

(iv) Dewatered or solidified ion exchange resin from light waterreactors, in secondary containers.


Decay heat not to exceed 400 watts. Fissile materials not to exceed thelimits of 10 CFR-§71.53. Maximum weightvof contents, including dunnageand secondary containers, not to exceed .10,000 pounds.

For the contents^Specified in 5(b)(l)r(t) and 5(b)(l)(ii):

Not to exceed, a Type.A quantity of transuranic materials.

6. (a) For any package contaijiing^Water. and/or organic-substances which couldradiolytically generate,'?conib"ustible gases, determination must be made bytests and measurements-or-by,,analysis\of. representative package such thatthe following criteria are met.over a period of time that is twice theexpected shipment time: '-\ !/t)\x-*C{:: < . '•/;•

(i) The hydrogen/generated must be limited to a molar quantity that wouldbe not more than 5% by volume (or equivalent limits for otherinflammable gases), of the secondary container gas void if present at STP(i.e., no more than^0.063• g-%oles/ft •-at 14.7 psia and 70°F); or

(ii) The secondary container and cask cavity must be inerted with a diluentto assure that oxygen must be limited to 5% by volume in those portionsof the package which could have hydrogen greater than 5%.

For any package to be delivered to a carrier for transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for gas generation is made. Shipment period begins when thepackage is prepared (sealed) and must be completed within twice theexpected shipment time.

(b) For any package containing materials with radioactivity concentration notexceeding that for low specific activity material, and shipped within 10days of preparation, or within 10 days after venting of drums or othersecondary containers, the determination in (a) above need not be made,and the time restriction in (a) above does not apply.

417

The secondary cask l i d s tuds and nuts must be torqued t o 200 ± 10 f t - l b s



7. Except for close fitting contents, dunnage must be provided in the shipping caskcavity sufficient to prevent significant movement of the contents or secondarycontainers relative to the outer packaging under normal condition.

8. Bolt Torque:

p(lubricated).

y(lubricated).


(a) Prior to each shipment i,;"thei packaging seals must be inspected. The sealsmust be replaced w,ith;new seals if inspection shows any defects or every 12months, whichever, occurs first. Cavity drain and test ports must be sealedwith appropriate^seal ant applied to the pipe plug threads. The cask must beleak tested in;accordance with the supplement dated November 24, 1992.

(b) The package^ toustbe^repared for shipment ancLoperatedTin accordance with theoperating procedure"s>\iiiCSection 7 0 of the apjîcîon except t h t theoperating procedure^s^fi^ Sect ion 7.0 of the.;apgl;1'ca'tion; except that thepackage shal,l be 1 eak>te>ted in-accordarite,iwith supplement dated November 24,1992. ' ^ — > ? ' X ; ' - 7 " -b'%%

(c) Each package mustj'jneei^t'h.eÂccep'tince^-Tês^sjga'nd Maintenance Program ofSection 8.0; of t;he1'^pp1 t c ^ be leak testedin accordance wii|jiithe s1ip^ment:dat0,d!^bVemb|W24, 1992.

10. Use of intumescfcn;lxcoati^ /

11. The package authorized by th{s cei fj||'|- %!is;/"he;»feby approyed for use under the

general license proyisvions of 10 CRR',7§7| 1:2.

12. Expiration date: July-'31s, 2001.

•''•REFERENCES

Nuclear Packaging, Inc., application dated April 17, 1991.

Supplements dated: May 24, 1991; November 24, 1992; May 19, 1993; January 20, 1994and May 16, 1996.

_ FOR T.HE U.S. NUCLEAR REGULATORY COMMISSION

s8

and Safeguards

Date: 7 llS'f^L

418

William D. Travels, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

mTKmmmmmmmmmmmmmmTremmmmmmmmmmTrem)

v^^

NRC FORM 618

10 CFR 71








. PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theappiicabie safety standards set forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEHESIGN OR APPLICATION 'a. ISSUED TO Mama and Addrassl ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Scientific Ecology Group, Inc.P.O. Box 25301560 Bear Creek RoadOak Ridge, Tennessee 37831-2530^.

Scientific Ecology Group, Inc., applicationdated October 26, 1993, as supplemented.

%. DOCKET NUMBER '7-1^9210

4, CONDITIONSThis certificate Is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and theconditions specified below.

\ N » SI'ondSI'

5,

(a) Packaging

(1)

(2) Description3V

i

Model No;.: 10-135B .^V. . «-' /&$'

Steel encased, rle)acl shielded cask fo^Vsôl^Tadioactive^niaterial. Theoverall &iinensfqi\s#of ^Tne^ts^&j&rfli-i-i^fi di|irn,eter by§130-inch height.The cask cpnsisW:o"%rJ 6-c<^cenjtipic,}'caiffbon stSj^'-cyi ironical shellssurroundingâ 3^2iifich ih/ickj 1'e'ajJJ shield. ,y|j;6ei" 1/2-^nch thick inner

Is byjcff fi 11 et and i.uX^/\pen'etraî^n^r-po|"a<wel ds. The top of the

cask is provide'd^with a primary lid and a secpriaary. lid. The primary lidis of a stepped construction which is made of^jtwo, Scinch thick steelplates of 76-inch diameterând 66-it)ch îfieter joined together to form anintegral 6-inch thick tid.^The^primary ilTd is secured to the cask bodythrough 16, 1-1/2 - 6 UNC high Strength bolts. The secondary lid whichcovers the 29-inch diameter hole at the center of the primary lid is alsoof stepped construction consisting of two, 3-inch thick plates. Thesecondary lid is secured to the primary lid through 16, 1-1/4 - 7 UNC highstrength bolts. High temperature silicone gaskets are provided at thecask-primary lid and the primary lid-secondary lid interfaces. The latteris also provided with an additional Neoprene seal.

Two impact limiters are located at the top and bottom of the cask. Theimpact limiters are 10-gauge stainless steel shells filled with rigidpolyurethane. The inner surfaces of the cask and the lid are clad with12-gauge 304-stainless steel. The portion of the cask body that is notcovered by the impact limiters is covered with a 10-gauge 304-stainlesssteel thermal shield. There is a 1/4-inch gap between the shell and thethermal shield which is maintained using 1/4-inch spacers.

419

Bft<Wreftgft«ftB?^^

NRC FORM 61SA(6-83)

Page 2 -

5.(a)(2)

(3)


(b)

(1)


Description (Continued)

The package gross weight is limited to 68,000 pounds.

Drawings

The packaging is constructed in accordance with Scientific Ecology Group,Inc., Drawing No. STD-02-106, Sheets 1 and 2, Rev. 1.

Contents


(i) Dewatered, solid, in secondary containers;

(ii) Activated sol4d\c^nponents in secondaryâoStainers; or

(iii) Dewatered solidified ion exchange resins ftfcjfn light waterreactorsîn secondary containers.

6.(a)

(2) Maximum

Greater th^n Type A q ^ i t t f e s .fissile qtiantities l|ffi||§d to tfie amouriNot to exceed a Type^ântityAof Jransucontents sspeci fi e,d i nInternal llfcay hemnd^p^ceecUAOcontents W& ' '^*vîrhi

For any pa|"f|ge cca^radiolyticaRfc, gen*1"tests and m&a'syremenTs olrYtoythat the folfoMng criteriathe expected shipment time:

per package

s^which may containempted unêr 10 CFR §71.53.material sêxcept for the

fl£ lowêcif ic activity.'' maximum weight of

15^000 pounds.

iMCsubstafices which could'eterminatloji must be made byIpresentStsive package such, . . _*. ^ . .L., - s t w i c e

(b)

(i) The hydrogen generated must be limitecUto a molar quantity thatwould be no more t h ^ 5 ^ y vo ujrte (oi? eqiJiivalent limits for otherinflammable gases) of tm secondary container gas void if present atSTP (i.e., no more than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

(ii) The secondary container and cask cavity must be inerted with adiluent to assure that oxygen must be limited to 5% by volume inthose portions of the package which could have hydrogen greaterthan 5%.

For any package delivered to a carrier for transport, the secondarycontainer must be prepared for shipment in the same manner in whichdetermination for gas generation is made. Shipment period begins when thepackage is prepared (sealed) and must be completed within twice theexpected shipment time.

For any package containing materials with radioactivity concentration notexceeding that for low specific activity material, and shipped within 10days of preparation, or within 10 days after venting of drums or othersecondary containers, the determination in (a) above need not be made, andthe time restriction in (a) does not apply.

420

w&fi®f&i*a&!S?i&^rfw®?iiM^^

NRC FORM 618A(6-B3) CONDITIONS (continued)




(a) The package must meet the Acceptance Test and Maintenance Program ofSection 8.0 of the application, as supplemented.

(b) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures of Section 7.0 of the application, assupplemented.

8. The containment vessel must be leak tested to 1.3 x 10"6 atm-cm3/sec (at thestandard conditions of ANSI N14.5):

ackage,1. prior to the first use of ead2. after the package' s tjjw rflusr, __3. within twelve montfv ltffMhe last lMkf4fe£t,Aand4. whenever gaskets w e replaced. ^

9. Prior to each shipmew, except when only low specific a^Uvity material istransported as exciS^ive use, the containment system shaf^be tested to 5.0 x10"3 atm-cm3/sec ,(ar t^s tandards conditions of ANSW5f4.5^/o verify that i thas been proper/ySassemfc

10. The package autJhorizedgeneral license^provision

11. Expiration datje. Dece(

Scientific Ecology

Supplements dated: Al£J?l 5 a

or use under the

Date: Dec. 21, 94

E U.S. NUCLEAlR-REGULATORY COMMISSION

V



4 2 1

^

NRC FORM 618(W5)10 CFR 71




4


USA/9215/Bfind. PAGE NUMBER

1


3PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafetystandardsset forth InTitle 10, Code




Neutron Products, Inc.22301 Mt. Ephraim RoadP.O. Box 68Dickerson, MD 20842


Neutron Products, Inc. application datedSeptember 14, 1992, as supplemented.

' c. DOCKET NUMBER

A. CONDITIONS .;- \ ' v fit '"'<-.''•,This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a)

(b)

<<:\

Packaging

(1) Model No:': NPI-2l |g£ Mkll__•

(2) Description p'zMt /v

A steel

-••f c - -

xl^|g|il ded casK^GdjitaKi ned/wi thi n a DOT Speci fi cati on--,^*..yi*-£M^T^ diameter with a 3/8-inch

thick steel sWeri^aJ sh^.lj iandsa-MViiy f$pe/d by an 8-1/4-inch ID by3/16-incHHhicl9^|e;^ | u | | ^ (! jPjo^it^ c l o | p r o f the "shielded cask isaccomplished by7Jb'o^^6na^Cidy^!?"^t%ac'h'^|hd of.the cavity. The maximumpackage gross wefghri^ 6,^005/Rpiinds,'?Mr •?"<•

•- f i J l*i's'!\ \VvVf %/'?•*: "^~':

(3) Drawings ; ^ ' ^ A * v * ° ' ^ ••^J":>

The Model No. NPI-2QWJC-6 Mkll packaging is cbhstructed in accordance withNeutron Products, Ihcy ^rawing Nos,, 24,0|l6, Rev. D, and 240122, Sheet 1 of2, Rev. G, Sheet 2 of 2/-Rev;"- - . ^ . i

Contents


Cobalt-60 as sealed sources which meet the requirements of special formradioactive material.

422

^



(b) Contents (Continued)


(i) For sources contained within drum assembly shown as Item 5 onNeutron Products, Inc. Drawing No. 240122, Sheet 1 of 2:

Maximum activity not to exceed 15,000 curies, maximum decay heat notto exceed 240 watts.

(ii) For sources contained within drum assembly shown as Item 4 onNeutron Products, Inc. Drawing No. 240122, Sheet 2 of 2:


(iii) For sources contained within drum assembly shown as Item 2 onNeutron Products, Inc. Drawing No. 240122, Sheet 2 of 2:


In addition to the requirements' of Subpart G of 10 CFR Part 71:

(a) The package must meet the Acceptance Tests and Maintenance Program ofSection 8.0 of the application.

(b) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures of Section 7.0 of the application.

The contents must be secured in the drum assembly so as to restrict movement inany direction to less than 0.25 inch, by lead, steel, or tungsten full diameterplugs and spacers.

The gross weight of the package must not exceed 6,000 pounds, and the innershield cask shall be snug-fitting with the wooden overpack.

423

a" a* ! a*'» !* a !*""*"™^ v*^* i»^

^





REFERENCES

Neutron Products, Incorporated application dated September 14, 1992.

Supplements dated: October 29, 1992, and November 17, 19.93.


Cass R. ph'appell, Section Leader[ Cask Certification Section

"Storage: and: Transport Systems Branch. . ^Division'"of Industrial and

.,.., , . / - > Medipal Nuclear Safety, NMSS«* 1 • Iw) - • "

Date: - ; :. •

424i4«!U&!iiaU^^

«"W^WAW7SW?^«^*i 'Wi W7^»riW?S-W7^WA*/NWriW7SW7^«

NRC FORM 618(W6I10 CFR 71



r

jIttiiiiiiiIi

iii

iIiiii

\ a. CERTIFICATE NUMBER


USA/9216/BC )Fd. PAGE NUMBER


42. PREAMBLE

a. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicablesafety standards set forth in Title 10. Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Chem-Nuclear Systems, Inc. applicationdated November 24, 1987, as supplemented.

. DOCKET NUMBER '"71W92<16

A. CONDITIONSThis certificate is conditional upon fulfilling-.thKrequirements of 10 CFR Part 71, as applicable, and the:conditions specified below.^^^^ NS.. )f /?

(a) Packaging

(1) Model

(2) Description

Steelprotecê jasteel pallet,a sil ico^rubldrain Ifneând

Cask ffeffjht, inCask diameter, inCavity heC nt , inCavity diameter, inLead shielding _Protective jacketProtective jacketPackaging weight, 1b

(3) Drawings

A doyble-jslpned steel cylinderâns.port.^t is bolted to a/A-aa-d flanged plug fitted with

cavîy is equipped with af ol 1 ows5*

ketêSJft.^nket width, tf

The packaging is constructed in accordance with Chem-Nuclear Systems, Inc.Drawing Nos.: C-110-B-06402-001, Rev. A; C-110-B-06402-002, Rev. A;C-110-B-06402-003, Rev. C; and C-110-B-06402-004, Rev. A.

4 2 5

I

Iiit

iI

Itiii;t

'{

iiiE

i

NRC FORM B18A(6-83)



5. (b) Contents

(1) Type, form and maximum quantity of material per package

Plutonium in excess of 20 curies per package must be in the form of metal, metalalloy or reactor fuel elements; and

( i ) Byproduct material and special nuclear material as solid metal or oxides.Decay heat not to exceed 600 watts. The radioactive material shall be inthe form of fuel rods, or plates, fuel assemblies, or meeting therequirements of special form radioactive material.

500 gm U-235 equivtftejpkma^s;[oiF ^S %Ji

( i i ) Neutron sourcssêeting the requirements of'special form radioactivematerial.

500 gm U-1

i

iii

t

( i i i ) I r rad ia te PuODecayjfieit not"fwithin<? closed39-5/S^nches.

(iv)

uivalent mass. Decay heat

fuel rods clac

o'

, p fi ,5-incyl§ched

Processfjplidsrsealed rajrjiairadioactwLmatw.,standardsXfoolO CFR §

o*Jxceed 50 watts; or

calloy ijr stainless steel,el rods Ch&ll be containedh a maximflftk useable length of

ile material per

d in a secondaryecif ic activity

exemption

i

j

!

(v) Solid nonfissêîrradiated metal hardware,'^âctor control rods(blades), reactor sta|?t-up sources, andêgmented boron carbide tubes(tube contents not lêx<pked.aLlyjiiÂ quantity) >

(vi) Radioactive (Hot Cell) waste materials immobilized with cement grout andcontained in a 55-gallon (or extended 55-gallon drum) DOT Specification17H or 17C steel drum, lid and closure. The Waste material must bepackaged in accordance with the Procedural Outline of the Immobilizationof Cell Waste Using Cement Grout, Attachment D of the application. Thecement grout must be at least 50 volume percent (estimated) of the drumcontents and relatively uniformly distributed throughout the drum. Atleast 3/4" thick layer of grout must cover all radioactive wastecontents. Decay heat not to exceed 100 watts, and fissile material notto exceed 500 grams U-235 equivalent mass.

426

^

NRC FORM 618A CONDITIONS (continued)U.S. NUCLEAR REGULATORY COMMISSION




10.

For contents described and limited in()()() ()

and 5(b)(l)(vi): 62.5

The U-235 equivalent mass is determined by U-235 mass plus 1.66 times U-233 massplus 1.66 times Pu mass.

(a) For any package contaitfin^%ferBaunb7oVffo^tfic substances which couldradiolytically genar^^e^tombustible gases, cfo&rtmination must be made bytests and measurements or by analysis of a representative package such thatthe following c^ter ia are met over a period of tiiffe^that is twice theexpected shipia&t time:

( i ) Theno mor^fhangases)of themore cn°3n 0.

(i i) The secondaryassurlfthatthe

For any pamust be prgas generatf(sealed) and

be limitedor equiva

9.7

ar«$«antity that would beits forgather inflammable

presaet) at STP (i le. , nod 70°F);

'd with a diluent to'those portions of

secondary containerdetermination for

w h e n c e package is preparedfelted shipment time.

(b) For any package'dbjrtjining materials with radioactivity concentration notexceeding that for Vow saecific activity material, and shipped within 10 daysof preparation, or w i t h ^ i O ^ y s ^ f t ^ v e ^ i n g of drums or other secondarycontainers, the determination^™ Ipf) Inrove need not be made, and the timerestriction in (a) above does not apply.

For packaging of neutron sources, the cavity drain line must be closed with a plugwith a melting temperature of 200°F and the cask cavity must be dry before deliveryof the package to a carrier.

For packaging of other than neutron sources, the cask must be delivered to acarrier dry and the cavity drain line must be closed with a plug which willmaintain its seal at temperatures up to at least 620°F.

For the shipment of irradiated metal hardware, the use of the auxiliary shieldedinner container and shoring plug shown in Chem-Nuclear Systems, Inc. Drawing Nos.8651-E-02, Rev. A and 8651-C-01, Rev. B is authorized. The inner container must beprovided with vent and drain lines.

427'*MM^±ufte9xM<uau»M*M*M&!>t*Ma!>uf^

Êt

NRC FORM 618A

J|t

I

t

I

•t

C

t

t

t

iii

E

I

I

I

E

it

i

Itiiiii

i

i

>

iiiI

ii

tii



11. Shoring must be provided to minimize movement of contents during accidentconditions of transport.


(a) The package shall be prepared for shipment and operated accordance with Chem-Nuclear Systems, Inc. Operating Procedures, Section 7.0.

Prior to each shipment the silicone rubber lid gasket(s) must be inspected. •This gasket(s) must be replaced if inspection shows any defects or everytwelve (12) months, whichever occurs first. Cavity drain line must be sealedwith appropriate sealant sappêdôRbiâds of pipe plug.

(b)

(c) Prior to each shipmeN^^the baseplate to casfe.^11 weld must be visuallyinspected in aci pfei&nce with Chem-Nuclear Systefns-Mnc. Operating Procedures,Section 7.0. - ^ ^

(d) The packagingi S §

13. For packaging ofjieutronfrom the surfaeettof a cas

14. The contents described Arailroad car, aTrcraf'assigned for scQjl use

15. The package authgpzed pgeneral license prpvisioifr

16. Expiration date: December 31,

Chem-Nuclear Systems, Inc. applic


meet Chem-Nuclear Systems,8.0.

eceptance Tests and

rieutron lose rate at one meterIrem/hr.

otor vehicle,seagoing vessel

or use under the

1987.



and Safeguards

Date:

428

^

NBC FORM 618IM6I10 CFR 71







2. PREAMBLEa. This certificate Is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code •


b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, Including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATIONa. ISSUED TO IName and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Siemens Power CorporationP.O. Box 130Richland, WA 99352-0130

Advanced Nuclear Fuels Corporation applicationdated October 12, 1987, as supplemented.

4. CONDITIONS . ^This certificate is conditional upon fulfilling.thetrequirements of 10 CFR Part 71, as applicable, and the/copdjtions specified below.

(a) Packaging

(1) Model Hoh* ANF-250^

(2) DescriptionH

A uraniumfpxida 16-gauge stebolted and=igaskinner vessel, islong, 16-tfa^ge stwelded to theînne tinch thick steff flange and

The,=jjackaging consists of57-^4 inches long with a

jldetihbottom plate. The£fl/2-inciriD by 68-3/8-inch

'diametej^spring steel rodsw™.rie bottgjMf the vessel. A 3/8-

„_ _.._ ige infjjer band^position and support thetop of the innWêssel within^ttie outer conta^'^?. The annulus between theinner vessel andôjiter container is filled wi^vermiculite.

The inner vessel is craled^y îx. lc/^tnph. square shank studs with hex headnuts at each end. The outer container is closed with a 12-gauge locking ringwith drop forged lugs and a 5/8-inch diameter bolt and lock nut. A productcontainer insert is positioned within the inner vessel.

The gross weight of the packaging and contents is approximately 610 pounds.

(3) Drawings

(i) The packaging is constructed in accordance with Siemens PowerCorporation Drawing No. EMF-306,175 R-9 ( Revision No. 9 ), Sheets 1,2, and 3.

429

• ; • • ' -

NRC FORM 618A(6-83)



(3) Drawings (cont'd)

(ii) The powder product container insert is constructed in accordancewith Advanced Nuclear Fuels Corporation Drawing No. ANF-607,244,Sheet 1, Rev. 5, Sheet 2, Rev. 1, and Sheet 3, Rev. 2.

(iii) The container insert and pellet product suitcase, respectively, areconstructed in accordance with Advanced Nuclear Fuels CorporationDrawing No. ANF-306,176, Rev. 1 and Siemens Nuclear PowerCorporation Drawing No. EMF-304,306, Sheets 1 and 2, Rev. 4.

(b) Contents

(1) Type and form of ntCte>

^ fi oxide powder enriched to a*minimum 5.0 w/o in the

^ and a maximum mass of 1149^H considering allof hydrogenous material within the*^|tfier vessel.

cjde pellets enriche^L^^maximam 5.0 w/o in the"" a maximum masj

lougqptefi;

fets /fenriofied^

(ii)

( i i i ) «Qfanium oxi,tfte U-2

i sotope^-sl

(2) Maximumfgaanti

/sidering al lvessel.

w/o in

in the U-235

Not to exceed 310 pounds

(i) For theec-pments described in 5(b)(l)i

The contents n o ^

MaximumEnrichment(wt% U-235)

3.43.84.65.0

MaximumUranium Mass(kg U)

62.455.141.636.9

towing:

MaximumU-235 Mass(kg U-235)

2.22.12.01.9

The contents must be contained in product containerdescribed in 5(a)(3)(ii).

(ii) For the contents described in 5(b)(l)(ii):

The total contents not to exceed 120 kg U, with the U-235content not to exceed 6 kg. The contents must be containedin product container described in 5(a)(3)(iii).

^430

V ^ ^

•PKK^WM&j^Bj't'j&jM^'Sj'M&^p^p^&roBTS'a^^

NRC FORM 61SA(6-03)




5.(b)(2) Maximum quantity of material per package (continued)


The total contents not to exceed 120 kg U, with the U-235content not to exceed 1.2 kg. The contents must be containedin product container described in 5(a)(3)(iii).

(iv) For the contents described in 5(b)(l)(iv):

The total contents not to exceed 120 kg U, with the U-235 contentnot to exceed 1.2 kg. The contents must be contained in productcontainer described^ iRJUtî)

(c) Transport Index fofofip/fcfcality Control

Minimum t r a n s p o r t ndex to be shown onlabel for nucijjj&r critical ity control:

For contentsêsclêityn 5(b)(l)(i) andlimited i n | p ) ( 2 ) i '

For content? descri be;limited

ntFor content^ des5(b)(l)(i\(pandand 5(b)(27(iv):i||f^

6. In addition to

a. The package mtifL>be preparedthe Operating Prpcfedures in Cha'

b.

fentânf operaise<i""in accordance withof the application.

The packaging must meet the Acceptance Testsând^Maintenance Program inChapter 8 of the applicaj|ony4^ A , J y "v^


Expiration date: January 31, 2000.

4 3 1&/HiJJ*^/M\/ ^

^NRCFORM618A CONDITIONS (continued)


ciit

ii


REFERENCES

Advanced Nuclear Fuels Corporation application dated October 12, 1987.Supplements dated: February 2, March 10, July 20, and December 7, 1989;and March 16, 1990.

Siemens Power Corporation application dated October 20, 1994.Supplements dated: December 19, December 20, and December 30, 1994, and January 5 andJanuary 10, 1995.


Date:

William D. Tra\4=r>| DirectorSpent Fuel ProjectfoMiceOffice of Nuclear Mcrte«rial Safety

and Safeguards ^-^

432




I.a.CERTIFICATE NUMBER

9218

b. REVISION NUMBER

7


USA/9?1fl/R(U)F

<J. PAGE NUMBER 8. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate Is issued to certify that the packaging_and contents described in Item 5 below, meets the applicable safety standards set forth inTitie 10, Code



a. ISSUED TO IName and Address)



Nuclear Packaging Inc. applicationdated March 3, 1989, as supplemented.

»<-;c. DOCKET NUMBER 71.-9218

A, CONDITIONS <v \ j j / • <'•,,-, ^This certificate Is conditional upon fulfilling.the requirements of 10 CFR Part 71, as applicable, and the. conditions specified below.

5,

(a) Packaging

(1) Model

(2) Description8 _

A stainlessdesigf^ltransuranicstain! ^containmentless steelyurethaneôam and a

shipping container" contact-handled

unvented, 1/4-rinch thickpositioned within an outer

unven.t|cf51/4-inch thick stain-10-irich thick layer of poly-

-, .. 4fi|fk outer^âinless steel shell. Thepackage isâfnight c ircular^yl iwier with outsê dimensions ofapproximately^ inches diameter and 122 indies? height. The packageweighs not morerthan,19,250 pounds when loaded with the maximum allowablecontents of 7,265 •*** "

The OCA has a domed lid which is secured to the OCA body with a lockingring. The OCV containment seal is provided by a butyl rubber 0-ring (boreseal). The OCV is equipped with a seal test port and a vent port.

The ICV is a right circular cylinder with domed ends. The outsidedimensions of the ICV are approximately 73 inches diameter and 98 inchesheight. The ICV lid is secured to the ICV body with a locking ring. TheICV containment seal is provided by a butyl rubber 0-ring (bore seal).The ICV is equipped with a seal test port and vent port. Aluminum spacersare placed in the top and bottom domed ends of the ICV during shipping.The cavity available for the contents is a cylinder of approximately 73inches diameter and 75 inches height.

433

^ ^

NRC FORM 618A(6-83)





(3) Drawings

The packaging is constructed in accordance with Nuclear Packaging Inc.Drawing No. 2077-500 SNP, Sheets 1 through 11, Rev. K.

The contents are positioned within the packaging in accordance withNuclear Packaging Inc. Drawing Nos. 2077-007 SNP, Rev. C, and 2077-008SNP, Sheets 1 and 2, Rev. C.

(b) Contents

(1)

(2)

Within

Type and form of matgti&\ v*

Dewatered, soTJ^pr:solidified transuranic dM J&itium-contaminatedwastes. Wastg^must be packaged in 55-gallon drptf, standard waste boxes(SWB), or bj&|T Wastes must be restricted to pr&imrit explosives,corrosives, TWirradioactive phrophorics and pre^syn^ld containers,a drum, b^n)or^Bw;adioactive pyrophoriwt^mjist no|^xceed 1 percent byweight aiidffree 19:^^1 must not exceeaXQ|g®cent by volume. Flammableorganicfi&e l i m i ^ ^ p \ 0 0 umd^Kth/h^âce of a p drum, bin or SWB.

Maximuraûantity

Conten^hotc o n t a i n ^ , wtpounds per SWBt

Maximumconfigurai

^ringîd secondary^galltgfedrum and 4,000

packaging

(i)(ii)(iii)(iv)(v)(vi)(vii)(viii)

, 55-gallon

SWB containin,2 .'/1 ten-dr1 TDOP, containing 1 SWB,1 TDOP, containing 1 bin within an SWB, or1 TDOP, containing 4 55-gallon drums within an SWB.

rone^bin,,. 55-gallon drums,containing 10 55-gallon drums,

Fissile material not to exceed 325 grams Pu-239 equivalent with no morethan 200 grams Pu-239 equivalent per 55-gallon drum or 325 grams Pu-239equivalent per SWB. Pu-239 equivalent must be determined in accordancewith Appendix 1.3.7 of the application.

Decay heat not to exceed the values given in Tables 6.1 through 6.3"TRUPACT-II Content Codes", (TRUCON), DOE/WIPP 89-004, Rev. 8.



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6.

8.

9.




7.

11.

12.

13.

14.

Physical form, chemical properties, chemical compatibility, configuration ofwaste containers and contents, isotopic inventory, fissile content, decay heat,weight and center of gravity, radiation dose rate must be determined and limitedin accordance with Appendix 1.3.7 of the application, "TRUPACT-II AuthorizedMethods for Payload Control", (TRAMPAC).

Each drum, bin or SWB must be assigned to a shipping category in accordance withTable 5, "TRUPACT-II Content Codes", (TRUCON), DOE/WIPP 89-004, Rev. 8, or mustbe tested for gas generation and meet the acceptance criteria in accordance withAttachment 2.0, to Appendix 1.3.7 of the application.

Each drum, bin or SWB must be labeled to indicate its shipping category. Alldrums, bins or SWB's within a^^agS2ii|fi5|'"'be«of the same shipping category.

Each drum, bin, SWB, os^ClOP* must be equipped wrej^filtered vents prior toshipment in accordaqc|>»#ith Appendix 1.3.7 of the app/Hcation. Drums which werenot equipped with I^tered vents during storage must tuf^aspirated beforeshipment. The mwKsnum aspiration time must be determin^fKfrom Tables 7.1

89-004, Rev. 8.

ParH1:

d operat£flMn accordance witherating Procedures", of the

p pthrough 9.3 in "TR«PACT-II Content Codes",

10. In addition tctjtne req'

(a) Each package mustthe procures desapplication.

(b)

The contents ofVach pa"Payload ControlVrocedures",vbf

Each p ^ gprocedures desProgram "f

Prior to each shipmein^the l id and vent port seal.!containment vessels muse be^leak tested to 1with Chapter 7.0, "0peratin ur

with theand Maintenance

endix 7.4.3. ,

the inner and outertd cm /sec in accordance

application.

All free standing water must be removed from the inner containment vessel cavityand the outer containment vessel cavity before shipment.



435

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NRC FORM 618A(6-83)




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REFERENCES

Safety Analysis Report for the TRUPACT-II Shipping Package dated March 3, 1989.

Supplements dated: May 26, June 27, June 30, August 3, and August 8, 1989;April 18, July 10, July 25, August 24, and December 20, 1990; April 11, April 29,and June 17 1991; September 24, 1992; April 22, and October 22, 1994.

"TRUPACT-II Content Codes", (TRUCON), DOE/WIPP 89-004, Rev. 8, dated October 1994.

r./NUCLEAR REGULATORY COMMISSION

William D. TravWsVt&rectorSpent Fuel Proleefc OpriceOffice of l^gfe^Mate&Ul Safety

and Sal

Date:

4 3 6

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USA/9221/B( )FA PAGE NUMBER e. TOTAL NUMBER PAGES

2. PREAMBLE






Safety Analysis for Radioactive MaterialShipping Cask NRBK-41 datedNovember 2, 1995, as supplemented.

c. DOCKET NUMBER 71-92214. CONDITIONS ,.. r - . •

This certificate is conditional upon fulfilling the requirements; of 1Q.CFR Part 7 i , as applicable,and the conditions specified below.

5.

(a) Packaging

(1) .Mqdel^Na.: NRBK-41

(2)

-Top loadi^[%y/ljndrical 1 ead ^s|^jded 3041^1^1658 steel

withhas

a Yea;i-welded, l/4¥fnbh|iithick; stainles% steel outer thermalshield^which provides'a 1/16-inch air .gap between the outersurface/of the cask outer shell aritfcthe inside surface of thethermal shfeldN A one-inch thick stainless steel plate iswelded to tne bottom of cask. --""A second one-inch thickstainless steel piatl With "a 1/8-inch deep, 25.5-inch diameterrecess is welded to the first plate to provide a thermalshield for the bottom surface of the cask. The cask is boltedto a 48-inch square, all welded, "I" beam skid. Gross weightof the package is approximately 9,000 pounds.

(3) Drawings

The packaging is constructed in accordance with BattelleMemorial Institute Drawing No. 41-0001, Sheet 1, Rev. D, andSheet 2, Rev. E, and Westinghouse Electric Corporation DrawingNo. 1755E01, Rev. D.

437

;re

,NRC FORM 6 1 8 A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-9S)

S Page 2 - Certificate No. 9221 - Revision No. 3 - Docket No. 71-9221

5. (b) Contents


Byproduct and special nuclear material in solid form,contained within either the MIN-41 or the HIP-41 productcontainers. The MIN-41 container is constructed in accordancewith Westinghouse Electric Corporation, Drawing No. 2D77456Rev. F. The HIP-41 product container is constructed inaccordance with Westinghouse Electric Corporation Drawing No.5D06622, Rev. B.


The fissile, contents of,the package must be limited to amaximum.of 350'equivalent grams-of U-235. The number ofequivalent grams of U-235 is detertoined by the equation:1.0 x grams U-235 + 1.4 x grams U-233 + 1.6 x grams plutonium.The maximum decay heat load per package must not exceed 240

"ir.

PIutohiunCiinêxcess of twenty li0?curies per package must bein the fpri|..of mejtal^ metal alloy or reactor fuel elements.

(c) Transport Inde||fbx Criticality ContrM.'A J._ i__ .-'<.*f ';_r?>

Minimum tr,a'risp,or0;4ndex to be sfibwn.iori w/. .1 abel for .'ritiplea.r• %it/icality control:,/• /;'<,.- 0.0

6. In addition to tfeêqujêments of. Subpart>.Gôf 10 CFR Part 71:

(a) The package must bejiOpeâled^nacc&rdance with the OperatingProcedures, in Section 7'fb !of;the application,/as supplemented.

