ML20059L066

Certificate of Compliance 5980,Rev 12,for Model GE-600

ML20059L066
Person / Time
Site:	07105980
Issue date:	09/19/1990
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20059L064	List: ML20059L060 ML20059L066
References
NUDOCS 9009260090
Download: ML20059L066 (4)

Text

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.emisenum u.s.wucLaAn neoutAvony connneseow i

CERTIFICATE CF COMPUANCE oam.

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POR RADWACTIVE 04ATERIALS PACKAGES

i. cenTwicars,*mseen

. neveion muusta

" Thaos icewtisication wuuman

. paoa wumeen. toint nom.ia enois i

I 5980 12 USA /5980/Bf 1F 1

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na.c.i.. u io c.na m.i m. p.cs.eine.no coni.ni. e c a in n.m s i io.. rno.. m..m.c.. i r.i.no.ro. iionn mtiti. 50.cw.

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n.iion o, w et,...e it Thi. Certific.t. 000, not role.v. th. con.ignor leom comoh.ne..ith.ny requirement of th. regul.teon. of th. U $ D.P.rtment of f r.n.pon.tson or other l

wic.oi. r.eui.iory.,ene

. incipaine m. oo.rnm.ni of.ny couniry mrouen or enio.h ch m. p.ca.

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1w,sgeng, cays _es,uyrTut asis o, a s*rerv Ahatvais negt,o,r,1, e ggo,e cesgogojaaeg g,

4 General Electric Company General Electric Company application dated Vallecitos Nuclear Center February 27, 1990, as supplemented.

Pleasanton, CA 94566

. meurt wu"*5a 71-5980 a coNottloN.

Thi. c.rtthe.t. is condellon.1 upon, fulfilling th. requir.rn.nts of 10 Cp R P.rt 71....pphe.bl.,.nd tn. conditions.poetti.d b.io..

6 (a) Packaging (1) Model No.: GE-600 y

e (2) Description l:'

A steel-encased lead shielded shipping cask. The basic cask body is 1

a cylinder 34 inches in diameter by 59.12 inches h19h formed by two-concentric steel shells whose annular region is filled with 6 iriches of lead. The cavity is 20-1/2 inches ID by G inches high, 3/8-inch h'

thick stainless steel cylinder.

A recessed pleg-type cask lid,

[i consisting of a steel weldment filled with lead, is secured to the L

cask body by six 1-inch diameter steel bolts..A silicone rubber gasket provides the seal. A protective jacket consisting of a double-walled structure of 1/2-inch thick carbon steel plates is i,

placed over the cask and bolted to a steel pallet by eight 2-inch diameter steel bolts. The cask has one 1/2-inch diameter drain line 1

from the cavity to the outer shell. The cask is shipped in the Lpright position. The total weight of the package is approximately 26,200 pounds when loaded.

l (3) Drawings I>

The packaging is constructed in accordance with the following General Electric Company Drawing Nos.:

129D4742, Rev. 4; 129D4743, Rev. 1; I

and 129D4744, Rev. 3; 12904745, Rev. 2.

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l Lifting and/or tie-down devices which are a structural part of the l

package must be in accordance with the above drawings.

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Page 2 - Certificate No. 5980 - Revision No. 12 - Docket No. 71-5980

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I 50 (Continued) l t

l (b) Contents I

I (1) Type and form of material i

I I

Byproduct material and irradiated special nuclear material in solid or l

solid oxide form, but specifically not loose powders. Contents are to i

be clad, encapsulated or contained in a metal encasement of such I

material as to withstand the comb {ned effects of the internal heat load and the 1475'Fdife Also, byproduct material,with thsic16she pre-tested for leak tightness.

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and irradiated 'special nuclear material I

meeting the reIguirements of special form radies,etive material.

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ep 3

i (2) Maximum quantity of material per package q

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I Plutonium in excess of twenty (20) curies per package.amust be in the 4

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form ohsetal,ymetal alloy or reactor fuel. elements,'and I

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(1)I;Fo,rthecontents'describedin5.(b)(l')yg Q

W.

A the maximum decay heat not i

to exceed 600' watts)and the fissile content not to exceed 500 i

I cgrams of U-235, 300' grams U-233,\\300 grams Pu, or a proratci I

, quantity.of each such that the sum of the ratios does not exceed I

eunity.. When the contents of this/ paragraph are in the form of l

rirra'diated reactor fue16 the fuelimust have been cooled for a i

sminimum of;90 days, and no more'than 10,000.ci ofl noble gases rod plenums. The mustbeavailableforrelease'fromthefuep/secundernormal i

3 cask must be 1eak tight:to:1 xjl07 atm-cm I

I conditions of.tran' sport; or;' % d '

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(ii) FoMhecontentsdescribedi

'O(1)themax#1 mum decay heat not to exceed 600 watts and the ftv 3 content'not to exceed 1200 i

i grams fissile provided: ' (1) the

,sile material is contained in I

standard'wa'ste liners constructed of 5-inch Schedule 40 pipe with j

l a maximum inside~ length of 39-5/16 inches, (2) no more than four I

such liners are' shipped at one1tirrie '(3) each liner contains no l

more than 300 grams fissile, and (4} the cask is provided with a i

positioning lattice to maintain separation between the liners.

