ML20204D160

Interim Rept on SER Review Re Fire Protection Program Covering Review of Fire Prevention,Detection & Suppression Capabilities.Present Program Gives Reasonable Assurance That Public Health & Safety Is Not Endangered

ML20204D160
Person / Time
Site:	Millstone
Issue date:	08/23/1978
From:	Randy Hall, Mcdougall E BROOKHAVEN NATIONAL LABORATORY
To:	Ferguson R Office of Nuclear Reactor Regulation
References
CON-FIN-A-3107 TR-780823, NUDOCS 7812110290
Download: ML20204D160 (2)

Text

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INTERIM REPORT l Accession No.

I Contract Program or Project

Title:

Fire Protection in Operating l Nuclear Power Stations Subject of this Document: Millstone - Unit 1 Safety Evaluation Report Review Type of Document: Letter Report Author (s): R. E. Hall and E.A. MacDougall Date of Document: August 1978 Responsible NRC Individual Mr. Robert L. Ferguson and NRC Office or Division: Division of Operating Reactors Office of Nuclear Reactor Reg.

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes, this document should not be considered

, 71nal.

Brookhaven National Laboratory Upton, NY 11973 Associated Universities, Inc.

for the U.S. Department of Energy Prepared for U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Under Interagency Agreement EY-76-C-02-0016 NRC FIN No. A 3107 INTERIM REPORT gg 2ai00@

t BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.

Upton. New York 11973 Department of Nuclear Energy (516) 345- 2144 August 23, 1978 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Robert L. Ferguson Plant Systems Branch

SUBJECT:

Fire Protection in Operating Nuclear Power Stations - Millstone -

Unit 1 Safety Evaluation Report Review The Safety Evaluation Report, as developed jointly by the NRC staff and Brookhaven National Laboratory, (BNL), adequately reflects the concerns and recommendations of the consultants. Throughout .he reevaluation of Millstone slit 1 there has been general agreement between tne NRC staff and the BNL consultants. Based on present data, the proposed fire protection, as set forth in the SER, will give reasonable assurance that the health and safety of the public is not endangered. The following exception represents a dif-fering engineering point of view that should be evaluated by the NRC staff.

Valve Supervision Electrical valve supervision should be provided on all valves controlling fire water systems and sectionalizing valves. The present proposal of administrative controls or locks is unacceptable. See letter dated July 13, 1977 to Mr. R.L. Ferguson from Mr. R.E. Hall.

The preceding statement is based on a detailed reevaluation of the fire protection program as implemented by the Northeast Utilities Company at the Millstone - 1 Nuclear Power Station. The analysis covered a review of the fire prevention, detection and suppression capabilities of the Millstone unit as interfaced with the nuclear systems requirements. This was accompli-shed by utilizing a review team concept with members from BNL and the Nuclear Regulatory Commission Division of Operating Reactors staff.

The fire protection evaluation for Millstone - Unit 1 is based on an analysis of documents submitted by the Northeast Utilities to the Nuclear

,, Regulatory Commission and a site visit. The site visit was conducted by Mr. T. Dunning and Mr. L., Derderian of the HRC; Mr. M. Antonetti of Gage-Babcock and Associates, Inc., under contract to BNL; and Mr. J. Townley

RC Researc1 anc "ec1nica 781211029 Assistance Report

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consultant'to BNL. Mr. Townley was under contract to BNL to review the manual' fire fighting capabil.ities of the station along with administra- i tive' controls. i The Millstone - 1l review has been. conducted under the' direction of

- Mr. :E. MacDougall and myself of the. Reactor Engineering Analysis Group at BNL.

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This review process has resulted in. identifying areas of the plant in which alfire could have undesirable effects on safe shutdown of the ,

reactor and on release of radioactivity'to the environment. The Utility's' I

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proposed modifications are significant steps in reducing the undersirable effects of a fire in this plant.

Respectfully'yours,_/

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/cobert T1E. Ha - a

, de p Leader Reactor Engineering Analysis l

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DISTRIBUTION M. Antonetti 1 I. Asp 1 V. Benaroya 1 E. Blackwood I W. Butler 1 R. Cerbone 1 D. Eisenhut 1 R. Feit 1 R. Ferguson 5 R. Hall 1 S. Hanauer 1 P. Herman 1 E. Imbro 1 W. Kato 1 J. Klevan 1 G. Lainas 1 C. Long 1 E. MacDougall 1 J. Riopelle 1 V. Stello 1 T. Telford 1 H. Todosow 2 J. Townley 1

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