ML20197F683

Certificate of Compliance 9044,Rev 14,for Model 1600. Approval Record Encl

ML20197F683
Person / Time
Site:	07109044
Issue date:	05/12/1986
From:	Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20197F658	List: ML20197F655 ML20197F683
References
NUDOCS 8605150647
Download: ML20197F683 (5)

Text

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• m.a-I U.S. NUCLEAD r.EEULATO7.Y COMMISSION nec Foned sis CERTIFICATE OF COMPLIANCE k

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'o CFR n FOR RADIOACTIVE MATERIALS PACKAGES E

i a CERTisiCATE NUMBER D REVIS60N NUMBER c PACKAGE IDENTIFICATION NUMBER d PAGE NUMBER e TOTAL NUMSER PAGLS

. I 9044 14 USA /9044/P( IF 1

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a in.s Cecif.cate s.

.auea to Cert.f y inat (n p Cnaging ano contents oesCno o in siem s e iow. meets t%.pphCaoie sateiy stanoares seivortn in T, tie to. coo.

E gj of r.oerai neguiai,ons Part ri. pac = aging ana Transportatiori of naa.caCliv. uateriai-g 1" -

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b This CertsfsCate does not reheve the Cons'Qnor from ComphanC. with any requerement of the regulat.ons of the U.S Department of Transoortation or otner l

applicaOle regulatory agenCaes encluding the government of any Country through or teto wnich the paChage will De transported k

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1 II 3 THIS CERTIFICATE IS ISSUED ON THE SA$iS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPUCAfiON a ISSUED TO shame e4 Adeessi b TITLE AND IDENTIFICATION OF REPORT OR APPLICATICN 1

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General Electric Company General Electric Company application dated

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Vallecitos Nuclear Center February 1,1982, as supplenented.

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I Pleasanton, CA 94566 i

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C DOCirET NUuBER

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This CertifsCate is Conditionai upon fulfilhng the requerements of 10 CFr.t Part 71, as apphCaele. and the Conditions spec.fied beiow lI 11

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Packaging i

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B (1) Fodel No.:

1600 l5

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(2) Description l

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Steel encased lead shielded shipping cask.

A double-walled steel il l4 8

I cylinder protective Jacket encloses the cask during transport.

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bolted to a steel pallet. The cask is closed by a lead-filled flanged

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plug fitted with a silicone rubber gasFet and bolted closure. The

'g cavity is equipped with a drain line and the physical description is

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as follows:

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Cask height, in 67.19 f9 n

I Cask diameter, in 38.5 i

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Cavity height, in 54.0 Cavity. diameter, in 26.5 n

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Lead shielding, in 5.0 in lI Protective jacket height, in 81.88 lid I

Protective jacket width, in 68.0'

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l Packaging weight, lb 25,500 I

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PDR ADOCK 07109044 j

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I CONDmoNS tcontinued) l l

Page 2 - Certificate No. 9044 - Revision No.14 - Docket No. 71-9044 j

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(a) Packaging (continued) '

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(3) Drawings

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ii The packaging is constructed in accordance with the following General

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Electric Company Drawing Nos.:

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12904735, Rev. 4*

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12904736, Rev. 3 I

12904737, Rev. 5

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l 12904738, Rev. 1 I

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• Except Item 2 hex hd bolts must be ten, 2.0-4.5 lE

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UNC-2A x 4.5 inches to. 5.0 inches long, A-449 bolts.

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

g package must be in accordance with the above drawings.

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-(b) Contents lg I

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(1) Type, form and ma::imun quantity of material per package

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Plutonium in excess of 20 curies per package must be in the form of l

metal,. metal alloy or reactor fuel elements; and lg I

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(i). Byproduct material and special nuclear material. as solid metal or l3 lI oxides. Decay heat not to exceed 600 watts.

The radioactive IB I

material shall be in the fom of fuel rods, or plates, fuel IE assemblies, or meeting the requirements of special form radioactive j g

material.

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500 gm U-235 eauivalent mass; or-

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(ii) Neutron sources meeting the requirements of special form radioactive j material.

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500 gm U-235 equivalent mass. Decay heat not to exceed 50 watts; lp I

or

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Irradiated Pu0 and UO fuel r ds clad in Zircelloy or stainless 2

s teel.

Decay beat not to exceed 600 watts. All fuel rods shall ly l

be contained within a closed 5-inch Schedule 40 pipe with a lh I

maximum useable length of 39-5/8 inches.

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1,200 gm fissile material with no more than 300 gm fissile material

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per 5-inch Schedule 40 pipe.

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(iv) Irradiated UC and ThC fuel particles clad in graphite and contained ln I

within a standard HTGR hexagonal cross-section graphite block.

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Decay heat not to exceed 600 watts.

Each graphite block shall be

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contained within a sealed cylindrical inner container constructed IN lj l

in accordance with General Atomic Company Drawing No. 021583, Issue A, with three,1/2-inch by 4-1/2-inch radial fins to g

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provide centering within the cavity.

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I 1,400 grams U-235 equivalent mass in each inner container with no lI l

more than one inner container per package.

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CONOlTlONS (contrnued)

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Page 3 - Certificate No. 9044 - Revision No.14 - Docket No. 71-9044 j

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5.