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(c) Fissile Class 11 and III I

I (1) Minimum transport index to be For the contents specified in shown on label for Class II 1

limited in l

I 8.4 I

I (2) Maximum number of packages For the contents specified in l

per shipment for Class III 5(b)(1)andlimitedin i

5(b)(2)(ii).

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l Two(2)

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,yum m Page 3 - Cert'.ficate No. 5980 - Revision No.12 - Docket No. 71-5980 i

l l.6. The U-235 equivalent mass must be determined by the following method:

U-235 equivalent mass equals U-235 mass plus 1.66 times U-233 mass plus I

1.66 times Pu mass.

7. - Package contents must be dry and the fissile material unmoderated (H to X atonicratiolessthan2).

8.

The cask must be delivered to a carrier dry and the cavity drain line must i

be closed with a plug which will mahtaitryiw saal at temperatures up to at M n C (j g l

1 east 620'F.

9.. Inadditiontotherequ(,

te of Subpart G of 10 C 71:

(a) Prior to eac t &$' dent, the silicone rubber lid gasket (4 must be inspected.

This gasket (t must be replaced if inspection shows anf fects or every 12 months,whif{e(alant 3

evertoccurs first. Cavity drain line.must pJsealed with appropriat

') threads of pip

/

4 (b) The. package shall be preper'ed for shipment,and operated in recordance with theLoading/ Unloading;ProceduVes'datedfu st" M r 1990.

N' Thepackagemustmeet'the' ins /

g 74f f' ',

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i (c) February}22,1990fp;~ tpf~~3#ptenance Procedules dated pection and M i

%.sp y7;/y1horized. ' f /,4

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,d Fabricationofadditionaljpackigiop'i not.au pa 10.

VRU P dr ll !K w-

=a The package autkrized 'by this ceftifi eteiisthereby'kppproved for.h 11.

use under l

the general licebsb providions;bf210'T/R.571'12.t~A,-

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12. Expiration date:

h31,19951

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(O REFERENCES General Electric Company appl [cationi'dat d February 27p1990.'

,b y%

dgusl(41,h990.

q Supplements dated:

April 26, 1990 and FOR THE U.S. NUCLEAR REGULATORY COMMISSION Yf h

l' Charles E. MacDonald, Chief Transportation Branch Division of Safeguards i

and Transportation, NMSS SEP 19 WO Date:

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2 _

w.r_,sww -w- -- - - - -- ---- ---

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,..y,.,k UNr O STATES a,8 NUCLEAR REGL,LATORY COMMISSION s

wae+nwarow p.c. noses APPROVAL RECORD t

Model No. GE-600 Certificate of Compliance No. 5980 Revision No. 12 By application dated February 27, 1990, as supplemented April 26, 1990, and August 31, 1990, General Electric Company requested that Certificate of Compliance No. 5980 be renewed for the Model No. GE-600 shipping container. The submission included an updated consolidated application which requested changes to the Certificate'of L

Compliance.

Revision No. 11 was issued on March 21, 1990, to renew the Certifi-cate of Compliance for a five year period, without change. On April 26, 1990, 1

General Electrie. Company submitted revised Loading / Unloading Procedures.

The chadges to the Certificate of Compliance requested by General Electric Company included a listing of total package weight and modification of weights of components to agree with Drawing 12904742.

Also, the length of the bolt attaching the protective jacket to the base changed from 5 inches to 4-1/2 inches

~

on Drawing 12904742. Next, references to neutron sources d' the SAR were elimi-nated and the description of the tissile contents were modified to reflect the wording of the Cer'or the hypothetical accident conditions was added to the SAR.

tificate of Compliance.

In addition, the results of a THTD thermal analysis f Finally revised Preshipment and Maintenance Procedures as well as revised Loading / Unloading Procedures were submitted.

The requested changes were reviewed by staff. The changes to the weights of components, the total weight and to the length of the bolt attaching the pro-tective jacket to the base do not affect the ability of the package to meet the requirements of 10 CFR Part 71.

The requested changes to-the neutron source and description of fissile contents were determined to have no affect o't the sbility of the package to meet the criticality requirements of 10 CFR Part 71.

The addition of the THTD thermal analysis and the revision of the Preshipment/

Mair,tenance Procedures and Loading / Unloading Procedures were also determined to be adequate.

These changes do not affect the ability of the package to meet the requirements of 10 CFR Part 71.

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Ch r es.MfcDonald, Chief Transportation Branch Division of Safeguards and Transportation, NMSS Date:

7

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