(b) The package must be maintained in accordance with the MaintenanceProcedures in Section 8.2 of the application, as supplemented.

7. The NRBK-41 shipping container may be covered with a wrapping ofpolyvinyl chloride (PVC) during shipment provided the shipment is made ina closed vehicle. The applicable requirements of 10 CFR §71.87 must besatisfied prior to wrapping the shipping container.


438

^jyatafarafaTataKaraTarwrnaZatatatatsElNRC FORM 618A(3-96)



REFERENCES

Safety Analysis for Radioactive Material Shipping Cask No. NRBK-41 datedNovember 2, 1995.

Supplement: Naval Reactors letter #S96-11965 dated August 28, 1996.


William D. Travfers, DirectorSpent Fuel Project Office

^Office of Nuclear Material Safetyand Safeguards

Date:

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5c. PACKAGE ID] [BER d. PAGE NUMBERBEF e. TOTAL NUMBER PAGES

2. PREAMBLE




Scientific Ecology Group,1560 Bear Creek RoadOak Ridge, TN 37831-2530

Inc. Hittman Nuclear application datedDecember 14, 1987, as supplemented.


4. CONDITIONSThis certificate is conditional upon fulfilling the requirementsof lOJCFR P art 71, as applicable/and the conditions specified below.

(a) Packaging ,v\>^

(1) Model No.: 14-21-5^

(2) Description / :*X

Steel encased lead shel led,!cas1|#or | ra !dt6a^ê material. The cask is aright circular cylindtejgfHh a ^7.25-inch\t|^b> 80.25-inch IH cavity. Theoutside diameter d ^ t h ^ f | s 1 k ^ ^ & 3 ^ ^ - | K ' ^ ^ ^ i t h ..a 92.2c5ginch height. Thewalls of th^ cas1c^contai||t^?0âd^,thick"({e^s^f ^j|8^ inched encased in0.38-inch:-thick ^rl i^,s^^^^Hejt 1 | !^f | l^ '^^ ' i n i^^^ c ' c PB"feer s t e e l shel l . Thetop cover and cas^l^fjpii ê.;ma<Je!]iip|6j two IfCeel p la t | s with thickness of2.0 inchesiVThe p]||m,a»?yjj: ^^^ q$l-indrical cask body byeight, l-l/4:rltich r1ê^^'nd[e^2%^C'ife|onâi(^ l id isêntered in the primarylid and is secured to the^prj | i{affp^«itH eîght, 3r£4vinch studs and nuts.Each l id is provided with a fil^cfejâsHtyseal;?^SB cask is provided witha 12-gauge stain14ss steel linefMêal welded a-l.ong all edges), a l id ventl ine with pipe pTiigând a 3/4-inch drain line;$ahd pipe plug. The cask isprovided with four equally spaced lifting/tie-down devices. The primary l idis provided with three Iff t ing' lugs and" the^ secondary l id is provided withone l i f t ing lug. The cask gross-weight is 58,400 pounds.

(3) Drawings

The package is fabricated in accordance with Scientific Ecology Group, Inc.Drawing No. STD-02-077, Sheets 1 and 2, Rev. 11.

The optional shield inserts are fabricated in accordance with ScientificEcology Group, Inc. Drawing No. STD-02-086, Rev. 0.

440

NRC FORM 6 1 8 A . CONDITIONS (continued) U.S . NUCLEAR REGULATORY COMMISSION(3-96)


5. (b) Contents


Dewatered, solids, or solidified waste, or activated solid components,in secondary containers, and limited to the following:


0.0001 mi H i curie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie;

0.005 mi H i curie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than.0.05 curie, but not morethan";T curie; or

0.-3 miliicurie of radionuclides forwljich the A2 quantity inAppendix'At of 10 CFR Part 71 i& more; than 1 curie.. •• •••-V--'.. • t .-,.- ' /\j?' .''.

(ii) Objects ofâwy'ad'ioac'tiVe/matertaiJ/externally/containinated withradioactiyesmaterial, provided thai the radioactive material is notreadily, dispersible and the surf4e<? contamination, when averagedover an [aê^pr^ square meter j. does/not, exceed 0.0001 miliicurie(220,000r.disihêgi»atji3hs-peîniê)j.tiet; square centimeter ofradionuclides) foVwhich the' A2"quantify in Appendix A of10 CFR P'art 7\ ii*/hot more than 0...uVcurie,, or 0.001 miliicurie{Z;>t00)00tiyjii;s^nt&grj^^ns''p&rldituie) per/square centimeter forotfier di'ljd^f^:' ?' "''

(2) Maximum quantity of material/ per package ;'.y

Greater than Type .A quantity of radioactive material which may containfissile material provided ihat.the fissile material does not exceed thelimits in 10 CFR §71.18 and~§71.-22. The decay heat load is limited to9 watts.

441^mmrarammmmjremram^mmmmramTyE^mmmm;^;^;!!

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3& 6. (a) For any package containing water and/or organic substances which could* radiolytically generate combustible gases, determination must be made byH tests and measurements or by analysis of a representative package such thatg the following criteria are met over a period of time that is twice theg expected shipment time:

jj (1) The hydrogen generated must be limited to a molar quantity that would beg no more than 5% by volume (or equivalent limits for other inflammable

gases) of the secondary container gas void if present at STP (i-e-> nog more than 0.063 g-moles/fr at 14.7 psia and 70°F); orn£ (2) The secondary container-and-cask cavity must be inerted with a diluent£ to assure that oxygen must be limited to 5% by volume in those portionsjj of the package which could have hydrogen greater than 5%.

z. For any package delivered to a carrier for transport, the secondary container£ must be prepared Tor shipment in the same manner in,which determination for£ gas generation is made. Shipment period begins when the package is prepared£ (sealed) and, must ;>e.;compl eted within twice the e'xpected shipment time.

5 (b) For any package shipped within,10.days of preparation, or within 10 daysafter venting of drums-; or. other secondary^containers, the determination ing (a) above, need not be\m£a>e, and. the time restriction in (a) above does not

apply. _,_ '}<'"Wyi;s\ r'-'' ' * •'^:f'"

7. Maximum gross weight o%the contents,: secondafyi containers, shield inserts andshoring is limited to,;2p|pjDp|pounds. .•:',:} : v :

8. Except for close. ffittingAcontintsi scoring musr be placed between secondarycontainers and the cask cavity',to Mnimfze movement during, normal conditions oftransport. . ' :i Vv ;;; '- -

9. The lid and shield pluglifting lugs must not be used for lifting the cask, andmust be covered in transit. „


(a) Prior to each shipment, the packaging Neoprene lid seals must be inspected.The seals must be replaced within twelve (12) months prior to shipment.Also, seals must be replaced with new seals if inspection shows any defects.Cavity drain and vent lines must be sealed with appropriate sealant appliedto the pipe plug threads.

(b) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures of Section 7.0 of the application and ScientificEcology Group, Inc. supplements dated May 16, 1990 and September 7, 1995.

(c) Each cask must meet the Acceptance Tests and Maintenance Program of Section8.0 of the application, as supplemented. In addition, the cask must be leaktested within twelve (12) months prior to shipment and each seal must be leaktested after replacement in accordance with Paragraph 8.1.3 of theapplication.

| 442

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NRC FORM 618A(3-96)



11. The cask body and each lid must be marked in accordance with 10 CFR §71.85(c).

12. The packages authorized by this certificate must be transported on a motorvehicle, railroad car, aircraft, inland watercraft, or hold or deck of a seagoingvessel assigned for the sole use of the licensee.

13. Optional shield inserts may be used as needed. The optional shield inserts mustbe fabricated in accordance with Scientific Ecology Group, Inc., Drawing No.STD-02-086, Revision 0.


15. Expiration date: April 1, 1999. . This certificate is not renewable.

.;/'"' REFERENCES./ '/ ,

Hittman Nuclear applicationSdated December 14, 1987. .!>'"" ':

Hittman Nuclear supplements datefe. January.26, MarchS|5, and June 10, 1988.

Scientific Ecology Group, Inc.?^up|>iimen1^/daied':1'"-|p%i| 3 and May 16, 1990;January 26, June 10, and 0ctqbe>5f4v 19.93;vFebruary^3J§F'ebruary 25, andMarch 2, 1994; and September;!t6^9>^\ ';;£#* ;/

8

^ v ^ J P ^ E . U,:S-. JSlUCLEAfl REGULATORY COMMISSIONfl REG^ , • \

Date:

/y -^William D. Trav'ers, tfirector^-,/Spent NFue^l..Project Office

Office^of Nuclear Material Safetyand Safeguards

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USA/9224/Ad. PAGE NUMBER e. TOTAL NUMBER PAGES

4

2. PREAMBLE



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OFTHE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND JDENTIFICATION OF REPORT OR APPLICATION:


Scientific Ecology Group, Inc.application dated May 18, 1993.

c. DOCKET NUMBER71 _ g 2 2 4

4. CONDITIONS

This certificate is conditional upon fulfilling the requirements' of lO.CFR Part 71, as applicable/and the conditions specified below.

(a) Packaging

(1) Model Nos.:.

(2) Description^

Steel encased, lead Iftieildetl cask-for rad£o>"|tive material. The cask is aright circular cyslin^t81~l/2!jsn/9h|s \\igffjfy?81-3/4 inches in diameter. Thecask cavity is 73\378^§ife)j^-;-h''iig'h*Dy775^încl\es in diameter. The caskside walls const^f^f'^3./^jich---th,tc"Ânj|i* sêet shell, a 1-3/4-inch leadshell, and% 7/8î$h,t1ra7c^^^ base is comprised oftwo, 2-inch?thick;ji|e9j} p l ^ form\;a 4-inch thick base

l i ^ % ^ t ^ shells of the sidesteel shells of the

p ^ ^ ; ^ p | ; inch thick steel plateswhich are stepped and weldedv€.qs[^t|i|f to-'inate with;th'e steel flange. Thecask closures afVsealed by aNe'dpfene gasket located between the l id andsteel flange, positive closure of the l id is accomplished by eight rachetbinders. The l id contains a centrally located shield plug comprised of two,2-inch thick steel plates'arid one, 1-incH thick steel plate stepped andwelded. The shield plug is sealed by a Neoprene gasket, and eight, 3/4-inchstuds and nuts are used to provide positive closure.Tie-down is accomplished by four tie-down lugs welded to the cask body.There are four cask l i f t ing lugs, three l id l i f t ing lugs, and one shield plugl i f t ing lug. The package gross weight is approximately 48,000 pounds.

(3) Drawing

The Model No. HN-190-2 packaging is fabricated in accordance with HittmanNuclear & Development Corp. Drawing Nos.: STD-02-080, STD-02-081, and STD-02-082, all Rev. 0.

444

!iif^^

NRCFORM618A(3-96)



(b) Contents



• • * !

( i )

(ii)

Materials in which the radioactivity is essentially uniformlydistributed and in which the estimated average concentration pergram of contents does not exceed:

0.0001 millicurie of radionuclides for which the A2 quantity inAppendix A of 10.CFR Part~71 is not more than 0.05 curie:

0.005-millicurie of radionuclides,for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 0.05 curie, but notmore/than 1 curie; or /y ,

0l'3^mi]licurie of radionuclides fo»>-which the A, quantity in-Appendix A. of 10 CFR Part 71 .i0more than 1 curie.

Objectsfof^nonradêt^vermatejlral externally contaminated withradioacîVelmateria^, proyidtd^that the radioactive material isnot ^readllyydispefsjble artd.fhTûrface contamination, whenaveâgedôy'ej;-arf area of*.l<squfre meter, does not exceed0.0fi0fc{mt^#t1e--(Z2(^,-p0qîînt^'rations^per minute) per squarecenînfeter;^f^diiBniiclijil^forrpii'd^ thexî quantity in

.Appen^x#of^0:;CFRPart;jl isl^fpi^more;than 0.05 curie, or-:0OOITipil JEU 'fe'(2; 0'pJ!Q00.4,1siiftegra-y>ob's per minute) per

rad,ionucl idei:

(2) Maximum quantity ofr. V-..

Greater than^Jype A^quantity of radioactive material which may containfissile material proyid^d the fissile/material does not exceed the limitsin 10 CFR §71.53/'The;..weight' of ihe'contents and secondary containersshall not exceed 14,200 pounds and the internal decay heat load shall notexceed 7 watts.

445

BFNRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)



(1) The hydrogen generated must be limited to a molar quantity that would beno more than 5% by volume (or equivalent limits for other inflammablegases) of the secondary container gas void if present at STP (i.e.,g) y cntainer gas void if presentmore than 0.063 g-moles/ft3 at 14.7 psia and 70°F); or

no

(2) The secondary container and cask cavity must be inerted with a diluent toassure that oxygen must be limited to 5% by volume in those portions ofthe package which could have hydrogen greater than 5%.

For any package, delivered to a carrier for transport, the secondary containermust be prepared for shipment in the same manner in which determination forgas generation is made. Shipment period begins when the package is prepared(sealed) and must^be completed within twice that expected shipment time.

(b) For any package shipped within 10 days of preparation, or within 10 daysafter venting of drlim^lor oth,er«;,secondary cpntainers, the determination in(a) above need not be made, and'the timeirestriction in (a) above does nota p p l y . '•-'?<v' .-..;••/;• ''•'•':•&•'•

Except for closet i d

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must be covered in transit!

p e, fitting{contents> s.hori.ng;roJstSbe, placed between secondarycontainers and the cask, .cavity^ prevent, mpyMenib during normal conditions oftransport.

The lid and the shield pilingJiftirig/TugVmust ndt>be used for lifting the cask, andmust be covered in transit. •% S ; V'-^

9. In addition to the requirements of'Sub'part G of 10 CFR Part 71:

(a) Prior to each shipment,*;the packaging lid seals if opened (or if securityseal is broken), must be inspec|edv_{rhd seals must be replaced with newseals if inspection shows any defects or every twelve (12) months, which everoccur first. Cavity drain line and optional vent/test connection must besealed with appropriate sealant applied to the pipe plug threads.

(b) Each packaging must meet the Acceptance Tests and Maintenance Program ofSection 8.0 of the application. In addition, the cask must be leak tested atleast once every twelve (12) months in accordance with Subsection 8.1.3 ofthe application.

(c) The package shall be prepared for shipment and operated in accordance withthe Operating Procedures of Section 7.0 of the application.

4 4 6

7&7K7K2£U&W?tUK7K71!!LZEJ£L2Qffiffi7&7W7ft7^

^NRCFORM618A(3-96)

CONDITIONS (continued). U.S. NUCLEAR REGULATORY COMMISSION



11. The package -authorized by this certificate must be transported on a motor vehicle,railroad car, aircraft, inland watercraft, or hold or deck of a seagoing vesselassigned for the sole use of the licensee.



' REFERENCES

Scientific Ecology Group, Inc., application dated May 18, 1993.

Supplement dated: June 23, 1393.

Y FOR THE U.S. NUCLEAR REGULATORY COMMISSION

William D. Trav^rs, DirectorSpent Fuel Project Office

, Offi ce of Nuclear Materi al Safety'and S f u d

Date:

iV'^ahd-Safeguards

447

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NRC FORM 618(3-96)10 CFR 71




10


USA/9225/RIin F

d. PAGE NUMBER

1


61. PREAMBLE



: ISSUED TO (Name and Address)

NAC International, Inc.655 Engineering DriveSuite 200Norcross. GA 30092


Nuclear Assurance Corporation applicationdated March 24, 1995, as supplemented.


4. CONDITIONS ., -i ' ^ . V . ->•This certificate is conditional upon fulfilling the requirements of Iff CFR Eart 71, Ss applicable^ and the conditions specified below.

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5.

(a) Packaging "

(1) Model No.: NAC-LWT/

(2) Description•••?.?*?•> ^^

The LWT is a steel-ttransport one

the package, with' impa^^jpni't^'^3r|e!?3EHf|f^he"s }M§/by 65-Jnches in diameter.The cask body is--appro7Rma^e;T^--2l&'d]Hhch^sUfn;Jengt.n-c|nd 44 inches in diameter.

The volume of the

The cask body consists ,of a .75-inchvfl^Tdk*'stainless s.te\eT inner shell, a 5.75-inch-thick lead gamma shield,,,^ 1.2-inch-tKick stainless steel outer shell, and a neutronshield tank. The inner arid outer shells are welded^to a 4-inch-thick stainlesssteel bottom end forging. The.cask bojttom consists "of a 3-inch-thick, 20.75-inch-diameter lead disk enclosed by a^r.SHnch-ihick^stainless steel plate and bottom endforging. The cask lid is 11.3-inch-thtck stainless steel stepped design, secured toa 14.25-inch-thick ring forging with twelve 1-inch diameter bolts. The cask seal isa metallic 0-ring. A second teflon O-ring and a test port are provided to leak testthe seal. Other penetrations in the cask cavity include the fill and drain ports,which are sealed with port covers and teflon 0-rings.

The neutron shield tank consists of a 0.24-inch-thick stainless steel shell with0.50-inch-thick end plates. The neutron shield region is 164-inches long and5-inches thick. The neutron shield tank contains an ethylene glycol/water solutionthat is 1% boron by weight.

448

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NRCFORM618A(3-96)




The cask is equipped with aluminum honeycomb impact limiters. The top impactlimiter has an outside diameter of 65.25 inches and a maximum thickness of 27.8inches. The bottom impact limiter has an outside diameter of 60.25 inches andmaximum thickness of 28.3 inches. Both impact limiters extend 12 inches along theside of the cask body.

The maximum weight of the package is 52,000 pounds and the maximum weight of thecontents and basket is 4,000 pounds.

(3) Drawings

93

(i) The packaging is constructed in accordance with the following Nuclear AssuranceCorporation Drawings:

LWT 315-40-01, Rev. 2LWT 315-40-02, Rev. 5LWT 315-40-03, Rev.LWT 315-40-04, Rev.LWT 315-40-05, Rev.LWT 315-40-06, Rev. 4 , .LWT 315-40-08, Rev. 5 (Sheets 1-3)

9 (Sheets 1-6)*5.4.

Cask AssemblyBody AssemblyTransport Cask BodyCask Lid AssemblyUpper Impact Limitertower Impact LimiterCask Parts Detail

* Packaging Unit Nos.Sfi 2, 3, 4, and 5 are constructed in accordancewith Drawing No. LWT 315-40,-03, Rev. 6 (Sheets 1-6).

(ii) The fuel assembly baskets ape constructed fn accordance with the followingNuclear Assurance Corporation.Drawings:

LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-LWT 315-

40-09,40-10,40-11,•40-12,40-045,40-046,40-047,40-048,40-049,40-050,40-051,•40-052,

Rev. 2Rev. 2Rev. 1Rev. 3Rev.. 2Rev. 2Rev. 2Rev. 0Rev. 2Rev. 2Rev. 2Rev. 0

PWR Basket SpacerVPWR. Basket'BWR Basket AssemblyMetal Fuel Basket Assembly42 MTR Element Base Module42 MTR Element Intermediate Module42 MTR Element Top Module42 MTR Element Cask Assembly28 MTR Element Base Module28 MTR Element Intermediate Module28 MTR Element Top Module28 MTR Element Cask Assembly

449

'vi

11NRC FORM 618A(3-96)



5.(b) Contents


(i) Irradiated PWR or BWR uranium oxide fuel assemblies, HEU and LEU MTR fuelassemblies, or individual PWR rods of the following specifications:

Fuel form

Nominal pelletdiameter, in.

Cladding material

PUR

Clad UO2pellets

0.3659 -

Nominal cladding < ,-r i'thickness, in. . '-i

Maximum fuel rod _.;;.*length, in.

Assembly array

••^zircalloy-4

162. .38.4

Maximum assemblyweight, lbs

Maximum initialfuel pin pressureat 70F, psig

Initial U 2 3 5

enrichment, w/o


Maximum averageburnup, MUD/MTU

1,650^;f;

/>

')• •565^)

3.7 (max)

475

35,000

565 n/a

4.0 (max) 80-94

Minimum cooling time 2 yr

186

30,000

2 yr

0.377

550,000

3yr*

n/a

20 (max)

1.722

90,490(50% U 2 3 5)

1 yr

* The maximum burnup for NISTR is 642,000 MUD/MTU, with a minimum cool time of 3.5 years.** Up to two of the 25 PUR rods may have a maximum burnup of 65,000 MHO/MTU.

450

BUR

Clad U02pellets.

0.487

Zircalloy-4

HEUMTR

Claddedplates

0.02i-(actfvefuel thickness)

Aluminum ". :>

LEUMTR

Claddedplates

0.021 (activefuel thickness)

Aluminum

PUR Rods

Clad U02pellets

0.3659

Zircalloy-4

0.0242

160

.Parallel"plates

./; -''13.0v

25 Rods(max.)

n/a

565

5.0 (max)

58.2

60,000**

150 days

,

• -. f . • • -

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5.(b)(l) (continued)

(ii) Metallic fuel rods containing natural enrichment uranium pellets with a-luminumcladding" 0.080-inches thick. The fuel pellet diameter is 1.36 inches and themaximum fuel rod length is 120.5 inches. The maximum weight of uranium per rodis 54.5 kg with a maximum average burnup of 1,600 MWD/HTU and a minimum coolingtime of one year.

5.(b)(2) Maximum quantity of material per package: Not to exceed 4,000 pounds,including contents and fuel assembly basket.

(i) For the contents described in Item 5.(b)(l)(i): one PWR assembly or two BWRassemblies positioned within the respective fuel assembly basket. Maximumdecay heat not to exceed 2.5 kilowatts per PWR assembly or 1.1 kilowatts perBWR assembly.

(ii) For the contents described in Item 5.(b)(l)(ii): up to 15 intact metallic fuelrods positioned within the appropriate basket. Maximum decay heat not toexceed 0.036 kilowatts per rod. Total weight of all rods not to exceed 1,805pounds. - -~- -. '• '

(iii) For failed metallic fuel rods of the type described in Item 5.(b)(l)(i.i):

(a) Up to six canisters containing one defective metallic fuel rodper canister. The canisters are 2.75-inchjj). failed fuel rodcanisters as shown on Nuclear Assurance Corporation Drawing No.340-108-D2, Rev. 10,'jand'are placed in a siXrhole'./Iiner as shownon Nuclear Assurance Corporation Drawing No. 315-040-43, Rev. 1.The maximum decay heat Toad for.a defective metallic fuel rod islimited to 5 watts; or,. . ,/ ; -j . •

(b) Up to three canisters containing either~up to three defective metallicfuel rods per canister or up t6;10; failed fuel filters per canister. Thecanisters are 4:00-inch I.D. failed fuel rod canisters as shown on NuclearAssurance Corporation Drawing No. 340-108-D1, Rev. 10, and are placed in athree-hole basket as shown on Nuclear Assurance Corporation Drawing No. 315-40-12, Rev. 3. The weight of the filters is limited to 125 pounds per canister.For canisters containing fuel rods, the maximum decay heat load is 15 watts percanister; and for canisters containing filters, the maximum decay heat load is5 watts per canister. The plutonium content of the filters shall not exceed 20curies per package.

(iv) For MTR fuel assemblies as described in Item 5.(b)(l)(i): up to 42 fuelassemblies positioned within an MTR fuel assembly basket. For NISTR fuel the42 fuel assemblies may be cut in half, producing 84 fuel bearing sections.Maximum decay heat not to exceed 1.26 kilowatts per package and 30 watts perfuel assembly.

451

rgg

g

g

* 5.(c) Transport Index for Criticality Control

not to exceed 1.0 kilowatts per package and 24 watts per fuel assembly.



5.(b)(2) (continued)

(v) For PWR rods as described in Item 5.(b)(l)(i): up to 25 intact individual rodsin a Type 304 stainless steel spacer canister with a wall thickness of at least0.12 inches positioned within the PWR or BWR basket. Maximum decay heat not toexceed 1.41 kilowatts per package.

(vi) For LEU MTR fuel assemblies as described in item 5.(b)(l)(i): up to 42 fuelassemblies positioned within an MTR fuel assembly basket. Maximum decay heat

d 1 0 kil k d 24 tt f l bl

(1) For Metallic Fuel Rods, HEU and 8LElhMTR fuelassemblies, and up to*25 PWR Rods: 0.4

(2) For BWR and PWR assemblies: • 100

6. Known or suspected failed fuel assemblies (rods) and, fuel with cladding defectsgreater than pin holes and hairline cracks are not,alithorized, except as describedin Item 5.(b)(2)(iii). -%^ S _., } .gp."

7. The cask must bedry (no fref :wat«r) when'deli yelre|j to a carrier for transport.

8. Bolt torque: The cask iMds^&pTts; must be torq.ue<£to ,2 60, ft-l.fc>s. The bolts used tosecure the vent and dra;in1port;?co)fey<S:TiiUst "b^Atoirqued^to 100 inch-lbs.

9. Prior to each shipment,-the package must;be ;ieak tested to 1 x 10"3 std cm3/sec,except that replaced seats.mu^t'i'be-leak tested: to; 5.5 x 10?. std cm /sec. Prior tofirst use, after third use, and. at I:ea's1f|once'with>in the 12-month period prior toeach subsequent use., the package must-;,be^.]^ak^tested to 5.5 x 10" std cm /sec.


(a) The metallic 0-ring seal tnust'be replaced prior to each shipment; and

(b) Each package must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application; and

(c) The package shall be prepared for shipment and operated in accordance with theOperating Procedures of Chapter 7 of the application, as supplemented, exceptthat replaced seals must be leak tested to 5.5 x 10 std cm /sec. If the caskis loaded under water or water is introduced into the cask cavity, the caskmust be vacuum dried as described in Chapter 7 of the application. The caskcavity must be backfilled with 1.0 atm of helium when shipping PWR or BWRassemblies.

452

^ ' . ; ^ ~ / r f . ? 5 7 - " ' - - * ^ :-"•:.•"»...•». '--'•>;.'• . •>:

NRC FORM 618A(3-96)



11. When shipping PWR, BWR, or MTR assemblies, or individual PWR rods, the neutronshield tank must be filled with a mixture of water and ethylene glycol which willnot freeze or precipitate in a temperature range from -40 °F to 250 °F. The waterand ethylene glycol mixture must contain at least 1% boron by weight.

12. A personnel barrier must be used when shipping PWR or BWR assemblies. Shipments ofMTR fuel assemblies or individual PWR rods must use the ISO container or a personnelbarrier.

13. Packages used to ship metallic fuel rods may be shipped in a closed shippingcontainer provided that the closed container, the cask tie-down and support systemand transport vehicle (trailer) meet the applicable requirements of the Departmentof Transportation. When the cask is shipped in a closed shipping container, thecenter of gravity of the combined cask^closed shipping container and trailer mustnot exceed 75 inches. -\ % ^ ' " ' '•.<•'/


15. Expiration Date: ,Eebrifary .28, 2000. . - '••'<>

• ••'':' N ' ^ & . \ REFERENCES '•'/%•>

NAC International, Inc., applic^%-dated/March 24yf§19j95.

i#%)d«15, Augusi'Ôflnd 24, November 3 and 30, andSupplements dated: May 12, \3fu)December 19, 1995;

?"'>'«<*

k k f ^ . ,J-'3FOR!TpfE; jf^. S . N.UCJEAR REGULATORY COMMISSION

Date:

William D. Travers," DirectorSpent Fuel Project OfficeOffice qfvNuciear Material Safety. and' Safeguards

453

îî^^^M^5L23^^

i ^ ^




88


9228

b. REVISION NUMBER

10


USA/9228/B(U)F

d. PAGE NUMBER

1


6REAMBLE



888


General Electric CompanyVallecitos Nuclear CenterP.O. Box 460, Vallecitos RoadPleasanton, CA 94566


General Electric Company applicationdated May 19, 1988, as supplemented.

c. DOCKET NUMBER 71-92284.CONDIT1ONS ; ' ' , " . ' . ' ' . •

This certificate is conditional upon fulfilling the requirements of lO.CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No.: 2000-

(2) Description. • «•';-'V

A steel encased l^d^hjelded'shipp.ingf^cjsk. The cask is within a double-walled overpack wtM3tor,oida^s;h|\^:impaef limiters at each end. Theoverall dimens(\^'nsfS^fe)^DproximatejS^i3^5 inches in'height and 72.0inches in diaiife%r. /- position. Thegross weight'ofvthe package: i s • app|;dWmate1-y; 33,550 .1 bs.

The cask is con^ru^te'd.iofi%o.>p6n"ere^tric^l-inch thick 304cylindrical.shells ^ASTM Ai2^pj^3oihed"i^the bottdm end t304 stainless steel fbrging^f(/\S|HA 182) The annul us bet

stainless steely ^ ^ p j ^ 3 ^ t o a 6-inch thick304 stainless steel fbrgin,g f(/\S|H>A 1.82).. The, annul us between the twoshells is filled with lead1 approximately 4 inches thick. The cask isapproximately-71.0 inches in height and has an outer diameter of 38.5inches. The cask cavity is approximately 26.5 inches in diameter and 54.0inches deep. / ,.. ,«. . . .

The cask lid is 304 stainless steel and lead, has a stepped design, and isfully recessed into the cask top flange. The lid is secured to the caskbody by 15, 1.25-inch diameter socket head screws. The cask is sealed byelastomeric 0-rings bonded to a thin aluminum disc-shaped ring. The caskis equipped with a seal test port on the side of the cask body, a ventport in the cask lid, and a drain port near the bottom of the cask.

The cask is positioned within an overpack constructed from two 0.5-inchthick concentric 304 stainless steel cylindrical shells (ASTM A 240). Theshells are separated radially by eight equally spaced tubes andhorizontally by two tube sections. A 304 stainless steel toroidal shellimpact limiter is attached to each end of the overpack. The overpackopens just above the lower impact limiter for access to the cask. The topof the overpack is joined to the base by 15, 1-3/8-inch diameter shoulderscrews.

454>%k >M<. T 7 K 7JC TIC TIC TIC TIC TIT 7*1; Tit TIC TIC TIC 7*(

Pr3

aHia3

:3«tatatCJ«cat3KMt3«cj«tJjttJ»t3«catat)t(>t( >tt»7w> w :



NRC FORM 618A(3-96)

5(a)(2) Description (Continued)

Gussets on the top and bottom impact limiters provide tie-down points forth'e package. The cask body is equipped with attachment plates for liftingdevices. The cask lifting devices are detached during transport.

(3) Drawings

(i) The packaging is constructed and assembled in accordance withGeneral Electric Company Drawing Nos. 129D4946, Rev. 9; 105E9520,Rev. 3; and 105E9521, Rev. 3.

(ii) Packaging Serial No. 2001 is constructed and assembled in accordancewith General Electric Company Drawing Nos. 129D4946, Rev. 9;101E8718, Rev. 11; and 101E8719, Rev. 10.

(iii) The HFIR fuel basket and liner are constructed and assembled inaccordance with General Electric Company Drawing No. 105E9523,Rev. .2.

(iv) The multifunctional rack is constructed and assembled in accordancewith General?.Electric Company Drawing>(!to. 105E9555, Rev. 2.

(v) The barrel rackiis constructed and ^assembled in accordance withGeneral Electpc;'Company Drawing |Jof*;i66D8066, Rev. 1.

(vi) The material ba.sjtet is construction accordance with GeneralEle.ctric>to'mp^^ 1.- .The material basketmay be us.ed<;with the mi|ltifunc1?ional^iiiapk and the barrel rack.

(vii) The TSR fufel;°Bas'ket£)is .con'struGted)'and assembled in accordance withGeneral Ele'rtfic^ComjjJin^ 105E9560Y Rev. 1.

(viii) The MTR;fuel basket i'sConstructed and assembled in accordance withGeneral(Electric Company Drawing No. 105E9557, Rev. 3.

(b) Contents i[J-- -.'•_. , .K


(i) Irradiated fuel rods, which may be cut or segmented.

(ii) Byproduct, source, or special nuclear material in solid form.

(iii) Irradiated High Flux Isotope Reactor (HFIR) fuel assembly,positioned within the HFIR fuel basket and liner as specified in5(a)(3). The HFIR fuel assembly is fabricated in accordance withOak Ridge National Laboratory Drawing.Nos. M-11524-0H-101-D, Rev. 0,and M-11524-0H-102-D, Rev. 0.

(iv) Irradiated.Tower Shielding Reactor (TSR) fuel elements, positionedwithin the TSR fuel basket specified in 5(a)(3).

4557&

F :WWWWWWWW:«i:WWWWWWWWWWWW_1 (NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION

(3-96)


5.(b) (1) Type and form of material (Continued)

(v) Irradiated MTR-type fuel assemblies, positioned within the MTR fuelbasket specified in 5(a)(3). The fuel material consists of U308 inaluminum clad plates. The maximum initial uranium enrichment is93.2 weight percent U-235, and the maximum U-235 mass is 355 gramsper fuel assembly. The fuel assemblies may be sectioned only in thenon-fuel bearing region of the assembly.

(vi) Irradiated MTR-type fuel assemblies, positioned within the MTR fuelbasket specified in 5(a)(3). The fuel material consists of U3Si2 inaluminum clad plates. The maximum initial uranium enrichment is20.0 weight percent U-235, and the maximum U-235 mass is 355 gramsper fuel assembly. . Jhe-fuel assemblies may be sectioned only in thenon-fuel bearing >/r4gion;"of:- tHe-assembly.

333«3

33

i8 , . . -

(2) Maximum quantity-of*material per package -Not to exceed; 5,450 lbs, including carrier racks,- shoring, secondarycontainersând^shielding liner.

(i)3

i

.maximum burnup of 45

Fifssjile c f ^ | ^ ^ < ^ ^ ^ c ' e ^ ^ d ^ g r a i n s U£235 equivalent mass withini t ia l enr;ichmept n^g%o||xceed'5tweight/percent in the f iss i leisotope; minimum^pe^fWfteametir/io/iF 0.35 4nch, maximum burnup of 38GWd/MT/jMnd minimum^bWng timevof 120^days. Fuel rods must becontaineîtf closed, 5-inch scheduleÔ^pipe, with a maximum of437.5 granis U-235 equivalent per..pipet"

( i i ) For the contents described in^ 5 (b) ( l ) ( i i ) :

2000 watts decay heat. Fissile contents not to exceed 500 gramsU-235 equivalent mass. Carrier racks specified in 5(a)(3)(iv) or5(a)(3)(v) must be used for contents exceeding 600 watts decay heatper package.

