ML19345B992
| ML19345B992 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah, Susquehanna, North Anna  |
| Issue date: | 11/21/1980 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| References | |
| NUDOCS 8012030675 | |
| Download: ML19345B992 (3) | |
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NUCLEAR REGULATORY COMMISSION g,-
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November 21, 1980 g;
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3 Chairman @ohnFLAhearne Honorable U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
TWO-HUNDRED-F0RTY-SEVENTH MEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, NOVEMBER 6-8, 1980
Dear Dr. Ahearne:
The Advisory Committee on Reactor Safeguards held its 247th meeting in Washington, DC on November 6-8, 1980.
Items considered at this meeting are summarized below:
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The Committee met with Governor Bruce Babbitt, Chairman of the Nuclear Safety Oversight Committee, to discuss methods to strengthen the ACRS' role in the regulatory process.
The Committee met with you and the other Commissioners to discuss clarifica-tion of Commissioner Cilinsky's request for,'CRS' comments regarding proposed changes in the residual heat removal system of the North Anna Power Station Unit 2, new safety concepts for future nuclear power plant designs, and de facto use of quantitative safety goals in the regulatory process.
The Committee met with representatives of the NRC Staff and the General Electric Company to discuss the seismic modifications and proposed operation of the General Electric Test Reactor (GETR).
The Committee met with members of the NRC Staff and representatives of Pacific Gas and Electric Company to discuss the study of potential systems interactions induced by possible seismic events performed for the Diablo Canyon Nuclear Power Plant.
The Committee continued its consideration of the proposed Nuclear Data Link.
The Committee responded to Commissioner Gilinsky's memorandum of October 2, 1980 regarding the format of findings in ACRS reports on license applications.
The Committee compic its review of Regulatory Guide 1.97, Instrumentation for Light-Water-Coo. y
- uclear Power Plants to Assess Diant and Environs Conditions During and Following an Accident.
Copies of the letters and memoranda pertaini..g to the above have been provided to you.
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Honorable John F. Ahearne. November 21, 1980 The Committee met with members of the NRC Staff to discuss the status of the effort to develop, a system to control combustible gases for the Sequoyah Nuclear Power Plant Unit One.
Additional work on this matter is planned for future meetings.
Since the.last report of ACRS Activities, the following site visits and subcommit-i tee meetings have been held:
i Site Visit to Idaho Nuclear Engineering Laboratory, Idaho Falls, ID on October 21, 1980 ECCS, in Idaho Falls, ID on October 22-23, 1980 Transportation of Radioactive Materials, in Washington, DC on October 27, 1980 General Electric Test Reactor in Washington, DC on November 4, 1980 Regulatory Activities, in Washington, DC on November 5,1980 Procedures and Administration, in Washington, DC on November 5,1980 The following items are tentatively scheduled for consideration during the 248th ACRS Meeting, December 4-6, 1980.
Three Mile Island Nuclear Station Unit 1 -- Restart Regulatory Guides regarding Utilities Management Structure and Technical Support North Anna Power Station Unit 2 -- Consider installation of a heat exchanger in the High Pressure Injection System and environmental oualification -of the Residual Heat Removal System, Plant Staffing, results of Augmented Low Power Test Program, Steam Generator Tube Integrity, and Probabilistic Assessment of the Plant Clarification of ACRS. Report on ATWS per GE Request
.. ACRS Generic Itens List -- Update of list Hydraulic Scram System for BWR Nuclear Plants New Safety Concepts for future reactor designs NRC Waste Confidence Proceeding -- Items needing further consideration I
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Honorable John F. Ahearne
- November 21, 1980 Indian Point Station Unit 2 -- Cavity flooding incident / plant status Meeting with NRC Commissioners 4
ACRS Review of. Procedures for certification of shipping containers for radioactive materials.
ACRS Review of Long. Range Safety Research Program.
r Sincerely yours, 1
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-A Milton S. Plesset Chairman i
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