ML20217B897

Amend 8 to License SNM-1097 for GE

ML20217B897
Person / Time
Site:	07001113
Issue date:	05/25/1999
From:	Sherr T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20217B885	List: ML20217B880 ML20217B897 ML20217B920
References
NUDOCS 9910130108
Download: ML20217B897 (5)

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. u.s. NUCLEAR REGUI.A' LORY COS1 MISSION MATERIALS LICENSF Pursuant to the Atemic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated 1 below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license sball be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations. and orders orthe Nuclear Regulatory Commission now or hereafter

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in effect and to any conditions specified below. I l

l Licensee {

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1. General Electric Company 3. License Number SNM-1097, Amendment 8 l

Nuclear Energy, Production j

2. P.O. Box 780 4. Expiration Date June 30,2007 Wilmington, North Carolina 28402 5. Docket No. 70-1113 Reference No.-

6. Bwoduct Source, and/or 7. Chemical and/or Physical S. Maximum amount that Licensee i Special Nuclear Material Form May Possess at Any One Time Under This License A. Uranium enriched to A. Uranium - any form A. 50,000 kgs U 235

<5% U 235 B. Uranium enriched in B. Any B. 0.35 kg U-235 U-235 -

C. Uranium enriched from C. Uranium compounds C. 0.35 kg U-235 5% to <10% U 235 D. Uranium-233 D. Uranium compounds D. 50 mg U-233 E. Plutonium E. Sealed neutron sources E. 20 g Pu F. Plutonium F. Analytical samples F. 0.002 g Pu G. Plutonium G. In nuclear fuel rods G. <1E-6 g Pu/g U 235

9. Authorized place of use: The licensee's ey.isting facilities at Wilmington, North Carolina.

9910130108 990525 I' POR ADOCK 07001113 C PDR 1

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NRC FORM 374A U.S NUCLEAR REGULATORY COMMISSION PAGE 2 or 5 PAGES License Number

. SNM-1097

' pocket or nererence Number

~ MATERIALS LICENSE SUPPLEMENTARY SIIEET 70-1113 Amendment No. 8

10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.

Both sections are part of the license and the licensee is subject to compliance with all listed conditions in each section.

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FOR THE NUCLEAR REGULATORY COMMISSION I

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Date: 6~l2(l%

C. M . ['SN[hief By: Theodore S. I Division of Fuel Cycle Safety and Safeguards, NMSS Washington, DC 20555

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' NRC FORM 374A ' U.S. NUCLEAR REGULATORY COND11SSION PAGE 3 or 5 PAGES j License Number SNM-1097 D eket r Rererence Number MATERIALS LICENSE SUPPLEMENTARY SilEET 70-1113 Amendment No. 8 SAFETY CONDITIONS S-1 Authorized use: For use in accordance with statements, representations, and conditions of application dated June 5,1997; and supplements dated June 11, June 27, September 19, and December 5,1997, March 10, and May 13,1998.

S-2 The licensee is hereby granted exemptions and 'special authorizaJons in Section 1.3 of the application.

S-3 The licensee shall maintain and execute the response measures in Revision 0 of the Radiological Contingency and Ernergency Plan, dated December 2c 1994, which has been partially revised as indicated by Revision 6 of page i (dated January 13,1999, and titled " Revision Date by Chapter / Appendix"). This Plan may be further revised by the licenGee consistent with 10 CFR

-70.32(i)-.

S-4 Notwithstanding the requirements of 10 CFR 70.22(i)(3)(xii) to conduct a biennial emergency exercise (BEE), the licensee may delay until August 31,1997, its next scheduled BEE. All future BEES shall be based on the August 31,1997, date.

S-5 The licensee shall work with the NRC to develop an outline for the ISA summry for the DCP, submit a revised ISA summary for the DCP,' complete the ISA for the balance of plant, submit an ISA summary for the balance of plant systems, and maintain the ISA current,in accordance with their letter dated May 27,1997, from Ralph J. Reda, GE, to M.F. Weber, NRC.

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NRC FORM 374A - U.S. NUCLEAR REGUI.ATuRY COMMISSloN PAGE 4 or 5 PAGEa  !

