ML17055C195

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Forwards Safety Evaluation on Util 831222 Request for Relief from 10CFR50,App R Requirements Re Fire Detectors & Automatic Suppression Sys.Supporting Analysis for Partial Coverage Detection & Suppression Sys Approved
ML17055C195
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 08/06/1986
From: Zwolinski J
Office of Nuclear Reactor Regulation
To: Mangan C, Seibert C
NIAGARA MOHAWK POWER CORP.
Shared Package
ML17055C196 List:
References
GL-83-33, TAC-53390, NUDOCS 8608190160
Download: ML17055C195 (6)


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+**y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 AUG 06

)98'ocket No. 50-220 Niagara Mohawk Power Corporation ATTN:

Hr. C. V. Mangan Senior Vice President c/o Hiss Catherine R. Seibert 300 Erie Boulevard West

Syracuse, NY 13202

Dear Mr. Mangan:

SUBJECT:

SAFETY EVALUATION - APPENDIX R, FUI L COVERAGE DETECTION AND SUPPRESSION SYSTEMS (TAC 53390)

Re:

Nine Mile Point Nuclear Station, Unit No.

1 Generic Letter 83-33, dated October 19, 1983, stated that to satisfy the requirements of Subsections III.G.2.b., III.Ci.2.c and III.G.2.e of Appendix R

to 10 CFR Part 50, fire detectors and automatic suppression systems need to be installed "throughout" the fire area.

By letter dated December 22, 1983, you requested an exemption from these requirements, as interpreted in GL 83-33, for the Reactor Building.

At the Appendix R Lessons Learned Workshop held in Region I on April 18, 1984, the NRC informed the industry of a draft revised interpretation of the above noted subsections that would accept partial coverage detection and automatic suppression systems that were supported by a fire hazards analysis as meeting the requirements of the subsections.

Accordingly, by letter dated May 11, 1984, you withdrew the exemption request dated December 22, 1983.

However, the supporting analysis for the partial coverage detection and suppression systems remained for staff review and approval.

During the period January 21-25, 1985, the NRC inspected the facility and reviewed your analysis for the reactor building.

The inspection team requested additional information, and the issues were referred to NRR for resolution.

By letter dated February 11, 1985, you provided the additional information requested by the inspection team.

The above-mentioned revised interpretation was approved by the Commission on March 6, 1986 (SECY 85-306/306B).

Therefore, we have evaluated the lack of full coverage detection and suppression systems for compliance with this interpretation, and find it acceptable.

In addition, we find your Fire Break BiosieoiiO 8SO806 PDR ADOCK 05000220 F

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AUG 06 1gas C. V. Mangan Zone concept to be acceptable.

The Safety Evaluation supporting our findings is enclosed.

Sincerely, ORIGIMI SIGHED BY John A. Zwolinski, Director BWR Project Directorate 0'1 Divisio'n of BWR Licensing

Enclosure:

Safety Evaluation cc w/enclosure:

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gUG 0 6 1986 Mr. C. Y. Mangan Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.

1 cco Troy B. Conner, Jr., Esquire Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, N.

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Washington, D. C.

20006 Frank R. Church, Supervisor Town of Scriba R.

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Oswego, New York 13126 Niagara Mohawk Power Corporation ATTN:

Mr. Thomas Perkins Plant Superintendent Nine Mile Point Nuclear Station Post Office Box 32

Lycoming, New York 13093 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126.
Lycoming, New York 13093 John W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
Syracuse, New York 13202 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza
Albany, New York 12223

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