ML20053B555

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Forwards License SNM-1857,authorizing Receipt,Possession, Insp & Storage of Fuel Assemblies Enriched in U-235 Isotope for Eventual Use at Facility.Request for Exemption from 10CFR70.24 Granted.W/O Encl 10CFR71 & Agreement B-87
ML20053B555
Person / Time
Site: 07002884
Issue date: 05/19/1982
From: Page R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Pollack M
LONG ISLAND LIGHTING CO.
Shared Package
ML20053B556 List:
References
NUDOCS 8205280568
Download: ML20053B555 (2)


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%jA M4, Long Island Lighting Company ATTN:

Mr. Millard S. Pollock (f

Vice President - Nuclear Gs ti,

175 East Old Country Road Hicksville, NY 11801 Gentlemen:

Enclosed is NRC Material License No. SNM-1857 which authorizes the receipt, possession, inspection and storage of fuel assemblies enriched in the23sU isotope for eventual use at the Shoreham Nuclear Power Station.

In addition, the license authorizes the packaging of fuel assemblies for delivery to a carrier for transport.

This latter authority enables you to return fuel assemblies to their shipping containers if there is a need to transfer the assemblies to another location, e.g., return to the manufacturer.

The delivery of the assemblies to a carrier must be in accordance with 10 CFR Part 71, " Packaging of Radioactive Materials for Transport and Transportation of Radioactive Material Under Certain Conditions," copy enclosed.

In this regard, your attention is directed to 971.12(b) of Part 71 which provides a general license under specified co1ditions for the use of certain shipping packages which have been licensed for use by another licensee.

Also enclosed are two copies of Indemnity Agreement No. B-87 for your review, acceptance, and the return of one signed copy.

The Nuclear Regulatory Commission (Commission) uses an electronic data processing system to record the location by licensee of special nuclear material.

This system uses a three letter Reporting Identification Symbol to identify licensees who submit the material transfer reports and periodic material status reports in accordance with 9970.53 and 70.54 of the Commission's regulations 10 CFR Part 70.

For this purpose, you should continue to use the Reporting Identification Symbol:

XMX, previously assigned to you.

This symbol is to be used in completing the transfer reports and the periodic material status reports and should be used in any other correspondence with the NRC relative to such reports.

You should also note the requirements of 670.51(b),

(c), and (d) regarding records, material control and accounting procedures, and physical inventories.

Your cooperation will be appreciated.

Your application for license requested an exemption from the provisions of 10 CFR 70.24.

Such an exemption would relieve you from the requirement of having a criticality alarm system.

Because of the inherent features associated with the storage and inspection of unirradiated fuel, the NRC staff has deter-mined that you have shown good cause for being granted the exemption and that 8205280568 820519 PDR ADOCK 07002884 C

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Long Island Lighting Company 2

MAY 1 S 1982 granting such an exemption will not endanger public life or property or the common defense and security and is otherwise in the public interest.

l Any future modifications to your procedures reviewed by the Commission must be made in accordance with your administrative controls for procedure review and i

approval as described in the Shoreham FSAR, Chapter XIII (Docket 50-322).

The procedures will be reviewed by the Commission on a sampling basis as part of the routine inspection program.

The license conditions were discussed with and agreed to by Mr. R. W. Grunseich, representing Long Island Lighting Company, and Mr. Norman Ketzlach of my staff on May 6, 1982.

i' Enclosed is our evaluation report in support of this lirense.

Sincerely,

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Originni signed by t W. T. Crow h R. G. Page, Cli f 1

Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety 4

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Enclosures:

1.

NRC Special Nuclear Material License 1

No. SNM-1857 l

2.

Safety Evaluation Report 3.

10 CFR Part 71 j

4.

Agreement No. B-87 l

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