ML20207S012

Certificate of Compliance 5942,Rev 13,for Model 700.Approval Record Encl

ML20207S012
Person / Time
Site:	07105942
Issue date:	03/13/1987
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20207S009	List: ML20207S008 ML20207S012
References
NUDOCS 8703180419
Download: ML20207S012 (7)

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1 E CERTIFICATE OF COf.1PLIANCE I to c,n "

FOR RADIOACTIVE MATERIALS PACKAGES !I i a c n.,,g n

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I ne==a I a in.. cwi.e cat. .. ..u.o io cert.#y mai m. pacnaging ano contents o crio.o in item s o.io.. me.i. in. appi cani. .ir sianoaraa ..i vorta in ritie to. coa. {ll t

l Of F.d.ral A.gulation.. Part Ft. Packaging ano tran.portation of Radioactiv. Mat.riai." !l 1 o. in . c.riivicai. oon noi r . m. con..gnor from comm.anc. ..m any r.ou.r.m.ni ce m r.guiai ons ce m. u s. o.oanm.ni ce iransportation or einer lI I appi.cani. r.guistory ag.nc . inciuo no m. go .en ni of any country inrougri or .nio n.cn in. pac.ag. ..ii n. iran oort.o. !I I lI l :I

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I I I General Electric Company General Electric Company application dated I I Vallecitos Nuclear Center dated May 30, 1985, as supplemented. I Pleasanton, CA 94566 l l

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a co,etio s i rn.. c.n.e. car. . cono. .ona upon evie.n.no m. ,.ou,r.m.ais oe io cFn Pan Fi. as som.cani.. ano m. cono i.on. c.#,.o n.io.

ll l , i I I l (a) Packaging I

I (1) Model No.: 700 1 I I (2) Description l l 1 I g A steel encased lead shielded shipping cask enclosed by a double-walled p

,1 protective jacket of the same shape with a rectangular baseplate. The l lI cask is a double-walled steel circular cylinder, 37-inch-diameter by i I 65-inch high with a centrai cavity 15-inch-diameter by 40-inch high. I I Approximately 10.25 inches of lead surround the central cavity. The cask is equipped with a cavity drain line, pressure relief valve set at 100 j

i l psig, and lifting device. Closure is accomplished by a silicone rubber I !n I Il gasketed and bolted steel lead filled plug. The maximum gross wei ll 1j the package (contents, cask assembly, protective jacket and base) is ght of;I j 35,500 pounds.

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The cask may be modiffod with a 14-inch high cavity extension with an additional silicone rubber gasket. The modified cask is 79 inches high, f.I i

t i The maximum gross weight of the package (contents, modified cask assembly, I protective jacket and base) is 40,200 pounds.

fI I II I (3) Drawings 'l I! lI I The packaging is constructed in accordance with the following Generai !I I Electric Company Drawing Nos.:

12904770, Rev. 5.

12904768, Rev. 3; 12904769. Rev. 4; and j

[ y i I I Lifting and/or tie-down devices which are a structural part of the (I l' package must be in accordance with the above drawings. jf I .I I fl I- jl I :I I ,1 1 I l' 0703100419 070313 P Dit ADOCK 07105942 !y

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• CON 0lTIONS (contmuod)

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I g i Page 2 - Certificate No. 5942 - Revision No.13 - Docket No. 71-5942 lg I g i

5. (b) Contents

! (1) Type and form of material  !

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

i l l (11) Co-60 metal contained within sealed liner and sleeve described in  !

I Neutron Products, Inc. Drawing Nos. 240139, Sheets 1 through 3, i I Revision No. F and 24_0138, Revision No. . I a a n .- rn l (2) Maximum quantity ofinaterial 'per'pic'k[g5/ I l u~ V7, g l l Nottoexceed700 pounds (includingshoring)./a,nd g 1 l , -

r g I (f) 740gmU-235,providedthatthemaximumUp235;enrichmentdoesnot I exceed 6 weight percent; or 3 l ,

l (if) 1,200 gm U-235, provided that the fuei materialmis in the form of l l MTR-type fuel: elements with a minimum active fuel length of 23 g I inches; or s p n ...a..~ m i j (iii) 220 gm fissile materia 1; or ,

g i i (iv) 1,650gmU-235,providedthat;themaximumU-235Nnrichmentdoes not exceed 3.5 weight percent: and the fuel material is in the 1 5

i form of 88 rods loaded with 0.376-inch-diameter pellets with a I n

j minimum active fuel length of 37 inches; or;' ,

l j (v) those values presented in Figure 1, U0,, Weight Limits for Model 700 Shipping Container, of Exhibit A to this. application, applicable Iln l

