hi-star 100 transportation coc 9261 license amendment

mMENEM HOLTEC INTERNATIONAL

Holtec Center, 555 Lincoln Drive West, Marlton, NJ 08053

Telephone (856) 797-0900 Fax (856) 797-0909

BY FAX AND OVERNIGHT MAIL

February 18, 2000

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

References:

Dear Sir:

USNRC Docket No. 71-9261; TAC No. L22085 IR-STAR 100 Transportation CoC 9261

License Amendment Request 9261-1, Supplement 2

1. Holtec Project 5014 2. Holtec Letter to NRC dated November 24,1999, LAR 9261-1

As committed during our telephone conversation yesterday, we enclose herewith replacement pages for proposed Safety Analysis Report (SAR) Revision 9, a sketch of the criticality model of the QUAD+ assembly, and revised wording for the Certificate of Compliance related to the AntimonyBeryllium neutron source. Please note that while the value of Sby presented in Appendix 2.R is different due to a unit conversion, the value used in the underlying calculation is unaffected and the 33% safety margin remains unchanged.

If you have any questions or require additional information, please contact us.

Sincerely,

inan G herman, P.E. Licensing Manager

Approval:

. ingh, Ph.D, P.E. President and CEO

cc: Ms. Marissa Bailey, USNRC (w/10 copies of enclosure) Mr. Mark. Delligatti, USNRC (w/ end.)

Document ID: 5014370

Enclosures: 1. Replacement SAR page 2.R-7, proposed Revision 9 (1 page) 2. QUAD+ Criticality Model Sketch (1 page) 3. Mark-ups of CoC 9261, Appendix A (2 pages)

A_(M S56 (PL))//,

//-I - C/ 2- 61

MENEM HOLTEC INTERNATIONAL

Holtec Center, 555 Lincoln Drive West, Marlton, NJ 08053

Telephone (856) 797-0900 Fax (856) 797-0909

U. S. Nuclear Regulatory Commission ATfN: Document Control Desk Document ID 5014370 of 2

Technical Concurrence:

Dr. Alan Soler (Structural Evaluation)

Dr. Everett Redmond II (Shielding Evaluation)

Dr. Stefan Anton (Criticality Evaluation)

Distribution (wlo encl.):

Recipient Affiliation

Mr. David Bland Mr. Ken Phy Mr. J. Nathan Leech Dr. Max DeLong Mr. Stan Miller Mr. David Larkin Mr. Bruce Patton Mr. Mark Smith Mr. Rodney Pickard Mr. Eric Meils Mr. Paul Plante Mr. Jeff Ellis Mr. Darrell Williams Mr. Joe Andrescavage Mr. Ron Bowker Mr. William Swantz Mr. Chris Kudla Mr. Keith Waldrop Mr. Matt Eyre Mr. Al Gould Dr. Seymour Raffety Mr. John Sanchez Ms. Kathy Picciott Mr. John Donnell Dr. Stanley Turner

Southern Nuclear Operating Company New York Power Authority Commonwealth Edison Private Fuel Storage Vermont Yankee Nuclear Power Corporation Energy Northwest Pacific Gas & Electric - Diablo Canyon Pacific Gas & Electric - Humboldt Bay American Electric Power Wisconsin Electric Power Company Maine Yankee Atomic Power Company Southern California Edison Entergy Operations - Arkansas Nuclear One GPUN - Oyster Creek Nuclear Power Station IES Utilities Nebraska Public Power District Entergy Operations - Millstone Unit 1 Decommissioning Duke Power Company PECO Energy Florida Power & Light Dairyland Power Consolidated Edison Company Niagara Mohawk Power Corporation Private Fuel Storage, LLC (SWEC) Holtec International, Florida Operations Center

57 t

The direct shear force/unit throat thickness is determined as:

Fr Sr :

Aweld

Sr = 4.012 x 104 -bf

in

The force/unit throat thickness at point D, which is farthest from the centroid of the

weld group, due to the two bending moments is determined as:

