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Ferm NRC418 U.S. NUCLE AR REGULATORY COMMISSION

i' 5 ' CERTIFICATE OF COMPLIANCE10 C1 R 71For Radioactive Materials Packages

1.fal Certificate Number 1.(b) Revision No. 1.(c) Package Identification No. 1.(d) Pages No. 1.(e) Total No. Pages

1 USA /9901/Bf IF' 1'

~5990f -

2. PRE AMBLE

2.fal This certificate is issued to satisty Sections 173.393a.173.394,173.395, and 173.396 of the Department of Transportation HazardousMaterials Regulations.(49 CFR 170180 and 14 CFR 103) and Sections MG--19-10a and 146-19--100 of the Department of. t '

' Transportation Dangerous Cargoes Regulations (46 CFR 146 :149), as amended.

2.(b) The packaging and contents described irtitem,5 below,, meets the safety standards se; forth in Subpart.C of Title 10, Code of . . . ,' Federet Regulations,' fart 77, '' Packaging bf Radioactis MaterMt for Transport ah'd Trerisportation of' Radioactive Material' Under ' ,. .. .". ' . .

Certain Conditions."

2.(c) This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department ofTransportation or other applicable regulatory agencies, including the government of any country through or into which the packagewill be transported.

3. This certificate is issued on the basis of a safety analysis report of the package design or application-

3.(a) Prepared by (Name and address): 3.(b) Title and identification of report or application:

Westinghouse Hanford Company, Hanford Engineering Development LaboratoryHanford Engineering Development Report No. HEDL-TI 76-018, December 1976.

LaboratoryP.O. Box 1970

3.(c) Docket No. 71-9901D 4. c h l a n d tfn QQ'it;9. ...--

This certificate is conditional upon the fulfilling of the requirements of Subpart D of 10 CFR 71. as applicable, and the conditions specifiedin item 5 below.

5. O,escription of Packaging and Authorized Conten.ts, Model, Number,, Fissile, Class ,Other conditions,pnd References:; ,, ,,,,,;.,, ,,,,,.y,,'

~ ('a )Packaging

(1) Model No.: Model 120

(2) Descrip' tion

A metal " birdcage" enclosing a steel containment vessel for unir-radiated fuel pins. The stainless steel containment vessel is a 12-inch diameter,154-inch long, Schedule 40 pipe. One end is closedwith a 1.25-inch thick cover plate, secured with sixteen 1-inch diameterbolts to a welded neck-type flange. The containment seal is a Flexitallictype-spiral wound, stainless steel, asbestos' filler gasket.

The containment' vessel is centered inside of a prismatic metal frame21.5 x 21.5 x 190 inches, and is supported by six 5/16-inch thick andtwo 1-1/4-inch thick steel plates equally spaced and welded to thesupport frame perpendicular to the longitudinal axis. The supportframe is constructed of 2- x 2- x 1/4-inch steel angles, covered withexpanded, metal.. mesh. . Impact :. limiters comprised .of interspersed styrofoann ., . .

and masonite are bolted to the ends. The package gross weight is| 2,200. pounds. |

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' age 2 - Certificate No. 9901 - Revision No.1 - Docket No. 71-9901P

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5. (a) Packaging (Cont'd)

(3) Drawings

The packaging is fabricated in accordance with Hanford EngineeringDevelopment Laboratory Drawings Nos. H-3-37350, Sheet 1, Rev. 4, Sheet2, Rev. 2, Sheet 3, Rev. 3, Sheet 4, Rev. 2; H-3.39691, Sheet 1, Rev. .

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1, Sheet 2, 'Rev. O'; H-3-32429, Sheet 3 of 4,:'Rev. ~6; H-3-38062, Rev.'

1;H-3-37042; Rev."l; and H-3-37412,- Rev.1.'

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(b) Contents.

(1) Type and form of material

(1) Unirradiated fuel pins containing mixed Pu0, in natural UO2 aspressed sintered pellets of the following specification:

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Pellet diameter, inch 0.19 to 0.20

Pin diameter, inch 0.22 to 0.24

Maximum length, inches 36.3

Maximum Pu0 in UO , w/o 312 2

'-~> v . . . , , ; :. ;... . .- Maximum.U-235 enrichment- : -: . * " - .~i. - . . - - -- -..

in~UO , w/o 0.72 -

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Minimum Pu-240 enrichmentin Pu0 , w/o 102

Cladding material Type 304 SS or 316 SS-

Minimum claddingthickness, inch 0.010

(ii) Unirradiated fuel pins containing mixed Pu0 in UO enriched to7 2any degree in the U-235 isotope as solid peTlets of the followingspecification:

