ML20043D964
| ML20043D964 | |
| Person / Time | |
|---|---|
| Issue date: | 05/29/1990 |
| From: | Michelson C Advisory Committee on Reactor Safeguards |
| To: | Carr K NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0370, ACRS-SL-370, NUDOCS 9006110316 | |
| Download: ML20043D964 (5) | |
Text
{{#Wiki_filter:........... -. p,3 Rig 8,. - UNITED STATES - f .f'g' g-g NUCLEAR REGULATORY COMMISSION -{' ,k ADVISORY COMMITTEE ON REACTOH SAFEGUARDS W ASHINGToN, D. C. 20566 May 29, 1990 The Honorable Kenneth M.-Carr Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dear Chairman Carr
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED SIXTY FIRST MEETING, 'OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MAY'10-11,:1990 During its 361st meeting, May 10-11, 1990, the Advisory Committee-on Reactor Safeguards discussed several matters and completed tho' report noted below. A summary of the activities of the Committee during this meeting is given below. Report to the Commission e Procosed Generic-Letter Sucolement on Individual Plant Examination for Severe Accident Vulnerabilities Due to External Events (Report to Chairman Carr, dated May 15, 1.990). . Summary of Matters Considered-bv the Committee NRC Research Procram on Plant-Acing-e The Committee heard presentations'by and held discussions with representatives-of the Offico of Nuclear Regulatory Research (RES) and their contractors regarding the status of. activities associated with the Nuclear Plant Aging Research (NPAR) program. In addition, the committee heard a presentation fron. NUMARC with respect to industry initiatives for handling aging-related issues, o Reactor Ooeratina Events Representatives of the Office of Nuclear Reactor Regulation (NRR) briefed the Committee on the following' operating events and certain regulatory actions: 480v circuit breaker problem at, the Pilgrim nuclear = plant. Recent problems with Essential Service Water Systems. Reactor vessel head crack's at-Quad Cities Unit 2 and Fitzpatrick nuclear plants. DESIGNATED ORIGINAL 6 9006110316 900$29 'g c0 n (,R \\0 RS Cortiflod By f // 6-
(.. 1 The Honorable Kenneth M. Carr 2 May 29, 1990 Regulatory actions in response to fuel = failures caused j by BWR channel box bowing - Bulletin 90-02, " Loss of - Thermal Margin Caused by Channel Box Bow, " March 20, j 1990. I The Committee requested that the NRR staff keep the committee ! j informed of the results of the investigations associated with i the reactor vessel head cracks, especially those related-to i the Fitzpatrick plant. 1 e Individual Plant Examination for External Events The Committee heard presentations by and held discussions with b representatives of RES and NRR'regarding their activities in implementing the Commission's Severe Accident Policy-for hazards due to external events. . The Committee discussed a proposed Supplement to Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities, and a draft, NUREG document that is intended to provide guidance and. recommendations to - the industry regarding the scope and acceptable methodologies for performing the IPEEE. Also, the Committee heard presentations from the Yankee Atomic Electric company and its consultant regarding their approach for seismic margins assessment for use in the IPEEE program. The Committee provided a report to the Commission on this .i matter. e BWR Core Power Stability I Dr.
- Catton, Chairman of the Thermal Hydraulic Phenomena Subcommitteo, provided a report of the' April 27, 1990 combined-meeting of the Thermal Hydraulic Phenomena and Core i
Performance Subcommittees at which the status of the staff's efforts in resolving the BWR core power stability issue were discussed. The-Subcommittee plans to discuss this matter further prior to recommending it to the full Committee for consideration. Sitina of Nuclear Power Plants e Representatives of RES briefed the Committee on the status of a study being conducted by
- them, as-directed by the-Commission, to examine _an alternate approach of decoupling siting from reactor design. -
The RES staff stated that a Commission paper, including the. results. of the study and-proposing a plan of action and schedule'will be submitted to the Commission on June 30, 1990. A draft of this Ccamission paper is-expected to be made available to the ACRS as soon as possible. The Committee plans to discuss the staff's proposed plan of action and schedule during the June 7-9, 1990 meeting.
