ML18130A629: Difference between revisions
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| issue date = 08/28/1979 | | issue date = 08/28/1979 | ||
| title = Discusses Proposed Fire Protection SER Review.Recommends Further Evaluation of Section Re Electrical Valve Supervision on Valves Controlling Fire Water Sys & Sectionalizing Valves | | title = Discusses Proposed Fire Protection SER Review.Recommends Further Evaluation of Section Re Electrical Valve Supervision on Valves Controlling Fire Water Sys & Sectionalizing Valves | ||
| author name = | | author name = Hall R | ||
| author affiliation = BROOKHAVEN NATIONAL LABORATORY | | author affiliation = BROOKHAVEN NATIONAL LABORATORY | ||
| addressee name = | | addressee name = Ferguson R | ||
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | ||
| docket = 05000280, 05000281 | | docket = 05000280, 05000281 | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:* | ||
* | * I1------------------------------ | ||
------------------------------ | BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC. | ||
Upton. New York 11973 Department of Nuclear Energy (516) 345- 2144 August 28, 1979 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert L. Ferguson Plant Systems Branch | |||
Mr. Robert L. Ferguson Plant Systems Branch | |||
==Dear Bob:== | ==Dear Bob:== | ||
==Subject:== | ==Subject:== | ||
Fire Protection in Operating Nuclear Power Stations Surry 1 and 2 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 mendations of the consultants. | Fire Protection in Operating Nuclear Power Stations Surry 1 and 2 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 recom-mendations of the consultants. Throughout the reevaluation of Surry 1 and 2 there has been general agreement between the NRC staff and the BNL consultants. | ||
Throughout the reevaluation of Surry 1 and 2 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 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. | ||
Based 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. | Valve Supervision - OSER Section 4.3.1.3 Electrical valve supervision should be provided on all valves controlling fire water systems and sectionalizing valves. The present proposal of adminis-trative controls or locks is unacceptable. See letter dated July 13, 1977 to Mr. R. L. Ferguson from Mr. R. E. Hall. | ||
The following exception represents a differing engineering point of view that should be evaluated by the NRC staff. Valve Supervision | The fire protection evaluation for the Surry 1 and 2 plants is based on an analysis of documents submitted by the Virginia Electric and Power Company to the Nuclear Regulatory Commission and a site visit. The site visit was conducted by Messrs. E. Sylvester and E. Butcher of the NRC, Mr. I. Asp of Gage-Babcock and Associates, Inc. under contract to Brookhaven National Laboratory, and Mr. | ||
-OSER Section 4.3.1.3 Electrical valve supervision should be provided on all valves controlling fire water systems and sectionalizing valves. The present proposal of trative controls or locks is unacceptable. | 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. * | ||
See letter dated July 13, 1977 to Mr. R. L. Ferguson from Mr. R. E. Hall. The fire protection evaluation for the Surry 1 and 2 plants is based on an analysis of documents submitted by the Virginia Electric and Power Company to the Nuclear Regulatory Commission and a site visit. The site visit was conducted by Messrs. E. Sylvester and E. Butcher of the NRC, Mr. I. Asp 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 administrative controls. | * The Surry 1 and 2 review has been conducted under the direction of Mr. E. A. | ||
* | MacDougall and myself of the Reactor Engineering Analysis Group at BNL. | ||
* The Surry 1 and 2 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 components, systems and structures with both combustibles and the associated fire detection and VJ ~'7~ 79092003~ | ~. ....: | ||
I E | 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 VJ | ||
~'7~ | |||
79092003~ I E | |||
The proposed modifications represent a *significant increase in the level of protection against serious fire-associated hazards. REH/EAM:dt | |||
* ' | Mr. R. L. Ferguson August 28, 1979 Page Two suppression systems. Our review has been limited to the aspects of fire protec-tion related to the protection of the public from the standpoint of radiological 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. | ||
& Control 2 .. ____ ____J}} | REH/EAM:dt | ||
* DISTRIBUTION ' | |||
M. Antonetti 1 I. 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 E. Imbro 1 | |||
: w. Kato 1 J. Klevan 1 G. Lainas 1 C. Long 1 E. MacDougall 1 V. Stello 1 T. Telford 1 H. Todosow 2 J. Townley 1 NRC - Division of Technical Information & Control 2 | |||
.. ____ ____J}} |
Latest revision as of 02:16, 3 February 2020
ML18130A629 | |
Person / Time | |
---|---|
Site: | Surry ![]() |
Issue date: | 08/28/1979 |
From: | Randy Hall BROOKHAVEN NATIONAL LABORATORY |
To: | Ferguson R Office of Nuclear Reactor Regulation |
References | |
NUDOCS 7909200348 | |
Download: ML18130A629 (3) | |
Text
- I1------------------------------
BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.
Upton. New York 11973 Department of Nuclear Energy (516) 345- 2144 August 28, 1979 Division of Operating Reactors U. 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 Surry 1 and 2 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 recom-mendations of the consultants. Throughout the reevaluation of Surry 1 and 2 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 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 - OSER Section 4.3.1.3 Electrical valve supervision should be provided on all valves controlling fire water systems and sectionalizing valves. The present proposal of adminis-trative controls or locks is unacceptable. See letter dated July 13, 1977 to Mr. R. L. Ferguson from Mr. R. E. Hall.
The fire protection evaluation for the Surry 1 and 2 plants is based on an analysis of documents submitted by the Virginia Electric and Power Company to the Nuclear Regulatory Commission and a site visit. The site visit was conducted by Messrs. E. Sylvester and E. Butcher of the NRC, Mr. I. Asp 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 administrative controls. *
- The Surry 1 and 2 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 components, systems and structures with both combustibles and the associated fire detection and VJ
~'7~
79092003~ I E
Mr. R. L. Ferguson August 28, 1979 Page Two suppression systems. Our review has been limited to the aspects of fire protec-tion related to the protection of the public from the standpoint of radiological 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.
REH/EAM:dt
- DISTRIBUTION '
M. Antonetti 1 I. 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 E. Imbro 1
- w. Kato 1 J. Klevan 1 G. Lainas 1 C. Long 1 E. MacDougall 1 V. Stello 1 T. Telford 1 H. Todosow 2 J. Townley 1 NRC - Division of Technical Information & Control 2
.. ____ ____J