( i i i ) For the contents described in 5 (b ) ( l ) ( i i i ) :

One HFIR fuel assembly. The fuel assembly is composed of one innerfuel element, with up to 2628 grams U-235, and one outer fuelelement, with up to 6872 grams U-235. The maximum uraniumenrichment is 93.2 weight percent U-235. The maximum burnup perassembly is 2300 MWd, the minimum cool time is two years. Decayheat not to exceed •600 watts per package.

4 5 6

7¥J&^^

j



5.(b) (2) Maximum quantity of material per package (Continued)

(iv) For the contents described in 5(b)(l)(iv):

A maximum of 4393 grams U-235 per package. The maximum uraniumenrichment is 93.2 weight percent U-235. Decay heat not to exceed35 watts per package. The TSR fuel elements must be positioned andlimited within the TSR fuel basket as follows:

or a combination of upper and lowerfuel elements, for a total U-235 massof 1412 grams.

Middle fuel basket, section - .Uptq 4 fuel cover (lune) plates, for''/i""" a total U-235 mass of 304 grams.

Upper fuel basket section - Up to 6 annular fuel elements plus one..; cylindrical 'fuel element, for a total' . U-235 mass of-2677 grams.

(v) For'the contents, described in 5(b>{3)(v):

A maximum ofci4|9,l6 grams U-235 rpjrjipackage, and a maximum of710 grams U-lf35|per fueT bajsket/'-tew* For each fuel assembly, themaximum bnrr\^.fs:'S33lQMd/MUy/^^iie minimumcool time is 880days. Dep^y eal- no t to exceed;^35|wsatts* per fuel assembly, and

(vi) For; the Contents descrIibecJMin^5(b)(l)(^vi): , "

A maximum of" 14^570^^njsJjU^S^perrpackage^.'and a maximum of695 grams U-235 p'er^6j)|l^asjcet'.ce]:l. Fon;each fuel assembly, themaximum:burnup is 10bvGWds/MTU, and'the minimum cool time is 880days. Decay heat not to exceed 35 wat^s-per fuel assembly, and1500 watts'/pen package. ,, v*"'

(c) Transport Index for CriticaTity Contrbf -


For the contents described in 5(b)(1)(i),5(b)(l)(ii), and 5(b>(1)(iii); and limitedin 5(b)(2)(i), 5(b)(2)(ii), and 5(b)(2)(iii): 100

For the contents described in 5(b)(l)(iv),5(b)(l)(v), and 5(b)(l)(vi); and limited in

457

Lower fuel basket section - Up to 4 upper or lower fuel elements,

5(b)(2)(iv), 5(b)(2)(v), and 5(b)(2)(vi): 50

a^

NRCFORM618A CONDmONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


6. Plutonium in excess of twenty curies per package must be in the form of metal, «metal alloy or reactor fuel elements. m

isg 7. The U-235 equivalent mass is determined by U-235 mass plus 1.66 times U-233 masss plus 1.66 times Pu mass.

a 8. Bolt torque:£ •g The cask lid bolts must be torqued to 690 ft-lbs (lubricated).£g The bolts used to secure the top of the overpack to the overpack base must beg torqued to 100 ft-lbs (dry).H£ 9. (a) For any package containing organic or inorganic substances which could£ radiolytically generate combustible.gases, determination must be made by£ tests and measurements or;by analysis of a representative package such£ that the following cr-iteria are met over,a period of time that is twice£ the expected shipment time: "--•'<''£ (i) The hydrogen generated must be limited t o a . molar quantity thatC would be no more than 5% by volume (or equivalent limits for otherc inflammable gases) of the secondary,container gas void if present atj STP (i.e.v^no/more than 0.063 g-moj^s/#t3 at<r14.7 psia and 70*F); or* (ii) The secondarj|-feofotaineY^nii cafsK'Jba^ty must be'inerted with a

" diluent to apsuf-e that-;oxygenvmij%t^| limited'to 5% by volume inthose portions.-^ the package..wH^J^could have .hydrogen greater than

% For any packag^dlllyer'ed^to'a:;c;armef fop^jinsportV." the secondary5 containermustê^pêpared; for] 'sHipptent in\,tHe same"m'anner in which5 determination fqr gâspg rierationl is-Jm^^^^^ begins when theS package i:^>jepa1fisd^>al^d^%'q3ûstêômp1e^d:within twice theS expected shipment time'f '^fMM^' *«-A?} <r'^3 "/'••••.- ' ' ' ^ i ^ ' '" i f ; : V ^S (b) For any package>'eontaining materials with a.^racfioactivity concentration\ not exceeding that fox low specific activity material, and shipped withinS 10 days of preparation^ >of. ,wj.thin,/10 days after venting of drums or otherS secondary containers, the dete^mination in (a) above need not be made, and§ the time restriction in (a) above does not apply.aS- 10. Prior to each shipment (except for contents meeting the requirements of special

form radioactive material), the package must be leak tested to 1 x 10'3 std3 cm3/sec. Prior to first use, after the third use, and at least once within the8 12-month period prior to each subsequent use, the package must be leak tested to3 1 x 10'7 std cm3/sec.S 11. The cask must be vacuum dried prior to shipment if contents are loaded under3 water, or if water is introduced into the cask cavity. During shipments for3 which vacuum drying is performed, the cask cavity must be filled with helium.33

3

I ' 4582£ ^K2SU&7^7^7V^J^7K^^7¥,7^7¥^7^7^7^L^J&J^7¥^7¥^7^7^7¥^7^7^2Ski

^dKwîrsiîiifwsKw^tn^ww

SSsa

SS





(a) Prior to each shipment the cask seal must be inspected. The seal must bereplaced with a new seal if inspection shows any defects or every 12months, whichever occurs first; and

(b) Each package must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application, except that inspections in Section 8.2 ofthe application must be performed at least once within the 12-month periodprior to each use; and

(c) The package must be prepared for shipment and operated in accordance withthe Operating Procedures of Chapter 7 of the application.

Appropriate carrier racks or shoring.must be provided to minimize movement ofcontents during accident conditions of.transport. A lead liner, as shown inGeneral Electric Company Drawing No. 129D4922t\Rev. -, which was included in theMarch 29, 1989, supplement, may be used inside the cask.

Each batch of ethyl&he propylene seals must be tested in accordance with Section8.1.4.2 of the application.

Fissile mass limits fororeactor fuel are based oricfissile mass prior toirradiation..;'. ••^--^X , ''-l?-'.:''

16. The package .authorized by^fhiVcer^fficate.isihêby approved for use under thegeneral license provision^-oniO ..C*FR/;§£1.12.§#7

' • *; i 'u'n ~^c? J^z)'-*' •• • V" • - ? * .*•' .

Expiration date: Jun'M30>%9Kvr(> V-i -%><t^ ,-frW.'

;r- %-M^ ^REFERENCES fe" " •-'

13.

14.

15.

17.

piircatf dGeneral Electric Compiihx appiircatfon d a i ^ M y fc'Ms. -•:"'-';

Supplements dated: MareK;;29 and AuguslC%Jlt^89; Mky 30, Ôctober 11, andDecember 12, 1990; May 22V1991; June 8, July 27, August^,''and December 9, 1993;April 29, July 28, and December u , 1994; May 19 and 30-ând November 20, ,1995-May 23 and July 2, 1996. : 1> / . ^ r

'FOR THE U.S. NUCLEAR REGULATORY COMMISSION


and Safeguards

Date:

459JSJ^


_ U.S. NUCLEAR REGULATORY COMMISSIONCERTIFICATE OF COMPLIANCE






PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theapplicablesafety standardsset forth in Title 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATION "a. ISSUED TO {Name end Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Transnuclear, Inc. applicationdated November 22, 1988, as supplemented.

v _ , V « a DOCKET NUMBER 7l^9.2'334. CONDITIONSCONDITIONS < \-jt ^'V/ <\

This certificate is conditional upon fulfilling;theVequirements of 10 CFR Part 71, as applicable, and the/conations specified below.A. •V^^/ /X

(a) Packaging y$

Modeler(1)

(2) Description

The packagelimit|V\s atThe overall JnB stijQnsand 9 2 @ c h e s ^ p i k e r 4is appro^mate>y^2îfcJjThe casleâ,vity'fhas^\lenxdiameterXofj.^ inche isteel innef^lêll, a

cased ,cask will? wood impact[e^sfjfî'n^ga^K i^-avr i ght~ei rcul ar cyl i nder.jth'e piaqklgt'ng afte^p'pYoximately 178 inches longfritfte"i!P!PAct l i j p e r s installed. The cask body

.a/iiottter diameter of 51 inches.^xj|aiely lU^/iches and an inside[j sfmade of^. 0.75-inch stainless

T, v le^d aniju tusT a 1.5-inch thickstainless s^tlejKputer she!lâÔ.5-inch thicfej-nner bottom plate and a2.5-inch thicR<*lutside bottom plate. Theîd shielding is 6 inchesthick in the bottorr£end_j3f tlje ca,sk. >The outer shell of the cask body iscovered with a staimes^TêeV'bhte7:iTial'>'ishield. The closure lid consistsof a 2.5-inch thick outer stainless steel plate and a 0.5-inch thickinner stainless steel plate separated by 6 inches of lead shielding. Thelid is secured by sixteen 1.5-inch diameter closure bolts. Twoconcentric silicone 0-rings are installed in grooves on the underside ofthe lid. The cask is" equipped with a sealed leak test port between the0-rings, a vent port in the closure lid and a sealed drain port in thebottom of the cask.

Each impact limiter is attached to the cask by eight 1.75-inch diameterbolts. The cask is equipped with 6 trunnions, four at the top and two atthe bottom.

The gross weight of the package is approximately 80,000 pounds, includingmaximum contents of 9,500 pounds.

4 6 0

^

ww^

NRC FORM 618A(6-B3)



(3) Drawings

The packaging is constructed in accordance with Transnuclear, Inc.Drawing Nos. 990-701, Rev. 5; 990-702, Rev. 6; 990-703, Rev. 6; 990-704,Rev. 3; 990-705, Rev. 4; 990-706, Rev. 3; 990-707, Rev. 2; 990-708, Rev.4; 990-709, Rev. 1.

(b)

-5.

7.

8.

9.

10.

Contents

(1) Type and Form of Material

Dry irradiated and contaminated non-fuel-bearing solid materialscontained within a seconds^ qpot'Mt

(2) Maximum quantity of ip-ferial per packagV£

Greater than^/fype A quantities of radioactive material which may includef i s s i l e material provided that the f i s s i l e mater4afi does not exceed thegenerally Hfensed mass limits specified in lOCFR^pl.lS, 71.20 and71.22. T+I.e, c6§tsttfcs may not exceed 2,000JtjilipânÂ£aquantity. The decayheat of gVMi conof the Contentspounds.

As appropriate1^ shorijigprevent significant

Both the inneVtaskwhen the package, is

In addition to tfrl req

(a) Prior to eaW^hipment,

(b)

(c)

The maximum gross weighting is |f?pited to 9,500

ary conta<wer sufficient toJ~ ~* dentlgeondi t i ons.

free of water

71:

^ ,t t _.. _v_, v be •j^Sjp^cted. The seals mustbe replaced"wifhyiew seals ifînspection showâny defects or every 12months, whicheverôccurs f i r s t ; and \

The package shall be i p § £with the Operating Procedures

|pment and operated in accordanceSection 7.0 of the application.

The package must meet the Acceptance Tests and Maintenance Program ofSection 8.0 of the application.

The package authorized by the certificate is hereby approved for use under thegeneral provisions of 10 CFR §71.12.

Expiration date: January 31, 2000

461

^

NRC FOHM 618A(6-83) CONDITIONS (continued)



REFERENCES

Transnuclear, Inc. application dated November 22, 1988.

Supplements dated: January 13, May 18, June 5, July 21, July 28, andAugust 11, 1989, and January 4, 1990.


Date:JAN 2 6 1995i

Cass R. Chappell^Section LeaderCask Certificatian^SectionStorage and Jj^^pd$t* Systems BranchDivision o^fMustritaCandMedicjrfJiHSPear Safety, NMSS

462

s ^



FOR RADIOACTIVE MATERIALS PACKAGES3 1.8.CERTIFICATE NUMBER


8C PACKAGE IDENTIFICATION NUMBER

USA/9234/B(U)Fd.PAGE NUMBER





. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE .DESIGN OR APPLICATIONa. ISSUED TO Wams and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Nuclear Containers, Inc.P.O. Box 1080Elizabethton, TN 37643

M

Nuclear Containers, Inc. applicationdated January 11, 1993, as supplemented.

^ 23 4» "c. DOCKET NUMBER

4. CONDITIONSThis certificate Is conditional upon fulfilling.thejequirements of 10 CFR Part 71, as applicable, and the/conditions specified below.

(a) Packaging

(1) Model No.*f^NCI-21P

(2) Descri pt<ifpff

OverpackrFor 30-overpacktU a rshells with thephenol ic-|crani pThe vol ume 'etweefilled witPo'ak w_.r _glued and najT&d togethe'the top half o^ktjie overpack"halves" are seewed with tenoverpack is 43-5/8/inches 0.Dpackage is 8,700 pound

no

uraniuêxafûoriê^ (UF65pcylinders. The"^mje^Bon^rucl^dôf two^stainless steel

hell sheila fil,4ed4with ,.fii:re resistant,

move

. ancfeSupplement K/TL-729.places of the two shells is

f of 3 layers of boardstroMsraminatiTjfEs of 3 layers of boaran^[<asketedaie,rizontal joint permitsoveip'from i-he^'base. The package

phe^'base. The packagefjeel toggle closures.

by 92 inches l%g. Maximum gross weight of the

A7TJ pg1-inch stainless'kfjeel toggle closures. Theb 92 i h l%g i

(3) Drawing

The Model No. NCI-21PF-1 packaging is fabricated in accordance with NuclearContainers, Inc. Drawing No. DED-206-B, Sheets 1 through 11, Rev. 5.

(b) Contents


Uranium hexafluoride contained within a Model 30B cylinder.


5,020 pounds uranium hexafluoride. Uranium enriched to not more than 5 w/o inthe U-235 isotope. The total quantity of radioactive material within apackage may not exceed a Type A quantity.

4 6 3

NRC FORM 61SA(6-83)




8.


The Model 30B cylinders must be fabricated, inspected, tested, and maintained inaccordance with American National Standard N14.1 (1990 Edition). Cylinders must befabricated in accordance with Section VIII, Division I, of the ASME (AmericanSociety of Mechanical Engineers) Boiler and Pressure Vessel Code and be ASME codestamped.

At least once every five years, each packaging must be inspected to verify thepresence and condition of the instffeti^^jffe inspection shall consist ofinserting a probe through eai£hfverfrhoieThô%firfie lid and base to confirm thepresence and rigidity of»%eHnsulation. For pac1las#igs which require drying, theinspection must be peKfoEmed after drying. " J^

In addition to the^&quirements of Subpart G of 10 CFR

Prior to eagaskets ^whichever tfcTcurs fir

Each packatjfng mustChapter 8.0T the

(a)

(b)

(c) The packacjjpshalthe Operating ProU

(d) The loadedprotector mustb .the cylinder % Removed from

overpack gaskets^jiu^be inspected. Thesespdefectsôr every 12 months,

oMaintenance Program of

atedSSP accordance with

projector. The valvenormal|ji|ndling practice when

Packagings manufacture'Oy/; Nuclear Containers, Incorporated, during the periodNovember 30, 1991, to October}, 1994, and having,NCnserial Nos. 487 through 619,but excluding 487A and 488A, Aqe auttôtfzed/^fûW until November 1, 1996.

10. Prior to each shipment, the stainless steel components of the packaging must bevisually inspected. Packagings in which stainless steel components show pitting,corrosion, cracking, or pinholes are not authorized for transport.



464WM«M«M8M j^î^^m^M^^^jû^g^^^

..•:'— -ir; • ;-1* • -' -

m&a>Kf>ft$?&>M^^

NRC FORM 618A(6-83)

. CONDITIONS (continued)



REFERENCES

Nuclear Containers, Inc. application dated January 11, 1993.

Supplements dated: September 10, 1993; and July 21, 1994.


Date:

V-Travers, Director

Spent FueSl^ject OfficeOffice of Nucfl sv Material Safety

and Safeguards^

4 6 5

^

^



FOR RADIOACTIVE MATERIALS PACKAGESLa.CERTIFICATE NUMBER





52. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJ3ESIGN OR APPLICATION 'a. ISSUED TO (Name end Address} b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

NAC Services Inc.655 Engineering DriveNorcross, Georgia 30092

Nuclear Assurance Corporation applicationdated August 20, 1992, as supplemented

fes-^Vi v'c. DOCKET NUMBER

4. CONDITIONSThis certificate is conditional upon fulfilling.the:requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a)•#f

PWR fuelf

t:

i mpacr Ti mi t e r « i eadh^ef a I i p^ paolf ol 1 ows^ WUiM I J ! I J f&

. _ . _ | d shipping xsask for irradiatediGa-skTbo!d^||^>idht/circu1^r cylinder with an" i f rL-1-^- r i-^e h.l^pproximate dimensions as

W Is

Cayj;tfy w _CasMfody outerliiattNeutrof^shield outer"aia¥eterLead shieltl thicknessNeutron shieTd^thigknessImpact limite'r/ai^m'eterX, J:r " v<Package length:

without impact limiterswith impact limiters

r7}l| inches^6St inches; *87 inches99 inches

3.7 inches5.5 inches124 inches

193 inches257 inches

The maximum weight of the contents is 39,650 pounds and the maximum grossweight of the package is 250,000 pounds.

The cask body is made of two concentric stainless steel shells. The innershell is 1.5 inches thick and has an inside diameter of 71 inches. Theouter shell is 2.65 inches thick and has an outside diameter of86.7 inches. The annul us between the inner and outer shells is filledwith lead.

The inner and outer shells are welded to steel forgings at the top andbottom ends of the cask. The bottom end of the cask consists of twostainless steel circular plates which are welded to the bottom end

465

J^wTwâAwTw^wAgAwAwrawSw^wnwAWTswrewTs^^

NRC FORM 818A(6-83)




5.(a)(2) Description (Continued)

forging. The inner bottom plate is 6.2 inches thick and the outer bottomplate is 5.45 inches thick. The space between the two bottom plates isfilled with a 2-inch thick disk of a synthetic polymer (NS4FR) neutronshielding material.

The cask is closed by two steel lids which are bolted to the upper endforging. The inner lid (containment boundary) is 9 inches thick and ismade of Type 304 stainless steel. The outer lid is 5.25 inches thick andis made of SA-705 Type 630 stainless steel. The inner lid is fastened by42, 1-1/2-inch diameter bolts and the outer lid is fastened by 36, 1-inchdiameter bolts. The inner lid is sealed by two metallic 0-rings. Theouter lid is equipped withâ sjh\gl*e metallic 0-ring. The inner lid isfitted with a vent apd $&£§IL por-tSihajh/are sealed by metallic 0-rings andcover plates. ^ %J> L.j/t

CM *V :ket shell constructed

)proximately 99 inchesiless steel fins which

Dper plates areriTled with NS4FR

each^Sfkl with an impact

The cask bodî^surrounded by a 1/4-inch thictfof 24 s t a i n > ^ r steel plates. The jacket shellin diametef^pd is supported by 24 longitudinal,are connected ^Hthe outer shell of thebonded tpfme fT^r^^tlie space between

_ eclimiterMade of re<35g§Si a^d

fccommodat*tfithiiJhin31,als<

The fue>Q)asket.assemblies.of stainlesssleevesV^Theinch diameterType 606JUT6 allsix, 1-5/8^PH s t a in l e s^ t ee l l

• ^

Four lifting t ^ ^ j o n s are welded to the topêwTorging. The package isshipped in a horn^ntal orientation and is sup^rted by a cradle under thetop forging and by twossirunBion.socketsJttfcated near the bottom end of thecask.

reade

,p to 26 PWR fuelquare sleeves madewalls of the-inch thick, 70.86as 20 fins made of

ns are connected bys made of Type 17-4

(3) Drawings

The package is constructed and assembled in accordance with the followingNuclear Assurance Corporation Drawing Nos.:

423-800, sheets423-802, sheets423-803,423-804, sheets423-805,423-806,423-807, sheets423-809, sheets423-810, sheets

1-2, Rev. 31-6, Rev. 6

Rev. 11-3, Rev. 2

Rev. 1Rev. 1

1-2, Rev. 01-2, Rev. 11-2, Rev. I

423-811, sheets 1-2,423-812,423-870,423-871,423-872,423-873,423-874,423-875,423-900,

Rev. 4Rev. 0Rev. 2Rev. 1Rev. 3Rev. 1Rev. 1Rev. 1Rev. 2

467iNJSui^yiusuausugiiXUBJSiM^^

NRC FOHM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


(b) Contents


Irradiated PWR fuel assemblies with solid U02 pellets. Each fuel assemblymay have a maximum burnup of 40,000 MWD/MTU when cooled for at least 6.5years, or 45,000 MWD/MTU when cooled for at least 10 years. The maximumheat load per package is 22.1 kilowatts. The maximum heat load perassembly is 850 watts. Prior to irradiation, the fuel assemblies must bewithin the following dimensions and specifications:

Assembly Type 14x14 15x15 16x16 17x17 j j j ^

Cladding Material Zirc-4 Zir.c-4 Zirc-4 Zirc-4 Zirc-4

Maximum Initial ^ • : k .:)Uranium Content v - 407 469 ,426 464 426(kg/assembly) • >,;>: ' •.

- > " v - ~ y/ „

M a x i m u m Initial ^ ^ --'•;ment ::-: v'" > > 4.2 4.2 ..s>-3'& '; 4.2 4.1

Enrichn

(wt% ^ U ) ;:;- -V£/\ ,/'ifSAssembly Cross- % %76 3 "8.20 ,,/> ; 8.10 '', 8.43 a 43

Section (in)" :>'to5:ll .'"to 8.54 \y^io 8.14 .to 8.54 *

Minimum Claddjng -;':;;ij|o23 '^(S)v024^•'"V" 0.025.-:^ 0.023 0.023Thickness (in) -••//,•'0\-\'< '• >

Pellet Diameter %^tQ J;|J*"^^390 ' , ? | ^ " to Sil'lll °-3088

Maximum ActiveFuel Length (in) 145.20 144 150 144 144


Twenty six (26) PWR fuel assemblies



468

U.S. NUCLEAR REGULATORY COMMISSIONNRC FORM 618A(6-B3)



6.

7.

8.

9.

10.

11,

12.

13.

14.

15.

The maximum heat load within the packaging at any time (transport, storage ortesting) shall not exceed the decay heat limits in 5(b)(l).

Known or suspected failed fuel and fuel with cladding defects greater than pinholes and hairline cracks are not authorized.

Water and residual moisture shall be removed from the containment vessel inaccordance with the procedures in Section 7.1 of the application.

least 2.9 X 10"5Containment vessel seals must be tested to a sensitivity of atstd-cm3/sec, and shown to have a leak rate no greater than 5.7!cm3/sec:

(a) Before first use of ,eac

(b) Within the 12-m@Vperiod prior to each

(c) After seal

All containmenuse.

79 X 10"5 std-

and

In addition tj^the requi

(a)

(b)

Each packagingspecif Rations

Each pacTragewith the#6eera

newj^rings after each

fabrication

n in accordanceapplication; and

W a i n e d inintena^ce Program in Chapter 8

(c) Each package must* yaccordance <«wfth the Acccof the applTe^on. v w ,

Prior to transport byrafll, the Association ofAmerkan Railroads must haveevaluated and approved the ^ J c a r a n d t h a s y « m used to support and secure thepackage during transport. ^ p ^ ~*jfc " ^ '

Prior to marine or barge transport, the National Cargo Bureau, Inc., must haveevaluated and approved the system used to support and secure the package to thebarge or vessel, and must have certified that package stowage is in accordancewith the regulations of the Commandant, United States Coast Guard.


Expiration date: September 30, 1999.

4 6 9

^ii}^s^sff l^^

NRC FORM 618A(6-83)

i




REFERENCES

Nuclear Assurance Corporation application dated September 27, 1990.

Nuclear Assurance Corporation supplements dated December 23, 1991; August 20, 1992;and August 19, 1993.

NAC Services Inc. supplements dated February 1 and 15, May 18, June 24, July 19,August 10, and September 30, 1994.

/ ULATORY COMMISSION

Date 03/26/96

William D. nravers.TSjrjQtorSpent Fuel Project Offrce^Office of Nuclear MateriWJcifety

and Safeguards

470

^^

^ *"7r''-.*'ji - * - • * ' '

fi®7V6riam7&m!r®Ki>Ki)m&i5^^

NBC FORM 618IM6)

10 CFR 71



i.a.CERTIFICATE NUMBER




42. PREAMBLE

a. This certificate is issued to certify that the packaging_and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."

b. This certificate does not relieve the consignor from compliance with any requirement of the reguiations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE43ESIGN OR APPLICATIONa. ISSUED TO Warns end Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Westinghouse Electric CorporationP.O. Box 355Pittsburgh, PA 15230

Westinghouse Electric Corporationapplication dated January 31, 1991,as.supplemented.

fec. DOCKET NUMBER 71~9239A. CONDITIONS c ^ \,J^ . J. \

This certificate Is conditional upon fulfilling tHe.requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

^'Fy

(a) Packaging Hi(1) Model N6s^: MCC-3 |M§§r4\ and^GC^ /

(2) Descr ip fCn * ^ ' '* ' % ', 1

\

The MCQ? p^ckagâ;fuel assfemblies^jassemblyêquippejcfassemblyV^Jhe atouter container b!1/2-inch T-Jjolts.1/2-inch T-" *

're ^Mpp^g-jGonâ-ftfers^for UnirradiaLted uranium oxide|Tê p%kagingsfcqr|| i i t 'of, a:'.steel fuel element cradle

1±n - -^r;piigb;a|ckland" an adpastable5fuel element clampingiblyjii'sij sjioejc mgyrjiea to a;<13-gauge carbon steel

....ura^ffeJffesM"CC#3Vcontain'er>is closed with t h i r t yThe^CC^fn^C(^ -5 t ; c | â iners t l j . e closed with f i f t y

The MCC-3 and MCCr4 containers are permanentftyi*equipped with vert ical Gd203neutron absorber platei^that are mounteoUon the center wall of thestrongback. Additional hî-zo^taVfed^y-heutron absorber plates, mountedon the underside of the s'trong'bickrâre required for the contents asspecif ied.

The MCC-5 container is permanently equipped with both the vert ical andhorizontal Gd20, neutron absorber plates. Additional vee-shaped, guidedGd203 neutron absorber plates are required for the contents as specif ied.

Approximate dimensions of the MCC-3 packaging are 44-1/2 inches O.D. by194-1/2 inches long. The gross weight of the packaging and contents is7,544 pounds. The maximum weight of the contents is 3,300 pounds.

Approximate dimensions of the MCC-4 packaging are 44-1/2 inches O.D. by 226inches long. The gross weight of the packaging and contents is 10,533pounds. The maximum weight of the contents is 3,870 pounds.

T

t

f

t

Iiiiit

I

I

i

NRC FORM 618A(6-83)




Approximate dimensions of the MCC-5 packaging are 44-1/2 inches O.D. by 226inches long. The gross weight of the packaging and contents is 10,533pounds. The maximum weight of the contents is 3,700 pounds.

(3) Drawings

The MCC-3 packaging is constructed in accordance with WestinghouseElectric Corporation Drawing No. MCCL301, Sheets 1, 2 and 3, Rev. 4.

t

The MCC-4 packag£ngPis?'ilonikfrac-6e^^|f accordance with WestinghouseElectric Coppd%itbn Drawing No. MCCLSQ^Sheets 1, 2, 3, and 4,Rev. 5.

with Westinghousethrough 9, Rev. 2.

The MCQ*^packaging is constructed in accorElectrffe* Corporation Drawing No. MCCL501

(b)

Unirfadiatejurlrrfum-2

Table 1/4.2dated July

Table 1-4.3, Rev. 6,dated July 26, 1994

Table 1-4.4, Rev. 6,dated July 26, 1994

Table 1-4.5, Rev. 4,dated January 14, 1994

h a maximum

tions^given inin^fche following tables

emefi^d:)y ParametersFuel Assemblies

el Assembly Parameters15 Type Fuel Assemblies

Fuel Assembly Parameters16x16 Type Fuel Assemblies*

Fuel Assembly Parameters17x17 Type Fuel Assemblies*

Fuel Assembly ParametersVVER-1000 Type Fuel Assembly**

* 16x16 CE fuel assemblies and the 17x17 W-STD/XL fuel assembliesmay be shipped only in the Model No. MCC-4 package.

** VVER-1000 fuel assemblies may be shipped only in the Model No.MCC-5 package.


Two (2) fuel assemblies

'••" t •

^

NRC FORM 618A(6-83)




10.


For shipments of 14x14, 15x15, 16x16, and 17x17 fuel assemblies with U-235enrichments of over 4.65 wt% and up to 5.0 wt%, horizontal Gd203 neutron absorberplates shall be positioned underneath each assembly. The horizontal absorberplates shall be placed horizontally on the underside of the strongback, as shownon Westinghouse Electric Corporation Drawing No. MCCL301, Sheet 1, Rev. 4, orWestinghouse Electric Corporation5Braw|2gEjlqâMCCL401, Sheet 1, Rev. 5.

For shipments of VVER-10gO^fue!lrassemblies withMK£3|*enrichments of over 4.80wt% and up to 5.0 wt%. ^jofded Gd Oj neutron absorbew p5*ate shall be positionedunderneath each assenjjfty. The guided absorber plates shaW be placedh i t l l t h t i d f th bk h fWestinghouse Electrichorizontally on theCorporation Drawin

ty g pside of the strongback, as shown

. MCCL501, Sheet 5, Rev. 2.

Each fuel assemfclJHnust .,sheath which mavNrot extethe sheath may ftot be foldliquids into or«?ût of the

The dimensions^fflinimuitesting of the aeutroilNeutron Absorber PI ateJanuary 14, 1994^ f tffthe vertical and'wtizon"The minimum Gd2O, 'qfoitingbe 0.027 g-Gd2O3/cm^

eathed or must b:d thfi<eMs o

sed in an unsealed plasticel asserfjETIy. The ends ofhat would-erevent flow of

atiiance*

Rev.coat

1 b(

and acceptanceBth the "Gd2O,

datedarea! density on

.054 g-Gd2O3/cm2

utron ^ o r b e r plates shall

(a)

In addition to the reimplements of Subpart G of 10 Cf3&?art 71:

The MCC-3 packaging sha^Cbeâccefftanc^têd in accordance with Notes 3,4 and 5 of Westinghouse Blecj^c^rplfrat ion Drawing No. MCCL301, Sheet 1,Rev. 4, and with the Acceptance Tests in supplement dated May 12, 1992.

(b) The MCC-4 packaging shall be acceptance tested in accordance with notes 4,5, and 6 of Westinghouse Electric Corporation Drawing No. MCCL401, Sheet 2,Rev. 5, and with the Acceptance Tests in supplement dated May 12, 1992.

(c) The MCC-5 packaging shall be acceptance tested in accordance with theAcceptance Tests in supplement dated May 12, 1992.

(d) The packages shall be maintained in accordance with the Maintenance Programin supplement dated May 12, 1992.

(e) The packages shall be operated and prepared for shipment in accordance withthe Operating Procedures in supplement dated January 14, 1994, as revisedin supplement dated August 2, 1994.

473

NRC FORM 618A(6-83)





REFERENCES

Westinghouse Electric Corporation application dated January 31, 1991.

Supplements dated: October 2, October 9, November 1, and November 13, 1991; January27, March 30, May 12, and June 18, 19J£2o[tocpitp&/r*lS93; and January 14, April 22, May24, July 26, and August 2, 1994.

^ate:

FOR THE U.S. NUCBEARvREGULATORY COMMISSION

, Direqjgrct Officr Materia#*§afety

474

^

^

NflC FORM 618(846)10 CFH 71










3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEX1ESIGN OR APPLICATIONa. ISSUED TO (Nome and Address) ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


,•&-->

Amersham Corporation applicationdated September 13, 1994, as supplemented.

C. DOCKET NUMBER

CONDITIONS < X * W ^ ^ V f <*>This certificate is conditional upon fulfilling^he requirements of 10 CFR Part 71, as applicable, and thaconditions specified below.

(a) Packaging

(1) Model Noy:?'934

(2) Description

A

contents jareplug.and 6 inches

(3) Drawings Y .

r-^-.-v, --j = p.—<-,- - =--3> J> fjgHographic exposure?ji%)ts conîstôl^^dute/^taini^ss steel shell,~~^êj!J7^3]n^^sKji" Ird, jrf J- a bronze source tube. The

-~^"*~J--'JMi^t-Ke^sou$|^*ube bâ padlocked shippingb^nder|^f$foxima't«<ly 20.5 inches long

•---^ •-^K't of the^package is 68 pounds.

ance with Amershamthrough 8.

The package isêtmstructed and assembled in^ccoCorporation Drawing No. 93400D, Rev. D, Shee^l 1

(b) Contents ^ 1^ ^ ^ "V^




240 curies (output)

Output curies are determined in accordance with American National StandardN432-1980, "Radiological Safety for the Design and Construction ofApparatus for Gamma Radiography".

475

NRC FORM 618A(6-83)



The source shall be secured in the shielded position of the packaging by theoperational locking plunger, shipping plug and padlock. The operational lockingplunger, shipping plug, and source assembly used must be fabricated of materialscapable of resisting a 1475 °F fire environment for one-half hour and maintainingtheir positioning function. The operational locking plunger must engage thelocking device during transport. The source rod assembly and the shipping plugmust be of sufficient length and diameter to provide positive positioning of thesource in the shielded position.

The nameplate shall be fabricated of materials capable of resisting the fire testof 10 CFR Part 71 and maintaining Jfejeiigjlegjikyity.

In addition to the requiremerfe^of Subpart G of%0^F^Part 71:

(a) The package shaJt\M prepared for shipment and op&jmed in accordancewith the Operartjftg' Procedures in Section 7, of thewpj,ication, assuppl emented , ^ d

(b) Each packaSection 8,,

t9. The packaging ap-fehorized b,

general license provisi""10. Expiration datey|anua

Amersham Corporation

Amersham Corporation suppFebruary 1, 1996.

