ML20133K496

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Revised Application to Renew License SNM-1097,clarifying Intent of Requested Authorization to Use Licensed Matl at Offsite Locations.Fee Paid
ML20133K496
Person / Time
Site: 07001113
Issue date: 07/12/1985
From: Vaughan C
GENERAL ELECTRIC CO.
To: Crow W
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
25535, NUDOCS 8508120250
Download: ML20133K496 (3)


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NUCLEAR FUEL MANUFACTURING DEPARTMENT OENERAL ELECTRIC COMPANY - P. O. 00X 780 - WILMINGTON. NORTH C AROLINA 28402

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Office of Nuclear Materials Safety & Safeguards U. S. Nuclear Regulatory Commission Washington, D.

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20555 Attention:

Mr.

W.

T. Crow, Section Leader Uranium Process Licensing Section M/S 396-SS

Dear Sir:

Reference:

NRC License SNM-1097, Docket #70-1113

Subject:

USE OF LICENSED MATERIALS AT OFF-SITE LOCATIONS With reference to activities authorized by NRC License SNM-1097 at the General Electric Company Nuclear Fuel Manufacturing Department, GE hereby requests approval of the attached revised Section 1.8.4.1 of Part I of the application to renew SNM-1097 dated 7/25/83, as amended.

These changes are proposed in order to clarify the intent of the authorization stated in that section.

Pursuant to 10 CFR 170.31, a check for $150 will be submitted to the NRC under separate cover.

General Electric personnel would be pleased to discuss this matter further with you and your staff as deemed necessary.

Very truly yours, e

c1, GENERAL ELECTRIC COMPANY DOCKDED

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JUL 181985 > ~4f Charles M. Vaughan, Manager 5

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Prior to shipment, each transfer is sampled and measured to assure that the concentration does not exceed three parts per million of uranium, General Electric shall maintain records under this condition of license including, as a minimum, the date, uranium concentration and quantity of all hydrofluoric acid transferred.

1.8.3.2 Nitrate-Bearino Licuids Authorization, pursuant to 10 CFR 20.302(a), to dispose of nitrate-bearing liquids, provided that the uranium concentration does not exceed a 30-day average of 5 parts per million by weight of the liquids and the nominal enrichment does not exceed 6 weight percent U235, by transport to an offsite liquid treatment system located at Federal Paper Board Corporation, Riegelwood, North Carolina, in.which decomposition of the nitrates will occur and from which the denitrified liquids will be discharged in the effluent from the system.

The environmental-monitoring pr'ogram as described in Section 5.1.4.2 is used to control these activities.

1.8.4 Use of Materials at Off-Site Iocations 1.8.4.1 Authorization to use up to 15 grams of U 235 at other sites within the limits of the United States and at temporary job sites of the licensee anywhere in the United States where the Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material.

LICENSE SNM-1097 DATE 7/12/85 PAGE DOCKET 70-1113 REVISION 10 I_1,1

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