ML20151U107

From kanterella
Jump to navigation Jump to search
Amend 6 to License SNM-1097 for General Electric Co,Nuclear Energy Production
ML20151U107
Person / Time
Site: 07001113
(SNM-1097-A-06, SNM-1097-A-6)
Issue date: 09/03/1998
From: Emeigh C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20151U089 List:
References
NUDOCS 9809100288
Download: ML20151U107 (5)


Text

.

t',s. St CI. EAR REGt't.ATORY CONDil5SION l

MATERI ALS LICENSE Pursuant to the Atomic 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 heense is hereby issued authorinng the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated

(

below; to use such material for the purpose (s) and at the place (s) designated below; to delis er or transfer such material to persons authorized to receive l

it in accordance with the regulations of the appheable Part(s). This license shall be deemed to contam 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 of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

Licensee

1. General Electric Company
3. License Number SNM-1097, Amendment 6 Nuclear Energy Production
2. P.O. Box 780 4.

Expiration Date June 30,2007 Wilmington, North Carolina 28402

5. Docket No. 70-1113 Reference No.

J

6. Byproduct Source,and/or
7. Chemical and'or Physical
8. Maximum amount that Licensee 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 existing facilities at Wilmington, North Carolina.

l~

l 9809100208 930903

(

hDR ADOCK 07001113

?

PDR

e e

NRC FORM 374A U.S. Nt'CI. EAR REGt'LAlORY COMMISSION PAGE 2 or 5 PAGl!S i

License Number l

SNM-1097 MATERIALS LICENSE Docket or Reference Number 70-1113 SUPPLE 3tENTARY SilEET Amendment No. 6 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.

l l

g

(

g',-

c sl-s

~

L

.A f%

FOR THE NUCLEAR REGULATORY COMMISSION c' x v. V L

./

Charleshor lgh. Acting Chief Y.3/9 /

By:

Eme Date:

Division of Fuel Cycle Safety and Safeguards, NMSS t

Washington, DC 20555

. ~ _

_ ~..- - _. -. _

NRC FOR31374 A U.S. NUCLEAR REGUI.ATORY CO%t%11SSION PAGE 3 of 5 PAGl:S License Number SNM-1097 MATERIALS LICENSE Docket or Reference Number 70-1113 j

SUPPLEMENTARY SilEET Amendment No. 6 1

SAFETY CONDITIONS S-1 Authorized use: For use in accordance with statements, representations, and conditions of application dated June.,1997; and supplements dated June 11, June 27, September 19, and December 5,1991, March 10, and May 13,1998.

S-2 The licensee is hereby granted exemptions and special authorizations 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 Emergency Plan, dated December 2,1994, which has been partially revised as indicated by Revision 5 of page i (dated December 16,-1997, and titled " Revision Date by Chapter / Appendix"). This' Plan may be further revised by the licensee consistent with 10 CFR 70.32(i).

l S-4 Notwithstanding the requirements of 10 CFR 70.22(i)(3)(xii) t6 conduct a biennial emergency exercise (BEE), the licensee may delay until August 31,1997lits next scheduled BEE. All future BEES shall be based on the August 31,1997, date.

s

' S-5 The licensee shall. work'with the NRC to develop an outlin'e for the ISA summary 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 lSA current, in accordance with their letter dated May 27,1997, from Ralph'J. Reda, GE, to M.F. Weber, NRC.

T l

l l

l l

T l

I

{

l a

NRC FORM 3NA U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 of 5 Pacts License Number SNM-1097 MATERIALS LICENSE nocket or nererence Number SUPPLEMENTARY SilEET 70-1113 Amendment No. 6 SAFEGUARDS CONDITIONS 1ECTION 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 16,1967, which has been partially revised as indicated by Revision 34 of page 1 (dated November 13,1997, and titled " Revision 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 Plan 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 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.

Receipt measurements and item controls associated with thes'e 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.

Pierson) dated January 24,1996.'

Notwithstanding h requirement within Section 5;1 of the Plan identified in Condition SG-1.1 to SG-1.3 conduct a physical inventory each year between' July 1st and September 1st, the licensee may initiate the 1996 annual physical inventory lon or before Septeriiber 9,1996. In order to satisfy regulatory intent to conduct inventories at an average intervat of 12 months, the licensee's 1997 annual physical Irwentory date shall be no later than August 6,1997.

9, SG-1.4 Notwithstanding the commitment, in Section 7.1 of the FNMC Plan identified in Condition SG-1.1, to perform receipt measurements and distribute _ DOE /NRC Form 741 within 30 days, the licensee shall have 60 days (from the date the U.S. Custo'ms releases the material) to fulfill the above stated commitments relative to the 980 containers of UO powder identified in the attachment to its letter 2

dated June 30,1998.

In addition, notwithstanding the commitments in Sections 6.1 and 6.2.3 of the FNMC Plan identified in Condition SG-1.1 to provide current knowledge and audit verification of all SNM items, the licensee shall maintain the above-mentioned material in seavans in the Customs bonded area and enter these items in its inventory and item control program when the material is released.

SG-1.5 Notwithstanding the commitment, in Section 9.3.6 of the FNMC Plan identified in Condition SG-1.1, to distribute the material status reports within 30 days after the start of the physical inventory, the licensee shall have 15 additional days to fulfill the above stated commitment relative to the July 1998, physicalinventory. This condition automatically expires on September 15,1998.

SRC FORM 374 A l'.S. NL' CLEAR REGt'LATORY COMMISSION PAM $

or 5 eact:s Ucense Number SNM-1097 MATERI ALS LICENSE Docket or Reference Number 70-1113 SUPPLEMENTARY SilEET Amendment No. 6 SECTIOR2.0 - PHYSICAL PROTECTION FOR SNM OF LOW STRATEGIC SIGNIFICANCE 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, 1981 through Revision 2 dated June 6,1986, and as further revised under the provisions of 10 CFR 70.32(e).

SECJ10N 3.0 - INTERNATIONAL SAFEGUARDS SG-3.1 The licensee shall follow all subicodeN withiri des 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 internally-generated forms that follow the IAEA's DlQ format.

t SG-3.3 Notwithstanding 10 CFR 70.54(a) and 74.15, the lice' see may. include the IAEA MBA Code for n

i import / Export transactions on the DOE /NRC Form 740M in lieu of the instructions to insert it a

parenthetically after the RIS in' Block 1 and 2 of the DOE /NRC Form 741.

^

v

~

qj
g;Lc'

?

1 h SG-3.4 Notwithstanding 10 C.FR 70.'54(a) and 74!1'$,Ithe 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 W

20A and C of the DOE /NRC Form 741.

)

Notwithstanding the requirements of 10 CFR 75.35(a) to' submit Material Balance Reports on SG-3.5

~

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 DOE /NRC Forms in format and contain the information specified in NUREG/BR-0007 unless otherwise excepted by license condition.

I SG-3.6 The licensee may disregard, for IAEA reporting purposes, the printed instructions contained in NUREG/BR-0007 relating to block 6H and 6M of DOE /NRC Form 742-C," Physical Inventory Listing (PlL)." 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.