ML20198Q140

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Amend 9 to License SNM-1227 for Siemens Power Corp
ML20198Q140
Person / Time
Site: Framatome ANP Richland
Issue date: 01/15/1998
From: Schwink W
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20198Q126 List:
References
NUDOCS 9801220352
Download: ML20198Q140 (8)


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!g ll g Pursuant to the Atomie Energy Act of 1954, as amended, the EnerFy Reorganication Act of 1974 (Public Law 93-438L and Tale 10 jg l! Code of Federal Regulations, Chapter 1. Parts 30,31,32,33,34,35,39,40 and 70, and in reliance on statements and representaticas heretofore jg ll rnade by the hcensee, a heenw is hereby issued authorizing the licensee to receive, acquire, possess, and transfer b3 product, murce. nd special ;l Ij. nuclear material designated below; to use such material for the purpow(s) and at the place (s) desi nated oclow; to dchver or transfer such material (I F

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to perwns authorized to receive it in accordance w ith the regulations of the applicable Part(sh This license shall be deemed to contain the conditiora j j.

]j opcified in Section 183 of the Atomic Energy Act of 1954, as emended, and is subject to all apphca g

Regulatory Commission now or hereafter in effect and to any condition specified Niow.

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3. Ucense number Amendment 9
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2101 Hom Rapids Road

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Richland, WA 99352-0130 November 30,2001 jI l

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special nuclear material form may possess at any one time I-f under this license I!

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Uranium enriched A.

Any A.

350 g U-235 hI I

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Uranium enriched up to B.

Uranium B.

25,000 kg U-235

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C, Plutonium C.

Sealed sources C.

1 mg Pu and not more it.

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and standare than 1.5 millicuries I!-

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PuO -U4 D.

500 g Pu f

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Plutonium D.

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stored waste it I

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Authorized place of uso: The licensee's existing facilities at Richland, Washington.

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h 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards l1, Conditions. Tiwse sections are part of the license, and the licensee is subject to compliance I

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with all listed conditionr. in each section.

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FOR THE NUCLEAR REGULATORY COMMISSION C

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bb By: Walter S. Schwink. Actina Chief b

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Washington, DC 20555 L

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. 9901220352 980115 ll PzKt ADOCK 07001257 1:l _

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L,cen.c Numner SNM-1227 Amendment 9

'El MATERIALS LICENSE onctri or nererence NumNr SUPPLEMENTARY SHEET 70-1257-(

U SAFETY CONDITIONS W

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!E S-1 Authorized use: For use in accordance with the statements, representations, and conditions of Part I of the licensee's application dated October 28,1996; and supplements dated June 14 and y

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November 11,19%; February 21, March 5, March 7, March 12, March 18, April 15, April 24, May 1, y

g May 21, May 22, June 6 June 0, July.10, July 14, July 15, August 4, August 8, August 13, y,

y August 28, Septcmber 29, November 14, December 3, and December 30,1997; and January 12, g

p1 1998.

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S-2 The licensee shall maintain and execute the response measures in the Emergency Plan, y

y Revision 21, dated April 28,1997; or as further revised by the licensee consistent with 10 CFR y

g 70.32(i),

p S-3 Notwithstanding Section 6.5 of Part I of the license dated October 28,1996, new uranium y

hexafluoride (UFe) cylinders purchased by SPC shall conform to ANSI N14.1 or to the tinning y

g requirements specified in NRC's Certificate of Compliance No. 9196 for Model UX-30 packages.

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SNM-1227 Amendment 9 Igl N,

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b-MATERI Al S 1 ICENSE Dtdet or Reference Numter SUPPLEMENTARY SHEET 70-1257 g

SAFEGUARDS CONDITIONS lN g

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Section 1.0 - Material Control & Act:ountina N

SG-1.1 The licensee shall follow Sections 0.0,1.0, and 6.0 (with all pages designated as Revision 28 and 4

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dated June 1996), and Sections 2.0 through 5.0, and 7.0 through 8.0 (with all pages designated as N

Revision 30 and dated February 1997) of its Fundamental Nuclear Material Control Plan, tMled N

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" Nuclear Materials Safeguards Procedures Description for the Fuels Fabrication Plants, EMF-12(P)."

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Revisions to this Plan shall be made in accordance with, and pursuant to, the provisions of either N

I 10 CFR 70.32(c) or 70.34 N

N 1 SG-1.2 Notwithstanding Chapter 0.0 of the Plan identified by Condition SG-1.1, which commits to 1

I meeting all Affirmation Statements contained in NUREG-1065 (Rev.1), the licensee is hereby N

I granted a limited exception from the fitst Affimiation contained in Section 4.3 of NUREG-1065 in N

that receipt of retumed fuel rods and/or fuel assemblies (that were originalty fabricated at the I

licensee's facility and whose SNM encapsulation has not been compromised) need not be N

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measured if the original fabrication values are booked as receipt values.

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, SG-1.3 A special shutdown, cleanout physical inventory shall be initiated whenever-4 f

(i) a loss / theft indication involving an SNM quantity equal to or greater than the 5

licensee's Detection Quantity (as defined in Section 8.2.7 of the Plan identified by

!8 Condition SG-1.1) cannot otherwise be resolved within 60 days of the initial -

recognition of such indication, and h

(ii) a Regulatory ID (as defined in Section 5.13 of the Plan identified in Condition SG-1.1) equals or exceeds the licensea's Detection Threshold Quantity (as defined in Section *.2.7 of the Plan identified by Condition SG-1,1).

N Whenever a special inventory is required by either (i) or (ii) above, all unsealed and i

N unencapsulated SNM items that are on hand at the time that such a situation is determined to exist, shall be measured (even if previously measured) for SNM content.

I SG-1.4 Operations involving special nuc' ear materials which are not described in the Plan identified in l

Condition SG-1,1 shall not be initiated until an appropriate safeguards plan has been approved by the appropriate safeguards licensing authority of the Nuclear Regulatory Commission.

M_lan 2.0 - Phv=irmi Protection For SNM of Low Strateoic SionificanGR SG-2.1 The licensee shall follow ihe physical protection plan entitled "Siemens Power Corporation Physical l.

Protection Plan for Special Nuclear Material of Low Strategic Significance," Revision 13, dated i

October 1995 (letter dated October 16,1995); and as it may be further revised in accordance with the provisions of 10 CFR 73.32(e).

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- SG-2.2 ' The licensee shal; ensure that the UO Building is locked when unoccupied.

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l U.S. NUCLE AR REoVL AToQY CoMMISSloN i PAGE O

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- N,n,c rQnM 37d A Liceriw Number i

I SNM-1227 Amendment 9 i

N' MATERIALS 1 lCENSE tw teiix neererte Numhet gf M

SUPPLEMENTARY SHEET 70-1257 g

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g SAFEGUARDS CONDITIONS r,

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{I giaction 3.0 - Intemational Safegue:tf s N

ll SG-3.1The licenseo shall follow, as applicable, Codes 2 through 7 of Transitional Facility Attachment l

No.1a dated May 1,1986, to the US/lARA Safeguards Agreement.

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SG-3.2 Notwithstanding the requirements of 10 CFR 75.11(d) to submit facility data on forms supplied by the Commission (irieluding lAEA DlQs), the I;censee may submit required data in the g

Advancad Nuclear Fuels Corporation license paper format.

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