Mx Shby

Sxx

_My

Sbx : = Syyb

Sb := Sbx + Sby

Sby = 1.337 x 10 4 lbf in

Sbx = 8.307 x 1 0 4 bf in

Sb = 9. 6 4 4 x 104 lbf in

The torsional force/unit of throat thickness at point D is determined as:

W2

Jw St = 7.148 x 10 3- bf in

The net force/unit of weld throat thickness is computed as a root mean square

Seq := [ Sb2 + (Sr + St)2] 0"5 Seq = 1.074 x 105 Ibf in

Dividing by the yield strength of the material yields a minimum required throat

thickness

Seq t r e q .- __ treq = 3.187in

2.R-7HI-STAR SAR Report HI-951251

Rev. 9

___________ E I 1

0 0. 0 00000 0000

0 C

C

~0

+

CD tz

0•

0

0

0

0

0

0

00000 00000 0 0 0

+

0 0 0 000o00 0000 0000

0000 0000 00000 0 0 0

_______________________________ ___________ ___________ I i I I ___________ I ___________

/

CD

I

0

T0 Lt. Lt•

1-1 p

k

Appendix A-Certificate of Compliance No. 9261

Table A. 1 (continued) Fuel Assembly Limits

I1. MPC MODEL: MPC-68 (continued)

5. Thoria rods (ThO 2 and U02) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following

specifications:

a. Cladding Type:

b. Composition:

c. Number of Rods Per Thoria Rod Canister:

d. Decay Heat Per Thoria Rod Canister:

e. Post-irradiation Fuel Cooling Time and Average Bumup Per Thoria Rod Canister:

f. Initial Heavy Metal Weight:

g. Fuel Cladding O.D.:

h. Fuel Cladding I.D.:

i. Fuel Pellet O.D.:

j. Active Fuel Length:

k. Canister Weight:

Zircaloy (Zr)

98.2 wt. % Th0 2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 23U.

< 18

< 115 Watts

A fuel post-irradiation cooling time > 18 years and an average burnup <_ 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches

<_ 550 lbs, including fuel

B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister plus any Any combination of damaged fuel

assemblies in damaged fuel containers and intact fuel assemblies, up to a total of 68.

C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68.

D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC

68. The Antimony-Berylium neutron source material shall be in a water rod location.

A-6



It, MPC MODEL: MPC-68F (continued)

7. Thoria rods (ThO2 and U0 2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:









k. Canister Weight:

Zircaloy (Zr)

98.2 wt.% ThO2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 23U.

< 18

< 115 Watts

A fuel post-irradiation cooling time > 18 years and an average bumup _ 16,000 MWD/MTIHM.

<_ 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches

< 550 Ibs, including fuel

B. Quantity per MPC:

Up to four (4) damaged fuel containers containing uranium oxide or MOX BWR fuel debris. The remaining MPC-68F

fuel storage locations may be filled with array/class 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A fuel assemblies of the

following type, as applicable:

1. Uranium oxide BWR intact fuel assemblies; 2. MOX BWR intact fuel assemblies; 3. Uranium oxide BWR damaged fuel assemblies placed in damaged fuel containers; of 4. MOX BWR damaged fuel assemblies placed in damaged fuel containers; or 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.

C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68F.

D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68.

The Antimony-Berylium neutron source material shall be in a water rod location.

A-13


Fr Sr := Aweld

Sr = 4.012 x 104 -bf

in

The force/unit throat thickness at point D, which is farthest from the centroid of the weld group, due to the two bending moments is determined as:

Mx Sby

Sxx

My

Sbx My

Syyb

Sb := Sbx + Sby

Sby = 1.337 x 10 4 Ibf in

Sbx = 8.307 x 10 4 lbf in

Sb = 9.644x 104 lbf in


W Mz.

