ML20237K841
| ML20237K841 | |
| Person / Time | |
|---|---|
| Issue date: | 06/19/1987 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-A-44, REF-GTECI-EL, TASK-A-44, TASK-OR ACRS-SL-0355, ACRS-SL-355, NUDOCS 8708270316 | |
| Download: ML20237K841 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
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g WASHINGTON, D. C. 20555
...s June 19, 1987 The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Comission Washington DC 20555
Dear Chairman Zech:
SUDJECT: THREE HUNDRED AND TWENTY-SIXTH MEETING 0F THE ADVISORY COMMITTEE ON PEACTOR SAFEGUARDS, JUNE 4-6, 1987 The Advisory Comittee on Reactor Safeguards held its 326th meeting in Washington, D.C. on June 4-6, 1987.
326TH ACRS MEETING:
The Comittee prepared Comments on Disposal of Mixed Waste. The Comit-tee commended the NRC Staff for its efforts in resolving relevant issues in the disposal of mixed waste but raised questions about the definition:
of mixed waste.
The Committee prepared a Report on Proposed Generic Letter on Individual Plant Examinations for Severe Accident Vulnerabilities.
The Committee identified deficiencies in the NRC Staff's proposed generic letter on individual plant examinations for severe accident vulnerabilities and provided recommendations.
The Committee prepared Comments on Quality Assurance Programs for a High-Level Waste Repository.
The Committee urged NRC and DDE to define acceptance criteria and to establish a schedule for conducting Quality Assurance readiness reviews with discrete steps throughout the-HLW repository development process.
The Committee prepared Comments on the NRC Staff Proposal for the Resolution of USI A-44, " Station Blackout." The Committee considers the proposed resolution of USI A-44 to be workable and comends the Staff for its efforts; however, it does not recommend issuance of the final rule at this time.
Rather, it recommends that the Staff continue to work with NUMARC.
If by September it is found that the NUMARC initia-tives will not be effective or timely, or will be unduly difficult to evaluate on a plant-to-plant basis, then the Staff should issue the final rule.
The Comittee prepared Comments on Draft NUREG-1226, " Development and Utilization of the NRC Policy Statement on the Regulation of Advanced Nuclear Power Plants."
(Report to Chairman Zech dated 6/9/87)
The Comittee identified several terms and concepts in the Draft Policy 8708270316 870619
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DESIGNATED ORIGINAL PDR ACRS SL-0355 PDR.
Certified By i
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The Honorable Lando W. Zech, Jr.
2 June 19, 1987 i
J Statement that should be clarified, and recommended that more definitive guidance for sabotage-protection considerations be included in the Policy Statement.
The Comittee proposed an International Workshop on-Quality in Design 3
and Construction of Nuclear Power Plants.
The Comittee recommended that the NRC consider the organization and sponsorship of an Interna-tional Workshop on Quality in Design and Construction and offered to j
participate in the planning of the Workshop.
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Reports'on the subjects noted above have been sent to you.
t The Committee prepared Coments on Proposed Revisions to Standard Review Plan Sections 6.5.2, " Containment Saray as a Fission Product Cleanup System" and 6.5.5.,
Suppression Poo's as Fission Product Cleanup Sys-tems."
The Committee inf ormed the Executive Director for Operations that it endorses the general approach proposed by the NRC Staff in revisions to the Standard Review Plan concerning decontamination factors applicable to containment spray and suppression pools.
The Committee prepared Coments on Proposed Revised Standard Review Plan Section 3.6.2, " Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping," Dated October 2, 1986.
The Committee advised the Executive Director for. Operations that it sees no problem with the issuance of the revised Section 3.6.2 of the Standard Raview Plan provided that the guidance in the Mechanical Engineering Branch Technical Positions 3-1,. subpart B.I.c.(4) is imple-mented.
The Committee informed the Executive Director for Operations of ACR$
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Action on Proposed Revision 2 of Regulatory Guide 1.100, " Seismic Qualification of Electric and Mechanical Eauipment f or Nuclear Power Plants."
The Comittee concurred with the Staff in its proposal to issue for public coment Proposed Revision 2 to Regulatory Guide 1.100, Draft 4, dated December 4,1986.
The Committee, in response to a request from Senator John Glenn, provid-l ed its views on the proposal to establish a nuclear safety board for overview of DOE activities (S.1085).