Maintenance Program in

or use under the

r 1995; and

I&REGULATORY COMMISSION

Date: k


and Safeguards

4 7 6

NRC FORM 6181W6I10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1 a. CERTIFICATED b. REVISION NUMBER

•5c.R RQAT'.QN NUMBER d. PAGE NUMBER e. TOTAL NUMBER PAGES

i. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafety standards set forth in Title 10, Code




Burnley Technology, Inc.Post Office Box 1226PIaistow, NH 03865

RTS Technology, Inc., applicationdated August 20, 1992, as supplemented.

c. DOCKET NUMBER^ 9\i<7//

4. CONDITIONStheThis certificate Is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the'conditions specified below.

(a) Packaging g

(1) Model No. 0

(2) Description^

Radiograpfiic

&•«••

an outer postaln^diameter aria Yl.

The oyerpack consists ofsteel fdrjum (14 inches in

v. -W ; , -« 7 -cffM-frrp'v'Pr-sssfy^ -*w/jf$m 2 £b9 a u9 e b o dy a n d

cover, welded seainsî^ i c^fnp^ji^g|,t!y#e headl^dsure.^The void spacebetween t h e ^ t | n e r * ^ p p t ^ ^ g p | ? ^ 1-122 inch thickmolded asbestos free^îh^TîiÊn^fepj^b^KtpiJf^ and sides, plus moldedpolyurethane^ffll to posi%ior|^Msl^re<;t}flfradiogr|pliic device within thedrum. Maximum^grpss weight of^fHe^pafekage^fiot to exceed 75 pounds. Themaximum weight of/the radiograph-devices withiq Êevpackage shall notexceed 51 pounds.^1 VlVW

(3) DrawingsHi

The overpack must be constructed in accordance with Burnley TechnologyInc., Drawing Nos. 42400, Rev. 0; 42500, Rev. 0; and 42600, Rev. 0.

The radiographic devices, as secondary packaging, authorized for use in theoverpack are constructed in accordance with the following Drawing Nos.:

For the Model No 424: RTS Technology, Inc., Drawing Nos. 42401, Sheets 1 &2, Rev. 1; 42402, Rev. 3; 42403, Rev. 3; 42404, Sheets 1, 2, and 3, Rev. 0;42407, Rev. 0; 42408, Rev. 0; 42415, Rev. 3; 42416, Rev. 0; 42417, Rev. 1;42421, Rev.0; 42422, Rev. 0; 42423, Sheets 1 & 2, Rev. 1; 42424, Rev. 1;42425, Rev. 0; and 42426, Rev. 0.

For the Model No. 425: RTS Technology, Inc., Drawing Nos. 42501, Rev. 0;42503, Rev. 0; 42505, Sheets 1 & 2, Rev. 0; 42506, Rev. 2; 42551, Rev. 1;42552, Rev. 0; and 42558, Rev. 0.

For the Model No. 426: RTS Technology, Inc., Drawing Nos. 42601, Rev. 0;42605, Rev. 0; 42606, Rev. 0; and 42609, Rev. 0.

4 7 75 ^ ^

tf&mS?ti^^

NRC FORM 618A(6-83)

U.S. NUCLEAR REGULATORY COMMISSIOrJ

!

t

t

5ii

ftE

ii

iI

1



(b) Contents




200 Curies.

6. The sources shall be secured in £heby the shipping plug, source, ^ |

bl d t b

exposition of the radiographic device^ device. The shipping plug andby the shipping plug, source, a§se^|ly4l\a^^)oki;ng device. 1\

source assembly used must b^PabVicated of mater$ls~capable of resisting a1475°F fire environmen^f-or* one-half hour and maintaining their positioning

/ f th bl d shipping plug must be ofunction. The ball Sto/of the source assembly and shipping plug must be ofsufficient length ap^diameter to provide positive positioning of the source inthe shielded posi^Jn. ^

7. In addition to req ts of Subpart G o

operated^Jin accordance withpplicatid©

ram/and Acjsgptance Tests inajne'^should,' be visual ly

s tW&l&pecifixations as described

>y approved 'for use under the

(a) Each package must bthe Operating Procetf

(b) Each packaging miChapter |waf t h ^examinedw assu*in the drawings sj

8. The package authoj$>zedgeneral provision&^tff iu

9. Expiration date: Sep efiit

RTS Technology, Inc., application dated August 20, 1992.

RTS Technology, Inc., supplements dated: July 31, 1991; and October 16, 1992.

Burnley Technology, Inc., supplements dated: October 16, 1992; and June 17, 1994.


NOV 0 1 1994Date:



478

»^

aTaTaTaTaTag a£.a7a7aTaTaLacaTaT5iiLac ataTaTaTW ! * ? w a i at w aTaNRC FORM 618(3-96)10CFR71








2

I, PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10,




National Institute ofStandards and Technology

Gaithersburg, HD 20899

andNational Institute of StandardsTechnology application datedFebruary 7, 1992, as supplemented.


4, CONDITIONSThis certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable; and the conditions specified below.

5.

(a) Packaging

(1) Model No.: ST

(2) Description

A closed steel pip;^ for the transport pfifan unirradiated research reactorfuel element. TKev.p.i/pe is a 5-1/2-inch ;0D; carbon steel pipe,approximately 71 TWPJie$ in, length, witfija^closed bottom end and flangedtop end. The ,;tqp en.d'*% closed by .acp.ver plate, which is 1/4-inchthick, and 6-1/2 1 incHe^n diameter,^artH ajja'sjcet. jhe cover plate issecured to the pipe flange by 8 cap<s;crew£i;V:Awooden nozzle support andtop support position1 the fuel assembly within the pipe- The packageweighs approximate,ly>-75'Tbs., including "the fuel element.

(3) Drawing

The packaging is constructed and assembled in accordance with NationalInstitute of Standards and Technology Drawing No. D-04-048, Sheet 1,Rev. 2, and Sheet 2., Rev. .2. .

4 7 9

5

5

faUK2K2E2iyiUKiiyBL3ygLgUgySUI^

9•3

3

M

£

9

*

g

g5

NRC FORM 618A(3-96)



5. (b) Contents


Unirradiated NBSR fuel element composed of enriched uranium andaluminum.


One fuel element containing 360 grams U-235. The total quantity ofradioactive material within a package may not exceed a Type Aquantity.

(c) Transport Index for .Critical ityV;Control; ,,

Minimum transport,?index to be shown onLabel for nuclear criticality control: 50.0

7.

8.

In addition to th&icequirements of Subpart G of 10 CFR<Rart 71, the packageshall be prepared fol^Mpment, operated, and maintfftied' in accordance with theloading, unloading, aiid:yp al,ity assurance proced^es in the application. Priorto each shipment, the - -- -- -"--•• •• —•-- -*-•--" -•'-<•--">—= --.•-.= — ^ ^ ^ _ J .... x.u.

NIST "ST" Seriesent, the sira||£er\shall.,,ma.ke tjje'determinations-specified in theies Shippin%|C;On>t|iner«fSKippe1r^Checklist in the application.

Vthori zed6^:Ejs? cer4i*iJEiate''rs|'HjB'reby approved for use underThe package authorizedgeneral

cert?i1:t'eate-'is«hjereby approved for use under the

National Institute of Standards ancl Tebhftbp'dg f application dated February 7, 1992.

Supplement dated: February'14, 1992. v ^ "

.'•/- , .. ../FOR(,TyE<uls. NUCLEAR REGULATORY COMMISSION

Date:

jWilliam D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

480









3

2. PREAMBLE



3. THIS CERTIFICATE IS ISSUED ONTHEBASISOFA SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Nuclear Fuel Services, Inc.P.O. Box 337, MS 123Erwin, TN 37650

Nuclear Fuel Services, Inc. applicationdated July 31, 1992, as supplemented.


4.CONDITIONS . ' . - . . , .

This certificate is conditional upon fulfilling the requirements of 10.CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

M -

(1) Model No.:,.110G-A-

(2) Description' s>^^ \

Concrete-filled, llftSgillpn drUm"fbr stheSfransport offradioactive material.The package is compqêdl of anHinner, D0J^s|e"cificationil7H, 55-gallon drum,excluding l id , c'epteêd^jthin an ou£e$"4§0-ga1 Ion dicurn by 5,000 psicompressive stVfer\gth fdone]f|te7;]YAftecip;%ape .emlicementin the inner drum,concrete is poU)|ed^1;p..fi;1^the:;inneV^^ a|ijpt6"'extentf above the top chimeof the inner druifc--!'fife out;er •drumliand[lid Iare^l6-gage" s tee l . The outerdrum is closed byîd^rgagC'SteetlTo^.lngt/rthg with->dr'op forged lugs, a 3/8-inch smooth; neoprerie^gasket,ândâ.^ys-jhcfi^diameter^bolt. The maximumweight of thjj. package, incl^di^gôntehts,j is 270^pounds.

(3) Drawings '";, - ^

The packaging is constructed in accordance with Nuclear Fuel Services, Inc.Drawing No. 000-M0034-B, Rev'. B.

481

•WWWWWWWJJK watt wag atwaKWW]

39




(b) Contents

Dry, solid waste material in the form of disks composed of super-compacted 40-gallon drums containing non-compactible or compactedwastes, and limited to the following:


0.0001 millicurie :of radionuclides for which the A, quantity inAppendixTA of 10 CFfTPart 71;is not "more than 0.05 curie;

0405 mi H i curie of radionuclides for which the A2 quantity in.Appendix A of 10 CFR Part 71 is more than 0.05 curie, but notmore than 1 curie; or

v 0.3*••jnjhUJ:curie of radionuclides^fof which the A2 quantity in/ AppendÂpf 10 CFR Part Jl^'mbre than. 1 curie.

(ii) Objects|p^:no,nrad}jbactive material externally contaminated withjtsojynqnrad;ibactive material externally contaminated withradioadfiê mater4vaji,/pro>ide:dVthat the radioactive material isnot^reaiil.|ly^d.rspersibTe attd- tjfe surface contamination, when-*.^~~A..*..^,.± ^ . - . ...t.,_.r,___. d o e s n o ^ e x c e e dexceed

>^.vy,,. ,-v ... ».., -,. „• --V-..;-- P e r minute) persqu|re^C!Bhtimeter;jOfi?rad.i,onuclfldesvfor which the A2 quantity in

x;:\ Appendi^ô|ya^CF<R;pRrtvi7vicis/not mo,re. than 0.05 curie, orVr>0.00l^'|hi^f^curte4|2^20p, 000;di;;si ntegratibns per mi nute) per

* square" centimeêfef^ôjher'.radi onucl ides.(2) Maximum '(quantity of material per packagefv'

Greater than Ty.pe A quantities o.fvfadioactive materials. The maximumweight of waste materjial is-1^000-pounds. The contents may includefissile materials, provided that the total quantity of fissilematerial per package meets the mass limit specified in 10 CFR§71.53(a).

I

i. 482i.2KJSC

NRC FORM 618A(3-96)

8.

9.

10.

11.

12



6. (a) For any package containing water or organic substances which couldradiolytically generate combustible gases, a determination must be made bytests and measurements or by analysis of a representative package that thefollowing criteria are met over a period of time that is twice th'e expectedshipment time:

The hydrogen generated must be limited to a molar quantity that would be nomore than 5% by volume (or equivalent limits for other inflammable gases) ofthe package gas void if present at STP (i.e., no more than 0.065 g-moles/ft3at 14.7 psia and 70 °F).

For any package delivered to a carrier for transport, the package must beprepared for shipment in the same manner in which determination for gasgeneration is made. Shipment period begins when the package is prepared(sealed) and must be completed within twice the expected shipment time.

(b) For any package shipped within 10 days after sealing of the drum, thedetermination in (a) above need not be made, and the time restriction in (a)above does not apply. -

7. Radioactivity per package shall be determined in;accordance with Sections 1.2.4and 4.8 of the application,.; . .

In addition to the requirements of Subpart;G;£f#10 CFR Part 71, the package shallbe prepared for shipment,and; operated,.in accordance with Section 4 of theapplication. •.,., % ' H \ '•' • '<:'j~If:

This certificate authorizes :.l%d transport;bitwee^ythe vicinities of Oak Ridqe,Tennessee, and. Barnwelly SputH,GaY-o1i,na,jonly. | V / V

The package auth'orizedVby^ih^ transported on a motor vehicleor railroad car .assigned forv;sol.;e|use!;|o;fvth.e

/licensee.. ;

The package authorized,.by this certificate is hereby approved for use under thegeneral license provisions of 10 CFR §71.12. v^--

Expiration date: April 1, 1999./ This/cerfific^te is not renewable.

REFERENCES

Nuclear Fuel Services, Inc. application dated July 31, 1992.



Date


483

[wwaagNRC FORM 618(3-96)10CFR71








5

2. PREAMBLE



u ISSUED TO (Name and Address)

'Siemens Power Corporation2101 Horn Rapids RoadP0 Box 130Rich!and, WA 99352-0130


Siemens Power Corporation applicationdated June 28, 1993, as supplemented.


4. CONDITIONS . - . ' - , ' • - • ' - < - : ' ;

This certificate is conditional upon fulfilling the requirements; 6f 10CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging .

(1) Model Nos.r SP-1 and SP-2

(2) Description V":^T

*-^Fuel assembly and^Se] rod shipping/tojTiajjriers. Trie; packages consist ofa right...rectangulaîinetai inner con|a,i|i,ej|)and a wooden outer container,with cushioning mlKfefcTai between* the\ iflrtgr- and outer, containers.

The metal ^m^:icon^^^Y^^:^p^r6^^pely/^lp'l/Z inches by 18 inches by179-1/2 inchel^long '"a'ifdjas:'bîtiqnld^wit^hâ^wooden; outer containerapproximately%0îfnches^by3i; inches by 207; {inches^Tong. The SP-1 andSP-2 packagingsiai#er<|n^the^^len^thco^the^"metal,;inner container and endpiece. •CushiontViî^>p^ inner-and outer containers byphenolicî.mpregnated hone^G^m^pd e.thafpam, or equivalent. Closure isaccompli shed, by bolts, lafGÎ^Vêquivalent^Â. pressure relief(breather) valveJs provided 'on the inner container, and is set for0.5 psi differential. The maximum weight of the packaging and contentsis 2,800 pounds. • ;

(3) Drawings

The packagings are fabricated and assembled in accordance with thefollowing Siemens Nuclear Power Corporation/Advanced Nuclear FuelsCorporation Drawing Nos.:

EMF-306,416EMF-306,424EMF-304,416EMF-306,272EMF-308,257, Rev. 1.

Rev. 1.Rev. 1.Rev. 5.Sheets 1 through 4, Rev. 6.

(4) Product Container

Five-inch, Schedule 40, stainless steel pipe fitted with screw type orflange closure. Container shall be vented in the event it containsmaterials which decompose at less than 1475 °F.

484

ww^NRC FORM 618A(3-96)



5.(b) Contents


(i) U02 fuel rods with a maximum U-235 enrichment of 6.5% by weight.Rods are clad with Zircaloy, Incaloy, Inconel or stainless steelsuch that the ratio of clad to fuel cross sectional area be atleast 0.26, and a maximum fuel pellet outside diameter of 0.508inch. Each rod must have a maximum length of 174 inches. The cladrods must be bundled (contained) in the product container describedin 5(a)(4).

( i i ) U02 fuel assemblies in a 7 x 7, an 8 x 8, or a 9 x 9 square arraywith a maximum fuel cross-section area of 25 square inches, maximumfuel length of 174 inches and maximum average enrichment of 3.3 w/oU-235. Minimumr.zircaioy clad thiekness is 0.025 inches; maximumpellet diameter/;is 0.555 inches. -Any number of water rods in anyarrangement,'ire permitted. " ' -

( i i i ) U02 fuel, assemblies in a 7 x 7, an 8 x 8, or a 9 x 9 square arraywith, a-maximum fuel length of 174 inches,, and a maximum averageenrichment^between 3.3 to 4.0 w/ot U-235^,"The maximum pelletdiameter is-0.555Ninch-} and the minjûnPclad thickness is 0.025inch'. Any numberVf water- rods/ inî^ arrangement is permitted,including parj^Tjength reel's?/' EScHiaJsembly contains at least 4 rodsith i l ^ ^ i h t t Gd^Sjshih i it

pwith nominal -'percent

meîcâare in. non-perimeter

^ ^ diagonal r~

(iv) UO^fuetjassê^ of 5.0 percentby weight: antlfa nia^jmuni.ayerja§e"U-235->hrichra%t of 4.0 percent bywei'ght. 'EichS^s^^ssem^f^-ys'^dide.Jiip:''of fuel irods in a 10 x 10square arfa#.jtwfihâ :^ section of 5.022 inchessquare? a n6mindtf^pv£WfoMOy511 inch, and aVmaximum fuel length of174 inches. The maxfmumipe|iet diameter, fs;00.3356 inch, theminimum dTad thickness'-is^.0225 inch, vahcj/ the maximum U-235enrichmerit'/jn any edge rod is 4.0 percent by weight. Each assemblycontains at least 6 rods with nominal 2 weight percent Gd2Q3, whichare symmetric about ihe:diagonal,vand each assembly contains atleast 4 water rods in the^4 central rod positions.

(v) U02 fuel rods with a maximum U-235 enrichment of 5.0 percent byweight, and a minimum Gd2O3 content of 1.0 percent by weight. Therods may be clad with zircaloy, steel or aluminum. The rods have amaximum fuel pellet diameter of 0.5 inch, and a maximum fuel lengthof 169 inches.

485

^fflffl ;



5.(b)(1) Type and form of material (Continued)

(vi) U02 fuel assemblies composed of fuel rods in a 10 x 10 square array,with a maximum fuel cross section of 5.0 inches square, and amaximum fuel length of 174 inches. The maximum U-235 enrichment is5.0 weight percent, the maximum U-235 enrichment for all edge rodsis 4.0 weight percent, and the maximum average enrichment,excluding perimeter rods and rods containing gadolinia (Gd2O3), is4.0 weight percent U-235. The maximum pellet diameter is 0.35inch, and the minimum clad thickness is 0.018 inch. Each assemblymust have a water channel in the central 3 x 3 rod positions. Anynumber of additional water rods in any arrangement is permitted,including part length rods. Each assembly must include at leasttwelve rods with a minimum nominal content of 2.0 weight percentgadolinia (Gd2O3),\in a pattern symmetric about one of the assemblydiagonals. At least eight of the twelve gadolinia rods must belocated in rows 2 and 9, and in columns 2-and 9 of the assembly.

(vii) U02 fuel assemblies composed of fuel rods,,in a 10 x 10 square array,with, a maximum fuel cross section o,f«;5.p inches square, and amaximum fuel length of 174 inches: /The maximum U-235 enrichment is5.0 weight percent. The;;maximum pellet diameter is 0.35 inch, andthe minimum ;&t-ad thickness is .0..0;18iinch. Each assembly must havea water chai\ii$l>in-the central .3 x^;rod positions. Any number ofadditional watferUrods in: any arrangement is permitted, includingpart length rods. -Each assembly <must include at least eight rodswith a minimum nominal, gadolinlay.(Gd?03); content of 2.0 weightpercent fn.Jall/.axiairegions:with enriched pellets. Additionalgad6liniaCr.od^specificatio;ns.are included in supplement datedApril 30, 1996.;;; ' '• " #$i/."

: ; V "

(viii) U02 fuel assemblies composed^ of fuel rods, in a 9 x 9 square array,with a maximum fuel cross "section of 5.0 inches square, and amaximum fuel length of 174 inches. The maximum U-235 enrichment is5.0 weight percent. The maximum, pellet diameter is 0.40 inch, andthe minimum clad thickness is,0.015 inch. Each assembly must havea water channel in the central' 3 x 3 rod positions. Any number ofadditional water rods in any arrangement is permitted, includingpart length rods. Each assembly must include at least eight rodswith a minimum nominal gadolinia (Gd2O3) content of 2.0 weightpercent in all axial regions with enriched pellets. Additionalgadolinia rod specifications are included in supplement datedApril 30, 1996.

486

C3CJE.J8LSB.MC'*' '»' JEag^Stj«.^.3K'*' T*'.ylLytLyiu.ywLjlC.

NRC FORM 618A(3-96)


3

3


5.(b) Contents (Continued)


Total weight of contents (fuel assemblies, fuel rods and rod shippingcontainers, or fuel bundles and product containers) not to exceed 1265pounds. Total quantity of radioactive material within a package may notexceed a Type A quantity.

(i) For the contents described in 5(b)(1)(i):

Two fuel bundles. A bundle is defined as an arrangement of rodswhich is contained within a product container.

(ii) For the contents described in 5(b)(l)(ii), 5(b)(l)(iii),5(b)(l)(iv), 5(b)(l)(yi), 5(b)(l)(vii), and 5(b)(l)(viii):

Two full length fuel assemblies. Two short fuel assemblies may besubstituted for each full length fuel assembly provided the twoshort.assemblies are shipped end-to-end and.the total fuel lengthdoes not exceed 174 inches.

(iii) For the contents described in 5(b)(l)(v):

Any number of-rods,, contained wttbirj^rod shipping containers asshown on Siemehs:.' Ppiwer Corporation-[Rawing No..EMF-309,141, Rev. 0.

(c) Transport Indexifor GKiticality Control-"

6.

7.

Minimum transport (index to be shown.ohlabel for nuclear criticaTity control>:

(1) For contents''desGribed-:ihvlCb)(l}(.i)»5(bHlHii) 5(bj'(l)t^^ifb);(I>(i5(bHlHii), 5 ( b j ( l ) t ^ ^ i fand 5(b)(l)(v) and lifnited:;in(b)(2)(i);5(b)(2(ii) and 5

(2) For contents described in 5(b)(l)(vi),5(b)(l)(vii), and 5(bj(l).(vi11.), andlimited in 5(b)(2)(ii):

0.4

1.0

Each fuel assembly must be unsheathed or must be enclosed in an unsealed,polyethylene sheath which may not extend beyond the ends of the fuel assembly.The ends of the sheath may not be folded or taped in any manner that wouldprevent the flow of liquids into or out of the sheathed fuel assembly.

Except for the contents described in 5(b)(l)(iv), 5(b)(l)(vi), 5(b)(l)(vii),and 5(b)(l)(viii), polyethylene shipping shims may be inserted between rodswithin the fuel assemblies up to a maximum of 0.20 gram H20 hydrogen equivalentper cubic centimeter averaged over the assembly. For contents described in5(b)(l)(iv), 5(b)(l)(vii), and 5(b)(l)(viii), polyethylene shipping shims arenot permitted. For contents described in 5(b)(1)(vi), polyethylene shippingshims may be inserted between rods within the fuel assemblies up to a maximumof 0.25 gram H20 hydrogen equivalent per cubic centimeter averaged over theassembly.

487



8. In lieu of the product container specified in 5(a)(4), U02 fuel rods with amaximum enrichment of 3.2 w/o U-235 may be bundled (bound with steel strappingsat two or more locations) with a maximum cross sectional area of 20.0 squareinches. The total breaking strength of the strapping must be 30 times theweight of the bound rods.

9. The maximum spacing between adjacent rods within a bundle must be 0.012 inch.The spacing must be maintained by the product container wall, metal strappingsor peripheral metallic dunnage with a melting point greater than 1475 °F.

10T Maximum average enrichment means the highest average enrichment through anycross sectional plane of the assembly.


(a) The package must be prepared, fof, sRipm ertt? and operated in accordance withthe Operating Prpcediires in Chapter 7'of-the application datedDecember 1, 199aC"; '' ">;-%

(b) Each packag$»gTmust be acceptance tested and maintained -jn accordancewith the Acceptance Tests and Maintenance Program-in Chapter 8 of theapplication^dateB^December 1, 1993. --^i~:/ /

p g y ^ f t \ t ;

the general license provision's of fOtCFR/

Expiration date':

Siemens Power Corporation

Supplements dated: December % 1993; p # »d S t b 12 1 9 9 5 f d Fbru 9 f^ f

. . . , , , „ . _v . I; Mardt>15, April 28, June 20,and" September 12, 1 9 9 5 ^ n ^ Februar^'g^ll^Wfil^lS^and 3 0 ^ 9 9 6 .

•f}} FOR THE U.S. NUCLtAR REGULATORY COMMISSION

Date:


and Safeguards

488

nNRC FORM 618(3-96)10CFR71






USA/9249/Ad. PAGE NUMBER e. TOTAL NUMBER PAGES

4

2. PREAMBLE

a. This certificate is issued to certify Chat the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10,Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."




Inc. Chem-Nuclear Systems, Inc., applicationdated June 25, 1993.

c. DOCKET NUMBER 71-92494.CONDITIONS . C ; ; " ,

This certificate is conditional upon fulfilling the requirements'pf 10.CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No,.V CNSJ4-170, Series I I I ^ , ;;

(2) Descri pinion " ^ j f x S , '*?f-£f

SteeT encased, T^' |^hi.eld^âsk foi^^loactive"material. The caskis a right circu^ffcylinder,81trl fl, iBpn^s high by'81-1/2 inches indiameter. TH'e<fca^§%viityHs^73-3|:8^jt^hes .high by?75-l/2 inches indi ameter. Tft^cas'B/îê^wal 1 -xonsi^||*6f Aa/3/8-indLthick innersteeT shell ^)d^/^*^Gh;iead-:sKe^^2~and^^/8-in^h; thick outersteel .shell.^Keâse^Jssbojnpri^l of two^2-incht?thick steel plates

at the top'^-The lid is cMpmêd'of'two, 2- nc|i thick steel plates,which'are stepped and weld'ed^together to rnate^with the steel flange.The cask closure is sealed by a Neoprene'gasket located between thelid and steel flangeV positiye closure/of %he lid is accomplished byeight, 1-3/4 inch ratcheV binders.' ~/The lid contains a centrallylocated shield plug comprised of two, 2-inch thick steel plates andone, 1-inch thick steel plate stepped and welded. The shield plug issealed by a Neoprene gasket, and eight, 3/4-inch studs and nuts areused to provide positive closure. The packaging is constructed of A-516, Grade 70, carbon steel. The outer shell has a minimum yieldstrength of 46,000 psi. Tie-down is accomplished by four tie-downlugs welded to the cask body. There are four cask lifting lugs,three lid lifting lugs, and one shield plug lifting lug. The packagegross weight is approximately 53,000 pounds.

(3) Drawings

The Model No. CNS 14-170, Series III packaging is fabricated inaccordance with Chem-Nuclear Systems, Inc., Drawing Nos.: C-110-D-0016, Sheets 1 and 2, Rev. 4; C-110-D-0017, Sheets 1 and 2, Rev. C;C-110-D-0018, Sheets 1 and 2, Rev. C; and C-110-D-0019, Rev. B.

4 8 95SJ&^

w NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


* 5. (b) Contents


Process solids, either dewatered, solid or solidified, insecondary containers, and limited to the following:

(i) Materials in which the radioactivity is essentiallyuniformly distributed and in which the estimated averageconcentration per gram of contents does not exceed:

l20.0001 millicurie of radionuclides for which the Aquantity in Appendix A of 10 CFR Part 71 is not more than0.05 curie.;, .v~; *£;- /

f

B.

«

iM

a•3

g

», .— cwtamSft|;olxrWelifi(v>âê^dver/an areipof 1 square

B

i?B

O.Q05Wiificurie of Vad1onuc4%jde,s for which the A, quantityiri appendix A of 10 CFR Part 7'r^s).more than 0.05 curie,bjut not more than 1 curie; or ^;'->

"O^S-jnillicurie of radionuclidesjgor which the A2 quantityirf^pêndix A of 10 CFR Par t^ ty^ movr.elthan 1 curie.

i\\) OMe^^f 'hpnna^j^t iy^r j^âl externally contaminatedwith f^tâcîve/materiaT^p^yided that the radioactive

andHfie surface

lpg^J'er ppCte) pe :"square centimeterthe:%^quant;4ty in Appendix A of

or

ceni^^^DOVOOO^sinteg^rfifontimgtefMoWotfter'radionuel3xdes.

per minute) per

(2) Maximum-quantity of material per pacMge1

Greater than^pe A quantity of Radioactive material which maycontain fissile m^teriaf ptoSHded the fissile material does notexceed the limits in TO'CFR^§71.53. The weight of the contents,and secondary containers shall not exceed 17,800 pounds. Theinternal decay heat load shall not exceed 7 watts.

4 9 0

(b) Each package must .meet the Acceptancenests and Maintenance Programin Chapter 7.0 of "the ftpTi6attpi£ >"

(c) The package shall be prepared for shipment and operated inaccordance with the Operating Procedures in Chapter 6.0 of theapplication.

8. Torque requirements for closure fasteners:

(a) Primary lid ratchet binders must be torqued to 175-200 ft-lbs.

(b) Secondary lid bolts must be torqued to 120 + 10 ft-lbs.

9. The package authorized by this certificate must be transported on a motorvehicle, railroad car, aircraft, inland watercraft, or hold or deck of aseagoing vessel assigned for the sole use of the licensee.

NRCFORM618A • CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)


6. (a) For any package containing water and/or organic substances whichcould radiolytically generate combustible gases, determination mustbe made by tests and measurements or by analysis of a representativepackage such that the following criteria are met over a period oftime that is twice the expected shipment time:

(1) The hydrogen generated must be limited to a molar quantity thatwould be no more than 5% by volume (or equivalent limits forother inflammable gases) of the secondary container gas void ifpresent at STP (i.e., no more than 0.063 g-moles/ft3 at 14.7psia and 70°F); or

(2) The secondary container and cask cavity must be inerted with adiluent to assure that oxygen.must be limited to 5% by volume inthose portions of/the package/which could have hydrogen greaterthan 5%. >;..;.

For any package delivered to a carrier for transport, the secondarycontainer? must be prepared for shipment in the same manner in whichdetermination^for gas generation is made.^Shipment period beginswhen the package>is prepared (sealedJ^nCmust be completed withintwice the expectedrshipment time. iJf.i

(b) For.any packagep|hipped wifhinflOd^jjbf preparation, or within 10days after venttifg!of.;drums,o]c; other;«s^condary containers, thedeterminatidnîn1|i)âbove^neVd'not^bgniade, and the time restrictionin (a) aboye-'does^not^-a'pplyi- .-•,--*'>i;\. &' .;/-./• '•"•-

7. In addition,to t^^<^rej^ts;of;:SuJp.art Gftof/TO CFR-Part 71:

(a) Prior 'eachîv^^^^^Wickdigins^Yd sealsj;'if opened (or ifsecurity/seal is broicenM^musJvê -inspected. .^THe seals must bereplaced'<wr£h new seals %t/liHsêctiovn'-'showsâny defects or every 12months, whichever occurs first. - >/; »

4 9 1


M




REFERENCES

Chem-Nuclear Systems, Inc., application dated June 25, 1993.


Date: ^ A

w v

William D. Travers, DirectorSpent Fuel Pro jejct *Of f i ceOffice of Nucle^MaterJal Safetyand Safeguards^'

H

i

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NRC FORM 618(3-96)10 CFR 71








4

t 2. PREAMBLE




Babcock and Wilcox CompanyP. 0. Box 785Lynchburg, VA 24505


Babcock and Wilcox Companyapplication dated October 29, 1992,as supplemented.


4. CONDITIONS . x ' .This certificate is conditional upon fulfilling the requiremenjs'of I0,CFR Part 71, as applicable/and the conditions specified below.

(a) Packaging , \ i !

(1) Model. NoV::~4INFD 5X22

(2)

(b)

Descjrtption ^ % ^ i v \

A Shipping container if or "uhi'r.radiat#d|u)rani urn of. any enrichment.The\outer druifllsta?p0T S*pecificati;on^7C, 55-gal,Xbn drum with aheavy-dutyhc\mptjrigsarid'^fdrged'i?igs|?' The inner.^vessel(c'Qntainm^hMveslp^^s.a^Schediil^^^^ s,t|inless;sjteel pipe with awelded bo££'om,;pap &arfd/i-:a %op^ Wel ni ck ^T|ngei The-inner vessel l idis a-blind>fTange \ihXph :is ;boltedx ' to tfte^weldneck-"flange withe igh&hex-h)^d ,b i^ ir^cl.udes double silicone 0-ringseals.Jand af^âk-^st' ppRt'i-'-.v5The€d3"me.n'jsions of-khe inner vesselare 5finches ID by^22^cfietsrj§|.gh.. Tfie inner<vessel is centeredwithin%h^ outer drum^bî^b'oafdrand supported by plywooddisks. The'maximum weigH'ô'f the package',.including contents, is300 pounds;.-'V> '> v ;

• • ' ' ' • .

(3) Drawings -'-.;' •-•-•• - --- "•.••--

The packaging is constructed in accordance with B&W Fuel CompanyDrawing Nos. 1220276 E, Rev. 1, and 1220277 E, Rev. 4.

Contents


(i) Unirradiated uranium as solid metals, compounds, or alloyswhich do not decompose at temperatures up to 250 °F; uraniumoxides as powder or pellets; and uranyl nitrate as crystals.The uranium may be of any U-235 or U-233 enrichment.Carbide compounds are not authorized.

4 9 3




(1) Type and form of material (continued)

(ii) Unirradiated liquid uranyl nitrate solution in sealed glasscontainers or screw top plastic vials, each within one ormore additional plastic vials with taped lids, and within asealed product can or polyethylene bottle containing asufficient amount of vermiculite to absorb twice the liquidcontents present. The uranium may be of any U-235enrichment. U-233 greater than a Type A quantity is notpermitted.

(iii) Unirradiated uranium as solid metal. The uranium may be ofany U-235 enrichment.

