ML20049K005

Application to Amend License DPR-65,revising Tech Specs to Allow Continued Power Operation Up Tp 7 Days W/Steam Driven Auxiliary Feedwater Pump Inoperable

ML20049K005
Person / Time
Site:	Millstone
Issue date:	03/20/1982
From:	Counsil W NORTHEAST NUCLEAR ENERGY CO.
To:	Clark R Office of Nuclear Reactor Regulation
Shared Package
ML20049K006	List: ML20049K005 ML20049K016
References
B10464, TAC-48073, NUDOCS 8203290313
Download: ML20049K005 (4)

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March 20, 1982 Docket No. 50-336 B10464

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Director of Nuclear Reactor Regulations _ . ,

Attn: Mr. Robert A. Clark, Chief p rgGS #'

Operating Reactors Branch #3 -

U.S. Nuclear Regulatory Commission _ gg26N ~

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Washington, D.C. 2 M55 7/ g urrstT .)

Gentlemen: y Millstone Nuclear Power Station, Unit No. 2 4 $

Proposed Revisions to Techrical Specifications Auxiliary Feedwater Pumps Pursuant to 10 CFR 50.90, Northeast Nuclear Energy Company (NNECo) hereby proposes to amend its Operating License, No. DPR-65, for Millstone Unit No. 2 by incorporating the changes identified in Attachment 1 into the plant Tech-nical Specifications.

The proposed changes allow continued power operation up to seven (7) days, ending 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br />, March 25, 1982, with the steam-driven auxiliary feedwater pump inoperable. The proposed amendment will enable NNECo to maintain the Plant at a steady-state condition and avoid a shutdown transient. . Currently the Plant must commence a shutdown at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br />, March 20, 1982.

The auxiliary feedwater system at Millstone Unit No. 2 consists of three pumps, two motor driven pumps and a steam-driven pump, each capable of providing the required feedwater flow to remove decay heat in the event of a plant trip.

The auxiliary feedwater system is comprised of two trains. Both trains can be fed by either motor driven auxiliary feedwater pump or the steam-driven pump.

Each motor driven auxiliary feedwater pump is supplied emergency power from one diesel generator.

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e The proposed License Amendment is a one-time only extension of the Action Sta?ement of Technical Specification 3.7.1.2 permitting power operation for up to seven (7) days with the steam-driven auxiliary feedwater pump out of serv .'ce. NNECo has reviewed the impacts associated with the proposed extension of the Action Statement time limits by means of probabilistic risk assessment techniques.

This involved the evaluation of the risk from potential station black-out events during which the steam-driven auxiliary feedwater pump would be re-quired for decay heat removal. NNECo has concluded from this evaluation that, for the short period of time during which power operation will continue with the steam driven pump out of service (7 days), the increased risk to the public health and safety is negligible. This is based on the fact that two redundant, one hundred percent capacity motor driven pumps are available to supply auxiliary feedwater to the steam generators in the event of a Plant trip. These two pumps are powered by redundant diesel generators as well as the two normal off-site power sources. This design is conalstent with the other engineered safety feature systems in use at Millstone Unit No. 2. It is noted that station black out is not included in the Millstone Unit No. 2 design basis.

NNECo has reviewed the attached proposed changes pursuant to the requirements of 10 CFR 50.59 and has determined that it does not constitute an unreviewed safety question. The basis for this determination is that the proposed change does not increase the probability or consequen:es of any accident previously evaluated in the Plant safety analysis report. The possibility for an accident or malfunction of a different type than previously evaluated in the safety analysis report is not created and the margin of safety as defined in the basis for any Technical Specification is not reduced.

The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved this change and has concurred in the above determination.

NNECo has reviewed the attached change pursuant to 10 CFR 170 and has determined that the change constitutes a Class III License Amendment. The basis for this determination is that the proposed License Amendment involves a single safety issue and does not involve a significant hazards consideration. Therefore, attached is the appropriate Class III License Amendment fee of four thousand dollars ($4,000.00).

Your expeditious review of this matter is appreciated.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY MtA~ -

W.' G. Counsil l Senior Vice President

STATE OF CONNECTICUT ) /9

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) ss. Berlin COUNTY OF HARTFORD )

Then personally appeared before me W. G. Counsil, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.

. a) PM bdf Notary Public' My Commission bpires March 31,1986

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Pocket No. 50-336 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specification Auxiliary Feedwater Pumps March, 1982 ,

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