ML19241B747
| ML19241B747 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/03/1979 |
| From: | Randy Hall BROOKHAVEN NATIONAL LABORATORY |
| To: | Ferguson R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907230513 | |
| Download: ML19241B747 (3) | |
Text
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BROOKHAVEN NATIONAL LABORATORY u o] J rj']
1 ASSOCIATED UNIVERSITIES, INC.
Upten. New verk 11973 Cepcrtment of Nuc!ecr Energy (516) 345 2144 July 3, 1979 Division of Operating Reactors V. S. Nuclear Regulatory 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 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 t.he health and safety of the public is not endangered.
The following exception represents a diffaring ^ngineering point of view that should be evaluated by the NRC staff.
Valve Suoervision - Section 4.3.1 Electrical valve supervision should be provided on all valves controlling fire water systems and sectionalizing 'alves. The present proposal of admin-istrative controls or locks is unaccepi.able. See letter dated July 13, 1977 to Mr. R. L. Ferguson from Mr. 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 recomend an additional 5200 CFM be on hand at the site to be more consistent with the BNL recommended minimum portable ventilation.
Interior Hose Stations - Section 4.2.1.4 We recocmend replacing the 1-1/2" nozzles with " Class C, all-spray electric type nozzles" where electrical shock hazard is a consideration for personnel safety. A suitable alternative is 1-1/2" adjustable nozzles providing a spray stream pattern without going through the straight stream made to open or close the nozzle.
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Mr. R. L. Farguson 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 analysis covered a review of the fire prevention, detection and suppression capabilities of the plant as interfaced with the nuclear systems requirements. This was acccmplished by utilizing a review team concept with members from Brookhaven National Laboratory and the Nuclear Regulatory Cornission Division of Operating Reactors staff.
The fire protection evaluation for the Dresden-1 Plant is based on an anal-ysis of documents submitted by the Comonwealth 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 Becokhaven National Laboratory, and Mr. J.
Riopelle, conruitant to BNL. Mr. Riopelle was under contract to BNL to review the manual firefighting capabilities of the station, along with administrative controls.
The Dresden-1 review I3s been conducted under the direction of Mr. E. A.
MacDou7all and myself of the Reactor Engineering Analysis Group at BNL. We have eviewed 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
.tems.
Our review has been limited to the aspects of fire protection related t.
he protection of the public from the steadpoint of radiological health and me.
We have not considered aspects of fite prntection associated with life s Fat; of onsice personnel and with property prt tection, unless they impact the health and safety of the public due to the releass of radioactive material.
The proposed modifications represent a significant increase in the level of protection against serious fire associated hazards.
Respectfully yours, N
obert E. Hall, Group Leader Reactor Engineering Analysis REH/ EAM/dt 4Cjk 250
s DISTRIBUTION M. Antonetti 1
I. Asp 1
V. Benaroya 1
E. Blackwood 1
R. Cerbone 1
D. Eisenhut 1
R. Feit 1
R. Ferguson 5
R. Hall 1
S. Hanauer 1
E. Imt:: o 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. Townley 1
NRC - Division of Technical Infonnation and Control 2
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