(b)

(1) Contents (continued) li;N I

(v) Process solids, either dewatered, solid, or solidified in a I

secondary sealed container meeting the requirenents for low

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specific activity radioactive naterial.

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(vi) Solid nonfissile irradiated netal hardware, reactor control rods h

l (blades), reactor start-up sources, and segmented baron carbide lgl i

I tubes (tube contents not to exceed a Type A quantity).

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(vii) Radioactive (Hot Cell) waste materials inmobilized with cement n

I grout and contained in"a 55-gallon (or extended 55-gallon drum)

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DOT Specification '17H 'or 17C steel drun, lid and closure. The l

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Waste material' nust be packaged in accordance with the Procedural lj I

Outline of the Innobilization of Cell Waste Using Cement Grout, g

I of the December 1,1981 supplement. The cenent

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grout must be at least 50 volume percent (estinated) of the drum

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I contents-and relatively unifomly distributed throughout the lI l

d rum.

At. least 3/4" thick layer of grout must cover all radioactive il 1

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waste contents. Decay. heat not to exceed 100 watts, and fissile I

material not to exceed.500 grams U-235 equivalent mass.

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(c) Fissile Class III ll ll j@

l Maximun number of_ packages ~

-(i) Contents 5.(b)(1)(i), 5.(b)(1)(ii),

per shipment

, 5.(b)(1)(iii), or 5.(b)(1)(vii):

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I Two (2); or 1l l

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(ii) Contents 5.(b)(1)(iv):

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One (1).

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6.

The U-235 equivalent mass isidetermined by U-235 mass plus 1.66 times U-233 nass i

I plus 1.66 times Pu mass.

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7.

For packaging of neutron sources, the cavity drain line must be closed with a l

g plug with a melting temperature of 200*F and the cask cavity must be dry before

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delivery of the package to a carrier.

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For packaging nf other than neutron sources, the cask must be delivered to a W

I carrier dry and the cavity drain line nust be closed with a plug which will N

l maintain its seal at temperatures up to at least 620*F.

9.

For the shipment of irradiated metal hardware, the use of the auxiliary shielded i

inner container and shoring plug shown in Chen-Nuclear Systems, Inc. Drawing

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Nos. 8651-E-02, Rev. A and 8651-C-01, Rev. A is authorized. The inner container ji j

must be provided with vent and drain lines.

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I CONDITIONS (contmoed) l

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Page 4 - Certificate No. 9044 - Revision No. 14 - Docket No. 71-9044

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10. Shoring nust be provided to mininize novement of contents during accident n

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conditions of transport.

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11. Prior to each shipment the silicone rubber lid gasket (s) nust be inspected.

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This gasket (s) must be replaced if inspection shows any defects or every twelve I

i (12) nonths, whichever occurs first. Cavity drain line must be sealed with

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appropriate sealant applied to threads of pipe plug.

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12.

For packaging of neutron sources, 50 times the measured neutron dose rate at one lN l

neter from the surface of a cask must be less than 1,000 mren/hr.

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13. The contents described in 5(b)(1)(v) rust be transported on a motor vehicle, f

I railroad car, aircraft, inland water craf ts, or hold or deck of a seagoing jg I

vessel assigned for sole use of the licensee.

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

l general license provisions of 10 CFR 571.12.

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15.

Expiration date:. April 30,1987.

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REFERENCES E

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5 ll General Electric application dated February 1,1982.

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' l Supplements dated: t%rch 30,1982; January 17 and February 4,1983; and April 28, I

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1986.

l Nuclear Plant Services supplement dated: July 7~,1975.

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I Chen-Nuclear Systems, Inc. supplement dated: April 6, 1984.

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I FOR THE. U.S. NUCLCAR REGULATORY C0ftMISSION E

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I Charles E. MacDonald, Chief l

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I Transportation Certification Branch l

Division of Fuel Cycle and l

l Material Safety, tilSS

,y MAY1 2 M I

Date:

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Transoortation Certification Branch Approval Record

??odel No.1600 Package Docket No. 71-9044 By application dated April 23, 1986, General Electric Company has added an alternate lid gasket and revised the bolts attaching the cask.iacket to the base for the ibdel No.1600 nackage.

The optional gasket for the cask lid is a 1/4-inch thick silicone flat gasket with a 30 to 60 duroneter. The ootional change should have no significant effect on the ability of the cask to remain sealed during normal conditions of transport. The cask seals have been assured by the NRC staff to fail under accident conditions of transport; and, therefore, the cask content have been limited previously.

On General Electric Comoany (GE) Drawing No.1290a735, Revision 4, the Iten 2 holt was revised from being 5.0-inches long to 4.0-inches long.

The ten bolts are used to attach the cask jacket to the base. The dimensions given on GE Drawing No. 12904736, Pevision 3 indicate the bolt must be at least 4.5 inches long in order to develop the full strength of the closure. Accordingly, the certificate has been conditioned to reouire these bolts to be between 4.5 inches to 5.0 inches long.

The package liodel flo. has been revised from GE-1600'to 1600 to be consistent to GE references to the packaging.

The revised package design neets the requirements of 10 CFR Part 71.

C arres T. idacDonald, ie Transportation Certification Branch Division of Fuel Cycle and Material Safety, if1SS Date:

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