ML20149K195

Amend 48 to License SNM-1097 for Ge,Authorizing Transfer of Test Quantities of Hydrofluoric Acid,Potentially Containing Trace Amounts of U,To Vendors Listed in for Evaluation of Matl Re Potential Usefulness

ML20149K195
Person / Time
Site:	07001113
Issue date:	02/15/1996
From:	Pierson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20149K194	List: ML20149K192 ML20149K195 ML20149K200
References
NUDOCS 9602210496
Download: ML20149K195 (4)

Text

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• ES to e U.S. NUCLE AR REGULATORY COMMISSION

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+l g MATERIALS LICENSE b

{N Pursuant to the Atomic Energv Act of 1954, as amended. the Energy Reorganization Act of 1974 (Public'g Law ,

( Code of flederal Regulations, Chapter I, Parts 30,31. 32. 33. 34. 35,39. 40 and 70, and in reliance on statements and representations heretofore

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% made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, anl I nuclear matenal designated below; to use such material for the purposets) and at the place (s) designated below; to deliver or transfer such material l l

to persons authorized to recche it in accordance with the regulations of th. applicable Part(s). This license shall be deemed to contain the conditions g

spcified in Section 183 of the Atomic Energy Act of 1954, as amended, ar'd is subject to all applicable rules, regulations and orders of the Nuclear y g Regulatory Commission now or hereafter in effect and to any conditions specified below, jg ,

l il l Licensee I l

I General Electric Company SNM-1097 Il l l

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1. Nuclear Energy Production 3. IJcense number Amendment 48 flI l

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P. O. Box 780 4. Expiration date June 30, 1989 IN I ll Wilmington, North Carolina 28402 5. Docket or pl l Reference No 70-1113 y; I 6. Byproduct, source, and/or 7. Chemical and/or physical 8. Maximum amount that licensee ,5 I special nuclear material form may possess at any one time il I t nder this license {U

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A. Uranium enriched to A. Uranium compounds A. 50,000 kgs U-235 l

<6% U-235 llg i B. Uranium enriched in B. Any B. 0.35 kg U-235 lN N U-235 ju l I C. Uranium enriched from C. Uranium compounds C. 500 kg U-235 lE l 1 6% to <10% U-235 Nl l l

D. Uranium enriched from 10% 0.

to <l5% U-235 Uranium compounds D. 9.649 kg U-235 f  !

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l E. Uranium-233 E. Uranium compounds E. 50 mg U-233 q F. Plutonium F. Sealed neutron sources F. 20 g Pu lN N

I G. Plutonium G. Analytical samples G. Pu i H. Plutonium H. In nuclear fuel rods H. 0.002

<10E-6 g'g Pu/g f'l l

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U-235 f e i 9. Authorized place of use: The licensee's existing facilities at Wilmington, North 1 l Carolina. I i E I 10. This license shall be deemed to contain two sections: Safety Conditions and l Safeguards Conditions. Both sections are part of the license and the licensee is )jE i

subject to compliance with all listed conditions in each section. !g i 1 1  !(

l FOR THE NUCLEAR REGULATORY COMMISSION E I N I tj i N i .h (-

I Date: h Mb M f( L By: _ Robett C. Pierson I Division of Fuel Cycle Safety l l and Safeguards, NHSS y i

i 9602210496 960215 Washington, DC 20555 g PDR ADOCK 07001113 I I C PDR IL , . . . , . , . . , , . . .... ,, .. .... ... .

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pOuii_uDiCiudiOiDiCJOi6iGiGiFWiniDw;saiBifininiBiTifiniBiniffi&iniBiOffEFFFFFiffu 2 4 U.S. NUCLE AR REGULATORY COMMISilON PAGE OF PAGES lg NRC FORM 374A ,

l Lkense Number jg l SNM-1097 Amendment 48  !

g MATERI ALS LICENSE uct or Retcrence Numter M 70-1113

'gl 2 SUPPLEMENTARY SHEET ji SAFETY CONDITIONS February 15,1996 gl gl y

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B SAFETY CONDITIONS For use in accordance with statements, representations, and

1. S-1 Authorized use:

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conditions of Part I of the application dated October 23, 1987; and supplements dated March 21, and May 16, 1988; February 16, and December 20, 1989; December 3, fl l

N 1990; January 9, October 10, and October 22, 1991; February 14, April 16, May 6, lg 8 May 12, September 24, and October 13, 1992; March 18, September 7, and gl N December 10, 1993; February 4, and July 21, 1994; April 14, 1995; and January 16, 5 1996; and letters dated December 3, 1984, and February 6, 1985. )g fj 13 N' S-2 The licensee is hereby granted exemptions and special authorizations in Sections N

1.8.1 through 1.8.16 Part I, of the application. (i' 5 S-3 The licensee shall maintain and execute the response measures in the Radiological B Contingency and Emergency Plan, Revision 0, dated December 2, 1994, and revisions pi E

N dated February 1, and February 14, 1995; or as further revised by the licensee lH,!

