ML20132A875

Certificate of Compliance 5942,Rev 10,for Model 700.Approval Record Encl

ML20132A875
Person / Time
Site:	07105942
Issue date:	09/18/1985
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20132A872	List: ML20132A868 ML20132A875
References
NUDOCS 8509260045
Download: ML20132A875 (6)

Text

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i.___----------------------------------------------9 I mic ronu' sis U.S. NUCLEAR REIULATORY CcMMISSION k i seu CERTIFICATE OF COMPLIANCE k I seco n FOR RADIOACTIVE MATERIALS PACKAGES I' to ceRTiricATe NUMBER ti REvtsloN NUMBER c. PACKAGE aOENTIFiCATION NUMBER e PAGE NUMBER e ToTAt NUMaER PAGEs l 5942 10 4

USA /5942/B( )F 1 y I z paeauste l' I a. Tnis certificate is issued to certJy that the packasmo and contents desenbed in item 5 below. meets the appi cable satety standards set forth m T tie io, code 5 g of Federal Regulations. Part 71, Packaging and Transportateon of Radeoactive Matenat"  %

I b. This certihcate does not relieve tne consegnor from compsiance with any requirement of the reguistions of the u s. Deoartment of Transportation or other k appicable regulatory agencees. encludeg the govemment of any country through or mto which the package will be transported.

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a ries,gwicAysissyUrrNe sAsis or A sArciv ANAtysis,RegTgr,NggeysgoR Aretic,Ar ou  ;

I I I General Electric Company General Electric Application dated May 30, 1985, I P.O. Box 460 as supplemented. l l Pleasanton, CA 94566

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i 4 . c. ooc er NUwe R 'i 71-5942 i a CoNotraoNs 4 l This certificate es conditional upon fulfeiling the requerement'#s of 10 CFR Part 7t. as appicable, and the cor@tions specshed below. I i I i s~ i g (a) Packaging ,l g i >

l (1) Model No.: 700 i I (2) Desckiptio'n[

b g ,4 . 3 i Of x A~ Mn i I A; steel encased-lead shielded shippingicask enclosed"by a double- f I walled protective-jacket ofRthedsam,e, shape with a rectangular baseplate. I i cylinder, iJ7Ainch-diameter l The*

by~65-inch cask ishigh.witha double-palled ' steel circular;iich-diameter

'a centraldavity k 15-i by 40-inch l y

g high. Approximatelj+10'.25 inches [ofilead' surround the~ central cavity, g g Thescask tistequi ppediwi th'arcavi tytdrairilj ne vpressure" relief valve ~

I i s'et/at 1001psig, and < lifting !dev,iceWClosureiis accosplished by a b i silicone rubber gasket'ed}a'nd ;b61 tid ~ steel Hlead- filled plug. The i i maximum gross;weightlof!theppackage}(contents, cask l assembly, protective '

I jacketsand base) iis 35;500 poundsiC)4 fa 1 v >;. ~ , a ,,: s ~.. ,- l l The cask may be modified <with all4-16ch high cavitf; extension with an i I additional, silicone rubb'er/ gasket. The/ modified' cask is 79 inches i l high. The. maximum gross weight ~ of the package.,(contents, modified h i cask assembly; protective jacket and base) Tis 140,200 pounds. t I .i i i (3) Drawings ,>_4 4 r . ,, . . . I r

y s 1 -.  ; y c8 y~ y The packaging is constructed in accordance with the following General l l Electric Company Drawing Nos.: 12904768, Rev. 3; 12904769, Rev. 4; g g

g and 129D4770, Rev. 5. i i i I Lifting and/or tie-down devices which are a structural part of the i I package must be in accordance with the above drawings. I I I l l I I I I i i l l I I B5092600458509g8 l l PDR ADOCK 0710 l l C -

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• I CONoiTioNS (contenutd) l Page 2 - Certificate No. 5942 - Revision No.10 - Docket No. 71-5942 I

q 5. (b) Contents l

(1) Type and fom of material l

l Byproduct, source, and special nuclear material contained in solid y oxide or metal form and in special form.

