B15508, Application for Amend to License NPF-49 Re Existing SRs 4.8.1.1.2.a.6 & 4.8.1.1.2.b to Require That DG Be Loaded to Greater than or Equal to 4986 Kw for at Least Sixty Minutes During Routine Surveillance

Application for Amend to License NPF-49 Re Existing SRs 4.8.1.1.2.a.6 & 4.8.1.1.2.b to Require That DG Be Loaded to Greater than or Equal to 4986 Kw for at Least Sixty Minutes During Routine Surveillance

ML20100R465
Person / Time
Site:	Millstone
Issue date:	03/04/1996
From:	Dacimo F NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20100R468	List: B15508, Application for Amend to License NPF-49 Re Existing SRs 4.8.1.1.2.a.6 & 4.8.1.1.2.b to Require That DG Be Loaded to Greater than or Equal to 4986 Kw for at Least Sixty Minutes During Routine Surveillance ML20100R486
References
B15508, NUDOCS 9603120427
Download: ML20100R465 (3)

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P.O. Box 270 i

I Hartford, CT 061410270 (203) 665-5000 MAR 0 41996 Docket No. 50-423 B15508 Re: 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Electrical Power Svstamm -- A.C. Sources Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Facility Operating License NPF-49 by incorporating the changes identified in the attachments into the -Millstone Unit No. 3 Technical Specifications.

Su===ry The existing surveillance requirements 4.8.1.1.2.a.6 (monthly) and 4.8.1.1.2.b (once per 184 days) require that the diesel generator (DG) be loaded to greater than or equal to 4986 kW (continuous rating) for at least sixty minutes during routine surveillance. l The proposed modification to the surveillance requirement is to specify error bands in loading the DG in lieu of the present requirement to load the DG greater than or equal to 4986 kW. For continuous load rating, the value specified is 4800-5000 kW (continuous rating accounting for instrumentation inaccuracies using the plant computer) . According to the existing technical specification surveillance 4.8.1.1.2.g.7, a 24-hour load run is required, the first two hours of which are with the DG loaded to l 110 percent of the continuous rating and the next 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> are at i

100 percent (continuous rating); specifically, at greater than or l equal to 5485 kW and greater than or equal to 4986 kW, I respectively. The proposed change to the surveillance requirement is to load the DG during the refueling outage load run between 5400-5500 kW for two hours and between 4800-5000 kW for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> as i indicated on the plant computer.

J l 960312C427 960304 PDR ADOCK 05000423 P , ('DR

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U. S. Nuclear Regulatory Commission B15508/Page 2 In support of this license amendment request, the following information is provided:

• Attachment ? forwards the marked-up technical specification pages.

Attachment 2 forwards the retyped technical specifications and reflects the currently issued version of the technical specifications.

• Attachment 3 describes the proposed technical specification changes.

Attachment 4 provides a safety assessment and significant hazards consideration for the changes. NNECO has reviewed the proposed technical specification changes in accordance with  !

10CFR50.92 and has determined that the changes do not involve a significant hazards consideration. The basis for this determination is discussed in Attachment 4.

Environmental Considerations NNECO has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not increase the types and amounts of effluents I that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, NNECO concludes that the proposed changes meet the

,' criteria delineated in 10CFR51.22 (c) (9) for a categorical exclusion from the requirements for an environmental impact statement.

State of Connecticut In accordance with 10CFR51.91(b), the State of Connecticut is being provided with a copy of this license amendment request.

Nuclear Safety Assessment Board The Nuclear Safety Assessment Board has reviewed the proposed changes and concurs with the above determination.

Schedule Required for NRC Approval 2

Regarding our proposed schedule for this amendment, we request i issuance at your earliest convenience, with the amendment effective

as of the date of issuance and to be implemented within 60 days.

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U. S. Nuclear Regulatory Commission B15508/Page 3 Commitment l

There are no commitments contained within this letter.  !

Should you have any questions, please contact Mr. W. J. Temple'at (860) 437-5904. ,

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY i

F. R. Dacimo Vice President - Nuclear Operations cc: T. T. Martin, Region I Administrator V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 A. C. Cerne, Senior Resident Inspector, Millstone Unit No. 3 Mr. Kevin T. A. McCarthy, Director Bureau of Air Management j Monitoring and Radiation Division l Department of Environmental Protection '

79 Elm Street Hartford, CT 06106-5127 l

Subscribed and sworn to before me this day of Wap- , 1996 otu i 9L hAQ L

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Date Commission Expires: _ R a s ,:

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