(2) Maximum quantity of material per package arid transport index forcriticali-ty control

The weight of the contents, including secondary containers,inserts, and o|he>> materials in the i Artery-vessel, shall not exceed50 pounds, andY " .,_ . .-VC

(i). For the material described \ir\~-ki%ih 5(b)(l)(i), above, with a; maximum, H/U. of 3, consignrig^afl sources of'moderation in. thepinner vessel,: \?V'%?P"' -, / ,•

s;>) - .;, ..rMaximum: Fissile^5" Mi pi muni;'Transport Index

FissiiV\:^Materjdl;'perw\: to/be-Shown:on Label forMaterial<;'•-' Paikage. (kg)Kt'A^Nuclear Critical itv Control~ ~ ~ '(-v~ Zy^x. '"'•':•'•/?• •,;.'•••'

U-235 '' 9^)>j€v^ ''..'-'•> '> 100

(ii) For the.material described in Item^5(by)(l)(i), above, with amaximum H/U of 20, considering all sources of moderation inthe inner vessel: . x -- '

Maximum Fissile Minimum Transport IndexFissile Material per to be Shown on Label forMaterial Package (kg) Nuclear Criticalitv Control

3 U-233 0.5 1.8

s U-235 4.0 100

494

aB NRCFORM618AC (3-96)

S Page 3

S 5.(b)

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CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION £i

- Certificate No. 9250 - Revision No. 4 - Docket No. 71-9250 s«

Contents (continued) K

(2) Maximum quantity of material per package and transport index for gcriticality control (continued) g

(iii) For the material described in Item 5(b)(1)(ii), above: £

Fissile material shall not exceed 400 grams U-235. The £quantity of uranyl nitrate shall not exceed 1000 mL of £solution. £

Minimum transport index £to be shown on 1abel for znuclear criticality control: 0.4 g

(iv) For the material described in Item 5(b)(l)(iii), above, with !a maximum H/U of 3, considering all sources of moderation in *the inner vessel: 2

•Maximum Fissile Minimum Transport Index §

Fissile Material per to be Shown on Label for 5MaterialT Package (kg) Nuclear Criticalitv Control S

•

U-235 . 9.0 2.5 B

U-235 1.6- 0.5 8

(v) For the material described in Item 5(b)(l)(iii), above, with £a maximum H/U of 3, considering all sources of moderation in Bthe inner.vessel, and with a solid aluminum disk insert £positioned in the. inner vessel, as shown on B&W Drawing No. g1220277 E, Rev. 4;(Part No. 6). g

Maximum Fissile Minimum Transport Index gFissile Material per to be Shown on Label for gMaterial Package (kg) Nuclear Criticalitv Control a

U-235 9.0 2.0 s

(vi) For the material described in Item 5(b)(l)(1ii), above, with ga maximum H/U of 20, considering all sources of moderation Hin the inner vessel: g

Maximum Fissile Minimum Transport Index gFissile Material per to be Shown on Label for gMaterial Package (kg) Nuclear Criticalitv Control p

U-235 4.0 2.0 g

•

495 ^

11



6. The vent holes on the DOT Specification 17C drum shall be capped ortaped closed during transport and storage to preclude entry of rainwater into the packaging.

7- In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) Each package shall be operated and prepared for shipment inaccordance with Chapter 7 of the application.

(b) Each package shall be acceptance tested and maintained inaccordance with Chapter 8 of the application.

8. The package authorized by this certificate is hereby approved for useunder the general license provisions of 10-CFR §71.12.

9. Expiration date:;N January 31, 1998. *</',.•

3 „ -,.-, -*_\

£

£

REFERENCES

Babcock and Wi 1 cox' Company^appTication-.dated .Octobey^ZQ, 1992.,

Supplements dat;ed": January£22v 1993;- November;S?|i;993; Novenib6r 30, 1994;December 20, 1995; and februaryx23.arid;March,.25j|t?96.


./•, -.^v.^.iawi'DVvTravers, <:Directorr SpentrFuel Project OfficeOffice of Nuclear! Material Safety

and Safeguards^"

Date: ^ ]^t> 1 <^L

£

496






5




3

I, PREAMBLE



3, THIS CERTIFICATE IS ISSUED ON THE BASIS OFASAFETY ANALYSIS REPORT OFTHE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Framatone Cogema FuelsP.O. Box 11646Lynchburg, VA 24506-1646

B&W Fuel Company applicationdated May 26 1992, as supplemented.


4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10,CFR Part 71, as applicable,,and the conditions specified below.

(a) Packaging

(1)

(2)

Model No;;: B»?29G1 , r ; • ;.

Description ^Kh - -.* '\J>-'"

A shipping contai^^:'~fp^/low/§nrfched\ur9|[|um oxide.powder and pellets,composed of an/jnn^cbntainlrjfvsurrounê^by insulating material, and anp ; j x ôuter drum. Tj iîr i^fôotainer iS'^nia;X^mum/11.15-jnch square by29.5-ineh lori§s'|^ne^^jojiî)fe|tT.cp;ns|r'u^fed ',o|/^nimum. 14-gauge s tee l ,with bolted and g.3s;ke^W$6£^ bottom sheet. Theinner cqntainerîS/^ 18-{gauge steel drum with16-gauge head ari^T)piR^Sp#iii^fjjeai16%vl^H^ 1 psure by.vaSbestos or ceramicsheet, plyWood, hardbffard,â^[^ The drum hasapproximate'4imensions lbf^4SV^c:h lb>by 34-inch height. The uraniumoxide is packaged in boxes^^ndvwood boards p.osjinon the boxes within theinner container/."s Three borated aluminum plates (approximately 25 inchesby 9.25 inchesby 0.375 inch) are posi.tionecTwithin the inner container.The maximum gross weight, of the package-is 660 pounds.

(3) Drawings

The packaging is constructed in accordance with B&W Fuel Company DrawingNos. 1215597D, Rev. 4, 1215598B, Rev. 1, 1215599E, Rev. 3, and 1215600D,Rev. 3.

497

^ 5



(b) Contents


(i) Sintered uranium oxide pellets enriched to a maximum 5.05 w/o inthe U-235 isotope. The minimum pellet diameter is 0.315 inch, andthe maximum pellet diameter is 0.375 inch.

(ii) Uranium dioxide as powder, pellets, or any combination thereof,enriched to a maximum 5.05 w/o in the U-235 isotope.

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£ label for


370 pounds, with the U-235 content not to exceed 7.47 kg. The maximumweight of the uranium oxide:, p'e11et;bMes,. and all packaging materialswithin the innejr;>'container is 427 pounds// Uranium oxide must be packagedin accordance wfi;th:<B&W Fuel Company DrawirigtNos. 1215597D, Rev. 4, and1215600D, Rev^3. The maximum mass of polyethylene within the innercontainer shall not exceed 1000 grams per package. Maximum quantity ofradioactive^material within a package may notêxceed a Type A quantity.

(c) Transport Index/for Cr^£i$i£l,ity Control

Minimum transport indexSt^lb'e jshown dnnuclear c r i t i c a l l y control :;• v e.5^0.7 •• -y

Each package^must bê;|is|iipjfe;|^;t4h..borrate^ within theinner container, otr|;hie t6p^pf0beiêen,:^0fon(ithp/ôttom of the rows ofpellet boxes. ...The Ihêe^borafecl: plates!rniist haveîniensrons and boronconcentration,'-and must? b^.po0t?6ne;d'ih^%ccor4ance' with;~B&W Fuel CompanyDrawing No. 1^W^P&^^-J^~-^J;^;'^rir)? >'£•'

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iC spacers, borated plates, and wood boards must provide a snug axial and cross

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For packages witliêtwer than" sixîêl^boxesj; sol id,'aluminum or wood pelletbox spacers must be'substituted foHêilet boxes, tliie'pellet boxes, pellet boxspacers, borated plates, and wood boaisectional fit in the inner container.

8. In addition to the requirements of Subpart G'of 10 CFR Part 71:

(i) Each packaging must be maintained and acceptance tested in accordancewith Chapter 8 of the application; and

(ii) The package must be prepared for shipment and operated in accordance withthe Operating Procedures of Chapter 7 of the application.

(iii) Prior to each shipment the insert (containment vessel) gasket shall beinspected. This gasket shall be replaced if inspection shows any defectsor every twelve (12) months, whichever occurs first.

498

NRC FORM 618A'.; (3-96)



• 9. The package authorized by this certificate is hereby approved for use under the"' general license provisions of 10 CFR §71.12.; 10. Expiration date: August 31, 1997.

REFERENCES

B&W Fuel Company application dated May 26, 1992.

Supplements dated: August 3 and October 30, 1992; April 30, 1993; May 24 andSeptember 22, 1995; and February 29, 1996.

- - . - , ;!

' - ; \ - . •• ' ' - • '••:>,: " •

/> V> FOR THE UvSv NUCLEAR REGULATORY COMMISSION

William D. Traweys, DirectorSpent Fuel PrAjict OfficeOffice of'I^luclJear Material

~ .-Safety arid^Safeguards

Date: _3J <\h

4 :.-/.I , •

- • ' ; / / /

, ,#in1 i-. - ' . •

4 9 9




. a. CERTIFICATE NUMBER

9252

b. REVISION NUMBER

2


USA/9252/AF

d. PAGE NUMBER

1


32. PREAMBLE




Framatome Cogema FuelsP0 Box 11646Lynchburg, VA 24506-1646

B&W Fuel Company application datedMarch 9, 1993, as supplemented.

c. DOCKET NUMBER 71 - 9 2 5 2

4. CONDITIONS . •" . ' . - - , .This certificate is conditional upon fulfilling the requiremente'of 1Q,(3FR Part 71, as applicable; and the conditions specified below.

5.

(a) Packaging ;•>;

(1 ) Model N o . : .-5LJO32-2

(2) Descri p"t i on ^ \ f C'•<<M;

A steel shipping|cp}i|;ainer,:for/fuel, .bugles, consisting of a strongbackand fuel bund! e> ;ikmping assembly,.slto'cl^ mounted toia steel outercontainer. /Nxn^lepjarator^biocksv^wli^fi are 6" x;;8J' x 8-1/2" long andhavearebolted^bXtween^UjeWbUnfllesU^ is composed of an11 gauge st%pf^%f;11 " feTp3po»x3!n ti<^ "43" ttifneter by .216" long. Themaxi mum • wei gfi|);b#rthg|'0fickage,'! ;in;e;l,ud Y , content^:,," i s 7,500 pounds.

(3) Drawings •!-, ;'^<\t^,;^ ' '"'i' .;-.-'-:;."

The packaging is constructed and assembled;in accordance with thefollowing B&W;Fuel Company Drawing Nos.: 1215926 C, Rev. 1; 1215929 D,Rev. 2; 1215930 D, Rev.:2; 1215931 D., -Rev. 2; 1215932 D, Rev. 2;1215933 D, Rev. 2; 1215934=C, Rev. 1; 1215935 D, Rev. 2; 1216010 D,Rev. 1.

500WJ^

CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONNRC FORM 618A(396) Page 2 - Certificate No. 9252 - Revision No. 2 - Docket No. 71-9252

(b) Contents


Unirradiated fuel assemblies, composed of uranium dioxide fuel pelletsclad in zircaloy tubes. Uranium is enriched to a maximum of 5.05 w/oin the U-235 isotope. The fuel assemblies may contain inserted controlrod assemblies. The fuel assemblies have the following specifications:

Type 15x15

Rods Per Assembly 208

15x15

204

17x17

264

Nominal Rod Pitch(in.)

Maximum PelletDiameter (in.)

Maximum PelletDensity (%TD)

Nominal Clad0D (in.)

Nominal CladID (in.)

Assembly CrossSection (in.)*

Active FuelLength (in.)

Maximum U-235Loading (kg)

0.568

0.3707;;'

%,\^0.563

0.3671 0.3252

17x17

264

0.496

0.3232

~97.5

.0.430£ 3 ^ % Iflo

8,

144 V^

25.20

f/~8.432

144

i^24;-2t J 24J62v

144

24.32

15x15

204

0.5625

0.3672

97.5

0.422

0.368

8.438

120

20.20

* Assembly cross section is the product of the nominal rod pitch and the number ofrods per edge.


Two fuel assemblies. Total weight of fuel assemblies, includingcontrol rod assemblies, not to exceed 3400 pounds. Maximum quantity ofradioactive material within a package may not exceed a Type A quantity.

501

*

NRCFORM618A CONDmONS (continued) U .S . NUCLEAR REGULATORY COMMISSION(3-96)




6. Each fuel assembly must be unsheathed or must be enclosed in an unsealedpolyethylene sheath which will not extend beyond the ends of the fuel assemblies.The ends of the sheaths must not be folded or taped in any manner that wouldprevent the flow of liquids into or out of the sheathed fuel assemblies.

7. Hydrogenous shims are not permitted within the fuel assemblies.

8. In addition to the requirements of Subpart G. of 10 CFR Part 71:

(a) The package shall be prepared for shipment and operated in accordance withChapter 7.0 of tha apptication. '

(b) Each packaging-!shall be maintained in accordance with^Section 8.2 of theapplication. . . ?*

(c) Each packaging shal^weet the acceptance te$t's.,4n Section 8.1 of theapplication.' °t^K' '- -.--, ,-/""T^''

9. The package authorized by%%$% certificate is\ftjetfeiiy approved for use under thegeneral license provisions^j£;10 CFR'§71^.12., ,;$%'.

10. Expiration date:y September 3(^1998'. :''''''*H%^v' .;•>;-', ";.

> 'Mi' w ^ I\LI U i \ L l i v L O \ C ' } / 'y!

B&W Fuel Company application dated MarchV^f'^9931- , V:

Supplements dated: May 10', and July 7, 1993; and April 13, '1994.


Date:


and Safeguards

502

NRC FORM 618(3-96)10 CFR 71




9253

b. REVISION NUMBER

2


USA/9253/B(U)F

d. PAGE NUMBER

1


3I. PREAMBLE

a. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title,10,Code of Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."


3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATIONa. ISSUED TO (Name and Address)

Public Service Companyof Colorado

Platteville, Colorado 80651


Public Service Company of Coloradoapplication dated March 31, 1993,as supplemented


4. CONDITIONS


5.

(a) Packaging

(1) Model No.: TN-FSV

(2) Description ':;:\ .

A steel and lead shielded shipping cask far irradiated high temperaturegas cooled reactor "(HTGR), fuer elements.. iTjie cask is a right circularcylinder, with a balsi and redwood impact 11miter at each end. xu~package has approximate dimensions and weights as follows:

The

Cav i ty di ameter •/,.{v /Cavity length;;* ;Cask.bodyfoiiter diaineter , 'Lead shield;thickhess; >, ., •Package overal 1 puter//ti1i ameter,

including impact Tfimiters; 'Package overall length/

including impact limitersPackaging weight..Gross package -weight,

including contents

18 inches199 inches31 inches

3.44 inches

78 inches

247 inches42,000 pounds

47,000 pounds

The cask body is made of two concentric shells of Type 304 stainlesssteel, welded to a bottom plate and a top closure flange. The inner shellhas an ID of 18 inches and is 1.12 inches thick. The outer shell has an0D of approximately 30 inches and is 1.5 inches thick. The annular spacebetween the inner and outer shells is filled with lead. The bottom plateis 5.5-inch thick Type 304 stainless steel. The closure lid is 2.5-inchthick Type 304 stainless steel, and is fully recessed into the cask topflange. The lid is fastened to the cask body by 12, 1-inch diameter-closure bolts. The lid is sealed with double silicone 0-rings, equippedwith a leak test port. A vent port and drain port are sealed with singlesilicone 0-rings and cover plates. The cask body is covered with astainless steel thermal shield composed of 0.25-inch thick stainless steelplate over a wire wrap. The impact limiters are constructed of balsa andredwood encased in stainless steel shells.

503J^T¥JJ{1£J£>1&T&MJ&M*TSJ2&J£J£J&J&^^



5.(a)(2) Description (Continued)

The cask has two lifting sockets bolted to the cask top flange. Two reartrunnions are provided for cask tie-down.

The fuel elements are stacked in a carbon steel fuel storage container,which has an OD of approximately 17.6 inches and an overall length of 195inches. The fuel storage container has a 0.5-inch thick shell, a 2.0-inchthick bottom plate, and a 1.5-inch thick lid. The lid accommodates aremovable depleted uranium plug.

(3) Drawings

The packaging is constructed and assembled in accordance with thefollowing Transnuclear,ylnc; Drawing-Nos.:

1090-SAR-l,. Rev. 2 ' 1090-SAR-6, Rev. 21090-SAR-2, Rev. 2 1090-SAR-7, Rev. 21090-SAR-3, Rev. 2 1090-SAR-8, Rev.1090-SAR-t4, Rev. 2 1090-SAR-9, Rev. 21090^SAR-5>~Rev. 2 J.O9O^SAR-lO, Rev. 1

^ (b) Contents

(1) Type arid form of mafefial ." ' . 3 £$-- V

Irradiated HTvGRKfjue1,^îheiits.. Eac^fiieêl.eênt coiisists of a graphitebl ock cpptai ning.Vfuel4^pds.} ; ;the! fu,e;l;. s-'comporsed of thori um/urani urncarbide and thpriu^carbide fliel ,par1;icless/*t/i,t.hin the.fuel rods. Thegraphite, block ;l^heXagph;al. ih;c>ossc^section and i^.approximately 14.2inches across thei -filafs'-/and .3|..2înches;ipng. Each;fuel element containsa maximum of 1.4 kg bKvUran^.enfxiched to a max irnum of 93.5 weightpercent U-235 and appr6xim%e,1^\>fe3-kg of thorium.' The maximum burnup isapproximately 70,000 MWD/MTIHMi "and the minimunucool time is 1600 days.


Six fuel elements, with decay heat not to exceed 60 watts per fuelelement. The fuel elements are contained within a fuel storage container.Total weight of contents not to exceed 5,000 pounds, including fuelelements, fuel storage container, and depleted uranium shield plug.

(c) Transport Index for Cri t ica l i ty Control

Minimum transport index to be shown onlabel for nuclear c r i t i c a l i t y control: 100

504

•"-."'" 7~ -" . -C~R7T f - - , \ ~ ' " "V "• •.7?';.'*vr-v"!-";",-?-i'5'-ST* ifS?'J^.'- * '• ?••'-•• '--"'••'•••

NRCFORM618A(3-96)



The package must be leak tested as follows:

(a)

(b)

Within the 12-month period prior to shipment, and after seal replacement,the package must be tested to show a leak rate no greater than 1 x 10std-cm /sec. The leak test must have a sensitivity of at least 5 x 10std-cm3/sec.

Prior to each shipment, the package seals (main seal and vent seal) mustbe leak tested in accordance with Section 7.1.2 of the application. Theacceptance criterion is a leak rate no greater than 1 x 10 std-cm/sec.The test must have a sensitivity of at least 1 x 10"3 std-cm /sec. Thedrain seal must also be tested if the drain port cover has been removedsince the seal was last leak tested.

In addition to the requirements of Subpart,G^of 10 CFR Part 71:

(a) The package must.be" prepared for shipment and operated in accordance withthe Operating Procedures of Chapter 7 of the application.

Each packaging .must meet the acceptance'tests and nnust be maintained inaccordance,with the Acceptance Tests and Maintenance Program of Chapter 8of the application^ l;v <^

(b)

(c) Prior to each shipment,, the cask main cjQsjire seal and vent seal must beinspected. The drjijnxseal must be inspfe^d if the ^drain port cover hasbeen removed durjng%rj!par.at^ „ All seals must be replacedwithin the 12-mp%tffsperidd: prior fp. sh^pT^nt;*/or earlier if inspectionshows any defectv. ' 4/*::*-:~- :" : i ^ ' - ^ JrA6 : ,

The package auth'orized;-by^hi^.ertifTcate'i-is hereby approved for use under thegeneral license provisions\'of<id CfR §71-f2r :";

Expiration date: >.l!1ay 31, ^

8.

9.

.. REFERENCES

Public Service Company of Colorado application dated March 31, 1993.

Supplements dated: February 24, June 2, and June 14, 1994; September 11,and December 7, 1995.



and Safeguards

Date

505K

W









32. PREAMBLE



g

££3s

H

ft.


Nuclear Fuel Services, Inc.P.O. Box 337, MS 123Erwin, TN 37650


Nuclear Fuel Services, Inc.,application dated July 2, 1993.


4. CONDITIONS

This certificate is conditional upon fulfilling the requirementepf IQGFR Part 71, as 'applicable/and the conditions specified below.

a

(a) Packaging

(1) Model No.:

(2) Description"

(3)

The packaging'?^constructed^o^ceordance^with./Nublear Fuel Services, Inc.,Drawing No. OO6-MPQ75-B, Revision A. ^ V - ^

5 0 6

^NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION(3-96)

Page 2 - Certificate No. 9254 - Revision No. 1 - Docket No. 71-9254 5

5. (b) Contents


Dry, solid waste material in the form of non-compactible materials andcompacted bales, approximately 16 inches by 16 inches and 2 to 10 inchesthick. The material shall have no sharp points, edges, or corners andshall be triple-wrapped in plastic. The material shall be limited to thefollowing:


0.0001 mi-11 icurie of radibnuelides for which the A2 quantity inAppendix A of 10 CFR Part 71 is not more than 0.05 curie;

0^005 millicurie of radionuclides for which the A2 quantity inAppendix A of 10 CFR Part 71 is more than 0.05 curie, but notmore.-than 1 curie; or

0.3 milVicurie of radionuclides for which the A2 quantity inAppendiÂtof 10 CEfC'Part 71 is;more than 1 curie.

(ii) Objects;^||ibnradipactive material externally contaminated withradio|cti^âter'iai;'"prov-ided.tthat/the radioactive material is

, ( not-'rwdilyvxlfspersible andl;the surface contamination, when•'•' avejfiaêdôyeri'an area of4Tsquarevmeter, does not exceed

0.00(UVmi1:iiciirie (220,0*0X1 disintegrations per minute) per square;centi§$ter^ the A2 quantity in

/ 2 q yAppendiÂ^priO^CFBvparir^VHsr/not more than 0.05 curie, or

-0.001 millicurie^(2f,^b0,000, disintegrations per minute) persquare centimeter^fbr.fother radionuclides.


Greater than Type'A- quantities-of; radfoactive materials. The maximumweight of the waste material is 300 pounds. The contents may includefissile material provided that the total quantity of fissile material perpackage meets the mass limit specified in 10 CFR §71.53(a).

507



6. (a) For any package containing water or organic substance which couldradiolytically generate combustible gases, a determination must be made, bytests and measurements or by analysis of a representative package, that thefollowing criteria are met over a period of time that is twice the expectedshipment time:

The hydrogen generated must be limited to a molar quantity that would be nomore than 5% by volume (or equivalent limits for other inflammable gases) ofthe package gas void if present at STP (i.e., no more than 0.065 g-moles/ft3at 14.7 psia and 70 °F).

For any package delivered to a carrier for transport, the package must beprepared for shipment in the same manner in which the determination for gasgeneration is made. The, shipment, period.begins when the package is prepared(sealed) and must be completed within twice the expected shipment time.

(b) For any package shipped within 10 days after sealing of the drum, thedetermination;^- (a) above need not be made, arid'the time restriction in (a)above does not apply. . ,>'.,

7. Radioactivity per package shall be determined in; accordance with Sections 1.2.4 and4.8 of the application. v?-^i - **.i&V/

: i' v l f t i > i^3:-":™" * / s*'•*>(•' ' ••

8. In addition to* the requir|$%n£s of Stibpart G oJJ&CFR Part 71, the package shallbe prepared for shipment aiid'foperatedJnUccordapf^ with Section 4 of theapplication. .,:.• .;•%.» ^T&V';' ''" "" "'"^ .-i^'W? <

9. The package authbrize!<b£;vtXi:^ on a motor vehicleor railroad car.assigned^p^sol-eiliseipf IthVlicensee:' •''-'

';-{. ^'\- I^^^Vi-'-:- >-- :ii-i^K >.yi-;i' ••>"':-

10. The package authorized bi?yt¥i«7cer'fc||-i!6H'eN1si:h'ei'e1)y approved for use under thegeneral license provision of 1.0 —-~"-—AN^

11. Expiration date: April L, 1999. This certificate isjnot renewable.

Nuclear Fuel Services, Inc., application dated July 2, 1993.



Date: ,

508


FOR RADIOACTIVE MATERIALS PACKAGESb. REVISION NUMBER




2PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



a THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DES1GN OR APPLICATIONIL ISSUED TO (fame end Address) ' ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Yankee Atomic Electric Company580 Main StreetBolton, MA 01740-1398

Yankee Atomic Electric Company applicationdated April 12, 1993, as supplemented.

yc. DOCKET NUMBER 1=c^ %,,//' 7 ; 1 ~ 9 2 5 6

4. CONDITIONS <s %.£ . N . .This certificate is conditional upon fulfilling therequirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging

(1) Model N o . : ^

(2) Description-;

Ste\m|Gene,rator m?

-welded nozzleconsists of the

The steam-1/4ininches

the tube __...._ ._„„„„,inches in th|,#jbe bundleKreg^fpp^l/Slfphes irrthe steam drum regionI he length of he^ steam generator] p'adltageMi'approximately 40 feet 7-3/8inches. The tube^bundle is comptfsia"Jof 1620 U-t.u6eV which have an 0D ofapproximately 3/4 ^ e h , and an average wall thtekness of 0.072 inch. Thenozzles and other penetrations are coveredwithVelded closures. The steamgenerator is filled withvTbw/dens-lty^onc^te on both primary and secondarysides. Three shear keys are^welded tb4the steam generator shell bottom foraxial restraint. Toroidal impact limiters, which are polyurethane foam with acarbon steel shell, are fixed at each end of the steam generator. Steelplates are welded onto the steam generator shell for radiation shielding asrequired. The maximum weight of the package is approximately 273,000 pounds

(3) Drawings

The package is constructed and assembled in accordance with the followinqChem-Nuclear Systems, Inc. Drawing Nos.:

C-110-B-46063-1, Rev. 1C-110-B-46063-2, Sheets 1 through 4, Rev. 0C-110-D-46063-3, Sheets 1 and 2, Rev. 0C-110-A-46063-4, Rev. 0

509

^

„„« r w ~ - ».«~ U.S. NUCLEAR REGULATORY COMMISSION«™,rw™»w.«», CONDITIONS (continued)


(b) Contents


Steam generator containing radioactive contamination, f i l led with low densityconcrete, meeting the requirements of low specific activity radioactivematerial.


Greater than a Type A quantity of radioactive material. Fissi le material maybe present provided the f i s s i l e material meets the exemption standards of 10CFR §71.53. ^ ;;?; ;7C }Z fy ,; ,_

6. In addition to the requirements of Subpart G of" lQJ|F/R Part 71:

(a) The package mus;1f)£e prepared for shipment and transported in accordance withChapters 7 and^8"'of the application. ", •

(b) The package^must^b^""t:rjinsported in accordanAce"^lth the-operational controls ofTable 1.1 -offthe appKt%txion. -!""M^S ~~

(c) Prior to transport , slne-Tding mixi% bxe weldecf^nto the package in accordancewith ChennNuclear Sys$ern|-i;Inc.^DraîngtNo;^||$110-B-46063^1, Rev. 1, asnQ°essary7:jsuch thât^t-Rel.âGkage^êet-s^h^vfexêrn.al, radiation standards of 10

7. This certificate" auth6î^\^"6rt^t-i|ne'sliiip^pnt for;|^«:h of four packages from theY k N l P S ^ t f ^ ? 6 $ t ! i ; B / W h l i

^ ^ \ ^ ^ i | i p ^ p ;|^ pYankee Nuclear Ptfwer Sâtfpn^to/a~?p6$nt!iie;aniBarnyi/eW, South Carolina.

8. The package authorized by^thS^ceiQt-^jcai^mus.t^'b.e'' transported on a motor vehicleand on a railroad sca'r assigned" for ^ t ieso lVuse 'o f the, licensee.

9. The package authorized byvthis certificate is herebyvapproved for use under thegeneral license provisions of 10 CFR §71.12.

10. Expiration date: September 30, 1998." ',

REFERENCES

Yankee Atomic Electric Company application dated April 12, 1993.

Supplements dated: April 20, July 30, August 2, and September 10, 1993.


Cs&s


OCT 2 8 199$ Medical Nuclear Safety, NMSSDate

510,*Jii!±!liyi4iJiti^ljmsM;j^JV^JflsM^

" V * . * " ' " V ••' - V " 1 • / . ' " • " ••*", •** '- ' * ( » > • ' -

NRC FORM 61B<M6I10 CFR 71


^^^ C ° M M ' S S I ° N

a. CERTIFICATE NUMBER





3

2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicabie safety standards set forth inTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE .DESIGN OR APPLICATIONa. ISSUED TO /Name and Address! b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Portland General Electric Company71760 Columbia River HighwayRainier, Oregon 97048

Portland General Electric Companyapplication dated January 23, 1995,as supplemented.

' c. DOCKET NUMBER 71-9059A. CONDITIONS .. ; .-> 'C -::


(a) Packaging

(1) Model M i : Trojari.-Steam Generator

(2) Description /--.._.«_—,_. .-_, .. ,._•,-,. -,... ._ Wlt|^ seal_

- . _ , consists ofthe steamsheet andwith an'OD of ~af^rpX^ma|^y;;ij4j;'fje^8 incJlWin the-41'pper shell (steamdome) region, andra'ffO^ feet ;$£jnches in the lowershell (tube^bundle) r&g]m0fpl^e^heJ^fa'\'\ thiQRnpss is approximately3.6 inches/anj the upper s e;i.l jre^gTon^an^ 2.8 ttf\3V^ inches in the lowershell region^^he length ofs't\\}e steam generator package is approximately67 feet 8 inchW. The tube bundle is compt>s§<f of 3388 U-tubes, whichhave an OD of approximately 0.875 inch3f andean average wall thickness of0.05 inch. The nozzTesT|ndxo

sther;*'penetrations are covered with weldedclosures. The steam gefferatb^ inf i l led with low density cellularconcrete on both primary and secondary sides. A series of five shear keybars are welded to the steam generator lower shell for axial restraint.Steel plates are welded onto the steam generator shell for radiationshielding, as required. The maximum weight of the package isapproximately 900,000 pounds.

(3) Drawings

The package is constructed and assembled in accordance with the followingTrojan Nuclear Plant drawings:

M-9249, Sheets 1 through 4, Rev. 0.M-9250, Sheet 1, Rev. 0; Sheet 2, Rev. 0; Sheet 3, Rev. 0;

Sheet 4, Rev. 1; Sheet 5, Rev. 0; Sheet 6, Rev. 1;Sheet 7, Rev. 1; Sheet 8, Rev. 1; Sheet 9, Rev. 0;Sheet 10, Rev. 0; and Sheet 11, Rev. 0.

M-9251, Sheet 1, Rev. 0.

511

Rfi??&il*&^*i?W^

NRC FORM 618A(6-83)




(b)

6.

7.

8.

9.

10.

11.

12.

Contents


Steam generator containing radioactive contamination, filled with lowdensity cellular concrete, meeting the requirements of low specificactivity radioactive material.


Greater than a Type A quantity of radioactive material. Fissile materialmay be present provided th& ftgsirjte.material meets the exemptionstandards of 10 C F R 7 0 5 ! ' '" ~ '

In addition to the recrements of Subpart G of ltJ^CR Part 71:

(a)

(b)

Prior to transport,system used !?cpssuppcertified th£t<t2the sjaccordance with=*the

Prior to transp*o)%, thcondition of thevyissel 'and

elding must be wjucl ear^-ELant

The package^^frst be prepared for shipment and tnajjsgorted in accordancewith Chapt Eg? 7 and 8 of the application.

Prior to^ranspaccordance* withthrougljM*, Rev.radiation standar

nto the package inM-9g?9, Sheets 1

he package_-.meets the external

3 evaluated thebarge,, and must have

m arfdfl Hja" pacjgge stowage are inpjhited_cS|ates Coast Guard.

must hjaye" inspected the'ackage<4)rPrhe barge.

This cer t i f ica te auf|)O%izes a one-time shipment fo^Jgarch of four packages fromthe Trojan Nuclear Plarvp'to a point near Richland, Washington.

4isThe package authorized by this

assigned for the sole use of the licfrfsee'.transported on a conveyance


Expiration date: June 30, 2000.

512

«!M»!JtM!R^V^«M«MiRi«iflaM«MRV^V^^TV^a^V^

!*&?^



REFERENCES

Portland General Electric Company application dated January 23, 1995.

Supplements dated: May 2 and 3, and June 15, 1995.


Date J"ne 29, 1995

Cass R. Chappell, Section LeaderCask Certification SectionSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

513*!>U'M*^

•C

NRC FORM 618(8-85)10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGESL CERTIFICATE NUMBER

a 9260»ti

b. REVISION NUMBER

0


1

o. TOTAL NUMBER PAGES

2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets theapplicablesafety standardsset forth InTitle 10, Code




Portland General Electric Company71760 Columbia River HighwayRainier, Oregon 97048

s..j. \ j-5' "*c.


Portland General Electric Companyapplication dated January 23, 1995,

. DOCKET NUMBER 7 1 ^ 9 ? 6 0

4. CONDITIONS N\\^This certificate is conditional upon fulfilling the;requirements of 10 CFR Part 71, as applicable, and the'cqnditions specified below.

(a)

(2)

TrojaWresSurizer-

A reactor vseal-0Ddedthe pressuripressurjjierapproximatelyshell *"'"

êlluijif concrete, withle prfsslirizer consists of

"elements. The| [ j p l rt /MnlPheaterel ements. Theia1Jyj%jindr||fl^withîT> overall length of

i.ien wd-i i Lini.K.rre5s-ms a^pmmte iv f||i:ncnes along trie cylinder wall,2.5 inches fa the uppet hejWte&oh,*arii)3 inches^n the lower headregion. The^nternal heatet/ftements, Ihich êâpproximately 9 feetlong, are arranged in concentric rings in the^Vower region of the vesselThe pressurizerîs fi,lled with low densityWllular concrete. A shearkey assembly is welite* totthenpress.ur<iszer shell for axial restraint.Steel plates may be welded fijjj^ the, support skirt flange for radiationshielding, as required. The maximum weight of the package isapproximately 250,000 pounds.

(3) Drawings

The package is constructed and assembled in accordance with the followingTrojan Nuclear Plant drawings:

M-9252, Sheets 1 through 3, Rev. 0.M-9253, Sheets 1 through 8, Rev. 0.M-9254, Sheet 1, Rev. 0.

514

gftgftgftaft^^

NRC FORM 61 DA(6-83)

t

I

it

i

t

t

c

Ir

t

iI

E

C

t

ii

iiI

'tcii

i

r

iI

E

I

I




(b)

6.

7.

8.

9.

10.

11.

12.

Contents


Pressurizer containing radioactive contamination, filled with low densitycellular concrete, meeting the requirements of low specific activityradioactive material.