License Number SNM-1097 MATERIALS LICENSE Docket or Rererence Number SUPPLEMENTARY SIIEET 70-1113 j Amendment No. 8 1

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SAFEGUARDS CONDITIONS  !

SECTIObl 1.0 -- MATERIAL CONTROL AND ACCOUNTING SG-1.1 The licensee shall follow Chapters 1.0 through 9.0 of its Fundamental Nuclear Material Control Plan dated December 16,1987, which has been partially revised as indicated by Revision 35 of Page 1

'(dated February 25,1999, and titled

• Revisions by Chapter) of said Plan. This Plan may be further revised in accordance with, and pursuant to, the provisions of either 10 CFR 70.32(c) or 70.34.

SG 1.2 Notwithstanding the requirements of Sections 6.1 and 7.1 of the han identified in Condition SG-1.1, the licensee may (1) utilize a computer system independent of its Manufacturing Information and Control System (MICS) to track the SNM contained in fuel bundles and loose fuel rods received from l I

the Wurgassen plant in Germany; and (2) have up to 90 days for completing shipper-receiver differences determinations and evaluations associated with the initial shipment of fuel assemblies from the Wurgassen plant, and up to six calendar months for subsequent shipments of loose rods. l

' Receipt measurements and item controls associated with these fuel assemblies and rods shall be in  ;

accordance with the commitments contained in the licensee's letter (from Dr. R. J. Reda to Mr. R. C. I Pierson) dated January 24,1996.

SG-1.3 Deleted by Amendment 8, May 1999.

SG-1.4 ' Deleted by Amendment 8, May 1999.

SG-1.5 Deleted by Amendment 8, May 1999.

I SECTION 2.0 - PHYSICAL PROTECTION FOR SNM OF LOW STRATEGIC SIGNIFICANCE j SG-2.1 The licensee shall follow its security plan titled, " General Electric Company, Nuclear Fuel and Components Manufacturing, Wilmington, North Carolina, Physical Security Plan," dated October 26, j 1981 throunh Revision 2 dated June 6,1986, and as further revised under the provisions of 10 CFR l

70.32(e). i SECTION 3.0 - INTERNATIONAL SAFEGUARDS SG-3.1 The licensee shall follow all sub-codes within Codes 1 through 8 of the 19-page Transitional Facility Attachment No.11 A, dated January 24,1996, to the US/lAEA Safeguards Agreement.

SG-3.2 Notwithstanding the requirements of 10 CFR 75.11(d) to submit facility data on forms supplied by the Commission (including lAEA DlQs), the licensee may submit the required data on intemally- j generated forms that follow the IAEA's DIQ format. j L SG-3.3 - Notwithstanding 10 CFR 70.54(a) and 74.15, the licensee may include the IAEA MBA Code'for  !

Import / Export transactions on the DOE /NRC Form 740M in lieu of the instructions to insert it parenthetically after the RIS in Block 1 and 2 of the DOE /NRC Form 741.

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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE $ or 5 PAGES l License Number i SNM-1097 l Ducket r Reference Number MATERIALS LICENSE l SUPPLEMENTARY SilEET 70-1113 Amendment No. 8 i

SG-3.4 Notwithstanding 10 CFR 70.54(a) and 74.15, the licensee may include the IAEA Country Code for -

Import / Export transactions on the DOE /NRC Form 740M in lieu of the instructions to insert it in Block 20A and C of the DOE /NRC Form 741.

SG-3.5 Notwithstanding the requirements of 10 CFR 75.35(a) to submit Material Balance Reports on DOE /NRC Form 742, Physical Inventory Listings on DOE /NRC Form 742C and Concise Notes on DOE /NRC Form 740, the licensee may use computer generated facsimiles for the report forms specified in 10 CFR 75.35(a). The facsimiles must as nearly as possible approximate the referenced j DOE /NRC Forms in format and contain the information specified in NUREG/BR-0007 unless

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otherwise excepted by license condition.' .  ;

SG-3.6 The licensee may disregard, for IAEA reporting purposes, the printed instructions contained in l

- NUREG/BR-0007 relating to block 6H and 6M of DOE /NRC Form 742-C," Physical Inventory Listing j (PIL)." The licensee may use Code "J"in block 6H of the PIL regardless of nuclear material ownership and may use Code "M"in block 6M of the PIL regardless of the basis of the measurement source data.

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