I I (2) Maximum quantity of material per package H

Not to exceed 700 pounds (including shoring), and l

! (i) 740 gm U-235, provided that the maximum U-235 enrichment does not gl exceed 6 weight percent; or $

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(ii) 1,200 gm U-235, Iprovide'd - that th'e ifuel material is in the fom of l 8 MTR-type fuelfelements with a mininium, active fuel length of 23 i

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s' (iii) 220 g# fissile material; or )r-, lj 6

<O 1 (iv) 1,650 gin'U-235, provided that the maximun U f235 enrichment does I not#exceeds 3IS weight percent and'the'. fuel matirial is in the

! form of 88iods' loaded _with 0.376di ncfi-diametenpellets with a h / minimum act'ivelfuel length of /37/iiiches; or '"

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g. . / / \w; O p those valuei presentedhin Figurell,300,, Weight-Limits for Model '700 4 (v) [: Shipping' Container,4 0f Exhibit 'Asto this application, applicable l' <to fuel: material /inttheT fonniof~ rods .with;a minimum pellet diameter

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'of 0.40 inch;

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g! (vi) 5,1.00 gm U-535, phovideditheifu'elJisin the (form of ETR-type fuel i elements (GETR Fuel)dith each'51ement containing no more than Hlj 510-gin U-235 and inserted in theis;iaced stairiless steel fuel l ship'pifig, basket described in GE Diawing No? l06D4150, Rev. 0.; or H

g. (vii) 6,200 gm"il-235, provided the fuel is il the fom of MURR TRTR I type elements containing not moresthan 775 gm U-235 per element;

$ loaded and spaced in*the.stainles's steel fuel shipping basket as i described in MURR Drawing No.1228, Sheets 1 thru 5, Revision 0.

l Fuel elements shall have at least 150 days cooling time since y last reactor operation; or R

I (viii) 3,510 gm U-235 provided the fuel is in the form of MTR-type fuel I elements with each element containing no more than 351 gm U-235 1 'and inserted in a spaced stainless steel fuel shipping basket l described in GE Drawing No.106D4150, Rev. I for GETR fuel. A lE y shoring device to limit vertical motion of the fuel elements nust g be included.

I W I (ix) 7,020 gm U-235 provided the fuel is in the form of MTR-type fuel f I elements with each element containing no more than 351 gm U-235 inserted in a spaced stainless steel fuel shipping basket described j

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l i g in GE Drawing No.106D4150, Rev.1, for 24-inch length fuel. p p Each shipment must contain 20 fuel elements in 2 fuel baskets i i

1 with the spacer plate shown on GE Drawing No. 21886061, Rev. O, located between the baskets.

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7" l CONDITIONS (contanusd)

N Page 3' - Certificate No. 5942 - Revision No.10 - Docket No. 71-5942 l

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I i 5. (b) Contents (continued)

I lI (3) Maximum quantity of radioactive decay heat per package l (i). 6,500 watts for dry shipments, or M

i (ii) 1,500 watts for wet shipments, provided that the cavity shall E contain at least a 1,000 cu in air void (at standard temperature l and pressure) at the time of delivery to a carrier for transport.

(c) Fissile Class III al tj

.- 18 nh ,i:G Maximun number of packages per shipment Q 2

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6. The radioactive material'mst be in the fonn of fuel ~ rods, or plates, fuel f: assemblies, or meetf(gJ the requirements of special fona r'adioactive material.

