ML20043H414

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Certificate of Compliance 5641,Rev 9,for Model UNC-2500
ML20043H414
Person / Time
Site: 07105641
Issue date: 06/22/1990
From: Macdonald C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20043H411 List:
References
NUDOCS 9006250375
Download: ML20043H414 (4)


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I u.s. Nucuum naiut. Atony goenussioN I

- uneconn m CERTIFICATE OF CEMPLIANCE I

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  • FIR RADl! ACTIVE MATERIAL 8 PACKARES L

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t. PAC 8%OE IDENT4FiCATION NUMBER e PAGE NUMBER
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1 shlFtCATE NUMBER 9

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5641 I

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a. This certificate le leeued to certify that the packaging and contente described in item 6 below, moots the op L

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I of r.derei naguistions, Part 71,"Packag6ng and Transportation of Radioactive Meterial."

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b. Thee certificate does not relieve the consignor from comphence with any reoutremer;t of the regulations of the

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' apphoebte reguietory agencies, including the govemment of any country through or into which the peckage will be treno 1

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3. THIS CERTIFICATE is ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PAC I

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a. ISSUED 10 femme aner Amessi.

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. United Nuclear Corporation United Nuclear Corporation application I

67 Sandy Desert Road dated February 1,1982.

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Uncasville, CT 06382 1 tus7 p CKET NuuaER 71 rg,4f l

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l Tnes cel'tificate le conditional upon futfdling the requirements of 10 CFR Port 71, es opphcable, and the condit6cne specified below 4 CONDITIONS s

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Specificpackagingis;/.notirequired}s:Safetyof'shipmentisindependent I

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(1) Type and form of' material' Ng

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I I Unirradiatedfuelclusters,modulesorother.aislimblies.

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l (2) Maximum quantity of material per shipment as? Fissile Class III l

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Not to exceed a Type A quantity of" radioactive material; and g

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[ Interspersed hy(drogenous material limited to an H to U-235 atomi l

ratio of three 3)orless.]

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Shipment limited to:

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I (i) The stated dry safe quantities (without reference to notes or supplements), but e.<cluding those parts named as " elements" as l

listed in the following pages of Table 10.0-1 to SNM License I

ho. 368:

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9006250375 900622 nDOCK 07105641 I

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I Page 2 - Certificate No. 5641 - Revision No. 9 - Docket No. 71-5641 I

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(b)] Contents (continued) l

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l P.10.0-4, dated June 4, 1976 I

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l P.10.0-6, dated June 4, 1976

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l P.10.0-7, dated June 4,'1976 l

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j P.10.0-7D, dated October 27, 1982*

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mceptgrItem 6d on page 10.0-70 he limited to two l

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    • Effhpt that' Item 7f on page 10.0-7E is not I
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(iii)51nglefabr[Ac',f e1[ht xcehdis40gU-inch.

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given in thejabovedreference I

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(ii) 50d rams U 235; or

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.(iii) A sing fabricated fuel _part not exceeding"20 g U-235/ inch.

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The name plate to which the mbd'el number is affixed'must be fabricated of l

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

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I general license provisions of 10 CFR 671.12.

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. Expiration date: April 30, 1991.

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V.S. NUCLEAR REGULATORY COMMISSION - [

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I Page 3 --Certificate No. 5641'- Revision No.-9'- Docket No. 71-5641 1

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REFERENCES l

I Un'ited Nuclear Corporation application dated February 1, 1982.

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I I Supplements dated: April 25, 1983; February 19 and 24, April 25 and 28,1986; l _ l, l

3 l and May 7, 1990, l

FOR THE U.S. NUCLEAR REGULATORY COMMISSION I

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Charles E. MacDona hjef i

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and Transportation, NMS$

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1 APPROVAL RECORD Certificate of Compliance No. 5641 Revision No. 9 By application dated May 7,1990, UNC Naval Products Company (UNC) requested an amendment to Certificate of Compliance No. 5641 for the Model UNC-2500 package to modify the allowable contents. UNC requested the addition of 4

contents specified on page 10.0-7E, dated December 23, 1988, of SNM License No. 368, and the deletion of contents specified on page 10.0-7C, dated May 13, 1983.

7 To support the additional contents specified on page 10.0-7E, the applicant submitted an analysis performed by the Knolls Atomic Power Laboratory.

This.

analysis used the STEMB Monte Carlo computer code with the RDS-6 cross-section set and 1,248,000 neutron histories. To benchmark the code,

. calculations for a number of different cores were compared aga,nst criticals for configurations similar to the current request.

The applicant reported results for nine different cases covering three new fuel assembly and' fuel module types.

Item 7f on page 10.0-7E was not i

evaluated for two times the maximum quantity per shipment fer normal conditions of transport as required by 10 CFR 971.61(a).- Taerefore Item 7f on page 10.0-7E was excluded from the list of authorized contents. Analyses for arrays of fuel modules other than Item 7f resulted in k-eff values less than 4

0.95, including uncertainties. The analyses demonstrated that these contents meet the requirements of 10 CPR Part 71 for Fissile Class III shipments.

The NRC staff performed independent calculations to confirm the applicant's conclusions. A simplified model was used to calculate k-eff for one fuel

- module type. The calculations yere performed using a 27 neutron group cross section library and the KENO-Va computer program in the SCALE 4 system.

The results for the two cases analyzed agreed well' with the' applicant's values.

This change does not affect the ability of the package to meet the requirements of 10 CFR Part 71.

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<a Charles E. MacDonald, Chief Transportation Branch Division of Safeguards and Transportation, HMSS Date 1

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