ML20245D983

Certificate of Compliance 5942,Rev 14,for Model 700

ML20245D983
Person / Time
Site:	07105942
Issue date:	04/18/1989
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20245D973	List: ML20245D970 ML20245D983
References
NUDOCS 8905010257
Download: ML20245D983 (8)

Text

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ame r'onar ets U.S. NUCLEAR REGULATORY COREINSSION cow CERTIFICATE CF CUMPLIANCE

"""" FOR RADIOACTIVE MATERIALS PACKAGES tt REVIS80N NUhelER c, PACKAGE 4DENTWICATION NUMHER d PAGE fAJMBER e. TOT AL NUMBER PAGES L T 1 1.4 CERTFT4hNUMBER S 14 USA /5942/B( )F 1 5 1

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a. Tha certificate m issued to certsty that the packagmg and contents described in item 5 be6ow, meets the appicab6e safety standards set forth in Title 10. code of Federal Regulations. Part 71.* Packaging and Transportation of Radioactive Matenal.*

tt The ceraficate does not reiseve the consegnor from comphance wrth any requirement of the regulations of the U.S. Department of Transportation or other applecable regulatory agercaes. includmg the govemment of any country through or 6nto which the package unit be transported.

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1 General Electric Company General Electric Company application dated

Vallecitos Nuclear Center dated May 30, 1985, as supplemented.

Pleasanton, CA 94566 rm -

,, n F (71-5942 a ooe n ,tana n i or io crR enri 73, as agiscahe."ada condmore spec *ed t* .

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(a) Packaging ( ,>,

(1) Model-No.: .700 , m. Q

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(2) Description

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A steel encasedllt:od' shielded shipping' cask enclosed by a double-walled protective jacket-of'the same-shape with a rectangular baseplate. The cask 'is a double-walled steel circular cylinder,-37-irich-diameter by 65-inch high with a . central cavityil5-inch-diameter by. 40-inc.h high.

Approximately '10.25 inches of pleadssurround the central cavity. The cask is equipped with a cavity; drain'line, pressure relief valve set at 100 psig,andliftingdevice.jClosure.isaccomplishedbyfasiliconerubber gasketed and bolted steel leadifilled plug. The maximum gross wei the package (contents, cask assembly,,$rotective jacket andisbase) ght of 35,500 pounds.

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Thecaskmay'bemodifiedwith'a)14-inchhighcavityextensionwithan additional silicone rubber gasket. The modif.ied cask is 79 inches high.

The maximum gr'oss weight of the package;(contents, modified cask assembly, protective jacket e'nd base).is.40,200' pounds, rs y em (3) Drawings The packaging is constructed in accordance with the following General Electric Company Drawing Nos.: 129D4768, Rev. 3; 12904769, Rev. 4t and 129D4770, Rev. 6.

Lifting and/or tie-down devices which are a structural part of the package must be in accordance with the above drawings.

8905010257 890418 PDR ADOCK 07105942 C PNU

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Page 2 - Certificate No. 5942 - Revision No. 14 - Docket No. 71-5942 I I I I I I

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5. (b') Contents l (1) Type and form of material i (1) Byproduct, source, and special nuclear material as solid oxide or I metal in the form of fuel rods, or plates, fuel assemblies, or l l meeting the requirements of special form radioactive material.

l (ii) Co-60 metal contained within sealed liner ant sleeve described in i l Neutron Products, Incn Draing Nos. 240139, Sheets 1 through 3,

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1 I Revision No. F M40138; Rdv;iQd o .

1 (2) Maximum quanti (ygf' material per package l Nottoexce'ed700 pounds (includingshoring),an#$/'N  !