7. Shoring must be pro ed-to minimize uvement of contents u ,ing accident conditions of transport.

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Prior to each shipment (except>for co _. _ .ntents mee ingithe require,ments of special i f orm radi oactive,nateri al ) tt:he4 pack liak tested by~s method capable j of determining 'that a leakage}of(10-gg'e'musg/d

,atm cm tEstandard temhratur pressure is not-exceeded.4 t'e, 3,D

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l i 9. Prior to each shipment easilidone yubt/rklidO}asket(s)'mustdh inspected.

i This gasket (s) must be lac 5d ifdipspectiongshows Lany'defedts' or every twelve

! (12) nonths, whichsver occiirslfirst.QCa'vityWrainQ11ne mstge sealed with

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l appropriate sealandapplieFtotth*re] ads {of ' pipe ugi ys Ol l: .> <r g ,o [-

l 10. The applicant must con'fyirm annually that'

the pre,ssure reljef valve -is operable a t 100 psig. / s

11. When needed, sufficient antifreeze any component of the package due#reezingt to,in the caskP Inust be used to prevent damage of

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12. Fabrication of additional packagings is not authorized.

l 13. The package authorized by this certificate is hereby approved for use under the g general license provisions of 10 CFR 971.12.

d i 14. Expiration date: July 31, 1990.

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l CONolTIONS (continucd)

E I Page 4 - Certificate No. 5942 - Revision No.10 - Docket No. 71-5942 1

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I I REFERENCES ,

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i General Electric application dated May 30, 1985. >

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g Supplements dated: June 5 and 7, August 7, and September 16, 1985.

4 i University of Missouri letter dated March 20, 1980.

i Appendix 6-A regarding University of Missouri's quality assurance program is not 3

l1 considered part of this application.

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a , rgTORTHEhu.S?NUCLEARREGULATORYCOMMISSION ,

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Charles .. MacDona d, Chief 4 , Ts Transportation Certification Branch 4 ,D Ypx Division of Fuel l> Cycle and"

@ AL/ Ygg N Material Safety,1tflSS .<-)

f' Date: SEP 181985 x

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• *k2 UCgj (o,, UNITED STATES Es o NUCLEAR REGULATORY COMMISSION 3 y WASHINGTON, D. C. 20555

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Transportation Certification Branch Approval Record Model No. 700 Package Docket No. 71-5942 Eiy application dated August 7,1985, as supplemented September 16, 1985, General Electric Company (GE) requested an amendment to the Model No. 700 cask to pennit the shipment of 20 MTR-type fuel assemblies.

The current fuel basket has been modified by reducing its height from 39.0 inches to 26.0 inches. Through the use of the previously approved

, 14-inch high cavity extension, two fuel baskets may be stacked within the modified cask. The fuel baskets are separated by a 0.188-inch thick 1 stainless steel plate.

GE did not provide a structural analysis for the stacked fuel baskets.

'However, even if some basket welds cracked with the cavity very tightly packed, the configuration of the fuel and basket components are not expected to change. The approval has been conditioned to require the shipment of a full load (20 assemblies).

GE has analyzed the criticality of both the 10 and 20 MTR-type assembly loadings in the Model 700 cask using KENO-IV, 27 neutron group cross-sections . An extremely conservative representation (September 16,1985) of the Model 700 cask for the 10 MTR-type loading gave a Keff of 0.92410.007.

This model assumed the lead too close to the stainless steel baskets at the top, bottom, and sides of the cask. The KENO-IV geometry option was used to represent the discrete fuel-plate / water regions, basket regions and outer regions of the cask and water reflector. For the 20 assembly loading in the Model 700 (August 7,1985), generalized geometry option was used to represent the discrete plate / water regions, basket regions, and shield reflector region. This model represented a realistic 700 cask with contents. It resulted in a keff of 0.88710.004.

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• The staff has performed homogenized calculations' (KENO-IV,123-group)

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for the 10 and 20 assembly loadings. In both cases, a 3x3 array of MTR-type assemblies within a steel basket (length of fuel array, 57.79 cms

. for 10 MTR-type assemblies; 115.57 cms for 20 MTR-type assemblies) represented the required loading with each assembly fissionable contant increased by 11% to account for 9 vs 10 and 18 vs 20 assemblies. Water, Pb, water reflector region surrounded the above basketed loadings. The keff for -10 assemblies was calculated to be 0.889+0.006; for 20 assemblies, the keff was 0.957+0.007.

Based on the above, the additional contents do not effect the ability of

! the package to meet the requirements of 10 CFR Part 71.

fa Charles E. MacDonald,' Chief 7 Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date: SEP18I!E5 t

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