ML20236E500

Certificate of Compliance 5980,Rev 10,for Model GE-600. Approval Record Encl

ML20236E500
Person / Time
Site:	07105980
Issue date:	10/28/1987
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20236E484	List: ML20236E481 ML20236E500
References
NUDOCS 8710290250
Download: ML20236E500 (4)

Text

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U.S. NUCLEAR REGULATORY COMMISSION

' unc ronu sis I ese CERTIFICATE OF COMPLIANCE E

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FOR RADIOACTIVE MATERIALS PACKAGES I

d PAGE NUMBER

e. TOTAL NUMBER PAGES

c. PACKAGE loENTIFICATION NUM8!RF i

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b. REVISION NUMBER l

,'a'cEntwicATE NU5@0 10 USA /5980/B(

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a. This certificate is issued to C.rtif y that the packaging and contents described in L tm $ below, meets the applicable safety standardt set forth in Title 10 Code I

g os rederai neguiations. Part 71," Packaging and Transportation of radioactive Material."

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b. Tni. certificate doe. noi reiseve ine con. anor trom compiiance witn any requirement or tne reguistions of ine u s o.oartment of Transportation or otner l

apphcable regulatory agencies, inciuding the government of any country through or into which the package will be transported.

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• '."'*J'"I"ff' .'*,*If.f" '"' ***'S ' ^ *^'"" ^**"S'S."'E"E A'o'"o'EEi*c^$oN E%i oE"#^A icATioN.

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General Electric Company General Electric Company application dated I

E I-Vallecitos Nuclear Center November 15, 1984, as supplemented.

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Pleasanton, CA 94566 1

c. wexET NuueEa 71-5980 E

4 CONolTIONS l

I ini. ceriivicai. i. conduisonai upon ruiviiiing ine requirements of 10 cra Pari ri. as appiicabie. and ine conditions specified beiow.

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(a)

Packaging l

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g (1) Model No.:

GE-600 R

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I (2) Description l

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.A steel-encased lead shielded shipping cask.

The basic cask body is a g

cylinder 34 inches in diameter by 59.12 inches high formed by two I

concentric steel shells whose annular region is filled with 6 inches l

l of lead.

The cavity is 20-1/2 inches ID by 46 inches high, 3/8-inch

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thick stainless steel cylinder.

A recessed plug-type cask lid,

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consisting of a steel weldment filled with lead, is secured to the s

cask body by six l-inch diameter steel bolts. A silicone rubber W

l gasket provides the seal. A protective jacket consistirg of a N

i double-walled structure of 1/2-inch thick carbon steel plates is R

placed over the cask and bolted to a steel pallet by eight 2-inch l>

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diameter steel bolts.

The cask has one 1/2-inch diameter drain line l

from the cavity to the outer shell.

The cask is shipped in the f

upright position.

The total weight of the package is approximately p

p 23,300 pounds when loaaed.

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(3) Drawings E

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The packaging is constructed in accordance with the following General l

Electric Company Drawing Nos.:

129D4742, Rev. 2; 129D4743, Rev. 1; y

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and 129D4744, Rev. 3.

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

I package must be in accordance with the above drawings.

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e710290250 071028 N

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I iPage 2:--Certificate'No.;5980'- Revision No."10 Docket No. 71-5980 lll 15.

(Continued)[

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). Contents N

'(b s

I (1) Tj pe'and form of material E

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- Byproduct material'and irradiated special. nuclear material in solid or.

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

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

material asito withstand the combined effects of the internal' heat I

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A1so,-byproduct. material and. irradiated special nuclear material.

- l load and the'14751F fire with the closure pre-tested for leak tightness.

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. meeting the requirements 7off.special form radioactive material.

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(2) Maximum quantity of material per ^ package i

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.f Plutonium in excess of twenty (20) curies <per package must be in the l

form ofsmetal, metal alloy or reactor fuel 1 elements, and g

I (1)i?For the contents described in 5.(b)(1) the maximum decay heat not-N u to exceed <600 watts and.the' fissile content not to exceed 500 t

grams of U-235, 300 gramsEU-233; 300 grams!Pu, or_a. prorated I

L quantity of~each such that the' sum of thefratios does not exceed-l4

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E unity. yhen the contents of this~paragraphmare in the: form of-

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.irradiatedtreactor~ fuel,"theffuel_must havelbeen cooled for.a-p minimum of 90 days, and no more thant10,000~ci of noble gases I

rod plenums.