I to fuel material in the form of rods with a minimum pellet r.% meter I i of 0.40 inch; or -

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4 (vi) 5,100 gm U-235, provided the fuel is in the form of ETR-type fuel lI elements (GETR Fuel) with each element containing no more than 510 gm U-235 and inserted in the spaced stainless steel fuel j

shipping basket described in GE Orawing No.106D4150, Rev. 0.; cr lg p

jl8 (vil) 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, ll i

loaded and spaced in the stainless steel fuel shipping basket as jl described in MURR Drawing No. 1228 Sheets 1 thru 5, Revision O. h fuel elements shall have at least 150 days cooling time since jp last reactor operation; or ,p i8

'l (vift) 3.510 gm U-235 provided the fuel is in the form of MTR-type fuel l

q elements with each element containing no more than 351 gm U-M5 and inserted in a spaced stainless steel fuel shipping basket ?l

q. described in GE Orawing No. 10604150, Rev. 1 for GETR fuel. A 1 shoring device to limf t vertical motion of the fuel elements must  !

d' be included; or j 1.. .........

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CONDITlONS (continued) U ' " O *

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I[P{ge 3 - Certificate No. 5942 devision No.13 - Docket No. 71-5942 l l

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

(ix) 7,020 gm U-235 provideo the fuel is in the form of MTR-type fuel elements with each element containing no more than 351 gm U-235 l i

'l inserted in a spaced stainless steel fuel shipping basket described i in GE Drawing No. 10604150, Rev. 1, for 24-inch length fuel. I Each shipment must contain 20 fuel elements in 2 fuel baskets I with the spacer plate shown on GE Drawing No. 21886061, Rev. O, I located between the baskets. A shipment may contain less than 20 elements provided each absent element is replaced by an aluminum l y

or steel spacer in the form of an open-ended pipe with a minimum y outer diameter of,2.5, inches' and a minimum wall thickness of i 0.125 inches, cThei space' must'be(of, sufficient length to replace I the absent 4uel'elementior j sV VJ,o, (x) 7,000 gm.U-235 provided tre fuel is in the* form of MTR-type fuel l sections with each section containing no more. than 175 gm U-235 g i inserted into the stainless steel Cask Divideh (fuel shipping I I

basket) shown in General Electric Company Drawing No.183C8253, I l Rev. 1. When a . shipment contains' Tess than the maximum number I i (40) of fuel sections,rempty fuel 'section basket spaces must be l l provided with an aluminum'or steel spacer in the)fom of an open- y I ended pfpe with a minimum outer- diameter of 2.5 inches and a l I minimum wall thickness of 0.125-inches,f The spacer must be of I l sufficient. length to = replace. the absent' fuel sections; or j l l (x1) 6,300 gms U-235'provided' the' fuel is in the foNM of MTR-type fuel elements or, sections. with each fuel element or section i

l I having an average linear density of-no more-than 13 gms U-235 g I per inch of length. Each fuel element or section is inserted into I I the stainless steel cask divider shown in' General Electric I Company Drawing No. 183C8257, Rev. O. >When a shipment contains I l 1ess than the maximum number of fuel elements and fuel sections, q

empty fuel basket spaces must-be provided with an aluminum or steel l l y I spacer in the form of an;open-ended pipe with a minimum outer p 1

diameter of 2.5 inches and a minimum wall thickness of 0.125 I l I

l inches. The spacer must be of sufficient length to replace the 1 lg absent fuel assembly and sections.

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I Page 4 - Certificate No. 5942 - Revision No.13 - Docket No. 71-5942 ll1 i lI I

5. (b) (3) Maximum quantity of radioactive decay heat per package I l k l (f) 6,500 watts for dry shipments, or g l

l (ii) 1,500 watts for wet shipments, provided that the cavity shall l 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.

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! (c) Fissile Class III l

1 I I Maximum number of packages per shipmen _t 2 I I , n. C b- ' O ,

I l 6. The liner required for Co-60 metalw ' hich;d6es~no;t' meet the requirement for I  !

special form radioactive. material, must be dried, leak tested, and back-filled i l q with an inert gas in accordance with Enclosure 2, Rev: ,2't, Neutron Products, y i Inc. letter dated February 28, 1986. O i I i l .

T' ~ , . , -, -s p; , j l 7. Shoring must be prov'ided'to minimize movement of contents duffng accident conditions y

i of transport. i

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. l p 8. Prior to each shipment (exceptIfor contehts meet'ing :the requirements of special u I form radioactive' material), the pack be leak tested by a method capable I 8 of detemining that a leakage of 10!gge.mus[/s'at atm cm standard temperature and 1 J, pressure is not exceeded'.- "-

,' y l ll 9. Prior to each shipment the siliconeJrubber 11d gasket (s) musbe inspected.