2 St

JW St 7 .14 8 x 10 3 Ibf in


Seq := [ Sb2 + (Sr + St)2]0"5 Seq = 1.074 x 10 5 bf in

Dividing by the yield strength of the material yields a minimum required throat thickness

Seq treq -=

G ytreq = 3.187 in


Rev. 9

-x I FriT� Fl

0000 0000

0000 o0000

z C)

0

+

S

C• 0 0 00000 00000 0 0 0

+

000 00000 0000 0000

0000 0000 00000 0 0

1T IH . . .. ........... ........... ...N/ N

0

0

t C,' Lit

I

0

00 p uj (-A

t



II. MPC MODEL: MPC-68 (continued)

5. Thoria rods (ThO 2 and U02) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:









k. Canister Weight:

Zircaloy (Zr)

98.2 wt. % ThO 2, 1.8 wt. % U0 2 with an enrichment of 93.5 Wt. % 235U.

< 18

< 115 Watts

A fuel post-irradiation cooling time > 18 years and an average bumup <_ 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches


B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister plus anyAny combination of damaged fuel assemblies in damaged fuel containers and intact fuel assemblies, up to a total of 68.


D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC68. The Antimony-Berylium neutron source material shall be in a water rod location.

A-6



Ill. MPC MODEL: MPC-68F (continued)

7. Thoria rods (ThO 2 and U0 2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:






h. Fuel Cladding L.D.:



k. Canister Weight:

Zircaloy (Zr)

98.2 wt. % ThO2, 1.8 wt. % U0 2 with an enrichment of 93.5 Wt. % 235U.

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches



Up to four (4) damaged fuel containers containing uranium oxide or MOX BWR fuel debris. The remaining MPC-68F fuel storage locations may be filled with array/class 6x6A, 6x6B, 6x6C, 7x7A, and 8x8A fuel assemblies of the following type, as applicable:

1. Uranium oxide BWR intact fuel assemblies; 2. MOX BWR intact fuel assemblies; 3. Uranium oxide BWR damaged fuel assemblies placed in damaged fuel containers; Of 4. MOX BWR damaged fuel assemblies placed in damaged fuel containers; or 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.


D. Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC-68. The Antimony-Berylium neutron source material shall be in a water rod location.

A-13

I


Fr Sr : Aweld

S, = 4.012 x 104 Ibf in


Mx Sby

Sxx

My Sbx MY

Syyb

Sb :Sbx + Sby

Sby = 1.337 x 104 lbf in

Sbx = 8.307 x 104 lbf in

Sb = 9 .6 4 4 ×x 104 bf in


W Mz.

St.- Jw StS=7.148x 103 -

in The net force/unit of weld throat thickness is computed as a root mean square

Seq := [ Sb2 + (Sr+ St)21 0 "5 Seq = 1.074 x 105 ibf in


Seq treq -

(T ytreq = 3.187in


Rev. 9

0000 0000 0000 0000

+ +I

0000 0000 0000 0000 0000 0000 0000 0000

u0.03 15" (typ.) 0.228" (typ.)

5.39"-q - -

MCNP Model of QUAD+ Assembly with Dimensions

0000 0000 0000 0000

ýWater

0.055" 4-





a. Cladding Type:

b. Composition:



e. Post-irradiation Fuel Cooling Time and Average Burnup Per Thoria Rod Canister:






k. Canister Weight:

Zircaloy (Zr)

98.2 wt.% ThO2 , 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 2-U.

< 18

< 115 Watts

A fuel post-irradiation cooling time > 18 years and an average bumup < 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches


B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister plus any Any combination of damaged fuel assemblies in damaged fuel containers and intact fuel assemblies, up to a total of 68.



A-6





Zircaloy (Zr)a. Cladding Type:

b. Composition: 98.2 wt.% ThO2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 2-U.









k. Canister Weight:

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches







A-13


Fr Sr : Aweld

10 lbf Sr = 4.012 x1

in


Mx Sby

Sxx

My Sbx M=y

Syyb

Sb :Sbx+Sby

Sby = 1.337x 104 IV in

Sbx = 8.307 x 10 4 lbf in

Sb = 9 .6 4 4 x 104 lbf in


U;

Mz.--2

o-t Jw St = 7.148 x 103 lbf

in


Seq = 1.074 x 105 lbf in


treq = 3.187 in


Rev. 9

Seq := [ S b2 + (S r + St)2]0"

Seq t r e q - -

C~Y

0 0 0 00000 100000 0 0 0

0 0 0 00000 00000 0 0 0

J +

0000 0000 0000 0000 0000 0000 0000 0000

0.0315" (typ.)