The I

must be availableifor: release from the fuej/sec under normal:

cask must;be leak tight to 1:x 10-3 atm-cm I

conditions'of: transport; or l

l (ii)

For the contents described in 5.(b)(1) the maximum decay, heat not I

to' exceed 600 watts and the fissile content not to' exceed 1200.

I grams fissile provided:

(1) the' fissile material is contained in I

' standard waste liners constructed of 5-inch Schedule 40 pipe with I

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

such liners are shipped at one time, (3) each liner contains no y

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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l (c) Fissile Class II and III l

(1) Minimum transport index to be For the contents specified in i

5(b)(1)(andlimitedin shown on label for Class II i

5(b)(2) 1).

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8.4 l

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i (2) Maximum number of packages For the contents specified in p

l 5(b)(1)(andlimitedin per shipment for Class III p.

5(b)(2) ii).

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Two (2) l li

a skuklam mm m mum mmm yu - -- - - - - - - - - - - -- ---- - - - - - - - - - - - - - - - - - - - -

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C NOfTl:NS (continu:d) l Page 3 - Certificate No. 5980 - Revision No. 10 - Docket No. 71-5980

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6.

The U-235 ecuivalent mass must be determined by the following method:

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

l.66 times Pu mass.

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Package contents must be dry and the fissile material unmoderated (H to X atomic l )l ratio less than 2).

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

i closed with a plug which will maintain its seal at temperatures up to at least N

j 620*F.

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9.

Prior to each shipment, the. silicone < rubber lid gasket (s) must be inspected.

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This gasket (s) must be replaced if inspection shows any defects or every 12 N

j months, whichever occurs first.

Cavity drain-line trust be sealed with N

i appropriate sealant applied to threads of pipe plug.

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i 10.

Fabrication of additional packaging is not authorized.

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The package authorized by this certificate is.hereby approved for use under the N

general license provisions of 10 CFR 671.12.-

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13.

Expiration date: March 31,'1990..

l REFERENCES I

General Electric Company's application dated November 15, 1984.

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Supplements dated:

February 25 and March 8, 1985; ana September 29, 1987.

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

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Charles E. MacDonald, Chief l

j Transportation Branch p

Division cf Safeguards and g-l Transportation, NMSS R

H OCT 2 8 sa7 m

Date:

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ems 7 4 UNITED STATES -

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NUCLEAR REGULATORY COMMISSION f g,

>?5" JK WASHING TON, D. C. 205$5' s

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OCT 2 81987

-Transportation Eranch

. A) proval Record o

Model 10. GE-600 Package

. Docket No.- 71-5980 Revision No. 10 By application dated September 29, 1987, General. Electric Company requested-1 the certificate of compliance be amended to-incorporate the latest revision.

1 level of the packaging. drawing.: Drawing No. 129D4744, Rev. 3, has'been revised to show the corrective action taken to isolate the tapped holes for.the' lift-lugs from the annulus formed by the outer cask' wall and-the lift lug backing ring.

The-corrective actionfis being taken in response to an operating-J problem which developed.on 'a similar package (Certificate of Compliance' No.

'9081)..Itwas'observedthat.afluidhad:leakedfrom.twoofthe: lifting;1ug ~

bolt holes. located on the side of the cask.

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To isolate the tapped holes from the annulus formed by.the. lifting lug backing-ring, each tapped hole will be drilled and tapped to_a larger diameter and

fitted with a threaded insert. ' The insert is seal welded to the lift lug Ladapter. plate.

LThe ' staff considers the: proposed corrective action to be a satisfactory -

1 resolution to the problem of restricting the entry of fluid.into the annulus formed by the lift lug backing ring.

The modification of the bolt holes has:

4 no adverse effect on the ability of the package to meet the requirements of-10 CFR Part 71.

h Charles E.- MacDonald j

Transportation Branch

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Division of Safeguards and Transportation, NMSS Date Ani 2 B tea 7 i

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