ML20043D947
| ML20043D947 | |
| Person / Time | |
|---|---|
| Site: | Point Beach, Robinson, Zion  |
| Issue date: | 03/27/1990 |
| From: | Michelson C Advisory Committee on Reactor Safeguards |
| To: | Carr K NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0368, ACRS-SL-368, NUDOCS 9006110301 | |
| Download: ML20043D947 (4) | |
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8 NUCLEAR REGULATORY COMMISSION g
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, p-ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D C. 20666 1
March 27, 1990 l
The Honorable Kenneth M. Carr chairman U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Chairman Carr:
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED FIFTY-NINTH MEETING-OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS,-
MARCH 8-10, 1990 During its 359th meeting, March 8-10, 1990, the. Advisory Committee on Reactor Safeguards discussed several matters and completed the' report noted below.
A copy of this report has already: been-provided to you.
In addition, the Committee authorized Mr. FraleyL to transmit a memorandum noted below to the EDO.
A summary of the activities of the committee during this meeting is given below.
Reoort to the Commission J
Containment Performance Imorovement-Procram Proposed =
I Recommendations for Mark II. Mark III. Ice Condenser, and-Dry
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Containments (Report to Chairman Carr, dated March 13,l1990).
Memorandum to the EDO SECY-90-057.
Advance Notice of Pronosed Rulemakina.
"Accentance of Products Purchased for Use in Nuclear Power Plant Structures. Systems and Components" (Memorandum - from R. F.
Fraley, ACRS, for J.
M. Taylor, EDO, dated-March 14, 1990).
Consistent with the Committee's decision, Mr.
Fraley has informed Mr. Taylor that the Committee ~ has decided-: not to review the above mentioned Advance Notice-of ' Proposed' Rulemaking.
Other Matters Considered by the Committee Evolutionarv Licht Water Reactor Certification Issues The committeo discussed the comments and recommendations' -
i proposed by cognizant Subcommittee Chairmen / members regarding the 15 evolutionary LWR certification issues identified by the staff in'SECY-90-016.
Owing to lack of time, the: Committee-was not able to complete the discussion-of all these items.
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.g The Honorable Kenneth M. Carr 2
March 27,1990 1
'l Consequently, it decided to continue.the discussion of this matter and an associated ACRS report to the Commission during i
l the April 5-7, 1990 ACRS meeting.-
In addition, the Committee decided to discuss the-following issues with representatives of the staff ~ and industry (as appropriate) during the April 5-7, 1990 ACRS meeting to gather add itional information:
ABWR Containment Vent Design Equipment Survivability' q
Reactor Operatina Exoerience The NRR staff briefed the Committee regarding the following operating events:
125V DC system circuit breaker design problem at Point Beach Units 1 and 2, November 7, 1989.
Potential failure of the swing bus under undervoltage condition in the LPCI system of certain BWRs,, October: 12, 1989.
Inadequate NPSH of auxiliary feedwater pump at : H. B.
Robinson Unit 2, August 16, 1989.
-r AEOD Activities L
The AEOD staff briefed'the Committee on the status / results 1.
of their following studies:
Review of Thermal Stratification in nuclear power plant piping systems j
Evaluation of Safety Equipment Outages at Zion Magtina with the Reactor Safety Committee (RSK) of the Federal l
Rebublic of Germany (FRG).
The Committee identified several specific topics for discussion with the Gurman RSK during the meeting in June 1990.
These topics. include. items related to LWR safety such as severe-accident management, use of PRA~in the regulatory process,- performance of : motor operated valves',.
-plant-life extension / aging,,and' fire protection.
Regarding
. Modular HTGR facilities members identified items such as severe accident scenarios, containment design / performance requirements, and-core-performance.
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-i The Honorable Kenneth M. Carr 3-March 27,1990 1
i Subcommittee Meetinag Since the last summary report of the ACRS activities, the following Subcommittee meetings have been held:
Severe Accidents, March 20-21, 3990 The Subcommittee discussed the Severe Accident Research Plan.
Reaulatory Policies and Practices, March 26, 1990 - The Subcommittee discussed the draft rule on License Renewal.
Joint Extreme External Phenomena and severe Accidents, March 27, 1990
.The Subcommittees discussed the Individual i
Plant Examination for External Events (IPEEE) program, and.the staff's position on fire protection features for Evolutionary LWRs listed in SECY-90-016.
Schedule for the 360th Meetina The Committee agreed to the following tentative schedule for the-360th ACRS Meeting, April 5-7, 1990.
Evolutionary Licht-Water Reactor Certification Issues (Ocen)
Hear briefings regarding selected certification issues such as equipment survivability anu ABWR containment vent design.
Also-continue discussion of the proposed ACRS comments and recommendations regarding Evolutionary Light-Water Reactor Certification Issues and their relationships to current regulations. Representatives of the NRC staff and 'the nuclear industry will participate, as appropriate.
Nuclear Power Plant License Renewal (Onen)
Revicw and comment on the proposed NRC rule regarding renewal of operating licenses-for nuclear power plants.
Representatives of the NRC staff and the nuclear industry will participate, as appropriate.
Individual Plant Examination for External Events (Ocen)
Review and comment on the proposed NRC generic letter and supporting documentation regarding Individual Plant Examination for External Events.
Representatives of the HRC staff and the nuclear industry will participate, as appropriate.
Severe Accident Research Plan (Ocen). - Briefing and discussion of the status of work in the NRC. Severe Accident Research Program.
Representatives of the NRC staff and their contractors will participate, as appropriate.
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The Honorable Kenneth M. Carr 4
March 27,1990 NRC Safety Research Procram ' (Open) --Discuss proposed ACRS report on the budgeting of the NRC safety research program.
Sincerely,
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l Carlyle Michelson P'
chairman-l O
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