0.228" (typ.)

_L, 5.39"

J,/,Water


0.055" 4-





a. Cladding Type:

b. Composition:






h. Fuel Cladding LD.:

L Fuel Pellet O.D.:


k. Canister Weight:

Zircaloy (Zr)


< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches


B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister plus any Arty combination of damaged fuel assemblies in damaged fuel containers and intact fuel assemblies, up to a total of 68.


Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC68. The Antimony-Berylium neutron source material shall be in a water rod location.

A-6

D.



I/l. MPC MODEL: MPC-68F (continued)


Zircaloy (Zr)

98.2 wt. % ThO2 , 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 235U.









k. Canister Weight:

< 18

< 115 Watts

A fuel post-irradiation cooling time > 18 years and an average burnup < 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches




1. Uranium oxide BWR intact fuel assemblies; 2. MOX BWR intact fuel assemblies; 3. Uranium oxide BWR damaged fuel assemblies placed in damaged fuel containers; oe 4. MOX BWR damaged fuel assemblies placed in damaged fuel containers; or 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.




A-13

a. Cladding Type:

b. Composition:


Fr Sr := -Aweld

Sr = 4.012 x104 lbf in


Mx Sby

Sxx

My

Sbx MY

Syyb

Sb := Sbx + Sby

Sby = 1.337 x 1 04 lbf in

Sbx = 8.307 x 10 4 1bf in

Sb = 9 .6 4 4 x 104 lbf in


WMzo

2

Jw St=7.148x 103 lbf in


Seq := [ Sb2 + (Sr + St)22]"' Seq = 1.07 4 x 10-5 bf in


Seq treq

G ytreq = 3.187 in


Rev. 9

0000

0000

0000

IFr H I ) I _____

0 00000 0000

0 0

0000 0000 0000 0000 0000 0000

0.0315"(typ.)

0.228" (typ.)

5.39"

0 0

�'- I

,Water

"Zr

0.055" 4-


0000

0

0 0





a. Cladding Type:

b. Composition:






h. Fuel Cladding lD.:

L Fuel Pellet O.D.:


k. Canister Weight:

Zircaloy (Zr)


< 18

< 115 Watts

A fuel post-irradiation cooling time > 18 years and an average bumup < 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches





A-6



I/. MPC MODEL: MPC-68F (continued)

7. Thoria rods (ThO. and U0 2) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:









k. Canister Weight.

Zircaloy (Zr)

98.2 wt. % ThO2, 1.8 wt. % U0 2 with an enrichment of 93.5 Wt. % 2-U.

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches




1. Uranium oxide BWR intact fuel assemblies; 2. MOX BWR intact fuel assemblies; 3. Uranium oxide BWR damaged fuel assemblies placed in damaged fuel containers; mf 4. MOX BWR damaged fuel assemblies placed in damaged fuel containers; or 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.


D. Dresden Unit 1 fuel assemblies with one Antimony-Betyllium neutron source are authorized for loading in the MPC-68. The Antimony-Berylium neutron source material shall be in a water rod location.

A-13


Fr Sr : Aweld

Sr = 4.012 x 104 Ibf in


Mx Sby :=

Sxx

My

Syyb

Sb := Sbx + Sby

Sby = 1.337x 10 4 1bf in

Sbx = 8.307 x 10 4 bf in

Sb = 9 .6 4 4 x 10-4 IV in


WMzW-

2 St

Jw St = 7 .14 8 x 103 lbf in


Seq := [Sb2 + (Sr+ st)+ °0 Seq = 1.074 x 105 lbf in


Seq treq : =

CyYtreq = 3.187in

2. R-7HI-STAR SAR Report HI-951251

Rev. 9

Sbx :=

U ____________ I ____________ I ____________ T rr�=..TT 1 T r

0 0 0 00000 00000 0 0 0

0000 0000 0000

0000 0000 0000 0000 0000 0000 0000 0000

0.228 0.228"

0315" (typ.)

