ML20134L994

Amended License SNM-1227 for Siemens Power Corp

ML20134L994
Person / Time
Site:	Framatome ANP Richland
Issue date:	11/15/1996
From:	Pierson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20134L993	List: ML20134L990 ML20134L994 ML20134L997
References
NUDOCS 9611220148
Download: ML20134L994 (4)

Text

p li NRC mmmm FORM 374mmmmmmmmmmmmmmm mmmma mmmmwammmmarmm ammmmmmmmmmmmmmyll PAGE } _ OF 4 glpo.e9) U.S. NUCLEAR REGULATORY COMMISSION PAGES; i

N;i y MATERIALS LICENSE g u.

g! Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, lig g Code of Federal Regulations. Chapter I, Parts 30. 31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore i d, made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special ,1 Nj nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliser or transfer such material lI to persons authorized to recene it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions g' specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject gto g Regulatory Commission .1ow or hereafter in effect and to any conditions specified below.

16 )

Licensee i i Nl 1. Siemens Power Corporation 3. License number SNM-1227 !I

[ Renewal j

2. 2101 Horn Rapids Road gj R!chland, WA 99352-0130 4. Expiration c' ate November 30, 2001 i N ,1 g! 5. Docket or 70-1257  ;

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7. Chemical and/or physical 8. Maximum amount that licensee

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%; 6.specialByproduct, source, and/or nuclear matenal form may possess at any one time I f under this license N! l ll ll

I II A. Uranium enriched A. Any A. 350 g U-235 Il in U-235 l1 1

1, I I i g! B. Uranium enriched up to B. Uranium B. 25,000 kg U-235 i ll 5.00 wt % U-235 compounds l 1

ll l C. Plutoniura C. Sealed sources C. 1 mg Pu and not more I 1j and standards than 1.5 millicuries I I

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g; I gl D. Plutonium D. Pu0,-00, D. 500 g Pu i q: stored waste I gl I I! Authorized place of use: The licensee's existing facilities at Richland, Washington. I I 9. I 4!10.Thislicenseshallbedeemedtocontaintwosections: Safety Conditions and l h Safeguards Conditions. These sections are part of the license, and the licensee i g is subject to compliance with all listed conditions in each section. I I I I I I

y FOR THE NUCLEAR REGULATORY COMMISSION i i

Date: beh II: WIk B obe' C. Pi I DivTsion of Fuel Cycle Safety and Safeguards ly Washington, DC 20555 1

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y SNM-1227 Renewal p MATERIALS LICENSE Duket or Reference Number p SUPPLEMENTARY SHEET 70-1257 N

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S-1. Authorized use: For use in accordance with the statements, representations, and l

U conditions of Part I of the licensee's application dated October 28, 1996, and I revised pages submitted with letter dated November 11, 1996.

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SAFEGUARDS CONDITIONS l

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Section 1.0 - Material Control & Accountina ,I N SG-1.1 The licensee shall follow Section 0.0, and Sections 1.0 through 8.0 (with all I N pages designated as Rev. 28 dated June 1996 and pages 7-2 and 7-3 designated as i N Rev. 29 dated November 1996), and Addendum 1 (with all pages designated as Rev. I N 26 and dated October 1994) of its Fundamental Nuclear Material Control Plan, I N titled " Nuclear Materials Safeguards Procedures Description for the Fuels I N Fabrication Plants, EMF-12(P)." Revisions'to this Plan shall be made in i N accordance with, and pursuant to, the provistoris of either 10 CFR 70.32(c) or Il N 70.34. Il B 1' N SG-1.2 Notwithstanding Chapter 0.0 of the Plan identified by Condition SG-1.1, 1 N which commits to meeting all Affirmation Statements contained in NUREG- t B 1065 (Rev.1), the licensee is hereby granted a iimited exception from i N the first Affirmation contained in Section 4.3 of NUREG-1065 in that i i

N receipt of returned fuel rods and/or fuel assemblies (that were I N originally fabricated at the licensee's facility and whose SNM l B encapsulation has not been compromised) need not be measured if the W original fabrication values are booked as receipt values.

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N SG-1,3 A special shutdown, cleanout physical inventory shall be initiated  ;

W whenever:

N g (i) a loss / theft indication involving an SNM quantity equal'to or l, greater than the licensee's Detection Quantity (as defined in g i g Section 8.2.7 of the Plan identified by Condition SG-1,1) cannot i g otherwise be resolved within 60 days of the initial recognition of 3 y such indication, and M

y (ii) a Regulatory ID (as defined in Section 5.13 of the Plan identified y in Condition SG-1.1) equals or exceeds the licensee's De.tection y Threshold Quantity (as defined in Section 8.2.7 of the Plan ,

y identified by Condition SG-1.1). i N 6 g Whenever a special inventory is required by either (i) or (ii) above, all ,

y unsealed and unencapsulated SNM items that are on hand at the time that  ;

y such a situation is determined to exist, shall be measured (even if i y previously measured) for SNM content. i l SG-1.4 Operations involving special nuclear materials which are not described in  !.

the Plan identified in Condition SG-1.1 shall not be initiated until an appropriate safeguards plan has been approved by the appropriate l

g safeguards licensing authority of the Nuclear Regulatory Commission.

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SNM-1227 Renewal N MATERIALS LICENSE Docket or Reference Number N SUPPLEMENTARY SHEET 70-1257 N

N SAFEGUARDS CONDITIONS N

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N Section 2.0 - Physical Protection For SNM of Low Strateoic Sionificance l

I SG-2.1 The licensee shall follow the physical proteccion plan entitled "Siemens Power

I Corporation Physical Protection Plan for Special Nuclear Material of Low I N Strategic Significance," Revision 13, dated October 1995 (letter dated i I October 16,1995); and as it may be further revised in accordance with the I' provisions of 10 CFR 73.32(e).

I SG-2.2 The licensee shall ensure.that Ithe' 00/ Building'isflocked when "

i N unoccupied. .-

I N i N Section 3.0 .. International Safeauardi i N l' N SG-3.1 The licensee shall follow, as applicable, Codes ~2 through'7 of -

l N Transitional Facility Attachment No. la dated May.1, 1980, to the US/IAEA I N Safeguards Agreement. I N I N SG-3.2 Notwithstanding the requirements of 10 CFR 75.ll(d) to submit. facility i N data on forms supplied by the Commission (including IAEA DIQs), the i N licensee may submit required data in the Advanced Nuclear Fuels i' N Corporation license paper format. ,1 N i N I, N

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