ML19269E827

Discusses Safety Evaluation Rept Review Re Facility Fire Protection.Proposed Mods Represent Significant Increase in Level of Protection

ML19269E827
Person / Time
Site:	Peach Bottom
Issue date:	04/06/1979
From:	Randy Hall BROOKHAVEN NATIONAL LABORATORY
To:	Ferguson R Office of Nuclear Reactor Regulation
Shared Package
ML19269E815	List: ML19269E821 ML19269E827 ML19269E838
References
NUDOCS 7906290685
Download: ML19269E827 (3)

Text

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BRCCKHAVEN NATION AL ABCDMCPi ASSCC%iED G.E7:SQE5 NC

m 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 has been general agreement between the NRC staff and the BNL consultants. Based on present data, the proposed fire protection, as set forth in the SER, will give reatona.ble 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 NR^ staff.

Valve Supervision Electrical valves supervision shauld 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 4.3.1(3)c - We recommend adding af ter the word year "To insure that there is no standing water remaining in the carrel or at the hydrant valve."

2145 168 790629067[

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 suporession capabilities of the plants as interfaced with the nuclear systems : equirements.

This was accom-plished by utilizing a review team concept wit members fram BNL and the Nuclear Regulatory Commission Division of Operai.'y Qeactors 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 ear 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 nas 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 components, 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 relateJ to the protection of the public from the standpoint of radio-logical health and safety. We have not considered 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, s

4<obert E. Hall, Group Leader Reactor Engineering Analysis REH:EAM:sd 2145 169

DISTRIBUTION M. Antonetti

l I. Asp 1

V Benaroya 1

E. Blackwood 1

W. Butler 1

R. Cerbone 1

D. Eisenhut 1

k. 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 i

E. MacDougall 1

J. Riopelle 1

V. Stello 1

T. Telford 1

H. Todosew 2

J. Townley 1

NRC - Division of Techlical 2

Infomation and Controi 2145 170

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