(typ.)

5.39"

0 ,Water

" Zr

0.055""-q


0 0 0





a. Cladding Type:

b. Composition:







L Fuel Pellet O.D.:


k. Canister Weight:

Zircaloy (Zr)


< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches



Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68.

Dresden Unit 1 fuel assemblies with one Antimony-Beryllium neutron source are authorized for loading in the MPC68. The Antimony-Berylium neutron source material shall be in a water rod location.

A-6

C.

D.




7. Thoria rods (ThO. and UO) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:

Zircaloy (Zr)

98.2 wt. % ThO2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 2-U.









k. Canister Weight:

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches







A-13


Fr Sr : Aweld

Sr = 4.012 x 104 IV in


Mx Sby

Sxx

My Sbx My

Syyb

Sb := Sbx + Sby

Sby = 1.337 x 10 4 lbf in

Sbx = 8.307 x 10 4 lbf in

Sb = 9 .6 4 4 x 10-4 IV in


W Mz*

2 St. Jw St = 7.148 x 103 lbf

in


Seq := [Sb2 + (Sr + St)21 0 "5 Seq = 1.074 x 105 lIV in


Seq treq -=

aYytreq = 3.187 in


Rev. 9

0000 0000 00000 0 0 0

0000 0000 0000 0000 0000 0000 0000 0000

L00315" (typ.) 0.228"

(typ.)

5.39"

/ Water

0.055"U �I I. U-


0000 0000 0000

0 0 00



IL MPC MODEL: MPC-68 (continued)


a. Cladding Type:

b. Composition:






h. Fuel Cladding l.D.:



k. Canister Weight:

Zircaloy (Zr)


< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches


B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister plus any Ay combination of damaged fuel assemblies in damaged fuel containers and intact fuel assemblies, up to a total of 68.



A-6





Zircaloy (Zr)

98.2 wt.% Th0 2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 23U.









k. Canister Weight:

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches

< 550 lbs, including fuel



1. Uranium oxide BWR intact fuel assemblies; 2. MOX BWR intact fuel assemblies; 3. Uranium oxide BWR damaged fuel assemblies placed in damaged fuel containers; Of 4. MOX BWR damaged fuel assemblies placed in damaged fuel containers; or 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.




A-13

a. Cladding Type:

b. Composition:


Fr Sr : Aweld

Sr = 4.012 x 104 -bf

in


Mx Sby

Sxx

Sbx My Syyb

Sb := Sbx + Sby

Sby = 1.337x 1 04 Ibf in

Sbx = 8.307 x 10 4 lbf in

Sb = 9 .6 4 4 x 10-4 IV in


W Mz-

2 St : Jw St = 7 .14 8 x 10 3 lbf

in


Seq := [ Sb2 + (Sr + St)2 ] 0 5 Seq = 1.074 x 105 lbf in


Seq treq - -

aYytreq = 3.187in


Rev. 9

0 0 0��=irr I ____________

00000 00000 0 0 0

0 0 0 00000 i0000

0 0 0+

00 0 0000 0000 0000 0000 0000 O0 000 0000

0.0315" (typ.) 4-

0.228" (typ.)

5.39"

/ Water

0.055"


0



IL. MPC MODEL: MPC-68 (continued)

5. Thoria rods (ThO 2 and UO') placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:







i. Fuel Pellet 0. D.:


k. Canister Weight:

Zircaloy (Zr)

98.2 wt. % ThO 2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 2-U.

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches


B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister plus anyAnty combination of damaged fuel assemblies in damaged fuel containers and intact fuel assemblies, up to a total of 68.



A-6



Ill MPC MODEL: MPC-68F (continued)


a. Cladding Type:

b. Composition:









k. Canister Weight.

Zircaloy (Zr)

98.2 wt. % ThO2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 235U.

