ML19281A840
| ML19281A840 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/12/1979 |
| From: | Randy Hall, Macdougall E BROOKHAVEN NATIONAL LABORATORY |
| To: | Ferguson R Office of Nuclear Reactor Regulation |
| References | |
| CON-FIN-A-3107 NUDOCS 7904110310 | |
| Download: ML19281A840 (4) | |
Text
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Ir1TERIM REPORT-NRC Rmh Y 00"i
[ 3.,~,U,,, iiY^.
Accession tio.FQOW/f)vjp Contract Program or Project
Title:
Fire Protection in Operating Nuclear Power Stations Yankee Rowe Subject of this Document:
Safety Evaluation Report Review Letter Report Type of Document:
Robert E. Hall and E.A. MacDougall Author (s):
Date of Document:
March 12, 1979 Responsible !!RC Individual Mr. R.L. Ferguson and HRC Office or Division:
Division of Operating Reactors U.S. Nuclear Regulatory Comission 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 IJational Laboratory Upton, !JY 11973 Associated Universities, Inc.
for the U.S. Department of Energy Prepared for U.S. Nuclear Regulatory Comission Washington, D. C.
20555 Under Interagency Agreement EY-76-C-02-0016 HRC FIH Ho. A-3107 i
INTERIM REPORT C n~m-f ch "'od ~
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79041103/ 6 Asshunce Report
BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.
Upton. Ncw Ycrk 11973 Department of Nuclear Energf (516i 34541L.
March 12, 1979 h
Division of Operating Reactors
,5.3 U.S. Nuclear Regulatory Commission g
Washington, D.C.
20555 g3- ]%
k A) g' 1
Attention:
Mr. Robert L. Ferguson Plani. Systems Branch 5Gs
Subject:
Fire Protection in Operating Fu' clear Power Stations Yankee Rowe Safety EvaluationsRecort Review N Y'S The Safety Evaluation Report,,as9feyeJcped jointly by the NRC staff and Brookhaven National Laboratory, (fpit), c@equately reflects the concerns and recommendations of the consulta s.3 Tfroughout the reevaluation of Yankee Rowe there has been general ag
' nt between the NRC staff and the BNL con-sultants.
Based on present dat the proposed fire orotection, 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 Suoervision Electrical val /e 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 Mr. R.E. Hall.
The preceding statements are based on a detailed reevaluation of the fire protection program as implemented by the Yankee Atomic Electric Comoany at the Yankee Rowe Nuclear Power Station.
The analysis covered a review of the fire prevention, detection and suppression capabilities of the plant as inter-faced with the nuclear systems requirements. This was accomplished by utilizing a review team concept with members from Brookhaven National Laboratory (BNL) and the Nuclear Regulatory Commission Division of Operating Reactors staff.
The fire protection evaluation for the plant is based on an analysis of documents submitted by the Yankee Atomic Electric Company, the Nuclear Reg-ulatory Commission, and a site visit.
The site visit was conducted by Mr. T.
Dunning and Mr. L. Derderian of the NRC; Mr. M.A. Antonetti of Gage-Babcock and Associates, Inc. under contract to Brookhaven National Laboratory; 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 admin-istrative controls.
l R.L. Ferguson March 12, 1979 The Yankee Rowe 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 cubmitted 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 related to the protection of the public from the standpoint of radio-logical health and safety. He have not considered aspects of fire protection associated with life safety of onsite personnel and with property protectica, 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, Ro5ert E. Hall, Group Leader Reactor Engineering Analysis REH:EAM:sd
4 DISTFIBUTION M. Antonetti 1
- 1. Asp 1
V. Benaroya 1
E. Blackwooo 1
W. Butler 1
R. Cerbone 1
D. Eisenhut 1
R. Fei t 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. Tel ford 1
H. Todosow 2
J. Town 1 ey 1
PDR 2