ML20148H251
| ML20148H251 | |
| Person / Time | |
|---|---|
| Issue date: | 01/20/1988 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0342, ACRS-SL-342, NUDOCS 8801270180 | |
| Download: ML20148H251 (4) | |
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- 'o "g UNITED STATES
!' n NUCLEAR REGULATORY COMMISSION i
{0 ; ,A ADVISORY COMMITTEE ON REACTOR SAFEGUARDS g WASHINGTON, D. C. 20555
- January 20, 1988 The Honorable Lando W. Zech, Jr. I Chairman U.S. Nuclear Regulatory Comission Washington, DC 20555
Dear Chaiman Zech:
SUBJECT:
THREE HUNDRED AND THIRTY-THIRD MEETING OF THE ADVISORY COMitIT- 1 TEE ON REACTOR SAFEGUARDS, JANUARY 7-8, 1988 l l
The Advisory Committee on Reactor Safeguards held its 333rd meeting in Washington, D.C. on January 7-8, 1988. A sumary of actions is present-ed below:
ACRS REPORTS / RECOMMENDATIONS The Comittee provided coments regarding the membership of the Advisory Corraittee on Reactor Safeguards in response to your memorandum of December 15, 1987 (Letter to Chairman Zech, dated January 11,1988) l OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS Representatives of the General Electric Company briefed the ACRS regard- I ing design characteristics of the GE Advanced Boiling Water Reactor l (ABWR). The ACRS Subcomittee on Advanced Boiling Water Reactors is l planning to continue discussions with GE and the NRC Staff on the ABWR l during a meeting in April 1988.
The NRC Staff briefed the Comittee on the procedures by which NRR l considers operating events. The Committee was also briefed on recent 1 operating events at Pilgrim-1 (loss of offsite power), at Fort Calhoun-1 l (water in the air system), and at Perry-1 (MSIV maloperation).
The Comittee discussed some issues that have been identified by ACRS members as important safety-related issues. It was agreed that this discussion will be continued during the ACRS February meeting.
1 The NRC Staff briefed the Comittee regarding problems with in-service testing of nuclear power plant components and systems.
The Comittee was briefed on recent activities of the ACRS Subcomit-tees on Metal Components and on Themal Hydraulic Phenomena. It was agreed that the ACRS not prepare a report on steam generator tube integrity at this time. The ACRS Subcomittee on Thermal Hydraulic g la g o 080120 SL-0342 PDR
l The Honorable Lando W. Zech, Jr. 2 January 20, 1988 Phenomena will follow the NRC Staff's effort to resolve Generic Issue 141, "Large Break LOCA Concurrent With Steam Generator Tube Rupture."
The Comittee was briefed on recent activities of the ACRS Subcomittee on Reliability Assurance. The members agreed to defer any action regarding this matter until the Qualification Risk Sco is available (estimated for March or April 1988 ACRS meeting) ping Study The Comittee discussed safety implications of control systems and the NRC Staff proposed resolution of USI A-47, "Safety Implications of Control Systems." Action was deferred pending further consideration of the manner by which the NRC Staff defines the scope of Generic Issues.
Issue A-47 is an example of an issue for which substantive changes have been made from the Scope as defined in NUREG-0606.
Representatives from NUMARC briefed the Comittee on recent nuclear industry initiatives to improve the operation of nuclear power plants and to improve the effectiveness of NRC-industry interfaces.
The NRC Staff briefed the Comittee regarding the proposed NRC policy for license renewals for nuclear power plants.
The Comittee discussed the ways in which the ACRS should participate in an International Workshop on Quality and Quality Assurance. It was i agreed that the ACRS should seek assistance of one of the National '
Laboratorit4 in organizing such a workshop.
The Comittee agreed not to comment at this time on the proposed reso- -
lution for USI A-40, "Seismic Design Criteria," and had no objection to the NRC Staff issuing it for public coment. The members expressed interest in seeing the proposed resolution after the NRC Staff's evaluation of public comments.
The Comittee agreed to request that the DOE Staff and the NRC Staff ,
brief the ACRS on their plans for submission and review of the DOE l Advanced Reactor Severe Accident Program (ARSAP).
Since the last report of ACRS activities, the following subcomittee meetings have been held:
Joint Metal Components and Thermal Hydraulic Phenomena, December 15, 1987 - To discuss the steam generator tube failure at the North !
Anna Nuclear Power Plant and to review R. L. Johnson's comments on i proposed revision to acceptance criteria for the ECCS rule with l respect to steam generator tube integrity. I l
Generic Items, December 16, 1987 - To discuss steps in implementing i the resolution of Generic Issues and Unresolved Safety Issues I (USIs) and the contribution to plant safety resulting from the l implementation of the resolution of Generic Issues and USIs. l I
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o The Honorable Lando W. Zech, Jr. 3 January 20, 1988 Reliability Assurance, December 16, 1987 - To explore the current status of equipment qualification research and to review plans for an equipnent qualification scoping study.
Reactor Operations, January 5,1988 - To discuss in-service test-ing.
Advanced Reactor Designs, January 6, 1988 - To discuss with the NRC Staff a proposed Commission paper regarding severe accidents and containment issues for DOE-sponsored advanced reactor designs.
FUTURE AGENDA The following items have been proposed for consideration during the ACRS meeting on February 11-13, 1988:
Advanced Reactors - Review and comment regarding key design fea-tures of advanced liquid metal cooled and gas cooled reactor plant designs.
Leak-Before-Break Requirements - Review and comnent on the proposed final revision of the NRC Standard Review Plan Section 3.6.3 re-garding leak-before-break evaluation procedures.
EPRI Requirements for Advanced LWRs - Briefing by EPRI representa-tives regarding proposed requirements for 600 MWe LWR nuclear power plants.
NRC Safety Research Program - Discuss proposed ACRS report to the U.S. Congress on the NRC safety research program and proposed ACRS comments to the NRC regarding methodology being considered for prioritization of research activities.
NRC Quantitative Safety Goals - Briefing and discussion regarding proposed implementation plan for the NRC Quantitative Safety Goals.
Maintenance Policy Statement - Discussion of and comment on, as appropriate, proposed NRC policy statement regarding nuclear power plant maintenance.
Diagnostic Evaluation Program (DEP) (Tentative) - Briefing on and discussion of NRC DEP including initial evaluation of the Dresden and McGuire nuclear power plants.
Systematic Assessment of Operating Experience - Briefing and discussion of recently completed AE0D studies of nuclear power plant operational data and related activities.
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The Honorable Lando W. Zech, Jr. 4 January 20, 1988 Nuclear Waste Management and Disposal - Report and discussion of I congressional redirection of the nuclear waste management and !
disposal program and related waste management issues.
TVA Nuclear Organization and Operations -
Review and comment 1 regarding proposed changes in TVA nuclear management structure and i proposed restart of TVA nuclear plants.
Safety Implications of Control Systems (Tentative) -
Discuss proposed ACRS connents regarding proposed NRC Staff resolution of l USI A-47, "Safety Implications of Control Systems." i Generic Issues - Discuss proposed ACRS connents and reconnendations i regarding the effectiveness of HRC Staff activities to resolve )
generic issues and USIs. 1 i
Sincerely, William Kerr Chairman
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