Greater than a Type A quantity of radioactive material. Fissile materialmay be present provided Jthe jf4£s41/e^material meets the exemptionstandards of 10 CFR,§j7aM. ~

In addition to the

(a)

frements of Subpart G o SFR Part 71:

(b) Prior ,saccordafi.ee withas necessary sueof 10XFR §71.47

Prior to transport,system usedlôcertified thataccordance with th

hielding mustNuclear^Pl

he

The packag^must be prepared for shipment and transported in accordancewith ChapTlers 7 and 8 of the application. _, <^tS

A*onto fRe package inM-^52, Sheet 3, Rev. 0,

exten^Lradiation standards

mst hja e evaluated thebange, and must havepa^^ge stowage are in

n i t ed^ t a t e s Coast Guard.

Efve inspected thepackage^fon the barge.

e package from the Trojan

Prior to transport, t\ .condition of trTe/vessef and?

This certificate a^Horizes a one-time shipmentNuclear Plant to a polm near Rich!and, Washington

The package authorized by^tfiisXc^rtîcê must be transported on a conveyanceassigned for the sole use of the lrcensee"


Expiration date: June 30, 2000.

515

A3&&K&$!!&&n&f8t^

NRC FORM 618A(6-83) CONDITIONS (continued)



REFERENCES

Portland General Electric Company application dated January 23, 1995.

Supplement dated: May 2, 1995.


V^ j p , Section Leader

Cask CerwFJcatjon SectionSpent Fuel Prtflect OfficeOffice of NucleiwH&terial Safety

and Safeguards

Date J u n e 29- 1 9 9 5

5 1 6

^NRC FORM 618<M6|10 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES1.a. CERTIFICATE NUMBEH b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER



2. PREAMBLEa. This certificate is issued to certify that the packaglngand contents described in Item 5 below, meets the applicable safety standards set forth inTitie 10, Code



3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEDESIGN OR APPLICATION 'a. ISSUED TO Warns end Address! ' b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

Yankee Atomic Electric Company580 Main StreetBolton, MA 01740-1398

Yankee Atomic Electric Companyapplication dated March 23, 1995,as supplemented.

c. DOCKET NUMBER

4, CONDITIONS %J ^ ! %This certificate Is conditional upon.fulfilling-thej'equirements of 10 CFR Part 71, as applicable, and the'conditions specified below.

(a)

a ,cyl i ndr^cal steel outer

p p l y l f gnozzles \are closed wtfjthwith three^-nch thick tinner waste/container, an

£3*^1 leer with concrete. The reactor"•^nchMn^ck cacbon steel vessel with

,. oKthe reactor vessel istijti, th^gprngth of^he reactor vessel is

ctor v^sel main coolantThe reactor vessel is surrounded

n. The^reactor vessel contains anlied with losw^ensity concrete.

The outer packaging/(is composed of aKthree^inch thick cylindrical shellwelded to a four-ificiT ttfjjck /bot|6m- pTate, and is constructed of-A516, Gr.70 carbon steel. The fo"ur-/mch ithick top plate is attached to thereactor vessel flange by the existing reactor head studs, and is weldedto the packaging outer shell. Caps are welded over the head studs. Theregion between the reactor vessel and the outer packaging is f i l l ed withfu l l density concrete. The overall dimensions of the package areapproximately 13 feet, 2 inches outer diameter, and 28 feet, 3 inchesouter length, excluding the head studs and caps which extend beyond thetop plate. The weight of the package is approximately 727,000 pounds.

(3) Drawings

The package is constructed and assembled in accordance with the followingYankee Atomic Electric Company Drawings:

YR-B-90-005,YR-B-90-006,YR-B-90-007,YR-B-90-008,

Rev.Rev.Rev.Rev.

1000

YR-B-90-009, Rev. 0

5 1 7

^^JK!rgjMKââ^g^WW'rf&^Xâ^g^!^!a^

NRC FORM 618A(6-83)

CONDITIONS (continued)U.S. NUCLEAR REGULATORY COPJIMISSION


5.(b) Contents

(1) Type and Form of Material

Irradiated steel reactor pressure vessel, containing radioactivecontamination and waste in solidified concrete, meeting the requirementsof low specific activity radioactive material.

(2) Maximum Quantity of Material per Package

Greater than a Type A quantity of radioactive material contained in anirradiated reactor pressure vessel and associated contamination andsolidified waste. Fissile material may be present provided the fissilematerial meets the exempt^n f%gajjs,of 10 CFR §71.53.

6. In addition to the reau%efiients of Subpart G ofdjHCFR Part 71:

(a) The Federal 'E^rgy Regulatory Commission must specifically approve theadequacy of^he Sherman Dam and spillway bridge airtransport of theModel No. YNPS-^V package. ~ ^

&^ X(b) The MasâGhuset

adequaeyôf thefrom the3Yankeethe Mod.§1 No.

(c) The packageaccor

This certificate^ authflYankee Nuclear^Rdwer

The package autKfacHjZed by this .^vehicle and on a rljitôad car ass

cifically approve thenlity a'odlroadway culverts,

1 line^for transport of

fst be^transported in

sing.Ten=package from the

p irTus1|'be transported on a motoror the soleîisj of the licensee.

8.

9. The package authorizef^y thjs certificate isjvfyereBy approved for use under thegeneral license provisions/b^l>04CFRÂ§71 JI-E-.'Y^

10. Expiration date: January 31, 2001.

REFERENCES

Yankee Atomic Electric Company application dated March 23, 1995.

Supplements dated: March 31, August 30, and December 15, 1995.


Trayers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

Date518;

^

NRC FORM 618(3-96)10CFH71






USA/9263/B(U)A PAGE NUMBER


2I, PREAMBLE



a, ISSUED TO (Name and Address)

Source Production andEquipment Company, Inc.

113 Teal StreetSt. Rose, LA 70087


Source Production and Equipment Company Inc.,application dated December 27, 1994, assupplemented.

c. DOCKET NUMBER 71-92634.CONDITIONS

{This certificate is conditional upon fulfilling the requirementsôf lOJCFR Part 71, as applicable,' and the conditions specified below.

(a) Packaging

(1)

(2)

\ \• • ' • \

Model No.: SPEC-150

Description^, r?^.*- ' . / ' 7

A welded titanium en£|s^>vurajiiw^^ exposure device.Primary components ofnSlstôf ^nûjfcerftjâ^jlim shell j> internal supports,depleted;;;uranium shijg^f/arid a t'Haiiiumi w^frcalloy S'Ctube. The contentsare securely posi^tidh^^jnVJhei^tube^By^^Surce cable^lock assembly and

| V | | ^ i | | ^ t isource safety ^^jîzi^S^ ^\\^\\x\i^0^^\^£j\ rectjfngular box"inches lonq. The

maximum weight

(3) Drawings

The packaging ;is, construfcte%anMasspmbled/in accordance with SourceProduction anclÊquipment Compra'fty:i rh*c. Drawing Nos. 15B000, Rev. 4;15B001-3, Rev. 0;^15B002A, Rev. 3; and 15B00MRet. 2.

(b) Contents l^ /., s A.^ J v < ^




150 curies (output)

Output curies are determined in accordance with American National StandardN432-1980, "Radiological Safety for the Design and Construction ofApparatus for Gamma Radiography."

519

fi NRCFORM618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION"" (3-96)


£ 6. The source shall be secured in the shielded position of the packaging by the£ source assembly lock, lock cap and safety plug assembly. The safety plug£ assembly, lock cap and source assembly used must be fabricated of materials£ capable of resisting a 1475 °F fire environment for one-half hour and maintaining£ their positioning function. The locking ball of the source assembly must engage£ the locking device. The flexible cable of the source assembly and safety plug™ assembly must be of sufficient length and diameter to provide positive

positioning of the source in the shielded position.

7. The nameplates shall be fabricated of materials capable of resisting the firetest of 10 CFR Part 71 and maintaining their legibility.

8. In addition to the requirements,.;of ûbpa^tG^bfj 10 CFR Part 71:

(a) The package shall(fBexip"repared for shipment and/bperated in accordancewith the Operating^ Procedures in Section 7, of-the application, assuppl emented, <|ind " // /;

(b) Each packaging mufsj-jneet the Acceptance Testsând>Maintenance Program inS Section 8,-\bf the^p^Mcâtion, as supplemenfjeja^'' /•'.

3 9. The packaging authorized bj^RisVerQlfiiater'is'^herTeby approved for use under the8 general license-,]s

10.



and Safeguards

Date:

X

B 520

*SJS5J£J^TKT^7&7&7&TSU£kJ£U3SJ3&^

. ^

!NRC FORM 61S(M6)10 CFR 71







22. PREAMBLE

a. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10. Codeof Federal Regulations, Part 71, "Packaging and Transportation of Radioactive Material."


i

tIiit

j

i

i

i

i

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t

a. ISSUED TO /Name and Address!



\ J

Amersham Corporation application datedOctober 2, 1995, as supplemented.

° c. DOCKET NUMBER '9^694. CONDITIONSCONDITIONS <\W " ^ f S>

This certificate is conditional upon fulfllling^he;requirements of 10 CFR Part 71 , as applicable, and the conditions specified below.

(a) Packaging^

(1)

(2)

miê o$mas^se'mbl y . fÛd-ttd on aloclî'ng assemblies Ow/M/.,v™âssemblies are used wVeot|*shielcfel^position during transport, •••^^....u , » « V i » Qrectanguf%r box approximately 10 inch%sVwide, 13.25 inches highand 8.25 inch|sl3ong. The n aximiLin> wefght of the package is 90pounds. " ^

shielded, iridium-192't of ciLbsteel or, dej)=leted uraniumis pimped in the

stop ÔTG the source650L (has two source

cove^glate . These

^ ' - s o u r c e i n a

Thejjtnit resembles a

>

(3) Drawings

The packaging is constructed in accordance with the AmershamCorporation Drawing No. R65006, Rev. C, Sheets 1-4.

(b) Contents


Iridium-192 as sealed sources which meet the requirements ofspecial form radioactive material.

5 2 1

• v • r

ttft8^

NRC FORM 618A(643)


7.

8.

9.

•10.



240 curies (output)

Output curies are determined in accordance with American NationalStandard N432-1980, "Radiological Safety for the Design andConstruction of Apparatus for Gamma Radiography."

The source shall be secured in the shielded position of the packaging by thesource assembly. The source assembly must be fabricated of materials capableof resisting a 1475° F fire environment for one-half hour and maintaining i tspositioning function. The cable-af lifoe goosce assembly must engage thesource hold-down assembly.^Ttf^fnBXTOletJcljjl/«f.the source assembly must beof sufficient length and\d^neter to provide pTfs{rh« positioning of thesource at the crimp oflQjiV"U" tube. ^

The nameplatestest of 10 CFR

In addition to

(a)

resisting the fire

(b)

The pacl/age shalOperatioopProcedurand ^

Each p a kChapter

fabricated of materials capabland maintaining their l g i b i l j j ^ ^

R Part 71:oj t f j P I I ) accordant with the

' a p t ' t

The package authe general lie

Expiration date:

supplemented,i

i

intefiAnce Program of

for use under

30, 2000^

REFERENCES

Amersham Corporation applicj

Supplement dated November 6, 1995.


Date: VI

William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material SafetyAnd Safeguards

522

NRC FORM 618(3-96)10 CFR 71




9274

b. REVISION NUMBER

0


USA/9274/AF

A PAGE NUMBER

1


32. PREAMBLE




Combustion Engineering, Inc.P.O. Box 107Hematite, MO 63047


Combustion Engineering, Inc. applicationdated May 30, 1996, as supplemented.


4.CONDITIONS r> .';-> !^> '"v'.''?v;This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable; and the conditions specified below.

(a) Packaging

(1)

(2)

Model No..:

Descri pinion

-'ABB-2901

A shipping contaan inne£ container^

p e l l e t s , composed ofand an outer drum.an inners container^sur^rounaea^ Dy insuaapng material-, ana an outer ur

The inner contai-n6^^}40F7S-#^/4^n.cfi.^square anfcapproximately 30inches .'-jjong,xM^^^^^^^fjinm^l^^pige/sêe^,J-With bolted andaasketfefd-5 toD Sl'anae 'cil' s'ufe-'ah'dlitteftfisaôtiqnfcsheet^^The inner contaigasketefd-5 top >Tange *cil %re-'ah'dj!WiB| gô f6jtii>sheet~. jThe inner containeris centered aKd;:|5%"0^W?i1n1a'n,;i8|gauge kxije.) drumiby asbestos orceramicCsheet.fplywoo^ insulating;nia"terial. The drum hasa 16-gdkgpc}o^r;4^^^^M^^^^^0e ring(w#h drop forged lugsand a 5/8-4nch dfameteV bj^|Pfh>.drum'fi'as approximate dimensions of22.5-inchs;;ID/by 36-inch Retg1)p^p"ne"-UKahium ,pîde pellets are packagedin boxes positioned within'a^tieel insert. ^The; maximum gross weight ofthe package is/660 pounds. <»

(3) Drawings

The packaging is constructed and assembled in accordance with CombustionEngineering, Inc. Drawing Nos. D-5018-8441, Rev. 0, and B-5007-8112,Rev. 1.

5«i

i

523TW^, TVs 7¥S /+\ T

W

g

«3

38g33g

3



5.(b) Contents


Sintered uranium oxide pellets enriched to a maximum 5.0 w/o in the U-235isotope. The maximum pellet diameter is 0.969 cm, and the minimum pelletdiameter is 0.818 cm.


227 pounds of pellets, with the U-235 content not to exceed 4.54 kg. Thepellets must be packaged on corrugated stainless steel trays, withinshipping container boxes and a shipping container insert in accordancewith Combustion Engineering Drawing Nos. D-5018-8438, Sheets 1 through 3,Rev. 1, and D-5018-8442, Rev. 0. ; <'

Maximum weight of contents within the inner container is 427 pounds,including radioactive material, secondary containers, and other packagingmaterial.

(c) Transport Index for Criticality Control , --'

Minimum transport index to be shown: ~.on label for nuclear criticality control: 0.5

6. Corrugated stainless steel trays must be positioned'between each layer ofpellets, and on the top, and 'bottom of the; pellet^stack. Spacers must beinserted in partially filled pellet shipping boxes to provide a snug fit.

7. The package may also contain stainless steel pallets, depleted uranium pellets,and neutron poisons such as gadolinia), e>bitirn, and boron carbide.


(a) Prior to each shipment the insert (containment vessel) gasket shall beinspected. This gasket shall be replaced if inspection shows any defectsor every twelve (12) months, whichever occurs first.

(b) The package must be prepared for shipment and operated in accordance withthe Operating Procedures of Chapter 7 of the application.


10. Expiration date: February 28, 1998.

524

NRC FORM 618A(3-96)



REFERENCES

Combustion Engineering, Inc. application dated May 30, 1996.

Supplements dated: June 3 and August 7, 1996.


William D. Trayers, DirectorSpent-Fuel Project OfficeOffice of Nuclear Material Safety

and Safeguards

Date:

~'VKo\'"\:.A'---'/ / ' / •

525

EUK2K;KM7¥V;^;ra^^^(ffiiffiffl;gL^M7y^^

NRC FORM 618(8-86110 CFR 71


FOR RADIOACTIVE MATERIALS PACKAGES•.CERTIFICATE NUMBER





I

I

Ii





U. S. Department of EnergyEH-33.3Washington, DC 20545

U. S. Department of Energyapplication dated February 26, 1991,

plemented

* c. DOCKET NUMBER

4. CONDITIONS iThis celtificate is conditional upon fulfilling the-jequirements of 10 CFR Part 71, as applicable, and thi'oon'di,tions specified below.

(a) Packaging

(1)

(2) DejIjcViption

ThlTpack.acasic bod

stainless^teel cask. The'-/-vL~~ OD>by 49 inches high.

pars in^d-iameter by 22.83le basket has either four,

atneter hoi£es that serve asIlevenc3;4i-inch high,

_ bod^§xterior. A covered ventport anMCjcpvered drairTpoH are located^ the side of the caskbody. Th<f<£ask lid is a one-piece forging, 28.78 inches in diameterby 12.84 inches^hick,. Twelve 1.5-^nchvdiameter bolts fasten thecask lid to the as^body^thriugifia^.S-inch thick flange. The casklid and port covers each^bavrconcentric, double 0-rings. The inner0-ring is metallic and retains the helium coolant which fills thecask cavity. The outer 0-ring is elastomeric and provides an annulartest volume for leak testing the metallic 0-ring. The cask has animpact limiter on each end. The impact limiter is polyurethane foamin a stainless steel shroud.

The overall dimensions of the packaging with impact limiters are 84.7inches in diameter by 107 inches high. The maximum total weight ofthe contents is 400 pounds. The maximum weight of the package,including contents, is 30,000 pounds. The shipping skid andpersonnel barrier, which are not part of the package, weigh anadditional 3,700 pounds.

526




(a) Packaging (continued)

(3) Drawings

The packaging is constructed in accordance with the followingdrawings:

Drawing No.

S54773, Sht. 1, Rev. BS48981, Sht. 1, Rev. HT73684, Sht. 1, Rev. N,

and Sht. 2, Rev. HR44382, Sht. 1, Rev

T73693, S h W I r e v - MS66574, S h t U l , Rev. B

T99946^Sht. 1, Rev. E

SKT 9 9 9 |

R44676, ShtR43fZ8, ShtS48929, Shts

rDJkR4C81, S

# 3 Sht. _,S50032, SK%IS5260% Sht^S5260cl%.Sht

S50053>fSM.S50054,S50055,

(b) Contents

Title

Cask with Impact LimitersCask AssemblyBody, Cask, 304 (BUSS)

#Alternate Detail N for Upper PortC / f Unit 1 , Heat No. 82V65-1-1

(BUSS) 304 SSTsion, 12 Point External

WrenchTTtg , FlangedSeal, He¥fcqflex, Cask Lid (BUSS)

•afiPgjUSS)elicor4ex,

In PlugiBUSS)Plug As^ertbly, Cask BodyPlug, Cas^Body

ct LimiteHBUSS

rtformjBfceBUSS^sk

T, Mounf^ig, Ca>fe Body, 4 Hole (BUSS)

'sket,^C>§k Body, 6 Hole (BUSS)( Body, 12 Hole (BUSS)

Cask Body, 16 Hole (BUSS)


Melt-cast cesium chloride (CsCl) or pressed-f i l led strontium f luor ide(SrF2) capsules meeting the requirements of special form radioactivemater ia l . The capsules are as described in supplement datedFebruary 28, 1992.


BasketType

16-Hole12-Hole6-Hole4-Hole

CapsuleType

CsClCsClSrF?SrF,

Maximum CapsuleThermal Power

(Watts)

250333650850

Maximum CaskThermal Power

(Watts)

4000400039003400

Maximum CaskActivity

(million Ci)

0.850.850.650.56

^^ M 527

^




For shipments of CsCl capsules, the shipment period must be completed withinthirty (30) days following the placement of the cask lid on the cask body.

The lifting lugs must not be used as tie-downs, and the lifting lug. holes must beplugged or covered during transit.

8. In addition to the requirements of Subpart 6 of 10 CFR Part 71:

(a) The package shall be operated and prepared for shipment in accordance withChapter 7 of the application, as supplemented.

(b) Each package shall be acceptance tested and maintained in accordance withChapter 8 of the application, as sup.plemented.

9.

10.

11-

The package author ized by th€» p r t i f i c a t F m a l ' t C b ' e / t r a n s p o r t e d on a conveyanceassigned fo r t he exclusi(v.e\j5e<i 'of t h i s package. ^d

The package authorize*<0>y this certificate is hereby appjfcftjed for use under thegeneral license prqui&ions of 10 CFR §71.12.

Expiration Date:

U. S. Department of Energy appl

plements dated February 1994 f

REG0UATORY COMMISSION

21199k

... Chappell, iej^ion LeaderCask Certificati directionStorage andjTKanspbrt Systems Branch

.vjsion^ofindustrial andMedical Nuclear Safety, NMSS

Date:

528

M#^^

T " T - " ' * ' ^ , ,_ v,'~ <*?"""- ,N" 'V f^ -f.i",';f^* "-'* I''* ~-~'<• . ' ' * • ' • ! • .* • • . -.'"—.-'






6 .




3

2. PREAMBLE






Safety Analysis Report for M-160 ShippingContainer dated October 18, 1968, assupplemented.


4. CONDITIONS :


5.

(a) Packaging

(1) Model No.:,'-M-lSp>,.

(2) Description * r C V ^ --;-. . •••J:'r :•'•

The packaging is a righfrîijcufar cylinder, 7§'-#m:hes in diameter by 199 inchesoverall height. The/packaging outer shell, consists of 84 evenly spaced verticalfins 151-1/2 inches ionj,%t|ac|ied to a 1-1/2-inch thick wall (fabricated fromcarbon steel and cladVith || ^ surface). The innershell, the containment^^ssî^jsjl-inchJihTCk (fiavitfg a 1/8-inch thickrollbonded stainless £t;ee1"claddi'ncjj< who,sevbase rs>7 inches thick. The 9-7/16-inch annul us between thVoufe^Wdj^nij^r'-shdl-^îs filled;with lead. The top ofthe container is covered witn. a jfaiable closure head fabricated of stainlesssteel 15 inches thick which is b%£edVfo;th'e container and seals the containmentvessel. An oblong access plug in'thV cover allows for! individual spent fuelcell loading or unloading.

The containment vessel has;an inside dlametet of 55 inches. The central regioncontains a secondary heat exchanger;which is supported by the closure head.(This heat exchanger is not used during shipment.) An inner backup cylinder, 21inches in diameter, occupies the central region of the containment vessel. Theannul us between the backup cylinder and of the containment vessel shell providesa space 17 inches wide by 160 inches high for spent fuel. The spent fuel iscontained in the annul us by aluminum module holders designed for the particularspent fuel to be shipped.

The packaging has external penetrations to the containment vessel for a steamand water vent line, which is capped during shipment. Shipments are by rail.The packaging is cradled in a support which permits the packaging to be nearlyhorizontal during shipment. The maximum loaded shipping weight is 237,000pounds.

JE2£2R2

529

)^5

jj NRCFORM618A commons (continued) U.S. NUCLEAR REGULATORY COMMISSION

i (3-96>8 Page 2 - Certificate No. 9781 - Revision No. 6 - Docket No. 71-9781

* 5.(a) Packaging (continued)

8 (3) Drawings

a The packaging is constructed in accordance with the description and§ Drawing Nos. contained in the Bettis Atomic Power Laboratory Safety3 Analysis Reports (WAPD-0P(R)C-243, WAPD-OP(R)C-558, and WAPD-OP(R)C-6213 dated May 1973, October 1, 1976, and March 1977.

3 5.(b) Contents

S (1) Type and form of material

M

H

Irradiated fuel assembliesândeJ^lanket modules of the following type:

(i) PWR Core 2 sSee'd>l Fuel Assembly.'^V >

M

ai (i) PWR Core 2sS^d"l Fuel Assembly.i ( i i ) PWR Core l.Se'ed 2 Fuel Assembly. ^// *,s ( i i i ) PWR Cofce Z Blanket Fuel Assembly. - ^s ( iv) S5G Fuel" Module, rodded or unrodded. / / ,s (v) S5GV Center^Cell. ^ ^ z ^B All shipments sfialili|&e^made dry and shapj?y|,e> one hdtddown device per PWR£ module." Jlach PWR^fôr^2\.Seedxl^pr Seed^2îjfel assembly shall contain aa poison'rod or a co'Hfrol, fod r^C ' " / : f r^ -s jk ?..'

Ik (2) Maximum

^ (i) l i lfuelâsji^^^ assemblies

« Sîpment^¥l^jio^bê1nia4e = Rrci% toa^614 daysâfter last power5 opVSt ion^MB^'e 'h^î t f i lxar t .^xceed 12346 Btu/hr of decay

(ii) 12 fuelfMsemblies asvcleWibed 1iiT5(b}0"Jfi1) which shall notexceed 1,100 Btu/hr per fuel assemblf<^%'"decay heat or 13,200Btu/hr per'shipment. >w *

( i i i ) 12 blanket fuel assemblies lis^des'cribed in 5(b)(1)(iii) which shallnot exceed 21,300 Btu/hr of decay heat per shipment. Shipment shallnot be made prior to 1,123 days after last power operation of thefuel.

8 (iv) 8 fuel assemblies as described in 5(b)(l)(ii) and 4 specificB blanket fuel assemblies, Serial Numbers G2A-F01-26B, G2A-F01-02,8 G2A-F01-10, and G2A-W01-73, which shall not exceed 12,016 Btu/hr of

decay heat per shipment. Shipment shall not be made prior to 1,487days after last power operation of the fuel, with the four blanketfuel assemblies located adjacent to each other in a clockwise or

* counter-clockwise direction as specified by the serial numbersa previously stated.x~ (v) 4 fuel assemblies as described in 5(b)(l)(iv) or 3 fuel assemblies^ and one center cell as described in 5(b)(l)(v). Shipment shall not8 be made prior to 168 days after last power operation of the fuel rod

and shall not exceed 12,800 Btu/hr of decay heat per shipment.

530 J

NRC FORM 618A(3-96)






100

REFERENCES

Safety Analysis Report for M-160 Shipping Container: Core Independent AnalysesSRSD-106 dated October 18, 1968, as transmitted by Naval Reactors Letter G#2097 datedJune 3, 1969.

Supplements: Knolls Atomic Power Laboratory letter 0NP-74520-414 dated November 26,1969; Naval Reactors letter G#3742 fcjajied May .15,-197.3;, Bettis Atomic Power Laboratoryletters WAPD-OP(R)C-284 dated^Augiist '23, 1973, and^PD-OP(R)C-297 dated October 8,1973; Naval Reactor letter<G#5582 dated December 17, 1976, G#5671 dated April 15,1977, G#5702 dated May 23,N 1977, G#5792 dated September 22, 1977, G#5793 datedSeptember 29, 1977, G * ^ dated December 20, 1977; G#5897 dated January 11, 1978;G#6658 dated April 14, 198R and G#92-03424 dated March 20, 1992.

FOR THE U.S. NUCLEAR: REGULATORY COMMISSION

-v- - :>

;Wy-l'fam-D''.- Jrayee/, Director-Spent Fueliproject OfficeQffi.cerpf Nuclear ^ e h i a l Safety

Date *S

5 3 1*U&2&2SJ&7&7Qffi7Kffi]!iU3USU&7K7KW7K7K

az ac aEaiaraz acagazarazaKaiiai: a7acaraK.aK ao&azaK a?az wwaYai [NRC FORM 618(3-96)10CFR71



I. a. CERTIHCATE NUMBER





42. PREAMBLE




U.S. Department of EnergyDivision of Naval ReactorsWashington, D.C. 20585


S3G Core Basket Disposal ContainerSafety Analysis Report for Packagingdated June 1980, as supplemented

71—Q7Rfic. DOCKET NUMBER ' * 3 ' O O

4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of It) GFR Part 71, as applicable, and the conditions specified below.

5- (a) Packaging V " v; -.

(1) Model No.: ,cS3G Core Basket Disposal Container Assembly

(2) Description ""->>..... <->~<^ '•'"/

The package consi~|]|siof eithejr OLne irrkjdl^fed S3G, SIC or S7G core basketpackaged in an inn^%JIead-fi^ll;ed* cofit||.rf|p (S5W Core-Basket RemovalContainer (CBRC))|iyh^ch As placed inside^i outer container (S3G CoreBasket Disposal Coi ta|ners>!>tC'.B.DC :);',. jh^^dkage weighs^ approximately

The S3G CBDC -§S^^Kfeh;fci|i;steefo|ylin^fc^9 intfies in outsidediameter,",131 ^jfe's^long-i'-wijth:?aOlS-inch^Jiick top.rehd plate and a 5-inch thick\bottqni:;en^Tpl:a%"e..vB^ are "welded to the cylinderwith full :penetrati1c)n^elds^«fv " - -; ••>.?•'''

The S5W CBRCsi-.which will bedi^ptfsed of along;{with the outer S3G CBDC andinner core basket, is basically a cylindrieai^shaped container comprisedof lead shielding sandwiched between two, 304"stainless steel shells. The1-inch thick inner shell is, 60 inches-OiD. and 107.5 inches long. Theouter shell is made up of two, geometries, a 72.5-inch O.D., 0.5-inchthick cylindrical shell that measures 66 inches long and joins atruncated conical shell which has a 64-inch O.D. at the small end. Thetwo shells are joined by a full thickness penetration weld and a weldbackup strap on the inside shell surface. Full penetration welds arealso made on both ends of the shells to the top canning and shield ring.

The S5W CBRC will contain either an S3G, SIC or S7G core basket. Theirradiated S3G core basket is an Inconel 600 cylindrical shell. Three,3-inch thick 304 stainless steel plates are positioned in the core basketprior to removal to provide overhead radiation shielding. The lowerplate is 46.2 inches in diameter. The upper plates have the samediameter but contain six extensions that fit inside recessed cutoutswithin the core basket. The total core basket weight is approximately9,650 pounds.

532

>

NRC FORM 618A(3-96)




The SIC core basket is a 304 stainless steel cylindrical shell positionedinside a 304 stainless steel thermal shield. The overhead shieldingconsists of a set of 2-inch thick 304 stainless steel plates attached tothe SIC core basket to provide radiation shielding during handling. Thecore basket weight is approximately 8,523 pounds.

The S7G core basket is an Inconel 600 cylindrical shell. A 304 stainlesssteel laminated plate (8-inches thick) with lifting attachments isattached to the top of the S7G core basket to provide radiation shieldingduring handling. The core basket weight is approximately 8,873 pounds.

The package may alternatively.consist of S8G irradiated componentspositioned within an;-irra^tatedicom|Qfients, discharge rack (ICDR) which isplaced in an S3GVCBJ3C>" the ICDR is 'a st ielâck approximately 128 incheshigh and 80 ijichesîn diameter, and is designed^to f i t inside the S3GCBDC. The ICDR consists of a center cylindef/aissembly surrounded by 23storage tubes!;''a top plate and a cylinder suppojc^base. The centercylinder fs HY 80 steel, has a 36-inch outer dijimeter and a 4.5-inch wallthicknessând^^117 inches high. Thereârr-^9' stoipage tubes positionedinside thevcenteêy1inder. The totaly,wf|*3jhjt of thVirradiatedcomponents, the rCDRând the,?S3G CBDC/âpproximately 125,000 pounds.

(3) Drawings'

Drawing No.Drawing No. 152D7009

(b) Contents


(i)

(ii)

An irradiated core-basket either the S3G, SIC or S7G and S5W CBRC.The shipment may include surface contamination in the form ofactivated corrosion products and for the S3G core basketapproximately 8 gallons of residual water.

S8G irradiated components within an ICDR. The shipment may includesurface contamination in the form of activated corrosion products.

533

i:>

B NRCFORM618A CONDmONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONC (3-96)


(2) Quantity of material per package

(i) Item 5(b)(l)(i) above:

One irradiated core basket and S5W CBRC as described in 5(b)(l).Surface contamination not to exceed 20.6 curies for the S3G corebasket, 7.45 curies for the SIC core basket or 1.2 curies for theS7G core basket. The activation level of the irradiated S3G corebasket is not to exceed 131,000 curies; the irradiated SIC corebasket not to exceed 20,000 curies; and the activation level of the

g irradiated S7G core basket is not to exceed 140,000 curies.

S (ii) Item 5(b)(l)(ii) above:

Irradiated compon ntsV, ineljudfrjjg/1.41 instrument lines, 18 lowercontrol drive jjeefiahism assemblies;^ .filled sleeves, and 1instrumentation stalk. Surface contamination not to exceed 65.5curies<;NOÂctivation level of the irradiated components not toexceeti? 2,440 curies. !(j)

Shipment of an;3ttradi:|ted,S3G core basket must be ifafter reactor;:sftutdown^;i|\x S~$jktf'

6. Shipment of an;.tr(radi:atedvS3G core basket must be made fio/earlier than 75 days

* 7. Shipment of ah;irradiateJ|J:§LC. eore^b^ket ûSC^f, made noârlier than 60 daysc after reactot shutdown."0SMJf : i \\€?0$£ '-"J.

C 8. Shipment of ianîrrad^ted^fG^cjore^ basket; musit?jbe âde no .earlier than 180 days* after reactor.jfshutd'^nÂ^ '^^M^'W^'-'îitfM^ JM^ ^-~* 9. Shipment of S8|}iirrao^ê||pompc|nents ;'mu| >be ma'de;;no earlier than 100 days

18 after reactor s^XdovnS^^^^^-^.^}^^^^^^ (Cf<

10. In addition to th'eyxequireme^tsi^û't^rt'^/qf 10 CFR^Part 71:

(a) Each packaging Just meet the following Acceptance Tests and MaintenanceProgram: v . K^

S3G Core Basket <~f >-{ ^-^

Section 8.0 of application dated June 1980

S SIC Core BasketS

Section 8.0 of application dated August 1983

S7G Core Basket

Section 8.0 of application dated May 1987

S8G Irradiated Components

i Section 8.0 of application dated September 19919

534

rat at at at at aTatat w az at wwata ta t at acazaz aa w w a? at aEataggtacaz.sitMK.-Sit az at at ME at az ataiiag^tt azatac^ l»NRC FORM 6 1 8 A CONDITIONS (continued) U .S . NUCLEAR REGULATORY COMMISSION

(3-96)


(b) The package shall be prepared for shipment and operated in accordancewith the following operating procedures:

S3G Core Basket

Section 7.0 of application dated June 1980

SIC Core Basket

Section 7.0 of application dated August 1983

S7G Core Basket

g Section 7.0 of application dated May 1987n '•- i •

a S8G Irradiated Components

a Section 7.0 of application dated September 1991

a 11. Expiration date: August 31, 2001.5 ' "H£

REFERENCES

S3G Core Basket Disposal Contaifefl Safety ;Analysis?Rep :ort for Packaging,WAPD-RE0(C)-122, dated Junel?d98Q|;asi, ;reyised (Rev t#dn 2 , / d a t e d May 5, 1986).

Safety Analysis Report foropackagihg^an SIC .Cdfe^Basketr-Thermal Shield Assembly inthe S3G Core Basket p l s p o s ^ C o t i t . a i n e ^ i S l C C B - ^ S , dated August 1983.

S7G Core Basket in the S3G Core BaskeVPisppVal, Container Safety Analysis Report forPackaging, dated May 1987., %'k\%>y ;J

S8G Irradiated Components' iii the S3G Core Basket Disposal-Xontainer Safety AnalysisReport for Packaging, Revision 2,. dated September 1991.

