ML19318C330
| ML19318C330 | |
| Person / Time | |
|---|---|
| Issue date: | 06/19/1980 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0251, ACRS-SL-251, SL-0251, SL-251, NUDOCS 8007010359 | |
| Download: ML19318C330 (3) | |
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NUCLEAR REGULATORY COMMISSION
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 g
%,***** $,g June 19, 1980 Honcriole John F. Ahearne Chairman U. '. Nuclear Regulatory Commission Washington, DC 20555
Subject:
TWO-HUNDRED-FORTY-SECOND MEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, JUNE 5-7, 1980
Dear Dr. Ahearne:
The Advisory Committee on Reactor Safeguards held its 2.42nd meeting in Washington, DC on June 5-7, 1980.
Items considered at this meeting are summarized below:
The Committee met with members of the NRC Staff to discuss the pro-posed Emergency Planning Rule,10 CFR Part 50 and Part 70.
Tne Committee completed its review of NUREG-0667, Transient Response of B&W-Designed Reactors.
The Committee has sent you separate reports on the matters noted above.
The Committee sent you a letter responding to your questions regarding the Committee's report of March 11, 1980 on Draft 3 of the NRC Action Plan, NUREG-0660.
The Committee heard a report from the NRC Staff on the status of work related to seismic qualification of auxiliary feedwater systems in PWRs.
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A memorandum was sent to the Acting Executive Director for Operations recommending that increased effort be devoted to this activity.
The Committee sent a memorandum to the Acting Executive Director for Operations recommending that the NRC Staff develop a rationale for including quantitative estimates in seismic safety evaluation and deci-sion making.
The Committee completed a memorandum to the Acting Executive Director for Operations recommending a value-impact assessment of the effects of seismic scram on various accident or transient scenarios.
Copies of the memoranda noted above have been provided to you.
The Committee met with members of the NRC Staff and representatives of the Tennessee Valley Authority to review the application for a full-power r
operating license for the Sequoyah Nuclear Plant.
Additional time will l
be scheduled during the 243rd ACRS Meeting to complete this review.
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Honorable John F. Ahearne June 19,1980 The Comittee met with members of the NRC Staff to discuss the proposed FY-1982 budget for the NRC's Reactor Safety Research Program. Additional time will be scheduled during the 243rd ACRS Meeting for the Committee to complete its annual report to the Commission on the proposed research budget.
The Comn.ittee heard a report from the NRC Staff regarding the April 19, 1980 incident at the Davis-Besse Nuclear Power Plant during which decay-heat removal capability was lost.
The Committee approved a memorandum from the ACRS Executive Director to the Director of the Office of Nuclear Reactor Regulation regarding the status of various ACRS recommendations and comments cited in H. Denton's memorandum of December 28, 1979 on the status of action on ACRS requests and recommendations.
The Committee directed the ACRS Executive Director to reply to the May 23, 1980 memorandum from the Director of the Office of Nuclear Reactor Regula-tion regarding the adequacy of a single refueling water storage tank, to determine an anticipated schedule for resolution of this matter.
Since the last report of ACRS activities, the following subcommittee meetings have been held:
Class-9 Accidents, in Chicago, IL on May 9, 1980 Reactor Operations, in Washington, DC on May 20, 1980 Site Evaluation and Reactor Radiological Effects, in Washington, DC on May 21-22, 1980 Sequoyah Nuclear Station, in Washington, DC on June 2,1980 Reactor Safety Research, in Washington, DC on June 3,1980 Regulatory Activities, in Washington, DC on June 4,1980 Extreme External Phenomena, in Washington, DC, on June 4,1980 Since the last report of ACRS activities, Committee members have met with the following foreign organizations to discuss nuclear safety matters:
Reactor Safety Committee (RSK), in Obrigheim, FRG, on May 19-20, 1980 Groupe Permanent Reactor (GPR), in Fontenay-aux-Roses, France, on May 28-29, 1980 l
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Honorable John F. Ahearne June 19, 1980 The following items are tentatively scheduled for consideration during the 243rd ACRS Meeting, July 10-12, 1980:
Sequoyah Nuclear Stetton Units 1 and 2 - full power operation ACRS Report to the Comm!ssion on the proposed Safety Research Budget Fire Protection of Nuclear Facilities - proposed NRC rule Reply to Chairman Ahearne regarding Main Coolant Pump Trip and Critaria for HPCI Termination Reply to Commissioner Gilinsky regarding the use of In-Core Thermocouples.
Sincerely yours, Milton S. Plesset Chai rman l
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