The Committee provided Senator Joseph Biden with its comments on his l
proposed bill, S.14, to create a Nuclear Safety Board for overview of NRC activities. The letter cites previous ACRS comments on such a Board ~
and explains that the Committee is still divided in its views on' this l
l question.
A copy of the memoranda sent to the Executive. Director for Operations l
and of the letters sent to Senator Glenn.and to Senator Biden have been 4
i sent to you.
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J The Honorable Lando W. Zech, Jr.
3 June 19, 1987 l
The Committee was briefed by the NRC Staff regarding recent operating incidents and events at nuclear power plants.
Operating events dis-i cussed included:
Management Control of Plant Activities at Ft. Calhoun 1, Catawba 2 and Oyster Creek 1; and events at Oconee 2, WNP 2 and Diablo Canyon.
The Committee discussed follow-up action to the operat-i ing events discussed.
Mr. Ebersole expressed his satisfaction with the l
NRC Staff's action to date.
He suggested, however, that at each brief-j ing on operating events the Staff should describe its follow-up actions.
Core liquid level indication systems, called into question by the Diablo I
Canyon event, will be discussed further by the ACRS during the July ACRS
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meeting.
I The Committee agreed to continue its discussion of safety features at
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foreign nuclear power plants.
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The Committee was briefed by the NRC Staff regarding proposed NRC plans f
to extend the licenses of nuclear power plants beyond their 40-year lifetime.
Further discussion of this matter is anticipated during the August ACRS meeting.
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Harold Denton briefed the Comittee on the proposed NRC Strategic Plan.
The Committee discussed with the Executive Director for Operations his reply to the ACRS letter of January 15, 1987 on recommendations for j
improved safety in future LWR power plant design.
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The Committee agreed to the appointment of a subcommittee to develop a l
response (or scope of work required to prepare such a response) to Chairman Zech's request that the ACRS address the feasibility, benefit and cost effectiveness of selected and combined systems recommended in i
the ACRS letter of January 15, 1987 per SECY memo to R. F. Fraley dated April 22, 1987.
Since the last report of ACRS activities, the following subcommittee neetings have been held:
l Waste Management, May 18 and 19,1967 - To discuss both high-and low-level waste management programs and waste management research.
Nuclear Plant Chemistry, May 19, 1987 - To discuss the proposed revisions to the Standard Review Plan concerning decontamination l
factors applicable to containment spray and suppression pools, i
Generic Items, May 27, 1987 - To discuss the process involved in identifying, prioritizing, resolving, and implementing generic issues, and unresolved safety issues.
Severe Accidents, May 28, 1987 - To continue the review of the proposed generic letter for Individual Plant Examinations as part of the NRC Implementation Plan for the Severe Accident Policy Statement.
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'2 The Honorable Lando W. Zech, Jr.
4 June 19, 1987 Joint Meeting, Severe Accidents /Probabilistic Risk Assessnlent, June 3,1987 - To discuss NUREG-1150, " Reactor Risk Reference Document."
FUTURE AGENDA The following items have bean proposed for consideration during the ACRS meeting July 9-11, 1987:
Im) roved Safety for Future Light Water Reactors - Discuss proposed ACRS action / comments regarding systems proposed for consideration to improve safety in future LWRs Control Room' Habitability - Discuss proposed ACRS. report regarding control room habitability in nuclear power plants Safety Features in Foreign Nuclear Plants - Discuss proposed ACRS report to the NRC regarding the applicability of safety features'ir, foreign nuclear plants to reactors in the United States TVA Nuclear Performance Plan - Discuss proposed ' revision of TVA Nuclear Performance Plan NRC Severe Accident Policy - Discuss proposed NRC Reactor. Risk ReferenceDocument(NUREG-1150)
Millstone Nuclear Power Station Unit 1 - Discuss the integrated l
safety assessment program report for this station Three Mile Island Nuclear Station Unit 2 - Report and discussion of core removal and examination activities by representatives of INEL Meeting with the Director, NRC Office of Nuclear Material Safe-cuards and Safety - Discuss topics of mutual interest Activities of NRC Office for Analysis and Evaluation of Operational Data - Review of 1987 case studies and startup-plant studies Assessment of _0perating Experience - Briefing' and discussion of the assessments of selected nuclear power operating incidents and events Sincerely, i
f William Kerr Chairman
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