DOE memorandums G#7627 dated November 16,>1983;-G#C86-3736 dated May 24, 1986;G#C86-3750 dated July 15, 1986; G#87-5663 dated July 7, 1987; G#91-10937 datedJuly 31, 1991; G#C91-11007 dated September 18, 1991; G#96-03335 datedFebruary 16, 1996.


William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material

Safety and Safeguardso I - \ ~ i

Date:

535

^

NRC FORM 618(8-86)10 CFR 71

CERT.F.CATE OF COMPLIANCEFOR RADIOACTIVE MATERIALS PACKAGES

C ° " M ' S S ' ° N






2. PREAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theapplicablesafetystandardsset forth InTitielO, Code





A1W-3 Power Unit Shipping ContainerSafety Analysis Report for Packagingdated August 1980, as supplemented.

#^9787'c. DOCKET NUMBER

CONDITIONS <\\J ^JThis certificate is conditional uponfulfillingxthoVequirements of 10 CFR Part 71, as applicable, and the;copajtions specified below.

5.

(a) Packaging

(1) MorfefNo.:

(2) Description

itainer (PUSC)

package isupport tekijce}attciched- o fehesecured t|p||§£shipftjng ^tMiLuM^g)for#2.25- |$c»ami

cyllffttlrical steefjgweldment. A moduleandotn energy absorber are

<Jfie module support device is"with tifcf 3-inch diameter

clampând cradle assembly withMod#]he support cylinders (with

devices, prevent fuel module orcTJ

lock^ngf nuts) andi\cocontroôd motion. ^jtqpWun'cTajf'e prot§c>fon cover, with 4-inchthick steeTside walls afidya 5-inch th i cOtee l top plate, f i t s downover the egjfcrate assembly and attaches^to the bottom plate of the modelsupport deviceÎth forty 2-inch diameter bolts. The top energyabsorber, w i t h in 80%ncHLpu£ep ammeter, a 54-inch inner diameter, anda height of 25 inched ishi/eldf?d to the top puncture protection cover.

At the bottom end of the A1W-3 PUSC, a 4-inch thick steel punctureprotection plate with a diameter of 50.5 inches is attached to thebottom of the power unit thermal shield by eight sets of U-bolts. Abottom energy absorber, with an 89.25-inch outer diameter, a 52.5-inchinner diameter, and a height of 36 inches cover the bottom punctureprotection plate and is attached to the thermal shield of the power unitwith twelve 0.875-inch diameter bolts. The support barrel, which ispart of the power unit assembly, and a stainless steel plug/bandassembly, which extends around the outside of the support barrel,provide puncture protection for the sides of the power unit.

536

ftgft«ft<W^

NRC FORM 618A(6-83)



(a)(2) Description (continued)

For shipment, the loaded A1W-3 PUSC is secured horizontally in ashipping pedestal. The shipping pedestal consists of a base on whichtwo support beams are mounted horizontally with rubber shock mounts. Thebase is bolted to the deck of a 300-ton rail car and to four stop blockswhich are welded to the railcar deck. The PUSC is secured to theshipping pedestal using the upper clamp and cradle assembly and thecenter and lower yoke/saddle assemblies. The yokes span across theupper side of the PUSC and are attached to the support beams while thesaddles suspend from the yokes and support the weight of the loadedPUSC. A 0.25-inch Ihiejc rUl&S«r&over is used to enclose the entireA1W-3 PUSC fo r s*rtpf

The loadelong, ha397,00a

(3) Drawi

J-3 PUSC (excluding the shipfliimaximum diameter of 134 inches,

hds.

(b)

The/packageskerches

Contents

One unirrâte

(c) Transport

Minimum traitsfbrt ._label for nucfâr critica

pedestal) is 349 inchesweighs approximately

with thCdrawings, figures andments (seSSReferences, below).

Control rods and contrcQ^rad holddown devices must be^&stalled in the power unit asdescribed in the application.

In addition to the requirementsô 0 CFR Part 71:

(a) The package must be prepared for shipment and operated in accordance with theOperating Procedures in Chapter 7 of the application.

(b) The packaging must meet the Acceptance Tests and Maintenance Program inChapter 8 of the application.

Expiration date: April 30, 2000

537

8&tSy&AM!UIKUayn!i&liJ91U91Jg^^

A ^

NRCFORM618A(6^3)



REFERENCES

A1W-3 Power Unit Shipping Container Safety Analysis Report for Packaging,WAPD-RE0(c)-118, dated August 1980.

Supplements: A1W-3 Power Unit Shipping Container Modified Top Energy Absorber RevisedSafety Analysis Report for Packaging, Attachment 1 to WAPD-RE0(c)-118, dated February1985; and Naval Reactors Memorandum G#94-03572 dated November 4, 1994.


Date:

ii

William D. Travers, uiinec^srSpent Fuel Project Office /Office of Nuclear Material

and Safeguards

Et

i

538

isu^jmjeAOijaij»ijfisua!ueiijmjeius^jajm2aiiB

jEaz az a? az az waz atai: az azw w a7a7az

swazaz. wwwa7.aga7 wazaraz a t 1NRC FORM 618

(3-96)10CFR71








3

I. PREAMBLE


b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportationpr otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.




Deactivated S5W Reactor Compartment SafetyAnalysis Report for packaging dated July 1981,as supplemented.


4 . C O N D I T I O N S •"' • " ;

This certificate is conditional upon fulfilling the requirements of lO.CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model Nqs,.: S2C>Reactor Compartment, S3W Reactor Compartment, S4W Reactor.'•"•-'' Coifipantmejit, and S5W Reactor:;Cpitipartment

(2) Description i^.}*: '; "'"':':'. ''' v'i£\ r' •

The package consisit:"pfU deactivated;aTno|defueled S2C, S3W, S4W, or S5WReactor Compart,rnent%ih|ch has been sep'arjtted from the-remainder of thesubmarine hulXîahd "p^pâred-forshipmenfi by/.sealingall openings andattaching hand:Tipg/ffxtîeyi; ;ft6r'e;%h: package^mode.T,-the reactorcompartment itsejf'&s between:two ôptainnient-bulkheads which are addedto the package^befofe-rslj-pping'. TJt|{ship's'hull and the containmentbul kheads. def i n^the«packagje%pntai hmient^bbundaries,; There i s anoverhang of"the hull stru%ufebônd the bulkheads at both ends of thepackage, the strength of "all!package"boundary, closures is equivalent tothe strength ;oxf;the ship's bulkheads. The^deactivated reactor plantremains in pi ate/ within the reactor compartment during shipment. Theplant is defueled and drained.except for small inaccessible pockets ofliquid, primarily water.?, otentialfly radioactively contaminatedcomponents and piping from other locations in the ship may be placedwithin the package and secured.

The S2C package is approximately 42 feet long and roughly cylindricalwith a maximum diameter of approximately 23 feet. In addition, the S2Cpackage has a concrete-filled tank exterior to the hull at the top of thepackage. New containment bulkheads made of HS steel are added at eachend of the package. The hull is constructed of HY-80 steel. The maximumweight of the S2C package is 1,344,000 pounds.

The S3W Reactor Compartment package is between 46 and 48 feet long andapproximately cylindrical with a maximum diameter of approximately 25feet. The S3W package has a concrete-filled tank exterior to the hull atthe top of the package. The containment bulkhead may include existingship structure which has been sealed to form a watertight bulkhead. Thehull is constructed of HT steel and the containment bulkheads are HT orHS steel. The maximum weight of the S3W package is 1,588,000 pounds.

5

i

i

i

»

i

539,

5

s



5.(a) (2) Description (Cont'd)

The S4W Reactor Compartment package is approximately 45-1/2 feet long andapproximately cylindrical with a maximum diameter of approximately 25feet. In addition, the S4W package has a concrete-filled tank exteriorto the hull at the top of the package. The containment bulkhead mayinclude existing ship structure which has been sealed to form awatertight bulkhead. The hull is constructed of HT. steel and thecontainment bulkheads are HT or HS steel. The maximum weight of the S4Wpackage is 1,801,000 pounds.

The S5W Reactor Compartment package is between 35 and 45 feet long andapproximately cylindrical with a maximum diameter of approximately 33feet. The forward containment bulkhead may include existing shipstructure which has been sealed to form a watertight bulkhead. The hullis constructed of HY-80 steel and the containment bulkheads are HT, HS orHY-80 steel. The maximum weight of the S5W package is 2,160,000 poundsfor the 598 and 585 classes and is 2,262,400 pounds for all otherclasses.

B£*BB£

(3) DrawingsB33BB

(b) Contents

The package is constructed in accordance with the drawings, figures, andsketches included in the application, as supplemented (see References,below).

Activated structural.components associated with" the S2C, S3W, S4w> or S5Wreactor vessel complex, plant piping, ion exchanger resin (S5W package only),and other miscellaneous components contaminated with radioactive corrosionproducts (crud). . : -

Ion exchanger resins with up to 3.1 curies of Co-60 may be shipped in the S5Wpackage.

6. Residual liquids contained within plant systems must be removed prior totransport to the maximum extent practical, in accordance with establishedprocedures, methods, and controls, as described in submittal datedApril 5, 1996, which result in not more than 660 gallons of residual liquidsper package.

7. The aft containment bulkheads and stiffeners, horizontal divider plate, and anystructure between the pressure hull and the outer non-pressure hull must berecessed at least 7.0 inches from the aft end of the S5W package, or at least15.0 inches from the aft end of the S2C, S3W and S4W packages. The forwardcontainment bulkhead and stiffeners, existing tank stiffeners, deck structure,and horizontal girder must be recessed at least-15.0 inches from the forwardend of the S2C, S3W, S4W, and S5W packages.

8. The Lowest Service Temperature (LST) must be determined for each package.The package shall not be shipped unless its LST is less than or equal to thenormal daily minimum temperature expected during the shipment of the package asdetermined on the basis of weather forecasts.

540




9. For S5W ships with a maximum of 3.1 curies of Co-60 on the ion exchanger resinat the time of shipment, the shipment shall not occur before 365 days after thefinal reactor shutdown. For S5W ships with fewer curies of Co-60 on the ionexchanger resin at the time of shipment, the minimum waiting period may varybetween 185 and 365 days. For S3W and S4W ships, the shipment shall not occurbefore 6 years and 10 months after the final reactor shutdown. For the S2Cship, the shipment shall not occur before 9 years and 3.25 months after thefinal reactor shutdown.

10. Additional shielding may be provided on the exterior of the package by steelplates securely welded to the package surface so as to remain in place underthe hypothetical accident conditions in 10 CFR Part 71.


(a) Each package must be prepared for shipment and operated in accordancewith the procedures described in Chapter 7.0, "Operating Procedures", ofthe application.

(b) Each package must be tested and maintained in accordance with theprocedures described in Chapter 8.0, '.'Acceptance Tests and MaintenanceProgram", of the application.

12. Expiration date: December 31, 1997. / ;-

REFERENCES ;

Deactivated S5W Reactor Compartment Safety Analysis Report for Packaging,WAPD-RE0(C)-250, dated July 1981. •

Supplements: Naval Reactors Memorandum'Z#C90-144J6 dated March 29, 1990, andsupplement dated July (6,i!i990; Naval Reactors MemorandumZ#C90-14456 dated August 30, 1990; Naval Reactors MemorandumZ#C92-14438 dated August 3, 1992; Naval Reactors MemorandumZ#C93-00069 dated October 14, 1993; Naval Reactors MemorandumZ#C95-00113 dated March 16, 1995; and Naval Reactors "Memorandum Z#96-14430 dated April 5, 1996; and Naval ReactorsMemorandum Z#96-14434 dated April 10, 1996.


Date:


and Safeguards

5 4 1rJS£2&.2&.I&?¥>?W?&MMJSU!&ffiM{ffi23UgJ3U&J!U3%J&W

^


FOR RADIOACTIVE MATERIALS PACKAGESb. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER


_ PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code





Safety Analysis Report for Packaging for theA1W-3 Core Barrel and Thermal Shield DisposalContainer dated April 1982, as supplemented.

"c. DOCKET NUMBER (i 71-9789

4. CONDITIONS j . ' ^ " " - ' , . : ,,This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a) Packaging ^ " < ^ > ^ ^ - . ^ <"-^

(1) Moctei/No.: li||^3sG§re Barrel and Jhejenfaf Shield'["Disposal Container

(2) Description

Fffa|

•Y" ""v

weldea, toconsj

-3 ft|preffa||âfd^ffiBka:f/S|fi|d Disposaliiontainer(A'l'Wr3 CB^^DC^â^.-up^gh^pi$se^cy/li.nder consisting of a 6-inchthick cyliinder..bda:v>vJa!ii2:4irichrMiel( bo||o1n''plate, (at the center l ine),

the!ke0er l ine) . Both end plates areloaded shipment. The container is

an overall height of 185 inchescons t ruc ted f te i%3l i t )<1^ i iaa i j fan overall height of 185 inches(froifc-bbttomvof crûsh^WrWto rt6pl>of liftrinf'lugs). Both the supportflangeând the side crusMngîng^fiich e repd from the container

l d d f 'cylinder (body have an outs-fde diameter of f l22' inches. Additionalshielding -fs/provided around the container^cylinder by an upper andlower annular shield p la te . 7 ^ "

y ;>The A1W-3 CB/TS DC fsûsed*for shipment and disposal of i rradiated andcontaminated A1W-3 components. Maximum weight of the package isapproximately 243,000 pounds.

(3) Drawings

The container general assembly is shown in Westinghouse drawings1573E43, 1573E40, and 1573E49. The packaging is constructed inaccordance with the description and drawings contained in Bett is AtomicPower Laboratory Safety Analysis Report dated A p r i l , 1982.

5 4 2

^ *

NRC FORM 618A(6-83)



(b) Contents


Irradiated Core Barrel, Thermal Shield Assembly (inner and outer thermalshields), thermal shielded shock ring (for shipboard shipments), andirradiated Thermal Shield Lower Plate Plug with up to 12 gallons ofwater and surface contamination in the form of activated corrosionproducts.


Section

6. Shipments shall not^Je^made prior to 180 days after finstpreactor shutdown forshipboard component^ or 2-1/2 years after final reactor shutdown for prototypecomponents. p~ ""— -^^ * rt

The maximum quan,tityvbf|radioXc|i-yf material contents (crud andactivation) shal^not exceed those(iquanti,ties specified in Secti1.2.3.1 of (gie*5afety Analysis R e p o r t ? ^ ^

7. In addition to

;amer top c l ^ r e > (Itaccordan£e\with West-fjnc

SFR Part 7=terequirejjislilsôf Subp.art Gi>T;^

(a) The container top c l « r e > fftop .ptate-toVcy^êr) weldâ l l be performed in20310^,

Operati ng^ProcedMfef^v

8.

(b)

(c) The packaging, mus'Chapter 8 o.fj the

Expiration date: May^l, 2000

E ? ! i P ? j M ^ e d S acco^dance wi

fid Maintenance Program in

REFERENCES

Safety Analysis for the A1W-3 Core •BarrglVandSTheTmal ^Shield Disposal Container,WAPD-REO(c)-302, dated April, 1982. ^ ^

Supplements: Naval Reactors memorandums G#7486 dated May 12, 1983, G#C89-2829 datedApril 19, 1989, and G#94-03572 dated November 4, 1994.


Date: DEC 0 5 1994



543

Timî'ws7^^



FOR RADIOACTIVE MATERIALS PACKAGES1.H.CERT1FICATE NUI b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER






3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJDESIGN OR APPLICATION 'a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


Safety Analysis Report for Packaging for theA1W-3 Holddown/Support Barrel and ShroudDisposal Container dated November 30, 1982,>s supplemented.

c. DOCKET NUMBER 71-97904. CONDITIONS ;x V j ? , ',-


(a) Packaging

(1) ModelfNo.: ^lty^Holddown/Support Barrel and Shroud DisposalContainer (Al»^?HP>SB & SDC) >' -SO>-

(2) Description

ThOlWS^SB^SD^ is a c losed^fo steel cylindrical containercoaystingJplân-84^ (at i ts center!ine), an8 . 0 0 J n c h ^ ^ U o j f % # ^ ; . ( ^ t i i i ^ ^ e n t ^ - i j 6 ) and a cylinder of fourindTj/all t^%khess^Paatlare|provide^6h'the inside wall of thecylinder an'd|^m{j"et'artside.;s|}rê .of/th"e bottom plate to aid inpositioning the cb^tai^jS^cp^tenTsÊour thin-walled rectangularsupport ,posts whicff are 'êlcfe^toitii.e: bottompTate pads maintain theholddoWn^barrel assembTytyat><aV height of approximately 33 inches abovethe bottom,pirate. The outside diameter.of the cylinder is 105 inches,the top cover diameter is 112.50 inches^ and the diameter of the bottomplate is 121 inches., .Additional shielding is provided at the lowerportion of the cylinder byTa 28Yinehi high by 3.5 inch thick annularshield plate. The overall height of the container, including thel i f t i ng lugs, mounted on i ts rai l car pad is 137.12 inches above therai l car deck. Total weight of the package is 160,000 pounds.

(3) Drawings

The container general assembly is shown on Westinghouse drawing 1526E20.The packaging is constructed in accordance with the description anddrawings contained in Bettis Atomic Power Laboratory Safety AnalysisReport dated November 30, 1982.

544

'fBi'W)ft8ftftftS^V!fiW^Sl^

NRC FORM G18A(6-83)


2 - Certificate No. 9790 - Revision No. 1 - Docket No. 71-9790

(b) Contents


Irradiated holddown barrel, support barrel and shrouds.


The maximum quantity of radioactive material contents (crud andactivation) shall not exceed the quantities specified in Tables 1.2.3-1,and 1.2.3-2, in the Safety Analysis Report.

6. Shipment shall not be made P5Sojj^^J8(nllaSsQf*e)r final reactor shutdown forshipboard components, or 2rl)^,years after finaVr/actor shutdown for prototypecomponents. O v X

7. In addition to the requirements of Subpart G of 1.0 CFR P © 71:

V& <shall be performed in(a) The container^to^e-losure (top plate-to-cylijaccordance,w£th We tMijhpuse Drawing 2015T"*

(b) Each package must be^^pared foJ^fypmenM|i operated^ accordance with thep r o c e d u r e k d e s c r i b e d S ^ a p t e r / T r o i " ^ ? / ^ ^ Procedures", of theapplicatfoiL T^m.\ f U. ,.\ \ m^>

(c) Each package

Program",

8. Expiration date: ^ay 31,

^Jbxdance^with the;s Bd Maintenance

RE-MRENGE

Safety Analysis Report for the<^pW-3 Holddown/Support Barrev'and Shroud DisposalContainer, WAPD-REO(c)-448, dated Nov|mber 30. 1982.2.

Supplements: Naval Reactors Memorandum fl744Cvdated March 31, 1983; G#C89-2829 datedApril 19, 1989; and G#94-03572 dated November 4, 1994.


DEC 0 5 1994.



Date:

545y!M^JV>U^^



FOR RADIOACTIVE MATERIALS PACKAGES^.CERTIFICATE NUMBER




4

2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicablesafety standards set forth In Title 10, Code





PWR-2 Lower Core Barrel Safety Analysis Reportfor Packaging dated January 1982,as,supplemented

' c . DOCKET NUMBER

4. CONDITIONS ; N 'K^ ' " ^<^f ^This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

(a)

%

Packaging

(1) Modeled.:

(2) Desqr-jption

The [packagei rrad fated \|assembly,an outer shi

ana Disposal Container

o-2 lower epjrp barrel (LCB) andan/S8G prgjiotype core basket

ct(ftt^ner,^wtiich is placed insidefjmmghs approximately 400,000

,fc£The outer'^conta'iner a s | [ ^#^h^ th i . c | t ^ t ee l cylinder, 127 inches inoutside Ufameter, 212 irf<|jj$sUMg*, W j i two 6^nch thick end plates. Thebottom encT<pT.a£e is welded^tcpfche cylinder,^bh a full penetration weldand the top end plate is bolted with 107£S;2k fnch diameter fasteners.

The package is eqdippe^-wi^lii-^twioSZ.^inch thick by 10-inch longcircumferential impact limiter ritigs on the side, two concentric impactlimiter rings on the ends, and aluminum honeycomb crush blocks in the topand bottom spaces between the inner and outer containers.

The container is supported horizontally on the railroad car by eightgussets attached to two horizontal plates. Each plate is bolted to thetop flange of an I-beam. The bottom flange of the I-beam is bolted to a300-ton railroad car.

5 4 6

^



5. (a) (2) Description (continued)

The inner disposal container is one of the following designs:

(i) For the PWR-2 LCB and the irradiated LWBR components, the innercontainer is a cylinder with two steel shells containing lead inbetween. The inner container is 117 inches O.D. and 181 incheslong. The inner steel shell is 1.0-inch thick and the outersteel is 0.5-inch thick. There are 4.25 inches of lead shieldingbetween the shells. Thejnner container is supported radially inthe outer conttai;rj|r By]; Cwofjjjings, one at each end, which have aradial CA1 eufeaneôf b.'ZWîhcYi^./f The inner container is centeredaxialTyîn/^he outer container byvitfie luminum honeycomb crushblooksvl The bottom end of the inneir^container is a 4.5-inchthjeklplate. The top end of the innerfcbntainer is an 8-inchthibjk plate attached to the cylinder wrfHf40 one-inch diameterfastejiisrs. A spiral-wound, graphUe-îlled^gasket is located^ t w e ^ t h e b o l t e d cover and th.e cy,1 1ider.*>-~The gasket is

xhlfiaVe an applied torque of 700âm primari5ly>from HY-80 steel,A a ^ t h top cover, which are made

s -"ft-lb.^"except f^ f r o m AST

cover and| ^ j 40 bolts, wtrej|i,nn§r cpr^s^ner/:r>tjffe lead sBijfdiMM (

over

(ii) r"3For ^|lS8^lo|o|:yi.plencojpe|1)f|^ asîpbly,^|e inner container£0i ^îde'^w1nEjh|i^ri]|Qbib^))pt<ox^/^1y 117:?i nches, and an

i.gtHi •6$]17;4V4 dhches, cpptr-ucted-of 304 stainless^HîwactlB^55/gHiches tfcitik, with a 4-inch

thick5cdver plate. The covercfed % t h / / | | n ^ t e r $m a sea l%ld. An 8-inch wide,

3H%Ph thick guiaetî|ig.Usypr6vfiied 25. i)»ches above the containerbottoiiuplate to prowde^ci close fi t between the inner containerand trfefirradiated cargo. A 12-incfi^Wide, 1-inch thick ring isweldecTtt) theôutside of the inner container near the top of the

t i t W t ^ l j h l ^ f i i h h t

T»4ck ^(M^W',attacfed

^ pcontainer toWsta^lj%h\a x lose^vfit with the outer container. Theinner container is4centered*axially in the outer container by thealuminum honeycomb crush blocks.

(3) Drawings

The packaging is constructed in accordance with Westinghouse Drawing Nos.1575E12 and 1574E96, and General Electric Drawing Nos. 977E709 and977E467.

547



<b) Contents


(i) An irradiated PWR-2 lower core barrel and the following LWBRirradiated contents: (a) six blanket support tubes, (b) 11 seedsupport shaft assemblies, (c) seven sectioned flux thimbles, and (d)five sectioned BIF supply tubes. In addition, the shipment mayinclude approximately 33 gallons of residual water and surfacecontamination in thecCorm^fffaotwated corrosion products.

(ii) An irradiat,edy;8'(r prototype core basêJttssembly, including corebasket-thermal shield and six survei11 ancestralns. In addition,shipmentây include approximately 8 gallonsfpf residual water andsurfac&contamination in the form of activated-corrosion products.

(2) Quantity iijftaterial in package

(i) __; ^ , t t } _ ^ . . , v. ^. ^

Oneffirradiate^TBêrf core barrel Vsffm^y and irradiated LWBR'"*' " * not to

(ii)

, —^.o^t^'p^ôê J>||êt assembly, as described in-v-#v-^^/- Surface 'cJjntamtn, tHon?n.6t tOxe^ceed 148 curies. Theirradiafeji|components nott/to^Jexceed 29,900' cjiiries.

The package will be operated iji,;accordance with the procedures described in Chapter7 of the application and NavaPêactors^letter- G^84-452 dated March 28, 1984, or inaccordance with Naval Reactors letter G#C.92HO3331 dated January 29, 1992. Thepackage will be tested and maintained in accordance with the procedures in Chapter8 of the application.


548»MWJWJl>&JWA}J&\ia!i/&A!&M$Ji&iJ&JS!S^^

^



REFERENCES

PWR-2 Lower Core Barrel Safety Analysis Report for Packaging, WAPD-LP(CES)CS-670 datedJanuary 1982.

Supplements: Naval Reactors letters G#7241 dated December 2, 1982, G#84-452 datedMarch 28, 1984, G#C92-03331 dated January 29, 1992, G#92-03546 dated June 5, 1992, andG#92-03589 dated July 2, 1992.

%JV

^ \ C | F Q P J T £ E | U ^ S > ^UCLEAR REGULATORY COMMISSION

AUG 0 7 199TfDate: r

Charles E. MacDonaidfpiiefTransportation Brancn^,Division of Safeg.UciFdsv'and

TransportatCo,i}*xNMSS'" -

%=.f=* Wi B I N mfW¥ *;/

%

5 4 9

^^^

NRCF0RMS18(8-86)10 CFR 71







REAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets the applicable safety standards set forth in Title 10, Code



a. ISSUED TO (Name end Address)



I

,.*A

Department of Energy application datedApril 22, 1991.

. DOCKET NUMBER ^-j' /f 71 "9792

4. CONDITIONS < , \^./> <"%s> ^This certificate is conditional upon fulfilling;the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.cond

o.(a) Packaging v-\- V - . ^-f > * ,

(1) Model No.T Model l^Gj'C.ore Bas.k^t-Thefma;i|Sh:ield Shipping and Storage">•••

(2) Description ,- '~*\\'\ v1 v - ' '"• iMZ-% x'-~~"

The Mod'eil 1 DlG^pre •Ba|ka^Therma|l-î^^'> rc^4TS) Shipping and StorageContainer is a^1^l)fe,c'#cul'ar'|cirtin^^p^^^ inches indiameterând ei;|"lieg4b9 i;n:che;s[jl|c|nôx 216/Jpfnes long> with access forloading R)^pvidedib^î?êjbâ!bTej^ The container, consistingof the c y W n d r i c a v s ^ ^ a p ^ ^ end, H'a|s a three layerconstructfofi^with a steel /i/pheifVê%el^f|proximatCi;y eight to nine inchesthick covefe^.-with approxima^riyjo^ne ihcfies ofJrej'nforced concrete whichis encased byJa^/8-inch thick outer shell. -|hej>CB-TS is secured inplace inside tfreVcontajner with an 8-inch thick steel preload ring whichis bolted to the innlri.ves.sel with;72 high strength bolts.

Closure of the containment vels'el i ? provided by the 6-inch thick steelclosure head which is fastened to the inner vessel with 72 high strengthbolts. A steel closure ring is welded over the bolts and providescontainment. A carbon steel inner impact limiter is welded to the topend of the closure ring. A wood outer impact limiter is bolted to thetop plate of the container outer shell.

The shipping container is transported with i ts axis horizontal and issupported by a shipping skid. The loaded container weighs up to 185tons.

(3) Drawings

Packagings for which fabrication was begun before March, 1991 areconstructed in accordance with the General Electric Company Drawingscontained in Appendix 2.10.4 of the application, and packagings for whichfabrication was begun after March, 1991 are constructed in accordancewith the KAPL Drawings for the redesign configuration in Appendix 2.10.4of the application.

550

I

I

I

j I

I

, I

I

eciit£t

, itiiit

i

NRC FORM 618A U.S. NUCLEAR REGULATORY COMMISSIONCONDITIONS (continued)


5. (b) Contents

One irradiated DIG core basket-thermal shield assembly, and not morethan one core's worth of irradiated DIG support assemblies, DIG lowercontrol rod drive mechanisms, and DIG upper support assemblies; surfacecontamination in the form of activated corrosion products; and not morethan 3.5 gallons of residual water.

6. (a) Preloading of the preload plate and the closure head and sealing thecontainer must be done with a temperature at or above +40 °F.

(b) Shipment of containers S/N 0000001 through 0000007 shall be made onlywhen the average daily tempgfetiiji^pSjflxpficted to be above +40 °F.Shipment of containers£SpM$0O008 Wrb&gflJ)Q[Q019 and S/N N00020 throughN00031 shall be njadeyurTy when the average S^fr temperature is expectedto be above +10<Jl^ subject to the following exception: shipment of anycontainer w i t h ^ e closure Head identified as 042*T 171D6617 P5, SERN00031 (Forg|S^ S/N BG-7140) shall be made only wrfe^he average dailytemperature v§> expected to be above +30 *F.

(c) Shipment M l bereactor. -

t

i

tiIti

i

The package sh^l be prethe OperatingJJTocedupackaging shafTbe tTests and Mairfj nanc

8. Expiration Date|f\Sepfcej

Department of Energy, Div^fton of Naval

after shutdown of the

>rdance witheachAcceptance

dated April 22, 1991.

Supplements dated: Naval Reattor&Aetters G#92-036G#C95-10762, A d ^ d l '

dated August 27, 1992; and

FOR THE U . S . NUCLEAR REGULATORY COMMISSION

Date:


and Safeguards

5 5 1« ^ & ^ ^




1. a.'CERTIFICATE NUMBER

9793

b. REVISION NUMBER c. PACKAGE IDENTIFICATION NUMBER

USA/9793/B(U)F


12. PREAMBLE





"Core Independent M-140 Safety Analysis Report forPackaging" and "S3G-3 Recoverable Irradiated Fuelin the M-140 Safety Analysis Report for Packaging"transmitted February 27, 1991, as supplemented.


4. CONDITIONS - - , % ?f> fj}i~C*..~^

This certificate is conditional upon fulfilling the requirements;pf 1CJ,'(2FR £art 71, & applicable, and the conditions specified below.

(a) Packaging

(1) Model No.:

(2) Description v

A stainless steel eas >,fojr trajpsôrt|ngêc;pverable firjadiated fuelmodules^"The cask^:^r i ighyeir |u lar<^$i |der and ^transported in theuprightSp'osition. Spiiie?package has approximate dimensions and weights as

1 >.CavityCay^y

BodyKsteel .Package overallPackaftejqverall „PackagiiVgêight, includTn

stancjaYd internalsMaximum packageîgjht,

including\con;te "i<~~*

70 inches46 Cliches98înches^nches; inchesinches

315,000 pounds

375,000 pounds

The cask body is made from 304 stainless steel forgings. The cask wallsare 14 inches thick and the bottom plate is 12 inches thick. The caskbody flange provides a seating surface for the closure head and itsprotective dome. The flange contains 36 wedge assemblies located radiallyaround the inside diameter. Retention of the closure head is achieved byengaging the wedges in a tapered groove in the circumferential edge of theclosure head. The cask body has 180 external cooling fins welded to theexterior wall. A support ring is welded to the external cooling fins at apoint above the center of gravity. The support ring seats on and isbolted to the rail car mounting ring during transport. The cask bottom isequipped with an energy absorber which is composed of five concentricstainless steel rings varying in thickness and height.

552;

NRCFORM618A(3-96)

Page 2 - Certificate No. 9793



«

l»


The closure head is made from forged 304 stainless steel and isapproximately 13 inches thick and 81.7 inches in diameter. The closurehead is equipped with an access port, which is approximately 24 inches indiameter, and is offset from the center of the closure head. The accessport plug is a stepped design with a maximum diameter of approximately 31inches and is attached to the closure head by 24 bolts. The closure headand access port are sealed with double ethylene propylene 0-ring seals.Seal test ports are provided for the closure head and access port seals.A stainless steel protective dome is positioned over the closure head andis secured to the cask body flange by 12, 1.38-inch diameter, 38.5-inchlong studs installed in a vertical direction and 6, 2.5-inch diameter, 9-inch long shear bolts installed in the radial direction.

The containmentvS^stemis composed of theffcask body, the closure head, andthe closure head..access port plug. There are five penetrations in thecontainment system: a drain port and vent portjin the closure head, athermocouple penetration, a water inlet penetration, and a water outletpenetration in-the cask body. Each penetratjor^ is>sealed with a plug anda double ethylene propylene 0-ring seal ampi's'equipped with a leak testport. •>".; •'"»*>.**. ..-*'*&?*

The fuel modules a>e .positioned in an ,fo0rnals assembly. The internalsassembly is composed;of stacked} internalSpacer plates which have openingsfor the fuel m^duleW^The^ ihêrnal^ as'sjlbly has atop plate or top platesubassembly whic^ isr>|)r |1badedr by^ springs against a retaining ring fittedin a groove in tfie cawâyityfWaî-^v^H'e {iif|ernals ras.sembly may be astandard, internals' assembly on,an S3G-3 intferjials assembly.

(3) Drawingst .' :'

The packagfngVis constructe1df^ndv,?issembl.ed in Accordance with theWestinghouse Electric Corporation Drawings inÂppendix 1.3.2 of theapplication. ; -

(b) Contents


Recoverable irradiated fuel modules, limited to the following types,including associated activated corrosion products:

(i) S3G-3 recoverable irradiated fuel modules.

(ii) S8G recoverable irradiated fuel modules,

(iii) DIG Core 2 recoverable irradiated fuel modules,

(iv) D2W recoverable irradiated fuel modules.

553T£JSU&7K7&7^7¥J¥J¥J3iJ3SJ&^^




* Total package weight, including fuel modules and internals assembly, not


Total package weight, includirto exceed 375,000 pounds; and

(i) For contents described in 5(b)(1)(i):

S3G-3 recoverable irradiated fuel modules, not to exceed 62,300Btu/hr decay heat per package.

(ii) For contents described in 5(b)(l)(ii):

S8G recoverable irradiated I'fMhmpdules, not to exceed 51,609 Btu/hrdecay heat per^fpicka'ge (prototypeModules), or 45,713 Btu/hr decayheat per package" (shipboard modufe'si.,x)

(iii) For contents described in 5(b)(l)(iii):<;/>^>

DIG,Cbre-2.recoverable irradiated fueTjnodulSs, not to exceed 37,750Btu/hr decjayviheat per package.

