ML20002B705
| ML20002B705 | |
| Person / Time | |
|---|---|
| Issue date: | 10/27/1980 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| Shared Package | |
| ML20002B702 | List: |
| References | |
| NUDOCS 8012220503 | |
| Download: ML20002B705 (3) | |
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4 UNITED STATES
!7 w[,j NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
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f W ASHINGTON, D. C. 20555 c
o October 27, 1980 Honorable John F. Ahearne Chairman U. S. Nuclear Regulatory Commission
'4ashington, DC 20555 TWO-HUNDRED-FORTY-SIXTH MEETING OF THE ADVISORY COMMITTEE ON
Subject:
SAFEGUARDS, OCTOBER 9-11, 1980
Dear Dr. Ahearne:
The Advisory Ccmmittee on Reactor Safeguards held its 246th meeting in Washington, DC on October 9-11, 1980.
Items considered at this meeting are sumarized below:
The Committee completed its report to the Commission on proposed Quantita-tive Risk Accectance Criteria.
Final editing of this report is in progress.
The Committee met with members of the NRC Staff to discuss the proposed fire crotection rule (10 CFR Part 50, Appendix R).
A report with Committee comments regarding this rule has been sent to you.
The Committee prepared a memorandum to the Executive Director for Operations providing its comments on the use of quantitative risk analysis in making decisions regarding the seismic desian and oualification of auxi_liary _. _
feedwater systems _._.c The Committee-approved a memorandum from the ACRS Executive Director to the -__
NRC Executive Director for Operations providing coments on.the.NRC Staff's preliminary plans for-addressing the requirements in Secal10 of the FY-80 NRC Authorization _ Bill (Bingham Amendment).
Cooies of the memoranda noted above have been provided to you.
The Ccmmittee met with Commissioners Bradford and Gilinsky to discuss Commissioner Gilinsky's suggestions regarding the content and femat of e
ACRS reports.
ACRS comments on the-NRC Staff's current position regarding resolution e
of the generic item, AT4S.
Further Committee ccmments regarding the adequacy of the NRC Staff's e
parameters and procedures for identifying unresolved safety issues to be reported to the Congress.
8012220
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Honorable John F. Ahearne October 27, 1980 Consideration of waste management and disposal matters, including the e
possible coordination of this program with those for other hazardous industrial wastes, Means for making the ACRS report to the NRC on the Reactor Safety e
Research Budget more meaningful.
The use of quantitative risk assessment in the regulatory process.
e The Committee was briefed by members of the NRC Staff regarding the current status of the proposed Nuclear Data Link.
Since the last report of ACRS activities, the following subcommittee meetings have been held:
Ad Hoc ACRS Subccmmittee/FRG Representatives, in Washington, DC on September 19, 1930 Waste Management, in Washington, DC on October 3,1980 Reactor Operations, in Washington, DC on October 7,1980 Safety Philosophy, Technology, and Criteria, in Washington, DC on October 8, 1980 Extreme External Phenomena, in Washington, DC on October 8,1980 Dresden Nuclear Plant Unit 1, in Washington, DC on October 8,1980 Advanced Reactors, in Washington,- DC on Octoberz8,.1980 The following items are tentatively scheduled for consideration during the 247th ACE 3 Meeting, November 6-8, 1980:
Regulatory Guide 1.97 - " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and.Following an Accident" General Electric Test Reactor -- seismic. modifications and proposed operation Diablo Canyon Nuclear Power Plant -- systems interactions related to seismic events ACRS Report Format -- comments regarding Commissioner Gilinsky's suggestion to eliminate the final paragraph
Honorable Jchn F. Ahearne October 27, 1980 BWR Scram Systems -- adequacy of system design TMI-2 -- status of recovery operations (Staff report to ACRS)
ACRS Generic Issues Applicable to LWRs -- review of current status Meeting with the NRC Commissioners -- items tentatively scheduled include:
Use of Quantitative Risk Assessment in the Regulatory Process a.
particularly as Applied to Auxiliary Feedwater Systems b.
Fornat of ACRS Reports North Anna Nuclear Plant -- Decay Heat Removal System (Clarification c.
of Commissioner Gilinsky's request for ACRS consideration of changes in decay heat removal systems) d.
New Safety Concepts for New Nuclear Plants -- interim response per your request for ACRS carnents.
Sincerely yours, f^
Milton S. Plesset Chairnan
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