ML19270H256

Fire Protection in Operating Nuclear Power Stations,Peach Bottom Units 2 & 3 SER Review.

ML19270H256
Person / Time
Site:	Peach Bottom
Issue date:	04/06/1979
From:	Randy Hall, Macdougall E BROOKHAVEN NATIONAL LABORATORY
To:	Ferguson R Office of Nuclear Reactor Regulation
References
NUDOCS 7906260023
Download: ML19270H256 (4)

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IllTERIM NEPORT Accession !!o.

Contract i.'cgram or Project

Title:

Fire Protection in Operating Nuclear Power Stations Subject of this document: Peach Bottom Units 2 and 3 Safety E.cluation Renort Review Type of Document: Letter Report Author (s): R.E. Hall and E.A. MacDougall Date of Document: April 6, 1979 Responsible flRC Individ'al Mr. R.L. Ferguson and ilRC Office or Civision: Plant Systems Branch 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 final.

Brookhaven !!ational Laboratory Upton, NY 11973 Associated Universities, Inc.

for the U.S. Department of Energy Prepared for U.S. Iluclear Regulatory Comission Washing ton , D. C. 20555 Under Interagency Agreement EY-76-C-02-0016 tiflC FIN flo. A-3107 2314 034 INTERIM REP 0tT 1

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NRC Research anCcChnicat ,

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Upton. New York 11973 Department of Nuclear Energy (516) 345-2144 April 6, 1979 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 Peach Bottom Units 2 and 3, 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 the reevaluation of Peach Bottom 2 and 3, there '1as been general agreement between the NRC staff and the BNL consultants. B' sed on present data, the proposed fire protection, as set forth in the SER, all give reasonable assurance that the health and safety of the public is not endangered. The following exception represents a differing engineering point of view that should be evaluated by the NRC staff.

Valve Supervision Electrical valves 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.

Manual Equipment 4.3.1(1) - We recommend the following be added " Provide two double female adapters to the outside fire department pumper; store at a central equipment location."

Hydrant Inspection 2314 035 4.3.1(3)c - We recommend adding after the word year "To insure that there is no standing water remaining in the barrel or at the hydrant valve."

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R.L. Ferguson April 6, 1979 The preceding statements are based on a detailed reevaluation of the fire protection program as implemented by the Philadelphia Electric Company at the Peach Bottom Units 2 and 3 Nuclear Power Station. The analysis covered a re-view of the fire prevention, detection and suppression capabilities of the plants as interfaced with the nuclear systems requirements. This was accom-plished by utilizing a review team concept with members from BHL and the Nuclear Regulatory Commission Division of Operating Reactors staff.

The fire protection evaluation for Peach Bottom Units 2 and 3 is based on an analysis of documents submitted by the Philadelphia Electric Company to the Nuclear Regulatory Commission and a site visit. The site visit was con-ducted by Mr. E. Sylvester and Mr. P. Atherton of the NRC; Mr. Ingemar Asp of Gage-Babcock and Associates, Inc. under contract to BNL; and Mr. J. Townley, consultant to BNL. Mr. Townley was under contract to BNL to review the manual fire fighting capabilities of the station along with administrative controls.

The Peach Bottom review has been conducted under the direction of Mr. E.A.

MacDougall and myself of Reactor Engineering Analysis Group at BNL.

We have reviewed the analyses submitted by the licensee and have visited the facility to examine the relationship of safety-related compor.ents, systems and structures with both combustibles and the associated fire detection and suppression systems. Our review has been limited to the aspects of fire pro-tection related to the protection of the public from the standpoint of radio-logical health and safety. We have not ccasidered aspects of fire protection associated with life safety of onsite personnel and with property protection, unless they impact the health and safety of the public due to the release of radioactive material. The proposed modifications represent a significant increase in the level of protection against serious fire associated hazards.

Respectfully yours, V

- obert E. Hall, Group Leader Reactor Engineering Analysis REH:EAM:sd 2314 036

DISTRIBUTION M. Antonetti 1

1. Asp 1 V. Benaroya 1 E. Blackwood 1 W. Butler 1 R. Cerbone 1 D. Eisenhut 1 R. Feit 1 R. Ferguson 5 R. Hall 1 S. Hanauer 1 P. Hennan 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 NRC - Division of Technical 2 Infonnation and Control