(iv) For contentsjêscflbed^^X5^)^)!^!-

D2W recoyera:^firradi4tf4,|fuel5 Ap.jCufes, not tbêxceed 63,000 Btu/hr

ZBtu^hrsidisâltâfe/p^^'package for shipboard Type5 .core ^ t W f u i e ^ : ! ij;|l|j;i^ Wk

(c) Transport Index yfor Cr^ti!ca:KityCorftrolv ^^^^ r ^-/2

Minimum transport<Andex to be sho^Wljol)^ *"*'"$ ^^>label for nuclear crit icali ty control^ ^v^lOO

6. For S3G-3 recoverable irradiated fue^ shipments:

(a) Only a full load is authorized;v A minimum of twelve fuel modules musthave either control rods or poison shipping rods. All rodded and unroddedmodules must be positioned as specified on page 6-11 (Rev. 1) of "S3G-3Recoverable Irradiated Fuel in the M-140 Safety Analysis Report forPackaging."

(b) Minimum fuel cooling time is 130 days after shutdown.

(c) Core age must be at least 4,000 logging corrected full power hours.

jj. (d) Control rod hold-down dev ices must be i n s t a l l e d on c e l l s which have* control rods.

(e) All cells must have top and bottom energy absorbers.

554

CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONNRC FORM 618A(3-96)


(f) The weight of the fuel modules must be limited as specified on page 1-23(Rev. 2) of "S3G-3 Recoverable Irradiated Fuel in the M-140 SafetyAnalysis Report for Packaging."

(g) S3G-3 internals assembly must be used for shipment of S3G-3 fuel modules.

7. For S8G recoverable irradiated fuel shipments:

(a) Only a full load is authorized. Full and partial fuel modules may beshipped in any combination. All full and partial fuel modules must havecontrol rods.

(b) Minimum fuel cooling time is 248 days after shutdown for prototype modulesand 157 days after shutdown for shipboard modules.

(c) All fuel modules mus^hâveiower-suppbHs/and grapple adapters.

(d) Standard internals assembly must be used for</shipment of S8G fuel modules.Full fuel modules must have two full (side) spacers, partial fuel modulesmust have tw>full (side) spacers and one partfal-Xinside) spacer.

(e) The weigh%of the>fuel modules must be limited as specified on page 1.23(Rev. 4) of "S8G\R|cbyerable Irradiatedtgf^lfin the M-140 Safety AnalysisReport/For Packaging^*, \ CfT^r* ?f <W%£ ^

8. For DIG Core 2-recoverable Irradiated, fuel shlpinents: v.v

(a) Up to eight fullfjnoditteis^^ modules ofdifferent type|Jmay^b^îpp^jin;;an|fcombpat;on. .y-i>

.,''"*\ •.. . / >>• * .• /} / ? ; u h > i > • ; . ' \^. i t ' ' , f t ' .

(b)

(c)

(d)

(e)

Mini mum Cf Uf 1 cojojifii ng ~jL\mg?y\ s! 1811 dayg, a|ter>shutdpWn .v

All normally rodded fuUl mojweîmst^have control^rods. Control rodhold-down devices must be"1|f|tja^\e3 on^rddded?mod.ules.

Rodded modules must have top and bottom energy absorbers. Unroddedmodules must have topênergy absorbers^-?

i \ • ^ ' \ *

Standard internals assembly miist bemused for shipment of DIG Core 2 fuelmodules. Fuel module cavity spacers must be used for all fuel modules.

For D2W recoverable irradiated fuel shipments:

(a) Up to eight fuel modules may be shipped per package. Fuel modules ofdifferent types may be shipped in any combination. Up to nine fuelmodules may be shipped per package, provided that one of the fuel modulesis the prototype removable fuel assembly (RFA).

(b) Minimum fuel cooling time is 180 days after shutdown.

(c) All normally rodded fuel modules must have control rods. Control rodholddown devices must be installed on all rodded modules. The universalgrapple adapters serve as the rod holddown devices.

555

wwwwwww w^wwwwwwwwwwww. W.W.W wwwwwwwwwwwwwwwwww :«£:«fw.:>«i;ai¥S NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSIONC P-96) . .

3 Page 5 - Certificate No. 9793 - Revision No. 5 - Docket No. 71-9793

s(d) The standard internals assembly must be used for shipment of D2W fuel

modules. All fuel modules must be shipped with the appropriate cellspacers, as shown in Appendix 1.4 of the application dated October 14,1994.

10. The package must contain no more than 6 gallons of residual water, except thatshipments of D2W recoverable irradiated fuel may contain up to 11 gallons ofresidual water.

11. Failed fuel or fuel with defective cladding is not authorized for shipment.

12. Each packaging must meet the Acceptance Tests and Maintenance Program ofChapter 8 of the application, except:

All containment seals, including the main closure head seal, must bereplaced with new seals'Within the'12-month period prior to each shipment,or earlier if inspection shows any defect: . s

13. The package must be>,prepared for transport and operated, in accordance withChapter 7 of the application, except: " <•;.

The containment ^ a l s , excluding the mai.r);e1;6isure head seal, must pass aleak tes t -a f te r fijiaT closure prior to-each/shipment. The leak tes t musthave a sensitivity]cofwat l e a s t s x 10"3^s|dvcm3/sec.•'".:

14. Prior to f i r s t use, andlv^tfiin the>^2-month, ferffod prior to each shipment, allcontainment seals , irtcludiincj^the mairi cTdsjur^/read seal , must be leak tested toshow a leak rate no>.gresater";jbfra'n> l x : 10-"*vst^tmi/s'ejk/; The1""1 ' ' 4"*~+ """••*• u"w"a sensi t ivi ty of at,»lea_s;t 5/xnLO std-j-cnn/jslc: •W////r .>

15. Expiration date:

"Core Independent H-140 Safety Analysis Report For Packaging," and "S3G-3 RecoverableIrradiated Fuel in the M-140 Safety Analysis Report ;For Packaging," transmittedFebruary 27, 1991. . . . : •{ .-

Supplements dated: May 23, June 21, and July 17, 1991; February 4 and 7, August 17,and December 2, 1992; and October 14, 1994.


Date:


and Safeguards

fi 556

?»YY»:>iYW.5ttv;KV?»W»W»SV/"»^^^

NRC FORM 618(8-85)10 CFH 71





0c. PACKAGE IDENTIFICATION NUMBER d. PAGE NUMBER

1


9REAMBLEa. This certificate is issued to certify that the packagingand contents described in Item 5 below, meets theapplicable safety standards set forth in Title 10. Code


b. This certificate does not reileve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or otherapplicable regulatory agencies, including the government of any country through or into which the package will be transported.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGEJ5ESIGN OR APPLICATION "a. ISSUED TO IName and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:


"Safety Analysis Report for Packagingfor CGN Reactor Compartment Disposal,1da'te;dûjy 12, 1994, as supplemented

c. DOCKET NUMBER -9794A. CONDITIONS ' N X ^ - ^ ^ ' f *«.

This certificate Is condltionai upon fulfillingJhe {requirements of 10 CFR Part 71, as applicable, and the/cqijditions specified below.

(a) Packaging";-?10'

(1) Model No.

(2)

reacjtor e>mp^mengw!it;hin[aj Welded SJIJBJ&T container. The packageisapproximafelice^ S T X t h i h d b tp g

^ p p i ^ STpXeet high and about31êe,t i n ^ i a m % r . . ^ h l » i f e S : p a g e is.Sixteen-sidedpolyhedron with an en/lamed^bas^c^ntainingVsupport fixtures, whichextend^pproximately lO^f^rbeyond the dvameter of the package andprovideîm points for the package. ThWcontainer is constructedof high strength, steel (MIL-S-22698).^The reactor compartmentcomponents areâr-ained of water .êxcept for small inaccessiblepockets. The maximum"wei.ghitof t\\e package is 2,780,000 pounds.Potentially radioactive contaminated components and piping fromareas outside the reactor compartment may be secured within thepackage.

(3) Drawing

The packaging is constructed in accordance with the drawings inAppendix 1.3 of the application.

(b) Contents


Activated structural components associated with the CGN 25/35reactor compartments, plant piping, purification media (which maybe removed or left installed), and other components contaminatedwith radioactive corrosion products (crud). A maximum of 750gallons of residual liquid, primarily water, some of which containslow level radioactivity may also be present in the package.

5 5 7 M»»v»u«vsi^*«»^ysy<««»M.'^^

-5*

^ t V ^ * ^ ^

NRC FORM S1SA(6-83)

I

Iittiftctfii

II






The maximum quantity of radioactive material contents (crudand activation) shall not exceed the quantities specified inSection 1.2.3.1 of the application.

The shipment shall be no earlier than 365 day after shutdown.

The Lowest Service Temperature (LST) must be determined for each package.The package shall not be shipped unless its LST is less than or equal tothe daily minimum temperature exjje&tecL during shipment of the package, asdetermined on the basis ^featBerfcgo^gcisis

6.

7.

8. The radioactivity~o,fM;ne ion exchanger resiff^y^be no more than thevalue listed tn\Tatfle 4.1 of the application. <r\~

9.

10.

The reactor .^effective lujf

In

(a)

(b)of'ttfie ap

Expiratioivdate:

JThe^package miaceoVdance wi

shall have been operated forJessfthan 28,530hours. ^^7 ^

10 CFR^P|irt 71:

it and opH|ted int ion.

n.

"Safety Analysis Repordated July 12, 1994.

U,inements of SubR

Packaging for CGN Reacto

^eordance with Chapter 8

ompartment Disposal,"

Supplements Dated: November 10, 1994; %rid July 14, 1995.

FOR THE U.S . NUCLEAR REGULATORY COMMISSION


and SafeguardsSEP 2 5 1995

Date:

558

«S.^^





9853

b. REVISION NUMBER

10


USA/9853/AF

d. PAGE NUMBER

- 1


3', PREAMBLE





Safety Analysis Report for Packaging:The Unirradiated Fuel Shipping Container,USA/9853/AF ORNL/TM-11994,dated October 28, 1991.



5.

(a) Packaging

(1)

(2)

Model No.; HFBR.Unirradiated Fuel Shipping Container

Description 'V, o ; . - ' /

A right cylindricafeti inless};steel drum êrfclos ing a" fuel basket providedwith seven (7) cavjj&iesY Five, (5) of tfieT.seven (7) cavit ies are blockedto prevent the;i,r,ruse}:%The outer^sheilâria l id are fabricated from11-gauge steelând tle /âse!-i& l /4"i tf lck Ipl /ate. Thfeouter l id is heldin place1 by six/{6), 5f6"v bolts' .and ixMs. ^The^basket shell is fabricatedfrom 16-gauge stainless "steeli ! Theibasketf top-and bottom plates are11-gauge stainT|ss.s*teet;SEig^t (.8);,;3/,8".bolts and nuts retain thebasket lid: (0.125I5;thick alujjiitium) in pi ice. '•":;

The basket <is.' supported on'zijity:^ timbers inside the outer shell,remaining space around the basket is filled with phenolic foaminsulation. '•• /) ;-;

The package has dimensions and weight as follows:

Outside dimension, in 24-1/2

Container length, in 75-1/2

Base, in 29 x 29

The

Inside cavity crosssection, in

Gross weight, 1b

4 x 4

590

5591&T&T&TB3S&SJ3ZJ3UBJ£U£J5UBJ£JS&£J&JB^

^NRC FORM 618A CONDITIONS (continued) U . S . NUCLEAR REGULATORY COMMISSION(3-96)



3 (3) Drawings

3 The packaging is constructed in accordance with the following ORNLDrawing Nos.:M-11518-0H-001-E, Rev. 0,M-11518-OH-002-E, Rev. 0 andM-11518-0H-003-D, Rev. 0.

(b) Contents


Unirradiated uranium fuel elements as U308-AL cermet enriched up to 95 w/oin the U-235 isotope, and clad in aluminum at least 10 mils thick.

The contents are described in the Babcock & Wilcox Company Drawing Nos.4-8002-D, Rev^f, and 9-8025-E, Rev. M, as modified by BrookhavenNational Laboratory letter dated October 17;,' 1991 (Chapter 1, Appendix B,of the application). * # >

(2) Maximum quantity>6f material:rper, packaged '<,.-

Two (2). fuel ,elem'etijt%,containing up ta 355 grams U-235 per fuel element.The maximum,.quantity; pfv.radioactive matJeriaKwithin a package may notexceed a Type- A .quantity/. • ; ' v? .M'/-'/: /••

(c) Transport Index forXrfticality Control

Minimum transport index to be shown on -label for nuclear criticality control: J . .100

: 6. The fire resistant phenolic foam shall be in accordance with AEC Materialsa and Equipment Specification SP-9 or as modified by ORGDP Report K/TL-729.

c 7. In addition to the requirements of Subpart G of 10 CFR Part 71:

c (a) The package shall be prepared for shipment and operated in accordance** with the Operating Procedures in Chapter 7.0 of the application; and

(b) The package must meet the Acceptance Tests and Maintenance Program inChapter 8.0 of the application.

sS3£ 560a ^_^_ _ ^ ,

NRC FORM 618A CONDITIONS (continued) U.S. NUCLEAR REGULATORY COMMISSION>«. 0-96)

a Page 3 - Certificate No. 9853 - Revision No. 10 - Docket No. 71-9853




REFERENCES

Safety Analysis Report for Packaging: The Unirradiated Fuel Shipping ContainerUSA/9853/AF ORNL/TM-11994, October 28, 1991.


561

m

William D. Travers, DirectorSpent Fuel Project Office .Office of Nuclear Material Safety

, . a n d Safeguards

Date: ^ W f l%> ^>-.-<-. ? < • . - r itf

•••?*.<" • •-'•• k

la

NBC FORM 618(ME)10CFR71


FOR RADIOACTIVE MATERIALS PACKAGES1.a-CERTIFICATE NUMBER



USA/9932/B( )


2. PREAMBLEa. This certificate is issued to certify that the packaging and contents described in Item 5 below, meets the applicable safety standards set forth InTitle 10, Code



a THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE.DESI6N OR APPLICATIONa. ISSUED TO (Nona and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION:

University of CaliforniaLawrence Livermore LaboratoryP.O. Box 808Livermore, CA 94550 ^

Safety Analysis Report on Model UC-609 ShippingPackage, Report No. UCRL-52424, August 1977

71-99324. CONDITIONS

This certificate is conditional upon fulfilling the;requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model

(2) Description

Packag-ing for1/8-inch^ thilong.Ân "containmentand the^-luicontainmentPositive <cjJosure"% __accomplishW,using eight Voo-;,>j<closure is s%led with an fflri

The containment vessel is"•'--n diameter by 44 inches

sr by=31.-inch long.. .. .^"nlesjsVsteel outer shellâluîpn' honeyepitib. Access to the

opening at one end.^jdver plate is

-^ *%••-* stee'Fbolts. The cover^copper gaske^tfana* outer Viton 0-ring

seal. A valverfôrt between these gaskets<^%xpfovided for leak testing.A manifold containing! a valve and 200 ipsig pressure gage is welded to thecenter of the cover^p/TateL ^h.e containment vessel is centered andsupported within a 16-ga'uge steelVdrum 25 inches in diameter by 54-1/2inches high using Celotex insulation. The package gross weight is 500pounds.

5 6 2

. * . « • - - -

w



(3) Drawings

The packaging is constructed in accordance with Lawrence LivermoreLaboratory Drawing Nos.: AAA76-109771-0C, AAA75-113967-0B,AAA75-113083-0A, AAA77-102165-00, AAA75-112930-0A, AAA77-104161-00,AAA77-104165-0A and AAA77-104163-0B.

(b) Contents


Tritium in any,.form hltfdpwfthin secondary containers.

(2) Maximum>quant'ity of material per-package

Decay)heat not to exceed 48 watts. Not/more than 25 gm-moles (150grams) of tritium. ":^^

6. The initial (presstirje^jthin the containmentês,$eT and-secondary containersshall be sucJC that 1fâ£Kgases were releasedfftfom the secondary containersthe maximujn";pVessure\3|în\the^conâinme1itMessels at 20*C (68°F) would not

•exceed: S i t ? / li \W$ 9

exceed,ja-total of 120 pounds.

Section 8.0 of

7. The weight o/fjthe s e # p a

8Lawrence Liverrff6r,e Laboratory'Re^bVtv^No: lfCRii52424v,:A"g

ust 1977.

9. Operating procedure^'equivalent to those specified in Section 7.0 of LawrenceLivermore Laboratory-Report No. UCRL-52424,Âugust 1977, shall be establishedfor use.

v10. The package authorized by this certificate is hereby approved for use under

the general license provisions of 10 CFR §71.12.


563

^

I

iii



REFERENCES

Lawrence Livermore Laboratory Report No. UCRL-52424, August 1977.


;

Date: MOV *

Charles E. MacDonaTa, Chiefv jT-ransportation Branch;4 Diiv tls ijp i ^of Safeguards

and transportation, NMSS

564

G>y&i£9i!i^

* - .V"-" r * " •<"-"•

U.S. Nuclear Regulatory CommissionList of Packages by Package Type

Type of Packaging: BYPROD. NORM. FORM

Model

CI-20WC-2

CI-20WC-2A

GE-8500

PAS-1

UC-609

Package ID #

USA/9098/B( )

USA/9098/B( )

USA/6697/B( )

USA/9184/B(U)

USA/9932/B( )

ExpirationDate

02/28/1998

02/28/1998

09/30/1996

07/31/1999

11/30/1995

565


Type of Packaging: BYPROD. SPEC. FORM

Model

A-0109

AI 500 SU

BUSS R-l

C-l

C-8

E-MEH-00-00004

GE-500

IR-100

IR-50

LCG-25A

LCG-25B

LCG-25C

MW-3000

NATICK IRRADI

NPI-20WC-6

NPI-20WC-6 MKII

OP-100

ORNL TRU CALIF

SENTINEL-100F

SENTINEL-25A

SENTINEL-2 5B

SENTINEL-25C

SENTINEL-25C3

SENTINEL-25D

Package ID #

USA/6280/B( )

USA/9006/B(U)

USA/9511/B(U)

USA/9036/B(U)

USA/9128/B(U)

USA/901l/B( )

USA/9049/B( )

USA/9157/B(U)

USA/9156/B(U)

USA/4888/B( )

USA/4888/B( )

USA/4888/B( )

USA/9030/B( )

USA/5362/B( )

USA/9102/B( )

USA/9215/B(U)

USA/9185/B(U)

USA/5740/B( )

USA/5862/B( )

USA/4888/B( )

USA/4888/B( )

USA/4888/B( )

USA/4888/B( )

USA/4888/B( )

ExpirationDate

01/31/2000

08/31/2000

07/31/1997

10/31/2000

02/28/1996

08/31/1996

12/31/2000

01/31/1998

01/31/1998

12/31/1996

12/31/1996

12/31/1996

10/31/2000

01/31/2000

10/31/1998

10/31/1997

01/31/1998

07/31/2001

09/30/2000

12/31/1996

12/31/1996

12/31/1996

12/31/1996

12/31/1996

566


Type of Packaging:

Model

SENTINEL-25E

SENTINEL-25F

SENTINEL-8

SNAP-21

SPEC 2-T

SPEC-150

URIPS-8A

URIPS-8B

100

100A

181361

181375

20

20A

200

200A

3206B

3218

3227B

4.5 TON CF

420

50

50A

5979

5984

BYPROD. SPEC. FORM

Package ID #

USA/4888/B( )

USA/4888/B( )

USA/9030/B( )

USA/5830/B( )

USA/9056/B(U)

USA/9263/B(U)

USA/6786/B( )F

USA/6786/B( )F

USA/9127/B(U)

USA/9127/B(U)

USA/5796/B(U)

USA/5796/B(U)

USA/9126/B(U)

USA/9126/B(U)

USA/9127/B(U)

USA/9127/B(U)

USA/9167/B(U)

USA/9167/B(U)

USA/9167/B(U)

USA/6642/B( )

USA/9245/B(U)

USA/9126/B(U)

USA/9126/B(U)

USA/5979/B( )

USA/5984/B( )

ExpirationDate

12/31/1996

12/31/1996

10/31/2000

11/30/2000

12/31/1999

04/30/2000

04/30/1998

04/30/1998

10/31/1999

10/31/1999

07/31/1997

07/31/1997

10/31/1999

10/31/1999

10/31/1999

10/31/1999

12/31/1998

12/31/1998

12/31/1998

10/31/1996

09/30/1997

10/31/1999

10/31/1999

09/30/2000

04/30/2001

567


Model

650

650L

660

660A

660AE

660B

660BE

660E

6717-B

676

676A

676AE!

676B

676BE

676E

680

680A

680AE

680B

680BE

680E

684

684A

684AE

684B

Package ID #

USA/9032/B(U)

USA/9269/B(U)

USA/9033/B(U)

USA/9033/B(U)

USA/9033/B(U)

USA/9033/B(U)

USA/9033/B(U)

USA/9033/B(U)

USA/6717/B(U)

USA/9029/B(U)

USA/9029/B(U)

USA/9029/B(U)

USA/9029/B(U)

USA/9029/B(U)

USA/9029/B(U)

USA/9035/B(U)

USA/9035/B(U)

USA/9035/B(U)

USA/9035/B(U)

USA/9035/B(U)

USA/9035/B(U)

USA/9028/B(U)

USA/9028/B(U)

USA/9028/B(U)

USA/9028/B(U)

ExpirationDate

10/31/1999

11/30/2000

10/31/2000

10/31/2000

10/31/2000

10/31/2000

10/31/2000

10/31/2000

09/30/1998

10/31/1999

10/31/1999

10/31/1999

10/31/1999

10/31/1999

10/31/1999

04/30/2000

04/30/2000

04/30/2000

04/30/2000

04/30/2000

04/30/2000

01/31/2001

01/31/2001

01/31/2001

01/31/2001

568


Type of Packaging: BYPROD. SPEC. FORM

Model

684BE

684E

702

715

741

741A

741AE

741B

741BE

741E

770

771

820

850

855

864

865

920

934

Package ID #

USA/9028/B(U)

USA/9028/BCU)

USA/6613/B(U)

USA/9039/B(U)

USA/9027/B(U)

USA/9027/B(U)

USA/9027/B(U)

USA/9027/B(U)

USA/9027/B(U)

USA/9027/B(U)

USA/9148/B(U)

USA/9107/B(U)

USA/9137/B(U)

USA/9147/B(U)

USA/9165/B(U)

USA/9166/B(U)

USA/9187/B(U)

USA/9143/B(U)

USA/9243/B(U)

ExpirationDate

01/31/2001

01/31/2001

03/31/1998

12/31/2000

02/28/2001

02/28/2001

02/28/2001

02/28/2001

02/28/2001

02/28/2001

03/31/1997

05/31/1998

11/30/1995

11/30/2000

12/31/1998

01/31/1998

12/31/1998

01/31/2001

01/31/2001

569


Type of Packaging: FISSILE URANIUM

Model

ABB-2901

ANF-250

ATR

A1W-3 PUSC

BU-7

BW-2901

DHTF

D2G POWER UNIT

FL 10-1

FPD-100

FSV-3

GE-21PF-1

HFBR UNIR CONT

INNER HFIR UN

MCC-3

MCC-4

MCC-5

MODEL B

MODEL 1 S-6213

MODEL 2 S-6213

NCI-21PF-1

NFS-URANYL NIT.

NNFD 5X22

NNFD-10

Package ID #

USA/9274/AF

USA/9217/AF

USA/9099/B(U)F

USA/9787/B(U)F

USA/9 019 /AF

USA/9251/AF

USA/9203/AF

USA/6441/B{ )F

USA/9009/B( )F

USA/9057/AF

USA/6347/AF

USA/4909/AF

USA/9853/AF

USA/5797/B(U)F

USA/9239/AF

USA/9239/AF

USA/9239/AF

USA/6206/AF

USA/9186/B(U)F

USA/9186/B(U)F

USA/9234/B(U)F

USA/5059/AF

USA/9250/B(U)F

USA/6357/AF

ExpirationDate

02/28/1998

01/31/2000

01/31/1999

04/30/2000

11/30/1998

08/31/1997

01/31/2001

12/31/1997

06/30/1999

09/30/2000

03/31/1997

11/30/1999

10/31/1996

10/31/1996

11/30/1996

11/30/1996

11/30/1996

09/30/2000

07/31/1997

07/31/1997

12/31/1998

08/31/1996

01/31/1998

04/30/2001

570

'->"-.-.•" . • • _'•'-»-•_'


Type of Packaging: FISSILE URANIUM

Model

NONE SPECIFIED

OUTER HFIR UN

PADUCAH TIGER

RA-2

RA-3

RCC

RCC-1

RCC-3

RCC-4

SP-1

SP-2

ST

S5W POWER UNIT

TRIGA-I

TRIGA-II

TROJAN PRESSUR.

TROJAN STEAM

UNC-2600

UNC-2901

UX-30

2.7 NEW FUEL

235R001

51032-1

51032-2

814A

Package ID #

USA/6406/AF

USA/5797/B(U)F

USA/6553/AF.

USA/4986/AF

USA/4986/AF

USA/5450/AF

USA/5450/AF

USA/5450/AF

USA/5450/AF

USA/9248/AF

USA/9248/AF

USA/9246/AF

USA/5580/B( )F

USA/9034/AF

USA/9037/AF

USA/9260/A

USA/9259/A

USA/5086/B(U)F

USA/6294/AF

USA/9196/AF

USA/5894/AF

USA/6386/B(U)F

USA/6581/AF

USA/9252/AF

USA/5149/B( )F

ExpirationDate

12/31/1997

10/31/1996

11/30/1998

10/31/1997

10/31/1997

09/30/1996

09/30/1996

09/30/1996

09/30/1996

12/31/1998

12/31/1998

02/28/1997

12/31/1997

12/31/2000

12/31/2000

06/30/2000

06/30/2000

01/31/1999

03/31/2001

02/28/2001

07/31/1997

07/31/1997

05/31/1999

09/30/1998

06/30/2000

571


Type of Packaging: FISSILE URANIUM „ .Expiratxon

Model Package ID # Date

927A1 USA/6078/AF 10/31/2000

927C1 USA/6078/AF 10/31/2000

572


Type of Packaging: IRRADIATED FUEL

Model

BMI-1

CNS 1-13G

FSV-1

GE-100

IF-300

M-130

M-140

M-160

NAC-LWT

NAC-STC

NLI-1/2

NLI-10/24

T-2

T-3

TN-BRP

TN-FSV

TN-REG

TN-8

TN-8L

TN-9

125-B

2000

Package ID #

USA/5957/B( )F

USA/9216/B( )F

USA/6346/B( )F

USA/5926/B( )F

USA/900l/B( )F

USA/6003/B( )F

USA/9793/B(U)F

USA/9781/B( )F

USA/9225/B(U)F

USA/9235/B(U)F

USA/9010/B( )F

USA/9023/B( )F

USA/5607/B( )F

USA/9132/B(M)F

USA/9202/B(U)F

USA/9253/B(U)F

USA/9206/B(U)F

USA/9015/B( )F

USA/9015/B{ )F

USA/9016/B( )F

USA/9200/B(M)F

USA/9228/B(U)F

ExpirationDate

03/31/2001

12/31/1997

05/31/2001

02/28/1998

09/30/2000

12/31/1997

10/31/1996

07/31/1997

02/28/2000

09/30/1999

04/30/2001

03/31/1997

05/31/1998

04/01/2001

06/30/1999

05/31/1999

05/31/2000

05/31/2001

05/31/2001

05/31/2001

04/01/2001

06/30/1999

573


Type of Packaging: LSA

Model

BS-33-180

CNS 14-170 III

CNS 14-195-H

CNS 21-300

CNS 6-75

CNS 6-80-2

CNS 6-80-2A

CNS 8-120A

CNSI 14-215H A

HN-100 SERIES 3

HN-190-1

HN-190-2

HN-194S

LL-60-150

LN 10-135A

LN 14-170 1

LN 14-170H

LN 14-170L

LN 14-170M

LN 14-195H

LN 14-195L

LN 6-80H

LN 6-80L

LN 7-100

Package ID #

USA/6722/A

USA/9249/A

USA/9094/A

USA/9096/A

USA/9108/A

USA/9111/A

USA/9Ill/A

USA/6601/A

USA/9176/A

USA/9151/A

USA/9086/A

USA/9224/A

USA/9089/A

USA/6568/A

USA/9177/A

USA/9151/A

USA/9159/A

USA/9159/A

USA/9159/A

USA/9176/A

USA/9176/A

USA/9179/A

USA/9179/A

USA/9178/A

ExpirationDate

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

574

U.S. Nuclear Regulatory CommissionLis t of Packages by Package Type

Type of Packaging: LSA

Model

NUPAC 10/140

NUPAC 14/190H

NUPAC 14/190L

NUPAC 14/190M

NUPAC 14/210H

NUPAC 14/210L

NUPAC 14D-2.0

NUPAC 50-1.5L

NUPAC 50-2.5L

NUPAC 50-3.0L

NUPAC 50-4.0L

NUPAC 6/100H

NUPAC 6/100L

NUPAC 7/100

YNPS RPV

YNPS STEAM GEN.

10-142A

110G-A

14-215

40G-A

589

Package ID #

USA/9177/A

USA/9159/A

USA/9159/A

USA/9159/A

USA/9176/A

USA/9176/A

USA/9079/A

USA/9145/A

USA/9145/A

USA/9145/A

USA/9145/A

USA/9179/A

USA/9179/A

USA/9178/A

USA/9262/A

USA/9256/A

USA/9073/A

USA/9247/A

USA/9222/A

USA/9254/A

USA/9139/A

ExpirationDate

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999'

04/01/1999

01/31/2001

09/30/1998

04/01/1999

04/01/1999

04/01/1999

04/01/1999

04/01/1999

575


Type of Packaging: PU AIR

ExpirationModel Package ID # Date

PAT-1 USA/036l/B(U)F-85 09/30/1998

PAT-2 USA/9150/B{U)-85 07/31/2001

576


Type of Packaging: PU NORM. FORM

Model

B-3

BETTIS WASTE

NRBK-41

TRUPACT-II

WAPD-40

6400

Package ID #

USA/6058/B( )

USA/6142/B( )

USA/9221/B( )F

USA/9218/B(U)F

USA/5874/B( )F

USA/6400/B( )F

ExpirationDate

12/31/2000

12/31/1997

09/30/2001

06/30/1999

07/31/1997

06/30/1997

577


Type of Packaging: PU SPEC. FORM

Model

BCL-2

BCL-3

BCL-4

MO-1

S5W REFUEL.SRCE

1500

Package ID #

USA/9068/B( )F

USA/9067/B( )F

USA/5950/B( )F

USA/9069/B( )F

USA/5757/B( )F

USA/5939/B( )F

ExpirationDate

05/31/1997

05/31/1997

08/31/1996

01/31/1997

12/31/1997

12/31/1997

578


Type of Packaging: WASTE, B

Model

AP-101

A1W-3 CB/TS DC

A1W-3 HD/SB SDC

CGN 25/35 RCDP

CNS 1-13C

CNS 1-13C II

CNS 10-160B

CNS 3-55

CNS 4-85

CNS 8-120B

DIG CB-TS

N-55

NAC-1

PWR-2 CORE BAR.

S2C REC. COMPT.

S3G CBDCA

S3W REC. COMPT.

S4W REC. COMPT.

S5W REC. COMPT.

TN-RAM

10-135B

10-142

3-82B

Package ID #

USA/907l/B( )

USA/9789/B(U)

USA/9790/B(U)

USA/9794/B(U)

USA/908l/B( )

USA/9152/B{ )F

USA/9204/B(U)

USA/5805/B( )

USA/6244/B( )

USA/9168/B(U)

USA/9792/B(U)

USA/9.0 7 0/B(U)

USA/9183/B( )F

USA/9791/B(U)

USA/9788/B(U)

USA/9786/B(U)

USA/9788/B(U)

USA/9788/B(U)

USA/9788/B(U)

USA/9233/B(U)

USA/9210/B(U)

USA/9208/B( )

USA/6574/B( )

ExpirationDate

12/31/1996

05/31/2000

05/31/2000

09/30/2000

12/31/1997

05/31/1999

10/31/2000

03/31/1999

04/30/2000

06/30/2000

09/30/1997

12/31/1999

09/30/1999

12/31/1997

12/31/1997

08/31/2001

12/31/1997

12/31/1997

12/31/1997

01/31/2000

12/31/1999

07/31/2001

05/31/2001

579

NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION

(JRCM1102,3201-3202 BIBLIOGRAPHIC DATA SHEET

(See instructions on the reverse)

2. TITLE AND SUBTITLE

Directory of Certificates of Compliance for Radioactive Materials Packages

Certificates of Compliance

5.AUTHOR(S)

1. REPORT NUMBER(Assigned by NRC, Add Vol., Supp., Rev.,and Addendum Numbers, if any.)

NUREG-0383Volume 2

Revision 19

3. DATE REPORT PUBLISHED

MONTH

October

YEAR

19964. FIN OR GRANT NUMBER

6. TYPE OF REPORT

7. PERIOD COVERED (Inclusive Dates)

8. PERFORMING ORGANIZATION - NAME AND ADDRESS (If NRC, provide Division, Office or Region, U.S. Nudear Regulatory Commission, and mailing address; if contractor,provide name and mailing address.)

Spent Fuel Project OfficeOffice of Nuclear Material Safety and SafeguardsU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

9. SPONSORING ORGANIZATION - NAME AND ADDRESS (If NRC, type 'Same as above'; if contractor, provide NRC Division, Office or Region. U.S. Nudear Regulatory Commission,and mailing address.)

Same as 8, above

10. SUPPLEMENTARY NOTES

11 . ABSTRACT (200 words or less)

The purpose of this directory is to make available a convenient source of information on packagings approved by theU.S. Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and correspondingCertificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is includedin the back of Volume 3 of approved Quality Assurance programs. The reports include a listing of all users of each packagedesign and approved Quality Assurance programs prior to the publication date.

12. KEY WORDS/DESCRIPTORS (Ust words or phrases that will assist researchers in locating the report.)

TransportationPackagingRadioactive Materials

13. AVAILABILITY STATEMENT

unlimited14. SECURITY CLASSIFICATION

(This Page)

unclassified(This Report)

unclassified

15. NUMBER OF PAGES

16. PRICE

NRC FORM 335 (2-89) This form was electronically produced by Elite Federal Forms. Inc.

directory of certificates of compliance for radioactive

Documents