Maximum pin diameter, inch 0.290

Maximum length, inch 37

: Minimum.Pu-24.0 , .. , . . . . 3, ., -.,. 3 .... .

enrichment in Pu0 , w/o 102

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1' Page 3 - Certificate No. 9901 - Revision No.1 - Docket No. 71-99014

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5. (b) Contents (Cont'd)i Cladding material Type 304 SS or 316 SS

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Minimum claddingthickness, inch 0.010

Maximum linear density of.. 3.0

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fissile . material, kg/ft~

. (if1). : Fast' flux;tes& facility (FFTF.) .fnel'.c' ve . - - - - d^- 2-' ' -

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(iv) Pu0, and U0, enriched in the U-235 isotope encapsulated in fuelpint or captules which meet the requirements of special formmaterial as defined in 10 CFR i 71.4(o).

(v) Solid dry oxides of Pu-238, Pu-239, Pu-240, Pu-241 (non-isolatedfom), U-233, U-235, Np-237 and Am-241, contained within capsuleswhich meet the requirements of special form material as defined:

in 10 CFR 9 71.4(o).

(vi) Pu-241, Am-242, Cm-243, Cm-244, Cm-245, Cf-247 or Cf-251 in anyform, contained in capsules which meet the requirements of specialfonn material as defined in 10 CFR 9 71.4(o).

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(2) , Maximum,,qua,n,tJJy,,of material,. per,,pa,ckage.

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Not to exceed 260 watts internal decay heat, and:

(1) For the contents described in 5(b)(1)(i) and 5(b)(1)(ii) 120 fuelpins with no more.than 6.75 kg Pu.

(ii) For the contents described in 5(b)(1)(iii) no more than oneassembly.

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(iii) For the contents described in 5(b)(1)(iv), greater than Type A.

quantity of radioactive material not to exceed the generallylicensed mass limits as specified in 10 CFR i 71.11(a).'

(iv) For the contents described in 5(b)(1)(v) no more than 230 gramsof fissile material.

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(v) For the contents described in 5(b)(1)(vi) no more than 3 grams ofthe isotopes specified.

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Page 4 - Certificate No. 9901 - Revision No.1 - Docket No. 71-9901

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(c) Fissile Class II and III

(1) Minimum transport index to be shown on label for Class II,

('i) For ' contents desdribid 'in 5(b)(1)(1)and limited in 5(b)(2)(i): 4.0

(ii)' For. contents described in 5(b)(1)(ii)-,

andlimitedin.5(b)(2)(1): 7.0 .

? m '' -' ' 52- # '>->. -(.iti)-D For contents described in.5(b)-(1)tifi)'' ^ *

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and limited in 5(b)(2)(ii): 015

(iv) For contents described in 5(b)(1)(v)i

and limited in 5(b)(2)(iv): 3.5

(v) For contents described in 5(b)(1)(vi)and limited in 5(b)(2)(v): 3.5

(2) Maximum number of packages per shipment for Class III

For contents described in 5(b)(1)(iv)and limited in 5(b)(2)(iii): One (1)

,6., For. the con, tents, described .in ,5,(b),(1)'(1),(ii ,(.i.v). an.d (,v), car,bi, des, or. nitrides , ,, .. .- may replace the oxides ~of. uranium and pluton um..

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

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8. Expiration date: May 31, 1988.

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Page 5 - Certificate No. 9901 - Revision No.1 - Docket No. 71-9901

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REFERENCE

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Hanford Engineering Development Laboratory Report.No. HEDL-TI 76-018, December 1976. :

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FOR THE U.S. NUCLEAR REGULATORY COMMISSION'

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1 rles E. MacDonald, ChiefTransportation Certification BranchDivision of Fuel Cycle and

j Material SafetyMAY 0 61983

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U.S. Nuclear Regulatory Commission'

Transportation Certification BranchApproval Record

Model No.: Model 120 PackagingDocket No. 71-9901

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Bi application dated March 22, 1983, Department of Energy, Safety Engineeringand Analysis Division, requested renewal of Certificate of ComplianceNo. 9901. No changes were requested or made to the package since approval

. of. the. original application dated December 1976.- --. . .

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The staff concludes that the statements. of the original . application . ..~ . . . .

' '"'- ''satt.sfies' the" req 6irement'foFnnewar of' thf Certificate''of CompliaricE. - " " ' ' ."' '~ '~'.

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,$C rles E. MacDonald, Chief,Transportation Certification BranchDivision of Fuel Cycle and

Material Safety, PNSS

Date:

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