I ry  %# p

'( i) 7 0, gin U-235, provided that the maximum U-235 eh,richment does not eceed6Neightpercent;or / 'd (

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' materialthe'fu is*in the form of l

(ii) [}1[,200 gm U-135,fprovided-that iTR-type fuel elements Vjth'a; minimum active fuel' length of 23 g

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(iii)b?20gm, fissile _ mater.ial;or

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,i (iv)(f)650gmU-235,providedthat;themaximu'mU-235enrichmentdoes 1, i not exceed 3.5 weight percent and the fuel, material-is in the l-form of 88 rods loaded with10.376-inch-diameter pellets with a I I

minimum v activs, g

fuel-length of 37dnches; or , Go - t u j _ ,

(v) tho'sk,valuespres'dntedinFigure1$'U0,,WeightOmitsforModel700 l Shipping Container, of-Exhibit A to this application, applicable I to fuel material in the form of rods with a' minimum pellet diameter I

of 0.40 inch; or O I

(vi) 5,100 gm U-235'Y'_

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, pro'videdsthe fel isln the form of ETR-type fuel (

a j elements (GETR Fuel) with each e?ement containing no more than [

] 510 gm U-235 and inserted in the spaced stainless steel fuel i shipping basket described in GE Drawing No. 10604150, Rev. 0.; or I i

1 (vii) 6,200 gm U-235, provided the fuel is in the form of MURR TRTR type elements containing not more than 775 gm U-235 per element;

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] loaded and spaced in the stainless steel fuel shipping basket as i 1 J described in MURR Drawing No. 1228, Sheets 1 thru 5, Revision 0. I J Fuel elements shall have at least 150 days cooling time since i J last reactor operation; or I J

(viii) 3,510 gm U-235 provided the fuel is in the form of MTR-type fuel n elements with each element containing no more than 351 gm U-235 and inserted in a spaced stainless steel fuel shipping basket I described in GE Drawing No. 106D4150, Rev I for GETR fuel. A I

, shoring device to limit vertical motion of the fuel elements must l be included; or p l-Lk

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g CONotTIONS (continued) o 1 l l l Page 3 - Certifica m No. 5942 - Revision No. 14 - Decket No. '/1-5942 i I I l l

5. (b) (2) (continued) l ('

! (ix) 7,020 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 h I inserted in a spaced stainless steel fuel shipping basket described l in GE Drawing No. 106D4150, Rev. 1, for 24-inch length fuel. [

Each shipment must contain 20 fuel elements in 2 fuel baskets l with the spacer plate shown on GE Drawing No 21886061, Rev. 0, f

, l l located between the baskets. A shipment may contain less than 20 I i elements provided each. absent-element is replaced by an aluminum [

l or steel spacer'ihthe\.foFm of snfopen-ended pipe with a minimum i I outer diameter 4f'2.5 inches and' a ininimum wall thickness of I i 0.125 inchesP The space must be of sufficient length to replace '

l the abs'ent' fuel elemen',;or # /s l l & f% l l (x) 7,000;tm U-235 provided the fuel is in the forni of MTP-type fuel L i sections with each section containing no more than 175 gm U-235 l

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ijserted into the o stainless steel Cask: Divider (fubl shipping (g I

basket) shown"in General Electric Company: Drawing No.183C8253, [.

jRev.1. When a" shipment-contains'less than the maximum number g i (40) of fuel' sections, empty fuel section basket spaces must be t I cprovided with anfaluminum or steel! spacer in the form of an open- t i , ended pipe with a minimum outer diameter of 2.5 inches and a L I rminimum wall thickness of 0.125 inches. The spacer must be of I l rsufficient v .

len'gth-to replace the absent fuel sections; or f.

- 1 ,; g i (xi) 6,300 gms U-235' provided the fuel is in the form of MTR-type f i fuel elementsror sections with each fuel element or section L i having an average -linear density .of no more than 13 gms U-235 per inch of' length. ,Each fuel element or section~is inserted into f l i j the. stainless steel cask divider shown in General Electric g i Company Drawing No. 183C8257, Rev. O. When a shipment contains L

! less than the maximum number of fuel elements and fuel sections, E l empty fuel basket spaces must be provided with an aluminum or steel I i spacer in the form of an open-ended pipe with a minimum outer [

! diameter of 2.5' inches erd a minimum wall thickness of 0.125 g l inches. The spacer must'be t,f sufficient length to replace the t i absent fuel assembly and sectians. E l  !

