ML20043D961
| ML20043D961 | |
| Person / Time | |
|---|---|
| Issue date: | 05/01/1990 |
| From: | Michelson C Advisory Committee on Reactor Safeguards |
| To: | Carr K NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0369, ACRS-SL-369, NUDOCS 9006110313 | |
| Download: ML20043D961 (4) | |
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UNITED STATES f
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8 NUCLEAR REGULAIORY COMMISSION 1
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r,I ADVISORY COMMITTEE O.i REACTOR SAFEGUARDS o
W ASHINGTON, D. C. 20665 May 1, 1990 The Honorable Kenneth M. Carr Chairman i
U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Chairman Carr:
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED SIXTIETH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, APRIL 5 7 AND 18-19, 1990 During its 360th meeting, April 5-7 and 18-19, 1990, the Advisory Committee on Reactor Safeguards discussed several matters and completed the reports noted below.
A summary of the activities of the Committee during this meeting is given below.
Reports to the Commission e
Proposed Rule on Nuclear Power Plant License Renewal (Report j
to Chairman Carr, dated April 11, 1990).
e NRC Safety Research Procram Budaet (Report to Chairman Carr, dated April 11, 1990).
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e Severe Accident Research Proaram (Report to Chairman Carr, 1
dated April 24, 1990).
Evolutionary Licht Water Reactor Certification Issues and Their Relationshio to Current Reculatory Recuirements (Report to Chairman Carr, dated April 26, 1990).
QTHER MATTERS CONSIDERED BY THE COMMITTEE e
Reculatory Impact Survey Dr. Murley, NRR, and Mr. Davis, Region III, briefed the l
Committee-on the results cf the regulatory impact survey of selected utilities conducted by NRC senior management groups.
These groups surveyed 13 utilities.
The senior-managers of the NRC are in the process of assessing the results of the survey to determine whether NRC should change-its regulatory approach to ensure continued safe operation of nuclear power plants.
The Committee plans to-gpk discuss this matter with the staff after the staff has completed its final assessment and taken a position on the need for changing the regulatory approach.
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I The Honorable Kenneth M. Carr 2
May 1,1990 i
e Containment Desian Criteria for Future Plants Mr. Ward, Chairman of the containment Systems Subcommittee, reported on the joint meeting of the ACRS Subcommittees on containment-Systems and Structural Engineering held on April 4, 1990.
This was the fifth meeting held so far to gather information for use by the ACRS in its development of proposed ce66.ainment design criteria for future plants.
The Committee plans to continue the discussion of this matter during future meetings.
o Nuclear Power Plant License Renewal The Committee heard presentations from and held discussions with representatives of the office of Nuclear Regulatory Research, Nuclear Management and Resources Council, Northern States Power Company, and the Yankee Atomic Electric Company regarding the proposed rule on license renewal. The Committee issued a report to the Commission on this matter dated April 11,.1990.
e ADoointment of New ACRS Members k
The committee discussed briefly the new procedures approved by Chairman Carr for appointment of new ACRS members that were transmitted through a memorandum from Sandy Showman, SECY, to Ray Fraley, ACRS, dated March 23, 1990.
These~ procedures apparently supersede the previous procedures approved by then NRC Chairman Zech that are delineated in memoranda dated March 14, 1988 and February 8, 1989.
The Committee plans to discuss this matter further during the June 7-9, 1990 meeting.
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Meetina with Japanese ReDresentatives The Committee tentatively agreed to meet with representatives of Hitachi, Toshiba, Tokyo Electric, and MITTI to discuss issues related to the ABWR and other items of mutual interest.
i-L This meeting is tentatively scheduled to be held in Japan l
during September 1990.
SUBCOMMITTEE MEETINGS Since the issuance of tt:e last summary report of the ACRS activities, the following subcommittee meetings have been held:
Advanced Pressurized Wate? Reactors, April 3, 1990 The e
Subcommittee reviewed the Licensing Review Basis document developed by the Combustion Engineering for the System 80+
standard design.
i
.The Honcrable Kenneth M. Carr 3
May 1,1990
~e-Joint Containment Systems and Structural Enaineerina, April 4, 1990 - The Subcommittees discussed the development of proposed containment design criteria for future plants.
o Joint Severe Accidents And Probabilistic Risk Assessment, April 18, 1990 - The Suocommittees continued their discussion of NUREG-1150, " Severe Accident Risks: An Assessment for Five U.S. Nuclear Power plants."
e Joint Thermal Hydraulic Phenomena and Core Performance, April 27, 1990 - The Subcommittees continued their review of the boiling water reactor core power stability pursuant to the core power oscillation event at LaSalle County Station, Unit 2.
SCHEDULE FOR THE 361ST MEETING The Committee agreed to the following tentative schedule for the 361st ACRS meeting, May 10-12, 1990:
Briefing and discussion e
Reactor Operatina Exoerience (Ocen) of NRC activities r31ated to reactor operations and nuclear plant operating events.
e Sitina of Nuclear Power Plants (ODen) - Briefing by NRC staff representatives regarding their efforts to decouple nuclear plant siting and source term.
Decommissionina of Nuclear Power Plants'(ODynl - Briefing by e
representatives of the NRC staff regarding the status of decommissioning of the Shoreham Nuclear power Station (SECY-90-084).
o Individual Plant Examination for External Events (Ocen) -The Committee will hear a briefing and discuss a proposed NRC generic letter regarding consideration of external events in Individual Plant Examinations (IPEs).
e Maintenance Performance Indicators (ODen) - Briefing by ERC staff representatives on the status of work related to the development of maintenance performance indicators.
Briefing by repre-e NRC Acina Research Procram (ODen) sentatives of NRC staff and industry as appropriate, regarding the NRC research program on aging of nuclear power plant components, systems, and structures.
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The Honorable Kenneth M. Carr 4
May 1,1990
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e BWR Core Power Instability (Ocen/ Closed) - Report by-cognizant Subcommittee Chairmen of the April 27, 1990 joint meeting of the ACRS Subcommittees on Thermal Hydraulic Phenomena and on Core Performance regarding proposed corrective actions to deal l
1 with the issue of BWR core power instabilities.
Sincerely, i
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Carlyle Michelson 1
Chairman j
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