( t l I The Honorable Kenneth M. Carr 3 Phy 29,1990 l e ' Maintenance Performance Indicators l .c Representatives of the Office for Arialysit era Evaluation of Operational Data (AEOD) provided an inform. tion briefing to the Committee on the status of a dwow ration project for-1 the development of maintenance performance indicators that was i initiated in response to the Commission's direction. The AEOD [ staff stated that through the coordination of NUMARC and the Institute of Nuclear Power Operations (INPO), six utilities volunteered to participate in this. project. The staff presented the findings and accomplishments of this project-and y stated that it plans to develop a Commission paper, including. its recommendations on this matter. e Decommissionina of the Shoreham Nuclear Power Station 1 The -NRR staff provided an' information briefing to the Committee on the current status-of activities related to the i decommissioning of the Shoreham Nuclear power Station. i e ProDosed NRC Staff's Schedule for Review of the Evolutionary Licht Water Reactors (ELWRs) and Passive Advanced Liaht Water Reactors (ALWRs) The NRR staff briefed the Committee regarding the process, schedule, and resources for the review of ELWRs and passive r ALWRs that are delineated in SECY-90-146. I Some' members of the. Committee stated that the schedule proposed initially in SECY-90-065 for ACRS review of ABWRs was tight but reasonable. They expressed concern' that the proposed schedule in SECY-90-146 is too compressed. They expressed similar concern about the proposed schedule for'the ACRS review of the EPRI ALWR Requirements Document. Dr. Miller, NRR, stated that if the Committee prefers to review the staff's SERs on each module of the ABWR and provide interim reports to the EDO, the staff Will try to accommodate. such reviews. He proposed a similar approach for review of the EPRI ALWR Requirements Document.. Additional ELWR Certification Issues 4 The Committee members discussed additional issues, other'than those proposed by the staff in SE0Y-90-016, that may be eppropriate for consideration in the certification process of ELWRs. The Committee plans to continue the discussion of this matter during the June 7-9, 1990 meeting.
The !!onorable Fenneth M. Care 4 May 29,1990 e Proposed Resolution of Generic issue 84. "CE PlhDis Without PORVs" Mr.
- Ward, Chairman of the Decay lleat Removal Systems Subcommittee, briefed the Committee on the staff's proposed resolution of Generic Issue 84.
There are six plants *with CE l reactors (Palo Verde Units 1-3, San Onofre Unita 2 and 3, and Waterford) operating without PORVs or any other primary system j manual high capacity venting capability. Generic ~ Issue 84 was established to determine whether such provisions 'should be r required for these plants. Based on ' the resultsLof-its evaluation, the staff plans to resolve Generio Issue 84' without recommending installation of
- PORVs, or other equivalent ' features on the above mentioned plants.
The committee-plans to discuss this matter with the staff during the June 7-9, 1990 ACRS meeting.- Meetina with Jacaneb;S Reoresentatives e The originally proposed dates, September 16-21, 1990, 'for meeting with Japanese representatives in Tokyo have' been deferred based on my discussion with you. The new tentative dates proposed by the. Committee for-this meeting are December 3-7, 1990. I Arrangements for this meeting will be deferred pending approval by you following the ACRS-RSK meeting in June. i i Subcommitteo Meetinos Since the issuance of ' the last summary report of the ACRS activities, the following Subcommittee meetings have been held: e Joint Rr41 ability Assurance 'and Materials and Metallurav, May 8, 1D90 The Subcommittee discussed the status of activities associated with the NRC's Nuclear Plant Aging Research Program and the industry initiatives for handling aging-related issues, Imoroved Liaht-Mater Reactors, May 9, 1990 - The Subcommittee o discussed the passive plant designs of Westinghouse, Combustion Engineering,.and General Electric,' and also EPRI's future passive plant requirements document. Materials and Metallurov, May 24, 1990 The Subcommittee e i discussed the low charpy upper shelf energy matters relating to the integrity of reactor pressure vessels, the lleavy i Section Steel Technology (IISST) program, and other related matters.
e The Honorable Kenneth M. Carr S }ey 29,1990 Schedule f.gr the 362nd Meetina The Committee agreed to the following tentative schedule for the 362nd ACR8 meeting, June 7-9, 1990. Certification of Evolutionary LWRs (Oogni - Discussion of issues other than those identified in SECY-90-016 for consid-eration in evolutionary light-water reactor certification. e Interim Standard for Hot Particles (Ocen) - Briefing regarding the status of proposed revisions to the standard for exposure of the skin from radioactive particles. Briefing e Accident Seauence Precursor Proaram (Oceni, regarding the Accident Sequence Precursor Program at the ORNL Nuclear Operations Analysis Center. Status of Imolementation of the Safety Goal Policy (ODen) Discussion of the status of implementation of the NRC's Safety Goal Policy. i Sy.ggematic Assessment of Licensee Performance (Ocent j e Briefing and discussion regarding proposed revisions to the NRC Manual Chapter on Systematic Assessment of Licensee Performance, Discussion of proposed nature e NRC Research Procram (Open) of the annual ACRS report to the U.S. Congress. i e ACRS Subcommittee Activities (Ocen) - Hear and discuss reports of ACRS subcommittees regarding the status of assigned activities such as the low charpy uppet shelf energy matters relating to the integrity of reactor prensure vessels, results of the MOV tests performed in FRG, and the reliability of i dampers. A report of the ACRS Subcomm:ttee on Planning and Procedures will also be discussed. I e Sitina of Nunlear Power Plants (ODcEl Briefing and discussion regarding NRC staf f activitius to decouple nuclear plant siting from source term. e Nuclear Power Plant Technical Snecifications (Ocen) - Briefing regarding the status of NRC staff activities regarding the devolegment of risk-based technical specifications, o Generic Issue 84: CE Plants Without PORVs (Ocen)_ - Briefing and discussion of proposed resolution of this generic issue. Sincerely, ) W j Carlylo Michelson l Chairman l l 1}}