ML20148J658
| ML20148J658 | |
| Person / Time | |
|---|---|
| Issue date: | 12/11/1987 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0341, ACRS-SL-341, NUDOCS 8801270457 | |
| Download: ML20148J658 (4) | |
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o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20555 December 11, 1987 The Honorable 1.ando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Comission Washington, DC 20555
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED AND THIRTY-SECOND MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, DECEMBER 3-4, 1987 1
The Advisory Comittee on Reactor Safeouards held its 332nd meeting in Washington, D.C. on December 3-4, 1987 A sumary of actions is pre-sented below:
ACRS REPORTS / RECOMMENDATIONS The Comittee prepared a report providing ACRS Comments on the Memoran-dum from V. Stello, EDO, Dated October 7,1987 Regarding the Embrittle-ment of Structural Steel.
(Report to the Executive Director for Opera-tions dated 12/8/87)
The Committee prepared a report providing ACRS Coments on the Revised ASB 3-1 of Standard Review Plan 3.6.1, Requirements for Arbitrarily Postulated det Impingement Effects in the Break Exclusion Tine.
(Report to the Executive Director for Operations dated 12/8/87)
Copies of the reports noted above have been sent to you.
OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS The NRC Staff briefed the Committee on the efforts of an NRC panel established to coordinate the Staff review of the Philadelphia Electric Company's organizational changes in management as a condition for restart of the Peach Bottom Nuclear Plant.
The Comittee expressed interest in additional information regarding the criteria that the NRC will use to judge the effectiveness of licensee management.
The Comittee discussed future ACRS actions concerning its review of TVA management changes and the restart of TVA nuclear power plants.
It was agreed that the Comittee will continue its discussion of this matter during the ACRS February meeting.
A subcomittee meeting is also being scheduled.
The NRC Staff briefed the Comittee on the status of the proposed implementation plan for the Safe'.y Goal Policy Statement.
The final 8801270457 871211 PDR ACRS SL-0341 PDR j
The Honorable iando W. Zech 2
Decembar 11, 1987 draft of the plan is expected to be issued in late January. The Comit-tee will continue its review of the plan after receipt of the NRC Staff final draft.
The Director of the Office of Nuclear Regulatory Research briefed the Comittee on current activities of the Offte, particularly tne establishment of an NAS expert review comittee to idvhe the Direct 6r, RES, and on the possible impact of bv<iget re@ctions.
The Comittee agreed to defer the preparation of coments on instrument air systems until after1 the NRC Staff has prioritized this generic issue.
The Comittee agreed to continue consideration of com6nts on the proposed resolution of USI A-47, "Safety Implications of Control-Sys-tems," during its January meeting.
Representatives from the EPRI ALWR Utility Steering Comittee briefed
.the Cormiittee on the Steering Comittee's efforts to develop a licensing requirements document for advanced light water reactors.
There was not sufficient time to discuss the passive reactor concept for smaller plants that is being developed. The representatives from EPRI agreed to return and to discuss the passive safety system concept.
This session has been scheduled for the ACRS February meeting.
The NRC Staff briefed the Comittee on the Staff's proposed response to the ACRS letter of December 17, 1986, regarding concerns about the performance of BWR Mark I containments. The NRC Staff plans to issue an interim report with recomendations by April 30, 1988.
The ACRS plans to review the NRC Staff report when received.
Election of Officers.
The Committee elected Dr. Kerr and Dr. Remick as Chairman and Vice-Chairman, respectively, for CY 1988 The Comittee agreed that the request by Pacific Gas and Electric Company for a one-year delay in the completion of the Diablo Canyon Long Term Seismic Program is acceptable.
Since the last report of ACRS activities, the following subcomittee meetings have been held:
Decay Heat Removal Systems, November 17, 1987 - To discuss (1) the decision by Toledo Edison not to install a dedicated blowdown system at Davis Besse, (2) implications of secondary side water level control in B&W once-through-steam generators vis-a-vis operator actions in accident situations, and (3) implications of the Diablo Canyon loss of shutdown cooling event vis-a-vis lack of steam generator water box vents.
The Honorable Lando W. Zech 3
December 11, 1987 Thermal Hydraulic Phenomena, November 18-19, 1987 - To review key elements of the NRC Five-Year Thermal Hydraulic Research Program and to discuss the status of NRC action on a potentially unanalyzed large break LOCA scenario.
Quality and Quality Assurance in Design and Construction, November 24, 1987 - To review QA experience in Readiness Reviews.
Safety Philosophy, Technology and Criteria, December 2,1987 - To discuss the NRC Staff proposed implementation plan for the Safety Goal Policy Statement and proposed final resolution for USI A-17 (SystemsInteraction).
FUTURE AGENDA The following items have been proposed for consideration during the ACRS meeting on January 7-9, 1988:
Advanced Boiling Water Reactor - Briefing regarding design features of GE proposed advanced SWR.
Operating Experience at Nuclear Facilities - Briefing and discus-sion of recent operating incidents.
Equipment Qualification - Briefing and discussion regarding pro-posed equiprrent qualification program for nuclear power plants.
Leak-Before-Break Requirements - Briefing and discussion regarding proposed final revision of 3.B.3 of the NRC Standard Review Plan, Leak-Befor'e-Break EvaTuation Procedures.
Nuclear Industry Initiatives - Briefing by representatives of the nuclear industry regarding industry initiatives to improve the operation and regulation of reactors.
AEOD Activities - Discussion regarding items of mutual interest regarding activities of the NRC Office for Analysis and Evaluation of Operational Data.
Safety Implications of Control Systems - Discuss proposed ACRS coments/ recommendations regarding proposed NRC Staff resolution of this unresolved safety issue (USI A-47).
Seismic Design Criteria - Briefing and discussion regarding pro-posed NRC final resolution of this unresolved safety issue (VSI A-40).
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The Honorable Lando W. Zech 4
December 11,1987 Renewal of Nuclear Power Plant Licenses - Briefing and discussion of proposed NRC policy statement regarding renewal of nuclear power plant licenses.
Sincerely, William Kerr Chainnan I
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