< 18

< 115 Watts

A fuel post-irradiation cooling time > 18 years and an average bumup <. 16,000 MWD/MTIHM.

< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches




1. Uranium oxide BWR intact fuel assemblies; 2. MOX BWR intact fuel assemblies; 3. Uranium oxide BWR damaged fuel assemblies placed in damaged fuel containers; or 4. MOX BWR damaged fuel assemblies placed in damaged fuel containers; or 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.



A-13


Fr Sr :

Aweld

Sr = 4.012 x 104 lbf in


Mx Sby

My Sbx My

Syyb

Sb :=Sbx +Sby

Sby = 1.337 x 104 lbf in

Sbx = 8.307 x 10 4 lbf in

Sb = 9 .6 4 4 x 104 lbf in


W Mz.

2 St

Jw St = 7 .14 8 x 103 IV in


Seq := [ Sb2 + (Sr + St)2]•0 5Seq = 1.074 x 105 lbf

in


Seq tre q : =

(TYtreq = 3.187in


Rev. 9

0 0 0 00000 0000 0000

0000 0000 0000 0000

+

j49O0315" (typ.) 0.228"

(typ.)

5.39"


0000 0000 0000 0000

/

0000 0000 0000 0000

.1:

,Water

\,ý Zr

0.055" 4--

11

5





a. Cladding Type:

b. Composition:









k. Canister Weight:

Zircaloy (Zr)

98.2 wt.% ThO 2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 23U.

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches


B. Quantity per MPC: Up to one (1) Dresden Unit 1 Thoria Rod Canister plus any Ay combination of damaged fuel assemblies in damaged fuel containers and intact fuel assemblies, up to a total of 68.



A-6




7. Thoria rods (ThO2 and UO) placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

Zircaloy (Zr)








i. Fuel Pellet 0. D.:


k. Canister Weight:

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches




1. Uranium oxide BWR intact fuel assemblies; 2. MOX BWR intact fuel assemblies; 3. Uranium oxide BWR damaged fuel assemblies placed in damaged fuel containers; ef 4. MOX BWR damaged fuel assemblies placed in damaged fuel containers; or 5. Up to one (1) Dresden Unit 1 Thoria Rod Canister.



A-13

a. Cladding Type:

b. Composition:

I I


Fr Sr:=

Aweld

Sr = 4.012 x 104 -bf

in


Mx Sby

Sxx

My

Sbx My

Syyb

Sb :Sbx + Sby

Sby 1.337 x 1 in

Sbx = 8.307 x 104 1IV in

Sb = 9.644 x 10 lbf in


w Mz*-m 2

St : Jw St = 7.148 x 103 Ibf in


Seq "= [ Sb2 + (Sr + St)2 ]"' Seq = 1.074 x 105 Ibf in


Seq tre q : =

(Y ytreq = 3.187in


Rev. 9

T �fl=ifl I

0 0 0 00000 00000 0 0 0

0 0 0 00000 00000 0 0 0

0000 0000 0000 0000 0000 0000 0000 0000

. 0.0315" (typ.)

0.228" (typ.)

5.39"

/Water

` Zr


0.055"


Table A. 1 (continued) Fuel Assemblv Limits


5. Thoria rods (ThO 2 and UO placed in Dresden Unit 1 Thoria Rod Canisters and meeting the following specifications:

a. Cladding Type:

b. Composition:









k. Canister Weight:

Zircaloy (Zr)

98.2 wt.% ThO 2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 235U.

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches





A-6



IlL MPC MODEL: MPC-68F (continued)


Zircaloy (Zr)

98.2 wt. % ThO 2, 1.8 wt. % U0 2 with an enrichment of 93.5 wt. % 2-U.







L Fuel Pellet 0.D.:


k. Canister Weight:

< 18

< 115 Watts


< 27 kg/canister

> 0.412 inches

< 0.362 inches

< 0.358 inches

< 111 inches

< 550 lbs, including fuel






A-13

a. Cladding Type:

b. Composition:

I

I

hi-star 100 transportation coc 9261 license amendment

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