ML19242A073
| ML19242A073 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/03/1979 |
| From: | Randy Hall, Macdougall E BROOKHAVEN NATIONAL LABORATORY |
| To: | Ferguson R Office of Nuclear Reactor Regulation |
| References | |
| CON-FIN-A-3107 NUDOCS 7907310186 | |
| Download: ML19242A073 (4) | |
Text
IllTERIll REPORT Accession ?!a.
Contract Program or Project
Title:
Fire Protection in Operating Nuclear Power Stations Subject of titis Document:
Dresder 1 Safety Evaluation Report Review Type of Document:
Letter Report Author (s):
R.E. Hall and E.A. MacDougall Date of Document:
July 3, 1979 Mr.
.s. '
Ferguson Responsible !!RC Individ 4al Plant. Systems Branch and i1RC Office or Division:
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 This document pas prepared primarily for preliminary or internal use.
It has :nt received full review and approvnl.
Since there may be substantive changes, this document should not be con-idered final.
Brookhaven flational Laboratory Upton, fly 11973
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Associated Universities, Inc.
7907 3 @ otac, u.S.DepaEE"ofenergy Prepared for U.S. Iluclear Regulatory Comission L'ashi ng ton, D. C.
20555 Uno'r lnteragency Agreement EY-76-C-02-0016
!!RC Fli! 1:o. A-3107 It1TERIl1 REPORT
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BRCCKHAVEN NAi!ONAL LABORATORY ASSOCIATED UNIVERSITIES. INC.
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f 5 N N5 2144 July 3, 1979 Division of Operatina Peactors U. S. Nuclear Regula ury Commission Washington, D. C.
20555 Attention:
Mr. Robert L. Ferguson Plant Systems Branch
Dear Bob:
Subject:
Fire Protection in Operating Nuclear Power Stations Dresden-1 Safety Evaluation Reoort Review The Safety Evaluation Report as develooed jointly by the NRC staff and Brookhaven National Laboratory (BNL), adequately reflects the concerns and recom-mendations of the consultants.
Throughout the reevaluation of Dresden-1, there has been general agreement between the ilRC staff and the BNL consultants.
Eased 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 differing engineering point of view that should be evaluated by the NRC staff.
Valve Supervision - Section a.3.1 Electrical valve supervision should be provided on all valves controlling fire water systems and sectionalizing valves.
The present proposal of admin-istrative controls or locks is unacceptable.
See letter dated July 13, 1977 to Mr. R. L. Ferguson from ftr. R. E. Hall.
Ventilation System - Section 4.4.1 The present portable system consists of two 5200 CFM fans with ducting, and additional portable units available from the local fire department. We recommend an additional 5200 CFM be on hand at the site to be more consistent with the BNL recommended minimum portable ventilation.
Interior Fase Stations - Section 4.2.1.4 We recommer.1 replacing the 1-1/2" nozzles with " Class C, all-spray ehtric type nozzles" wnere electrical shock hazard is a consideration for personne safety.
A suitable alternative is 1-1/2" adjustable nozzles providing a sprec stream pattern without going through the straight stream made to open or close the nozzle.
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Mr. R. L. Ferguson July 3, 1979 The preceding statements are based on a detailed reevaluation of the fire protection program as implemented by the Commonwealth Edison Co. at the Dresden-1 Nuclear Power Station.
The analy3is covered a review of the fire prevention, detection and suppression capabilities of the plant as interfaced with the nuckar systems requirements.
This was accomplished by utilizing a review team concept with members from Brookhaven National Laboratcry and the Nuclear Regulatory Comission Division of Operating Reactors staff.
The fire protection evaluation for the Dresden-1 Plant is based on ar. anal-ysis of documents submitted by the Commor. wealth Edison Co. to the Nuclear Regula-tory Commission and a site visit.
The site visit was conducted by Messrs.
T. Dunning and L. Derderian of the NRC; Mr. M. Antonetti of Gage Babcock &
Associates, Inc., under contract to Brookhaven National Laboratory, and Mr. J.
Riopelle, consultant to BNL.
Mr. Riopelle was under contract to BNL to review the manual firefighting capabilities of the station, along with r.dministrative controls.
The Dresden-1 review has been conducted under the direction of Mr. E. A.
MacDougall and myself of the 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 comoonents, systems and structures with both ccmbustibles and the associated fire detection ana suppression systems.
Our review has been limited to the aspects of fire protection related to the protection of the public from the standpoint of radiological h9alth and safety.
We have not co.isidered 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 r dioactive material.
The proposed modifications represent a significant increase in the level of protection against serious fire associated hazards.
Respectfully yours, fD r.)
!l 6
Robert E. Hall, Group Leader Reactor Engineering Analysis REH/ EAM/dt 45L
pISTRIBUTION M. Antonetti 1
I. Asp 1
V. Benaroya E. Blackwood 1
R. Cerbone 1
D. Eisenhut 1
R. Feit 1
R. Ferguson 5
R. Hall 1
S. Handuer 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
H. Todosow 2
J. Townle' 1
NRC - Division of Technical Information and Control 2
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