E consistent with 10 CFR 70.32(i).

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! NRC FORM 374Q . U.S. NUCLE AR REGULATORY COMMISSloN PAGE 3 or 4 PAGES l 1xense Number l 4 SNM-1097 Amendment 48 0 i

h M ATERI ALS LICENSE SUPPLEMENTARY SHEET th ket or Reference Number 70-1113 yl SAFEGUARDS CONDITIONS U lb b E!

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i SAFEGUARDS CONDITIONS g l E N

SECTION 1.0 -- MATERIAL CONTROL AND ACCOUNTI!LQ ,,

l N SG-1.1 The licensee shall follow Sections 1.0 through 9.0 of its Fundamental Nuclear h 8 Material Control Plan dated December 16, 1987, whichhasbeenpartiallyrevisedasj indicatedbyRevision30ofpage1(datedDecember1,1995andtitled"Revisionbig N

f Page") of said Plan. This Plan may be further revised in accordance with, and p pursuant to, the provisions of either 10 CFR 70.32(c) or 70.34. (lg h SG-1.2 Notwithstanding the requirements of Sections 6.1 and 7.1 of the Plan identified in 5 Condition SG-1.1, the licensee may (1) utilize a computer system independent of r E

N its Manufacturing Information and Control System (MICS) to track the SNM contained N in fuel bundles and loose fuel rods received from the Wurgassen plant in Germany; E E

N and (2) have up to 90 days for completing shipper-receiver differences t N determinations and evaluations associated with the initial shipment of fuel E B

9 assemblies from the Wurgassen plant, and up to six calendar months for subsequent shipments of loose rods. Receipt measurements and item controls associated with fl l N these fuel assemblies and rods shall be in accordance with the commitments Ell I

E N contained in the licensee's letter (from Dr. R. J. Reda to Mr. R. C. Pierson)

N dated January 24, 1996. E N E SECTION 2.0 -- PHYSICAL PROTECTION FOR SNM 0F LOW STRATEGIC SIGNIFICANCE E N

E i The licensee shall follow its security plan titled, " General Electric Company, NlSG-2.1 W

N Nuclear Fuel and Components Manufacturing, Wilmington, North Carolina, Physical E

E N Security Plan," dated October 26, 1981 through Revision 2 dated June 6, 1986, and E W as further revised under the provisions of 10 CFR 70.32(e). 'E B E N SECTION 3.0 -- INTERNATIONAL SAFEGUARDS E N E g SG-3.1 The licensee shall follow Codes 1 through 7 of Facility Attachment No.11b dated E W February 29, 1988 to the US/IAEA Safeguards Agreement. E 9 E p SG-3.2 Notwithstanding the requirements of 10 CFR 75.ll(d) to submit facility data on E g forms supplied by the Commission (including IAEA DIQs), the licensee may submit E g the required data on internally-generated forms that follow the IAEA's DIQ format.E N E p SG-3.3 Notwithstanding 10 CFR 70.54(a) and 74.15, the licensee may include the IAEA MBA E p Code for Import / Export transactions on the DOE /NRC Form 740M in lieu of the W g instructions to insert it parenthetically after the RIS in Block 1 and 2 of the E g DOE /NRC Form 741. E N E g SG-3.4 Notwithstanding 10 CFR 70.54(a) and 74.15, the licensee may include the IAEA E g Country Code for Import / Export transactions on the DOE /NRC Form 740M in lieu of E g the instructions to insert it in Block 20A and C of the DOE /NRC Form 741. E b E R El bor n = = m -

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NRC FORM 374A . U.S. NUCLEAR REGULATORY CoMMISSloN PAGE 4 OF k PAGES .

Lkense Number !l SNM-1097 Amendment 48 fl l

g M ATERI AI.S I,1 CENSE twei or Referena sumner ;i y SUPPLEMENTARY SHEET 70-1113 g l SAFEGUARDS CONDITIONS > ~ 390 h y E >

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y g E l N SG-3.5 Notwithstanding the requirements of 10 CFR 75.35(a) to submit Material Balance Nj Reports on DOE /NRC Form 742, Physical Inventory Listings on DOE /NRC Form 742C and f

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I B Concise Notes on DOE /NRC Form 740, the licensee may use computer generated g J

N 6 facsimiles for the report forms specified in 10 CFR 75.35(a). The facsimiles mustIg N' as nearly as possible approximate the referenced DOE /NRC Forms in format and g N contain the information specified in NUREG/BR-0007 unless otherwise excepted by g 1

i . license condition. y N SG-3.6 The licensee may disregard, for IAEA reporting purposes, the printed instructions l i

N contained in NUREG/BR-0007 relating to block 6H and GM of DOE /NRC Form 742-C, , )

N " Physical Inventory Listing (PIL)." The licensee may use Code "J" in block 6H of g I N

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. g N e N jE g E 8

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