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(l l CONDITIONS (continued) l l l

Page 4 - Certificate No. 5942 - Revision No. 14 - Docket No. 71-5942 l '

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5. (b) (3) Maximum quantity of radioactive decay heat per package l

! (i) 6,500 watts for dry shipments, or g i i I (ii) 1,500 watts for wet shipments, provided that the cavity shall I I contain at least a 1,000 cu in air void (at standard temperature I l and pressure) at the time of delivery to a carrier for transport. l l 1 i (c) Fissile Class III i l 1 p r- l I

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Maximum numbery ofy packages ker[shipmsnt' / f 2 () G r, l The liner required for CS60' metal which does not mee't-thie requirement for I l 6. special form radioact i

with an inert gas in..aive material, must be dried, leak2tested, and Products, back-filled l l ccordance with Enclosure 2, Rev. to Neutron I I Inc. letter dated February 28, 1986. 5i> b l Q; $ .

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7. Shoring must be:p[ovided'to ' minimize movement of coritenti durinficcident conditions  !

i of transport. / -

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. ll l 8. Prior to each shipment (exceptifor; contents. meeting the requirements of special R 4 form radioactive material),.the pack be leak tested by a method capable of determining that a. leakage ofatm 10~gge cm musj/s,at standard temperature and l l a g pressure is not exceeded. j i 4 c 1, i 9. Prior to each shipment the. silicone rubber' lid gasket (s) must be inspected. 1'1 i This gasket (s) must be replaced if. inspection shows any defects or every I i 12 months, whichever occurs first. -' Cavity drain line must be sealed with l l appropriate sealant applied to threads of pipe plug. g; i l '

i 10. The applicant must c'onfirm annually that the pressure relief valve is operable 1 l at 100 psig. I I I

! 11. When needed, sufficient antifreeze in the cask must be u' sed to prevent damage of l l any component of the package due to freezing, y i I i 12. Fabrication of additional packagings is not authorized. I I

l 13. The package authorized by this certificate is hereby approved for use under the l general license provisions of 10 CFR 571.12. l l

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!' l 14. Expiration date: July 31, 1390. I I I i

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"*: m 6m U S. fiUCLEAT5 REGUtlTC EY CLim 55t04 CONDmONS (continued)

Page 5 - Certificate No. 5942 - Revision No. 14 - Docket No. 71-5942

! REFERENCES General Electric application dated May 30, 1985.

General Electric supplements dated: June 5 and 7, August 7, and September 16, 1985; February 28, May 8, July 11, August 15, and Nover/aer 26, 1986; and December 13, 1988 and April 15, 1989.

University of Missouri letter dated March 20, 1980.

Appendix considered part 6-Aofregarding this applicatio University

' kfhhyf assurance program is not fjshuri.

Neutron Products, Inc. supplenients dated: November 11,1985;*and C#V 4. February 28, March 11 and 31, April 1 and 10, QB6'.

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as OQ N FORTHEU.S.NUCLEARREGULAT03)Y:  ?' -/

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E M f Charles E.rMa'c onald, Chief u

i OY? i Transportation, Certification Bra (tich

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,4 O.r M y, i % Division 1.?N of Fuel.WNMSS Material-Safety Cycle and , .

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Transportation Branch Approval Record Model No. 700 Docket No. 71-5942 Revision 14 By application dated December 13, 1988, General Electric Company (GE) requested an amendment to Certificate of Compliance No. 5942 to eliminate the pressure relief valve from the Model 700 shipping cask. The amendment also requested that the option to make wet shipments be eliminated.

3y supplement dated April 5,1989, GE withdrew its request to eliminate the pressure relief valve and authority to make wet shipments. The April 5, 1989 supplement also requested minor design changes to repair a crack in the weld between the pressure relief line and cask lid that. developed in one of GE's two Model 700 casks. This would be accomplished by replacing the cask vent tube in the lid and welding a second steel plate to the bottom of the lid. Staff has determined that the proposed change does not affect the ability of the cask to meet the requirements of 10 CFR Part 71. The proposed change is shown as an optional feature (Detail B) on Drawing No. 129D4770, Rev. 6.

n Charlesf.MacDonald,& $./ Chief Transportation Branch Division of Safegucrds and Transportation, NMSS AFit 1 6 W s Date-l 1

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