ML20205F123
| ML20205F123 | |
| Person / Time | |
|---|---|
| Issue date: | 10/28/1985 |
| From: | Lewis H Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0315, ACRS-SL-315, NUDOCS 8511040487 | |
| Download: ML20205F123 (4) | |
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UNITED STATES E
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October 28, 1985 Honorable Nunzio J. Palladino Chairman U. S. Nuclear Regulatory Commission Washington, D. C.
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Dear Dr. Palladino:
SUBJECT:
THREE HUNDRED AND SIXTH MEETING OF THE ADVISORY COPtilTTEE ON REACTOR SAFEGUARDS, OCTOBER 10-12, 1985 The Advisory Committee on Reactor Safeguards held its 306th meeting in Washington, D. C. on October 10-12, 1985.
Items considered at this meeting are sumarized below:
306th ACRS Meeting The Comittee met with you and the other Comissioners on October 10, f
1985, to discuss comments regarding the EPA Standards for a High-Level
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Radioactive Waste Re]ository which were published as a final rule on September 19, 1985, )y the U. S. Environmental Protection Agency.
The Comittee discussed the proposed NRC's Revised Advanced Reactor Policy Statement (SECY-85-279).
The Committee met with representatives of the NRC Staff, in response to the requests of Comissioners Asselstine, Bernthal, and Zech to review and evaluate impacts of natural phenomena on off-site emergency ia-sponse.
The Committee met with representatives of the NRC to review the proposed amendments to 10 CFR Part 50, Appendix E, Consideration of Earthquakes in Off-Site Emergency Planning as set forth in SECY-85-283, Final Amend-ments to 10 CFR Part 50, Appendix E, issued on August 21, 1985.
Reports on the subjects noted above have been sent to you.
The Comittee discussed proposed Revision 2 to Regulatory Guide 1.105,
" Instrument Setpoints for Safety-Related Systems," proposed Regulatory Guide, Task No. IC 609-5, " Criteria for Power, Instrumentation, and Control Portions of Safety Systems," and proposed Revision 1 to Regula-tory Guide 1.23, " Meteorological Measurement Program for Nuclear Power Plants."
The Committee's coments on the subjects noted above have beer, provided to the Executive Director for Operations. A copy has been sent to you.
DISIG;igED ORIGIWAU
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Honorable Nunzio J. Palladino October 28, 1985
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The Committee discussed a proposed ACRS report regarding the request for a Final Design Approval of the General Electric Standard Safety Analy-sis Report (GESSAR II) BWR/6 Nuclear Island Design applicable to future plants. Additional discussion regarding this matter is scheduled during the 307th ACRS meeting.
The Committee met with the NRC Staff to review the intended application of NUREG-0956, " Reassessment of the Technical Bases for Estimating Source Terms" and regulatory applications of new source tenn technology.
Additional discussion is planned during the 307th ACRS meeting.
The Comittee met with representatives of the NRC Staff and Toledo Edison Company to discuss the restart plan for the Davis-Besse Nuclear Power Plant, Unit 1 following the June 9,1985 loss of main and auxili-ary feedwater event.
The ACRS plans further consideration of plant restart when the NRC Staff has completed its safety evaluation report regarding this aspect of plant performance.
The Committee deferred action regarding the specific questions asked by Commissioner Asselstine in his letter of September 19, 1985 pending further consideration of this matter.
The Comittee heard a briefing by representatives of the Tennessee q
Valley Authority (TVA) and the NRC Staff regarding changes to the TVA h
Nuclear Organization in response to management problems at the corporate 4
and nuclear site levels.
Since the last report of ACRS activities, the following Subcommittee meetings have been held:
Human Factors, in Russellville, AR on September 17-18, 1985 to examine ANO-l's emergency procedures (symptom based) and to tour plant facilities Joint Structural Engineering and Seismic Design of Piping, in Washington, D.C. on September 23-24, 1985, to review the status of research programs on containment integrity, seismic margins, piping reliability, and other related matters Advanced Reactors, in Washington, D.C. on September 25, 1985, to discuss the proposed NRC policy statement for regulation of ad-vanced nuclear power plants Procedures and Administration, in Washington, D. C. on September 26, 1985, to discuss implementation of the recommendations of the Panel on ACRS Effectiveness Class 9 Accidents, in Washington, D. C. on September 27, 1985, to discuss draft NUREG-0956, " Source Term Reassessment," with the NRC Staff
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Honorable Nunzio J. Palladino October 28, 1985
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Davis-Besse, in Oak Harbor, Ohio on October 4, 1985, to review actions taken prior to restarting following the loss of feedwater incident and other related matters Reliability Assurance, in Washington, D. C. on October 8,1985, to continue discussions on valve reliability including development of a risk perspective on valve performance and the importance of valves from a safety standpoint Regulatory Activities, in Washington, D. C. on October 8,1985 to review:
(1) Regulatory Guide 1.23, Revision 1, " Meteorological Measurement Programs for Nuclear Power Plants," (2) proposed Regulatory Guide (Task No. IC 609-5), " Criteria for Power, In-strumentation, and Control Portions of Safety Systems," and (3)
Regula tory Guide 1.105, Revision 2,
" Instrument Setpoints for Safety-Related Systems" Joint Site Evaluation and Extreme External Phenomena, in Wash-ington, D. C. on October 9, 1985 to evaluate, from a probabilistic approach, the relative importance of natural phenomena in terms of their potential impacts on Emergency Planning and attempt to develop an ACRS consensus on this rulemaking regarding the Final r
Amendments to 10 CFR Part 50, Appendix E; Consideration of Earth-quakes in Emergency Preparedness State of Nuclear Power Safety, in Washington, D. C. on October 9, 1985, to discuss the draf t ACRS report on the " State of Nur.. ear Power Safety" Safety Philosophy, Technology, and Criteria, in Washington, D. C.
on October 9,1985, to continue review of the two-year trial use of the proposed Safety Goal Policy, the future use of safety goals, and containment performance guidelines Future Agenda The following items are tentatively scheduled for consideration during the 307th ACRS meeting, November 7-9, 1985:
Palo Verde Nuclear Generating Station -- Briefing by the NRC Staff regarding the operating experience and tha startup test program for Unit 1 Comittee to Review Generic Requirements -- Briefing by Chairman, j
CRGR, regarding activities of this NRC Comittee General Electric Standard Safety Analysis Report (GESSAR II) l Continue ACRS review of the FDA for this standardized NSSS l
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i Honorable Nunzio J. Palladino October 28, 1985
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Meeting with NRC Comissioners to discuss ACRS report on consid-eration of extreme environmental phenomena in emergency planning Briefing by NRC Staff of Recent Events at Operating Nuclear Power Plants R_eaver Valley Power Station Unit 2 -- OL review Use of Aptitude Selection Testing in the Nuclear Power Industry --
ACRS coments Nuclear Accident Source Tenn - ACRS corrnents regarding NUREG-0956, Source Term Reassessment Sincerely, 1/
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Harold W. Lewis Acting Chairman cf
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