ML20024B536
| ML20024B536 | |
| Person / Time | |
|---|---|
| Site: | Salem, Seabrook, Yankee Rowe, 05000000, Clinch River |
| Issue date: | 04/29/1983 |
| From: | Ebersole J Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0285, ACRS-SL-285, NUDOCS 8307090095 | |
| Download: ML20024B536 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 3
- p WASHINGTON, D. C. 20555 April 29,1983 j
i Honorable Nunzio J. Palladino Chairman U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Dr. Palladino:
Subject:
TWO-HUNDRED-SEVENTY-SIXTH MEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, APRIL 14-16, 1983 276th ACRS Meeting The Committee met with representatives of the NRC Staff and Public Service Company of New Hampshire, acting as agent for the Seabrook Owners Group (the Applicant), to review the request for an Operating License for the Seabrook Station, Units 1 and 2.
The Connittee provided an interim report on low power operation for this plant.
The Committee met with representatives of the NRC Staff and the U.S.
Department of Energy, the Tennessee Valley Authority, and the Project Management Corporation (the Applicants) to complete its review of the rcquest for a permit to construct the Clinch River Breeder Reactor plant.
The Committee met with representatives of the NRC Staff and Yankee Atomic Electric Company (the Licensee) to review the results of the Systematic Evaluation Program, Phase II, as it has been applied to the Yankee Nuclear Power Station.
The Committee discussed the safety implications of the Regionalization of NRC Staff Activities.
Copies of reports on the subjects noted above have been sent to you.
The Committee was briefed by members of the NRC Staff regarding circuit-breaker malfunctions at the Salem Nuclear Generating Station on February 22 and 25, 1983.
The Committee met with J.
Heltemes, Director of AE00, to discuss the proposed rule on Immediate Notification Requirements (10 CFR 50.72) and the revised Licensee Event Report (LER) Rule (10 CFR 50.73).
The Committee was briefed by the NRC Staff, ORNL, and Science Applications, Inc.
regarding the NRC/0RNL Accident Precursor Study, NUREG/CR-2497,
" Precursors to Potential Severe Core Damage Accidents:
1969-1979, A Status Report," Volumes 1 and 2.
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f Honorable Nunzio J. Palladino April 29, 1983 Subcommittee Activity Since the last -report of ACRS activities, the following subcommittee meetings have been held:
Qualification Program for Safety-Related Equipment, in Washington, DC on March 15, 1983 to discuss " Seismic Qualification of Equipment for Operating Reactors," Status of USI A-46, the NRC research program for plant aging, and the use of seismic experience data for seismic qualification of certain types of equipment Clinch River Breeder Reactor Working Group on Structures and Materials, in Washington, DC on March 16-17, 1983 to continue the review of the CRBR construction permit application Regulatory Policy and Procedures, in Washington, DC on March 16, 1983 to discuss Nuclear Regulatory Reform and NRC regionalization Waste Management, in Washington, DC on March 18, 1983 to review and comment on the Department of Energy's proposed general guidelines for recommendation of high-level waste repository sites Joint Metal Components and Combination of Dynamic
- Lcads, in Washington, DC on March 29, 1983 to review the reevaluation of double-ended guillotine pipe break design requirements for Westinghouse PWR plants Seabrook Nuclear Power Station Units 1 and 2, in Hampton Peach, NH on April 1-2, 1983 to review the application of the Public Service Company of New Hampshire for an operating license Reactor Operat; ions, in Washington, DC on April 6,1983 to review the draft final rules, "Immediate Notification Requirements," 10 CFR 50.72, and the revised " Licensee Event Report (LER) Rule,"
10 CFR 50.73 Systematic Evaluation Program (SEP), in. Washington, DC on April 7, 1983 to discuss the SEP review of the Haddam Neck Plant Joint Reliability and Probabilistic Assessment and Extreme External Phenomena, in Washington, DC on April 13, 1983 to discuss NREP (National Reliability Evaluation Program) and the use of probabilistic assessment in the licensing process, systems interactions, the Safety Goal Policy Evaluation Plan, seismic design margins, and the reeval-uation of design basis earthquakes for plants in the Eastern United States.
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Honorable Nunzio J. Palladino April 29,1983 i
Future Agenda i
The following items are tentatively scheduled for consideration during the 277th ACRS Meeting, May 12-14, 1983.
Lacrosse Nuclear plant--SEP review Haddam Neck Nuclear Plant--SEP review GESSAR-II--PDA for improved GESSAR-238 nuclear island Resolution of USI-A-44, " Station Blackout"--ACRS comments on NRC Staff recommendations NRC/0RNL Precursor Study--Complete ACRS Report Meeting with NRR--Discuss ongoing regulatory activities fleeting with NRC Commissioners--Discuss the NRC Severe Accident Research Program and the Accident Source Term Program Sincerely,
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Jesse Ebersole Acting Chairman t
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