ML20125D998
| ML20125D998 | |
| Person / Time | |
|---|---|
| Issue date: | 10/18/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0243, ACRS-SL-243, NUDOCS 8001240048 | |
| Download: ML20125D998 (3) | |
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NUCLEAR REGULATORY COMMISSION
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8 WASHINGTON, D. C 20555 j
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October 18, 1979 Honorable Joseph M. Hendrie Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
'INO-HUNDRED-THIRT'l-FCURTH MEETING CF THE ADVISCRY CCMMITTEE ON REACTOR SAFEGUARDS, CCTCBER 4-6, 1979 IN WASHINGTON, CC
Dear Dr. Hendrie:
The Advisory Committee on Reactor Safeguards held its 234th meeting in Washington, CC on October 4-6, 1979.
Items considered at this meeting are summari::ed briefly below:
The Committee continued its evaluation of the March 28, 1979 accident at Three Mile Island Nuclear Statien Unit 2 (T.I-2) and the implications of this accidant. The Committee members also ey. changed preliminary views regarding the effectiveness of the nuclear regulatory process.
The Committee responded to an inqui n from Rep. Morris K. Udall regarding the develop-ent of a hybrid standard nuclear plant design. A copy of the resulting letter has been provided to you.
'Ihe Committee responded to an inquiry from Comnissioner Gilinsky regarding control of xenon emissions which ma'i occur during nuclear plant accidents.
A copy of the resulting letter has been provided to you.
The Committee discussed a request from Commissioner Bradford to identify URC regulations that the Committee believes should be changed, and to comment on the adequacy of the process for implementation of Comnittee recommendations in this area. This matter has been scheduled for further consideration during the 235th ACRS Meeting.
We Committee provided comments to you regarding the scope and pace of the NRC's Systematic Evaluation Program.
The Committee provided the Executive Director for Operations with its comments regarding the proposed analysis of systems interactions at the Indian Point Nuclear Generating Station Unit 3.
A copy of this memorandum has been provided to you.
The Cornittee discussed procedures for developing its annual report to Congress on the NRC's Reactor Safety Research Prcgram, and the setting of priorities for the projects in this program. mis matter will require additional work and has been scheduled for further discussion.
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5 Honorable Joseph M. Hendrie October 18, 1979 i
The Committee was briefed by members of the NRC Staff regarding the se-quence cf events during the September 25, 1979 transient at the North Anna Power Station Unit 1.
The Ccmmittee discussed with members of the NRC Staff the current actions and fucure plans as a follow-on to the analyses of the TMI-2 accident.
Since the last report of ACRS activitics, the following subcommittee meetings have been held:
Reliability and Probabilistic Assessment, in Los Angeles, CA on September 11-12, 1979 Fluid Dynamics, in Los Angeles, CA on September 13-14, 1979 Waste Managenent, in Washington, DC on September 18-19, 1979 T1I-2 Accident Bulletins and Orders, in Washington, DC on October 2,1979 TMI-2 Implications Re. Nuclear Power Plant Cesign, in Washington, DC on October 3,1979.
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The following items are tentatively scheduled for consideration during the 235th ACRS Meeting, November 8-10, 1979:
l Review of Regulatory Processes and Procedures -- effectiveness of program I
Westinghouse NSSS Using Ice Condenser Containments -- TMI-2 accident implications Diablo Canyon Nuclear Power Plant Unit 2 -- TMI-2 accident implications Resolution of ACRS Generic Items -- evaluation of status NRC Staff Task Action Plans -- status of resolution Westinghousa USSS/ Salem Nuclear Generating Station Unit 1 -- Steam Line Break Implications Regulatory Guide 1.97, Instrumentation for DiRs to Assess Accident condi-tions -- preposed revision NURDG 0600, Investigation of TMI Accident -- TMI-2 accident implications ATWS - status of resolution
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Honorable Joseph M. Hendrie October 18, 1979
!JRC Rules and Regulations -- proposed changes Wolf Creek Generating Station - Seismic Design Basis Sincerely yours, 1'W^
Max W. Carbon Chairman
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