This gasket (s) must be replaced-if. inspection:shows any defects or every u

I 12 months, whichever occurs first. Cavity drain line must'be' sealed with I j appropriate sealant applied to threads.of pipe plug.

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s l 10. The applicant must confirm annually that' the pressurecre1fef valve is operable l g at 100 psig. '

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l N 11. When needed, sufficient antifreeze in the cask must be used to prevent damage of I any component of the package due to freezing.

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.l l 12. Fabrication of additional packagings is not authorized. l 1

i 13. The package authorized by this certificate-is hereby approved for use under the lh p

d general license provisions of 10 CFR 571.12. ia I il l 14. Expiration date: July 31, 1990. j i i I E R ,5 I 'l N 5 i

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! Page 5 - Certificate No. 5942 - Revision No.13 - Docket No. 71-5942 l l l l l l REFERENCES I I  !

'g l General Electric application dated May 30, 1985. l l l l Supplements dated: June 5 and 7, August 7, and September 16, 1905; and February 28, i l May 8, July 11, August 15, and November 26, 1986. g I I l University of Missouri letter dated March 20, 1980. j

! Appendix 6-A regarding University of Missouri's quality assurance program is not l l considered part of this application. y l . Q iQ :: p - l l

Neutron Products, Inc. supplementsrdated:' NovembeF 11;jl985; and February 28, March 11

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, and 31, and April 1 and 10, 1986. , 7 syj s I y V < fs

,O FOR THE U.S. NUCLEAR REGULATORY COMMISSION l

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l Charles t Macdonald, Chief

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y I MAR 131987 'r i Date: ,

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• Transpcrtation Certification Branch Approval Record Model No. 700 Package Docket No. 71-5942 By apolication dated November 26, 1986, General Electric Company (GE) requested an amendment to the Model No. 700 package to pemit the transportation of up to 6,300 gm U-235 in MTR-type fuel sections or elements. Each fuel section-or eleuent contains no more than 13 gm U-235 average linear density per inch of length and is inserted in a stainless steel cask divider shown in GE Drawing No. 133C8257, Rev. O.

STRUCTURAL The applicant has performed analysis to show that the cask divider will not fail due to 30-foot free drop of the package. We agree with the applicant's conclusion that the cask divider will be able to maintain its loaded configuration under the hypothetical accident conditions of transport.

CRITICALITY GE has established (see application dated February 28,1986) the subcriticality of the Model No. 700 package when loaded with fuel in the fom of MTR-type fuel sections, with each section containing no mere than 175 gms U-235 inserted in a spaced stainless sceel fuel divider (0.1875-inch vs actual 0.25-inch (less reactive) thick lis) with the total fissionable loading not to exceed 7,000 (vs actual 6,300) gms U-235.

The KENO IV code with the 27-group neutron cross-section set was used with generalized geometry to describe the flooc!ed loaded package in the ten (four sections each) fuel divider locations. The lead reflector followed by a water all-around reflector was modeled in the criticality calculation.

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2 Two flooded packages in contact and surrounded by water reflector were calculated:

(a) Fuel / water in each divider pushed as close to one another towards center; Max keff = 0.928 (av. keff = 0.892).

(b) Fuel / water in each divider pushed out towards lead reflector; max keff =

0.869 (av. keff = 0.834).

Also calculated to estimate homogeneous vs heterogeneous modeling of fuel; 2 cases of 4 fuel dividers as a 2 x 2 array:

(a) Discrete fuel plate-water modeling - keff = 0.726 (b) Homogeneous fuel plate-water modeling - keff = 0.724.

The NRC staff has analyzed 9 fuel locations (3 x 3 array) homogenized U-235/H 2O regions with cask divider with a total of 7,734 gms U-235 vs a total of 6,300 gms U-235 actually in the divider. The staff KENO IV (123-group) (NUREG/CR-0200) analysis gave a keff of 0.976 i 0.007, which when normalized to 7,000 gms U-235 would reduce to a keff of 0.976 - 0.033 = 0.943 versus 0.924 which is in good agreement with the previous GE calculations.

The certificate has been conditioned to require appropriate aluminum or steel pipe spacers when a shipment contains less than the maximum number of fuel assemblies or sections. This is consistent with previous approvals for the same fuel.

The applicant and the NRC staff have concluded that the revised packaging and contents meet the requirements of 10 CFR Part 71.

. Charles E. MacDonald, Chief Transportation Certification Branch Division of Fuel Cycle and Material Safety, NMSS Date:

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