ML20056C529
| ML20056C529 | |
| Person / Time | |
|---|---|
| Issue date: | 06/16/1993 |
| From: | Wilkins J Advisory Committee on Reactor Safeguards |
| To: | Selin I, The Chairman NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0406, ACRS-SL-406, NUDOCS 9306240422 | |
| Download: ML20056C529 (8) | |
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SL-0406 ? NUCLEAR REGULATORY COMMISSION n -{ E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS PDR f/4/hy o g . WASHINGTON, D. C. 20566 '+4 f i '] June 16, 1993 The Honorable Ivan Selin Chairman U.S. Nuclear Regulatory Comission Washington, D.C. 20555 l
Dear Chairman Selin:
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED AND NINETY SEVENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MAY 13-15, 1993, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 397th meeting, May 13-15, 1993, the Advisory Comittee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports, letter and memoranda, as noted. Reoorts Backfit Rule (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated May 20,1993) Draft Report of the PRA Workino Group (Report to Mr. James M. Taylor, Executive Director for Operations, from Paul Shewmon, ACRS Chairman, dated May 20, 1993) i Staff Anoroach for Assessino the Consistency of the Present Reculations with Resoect to the Comission's Safety Goals (Report-to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated May 26, 1993) Proposed Resolution of Generic Issue 105. "Interfacino Systems LOCA in-LWRs". (Report to Mr. James M. Taylor, Executive Director for Operations, from Paul Shewmon, ACRS Chairman, dated May 20, 1993) Letter Letter to Chairman Adolph Birkhofer, German RSK, and Chairman Francois Cogn6, French GPR, from Paui Shewmon, ACRS Chairman, dated May 25, 1993, q proposing a list of five topics for the Quadripartite Meeting of _ Advisory Comittees in October 1993. DEIGNATED ORIGINAL 9306240422 930616 i PDR ACRS PDR Certified By s SL-0406 i
r-4 i 2 Memoranda Proposed Resolution of Generic Issue 153. " Loss of Essential Service Water in LWRs" (Memorandum for Warren Minners, Director, Division of Safety Issue Resolution, NRR, from John T. Larkins, Executive Director, ACRS, dated May 24,1993) Resolution of Human Factors Generic Issues 4.4. " Guidelines for Vooradina Other Procedures" and 5.2. " Review Criteria for Human Factors Asoects of Advanced Controls and Instrumentation" (Memorandum for Brian W. Sheron, Director, Division of Systems Research, NRR, from John T.
- Larkins, Executive Director, ACRS, dated June 1, 1993)
HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE 1. Evolutionary and Advanced Licht Water Reactor (LWR) Schedules A representative of the Office of Nuclear Reactor Regulation (NRR) briefed the Committee on the issued SECY-93-097, " Integrated Review Schedules for the Evolutionary and Advanced Light Water Reactor Projects." SECY-93-097 outlines the process and assumptions that the staff has used in establishing the integrated schedule for completing its reviews of the evolutionary and advanced LWRs, including EPRI's Utility Requirements Document (URD) for the passive designs. The NRC staff proposed and discussed the following schedule: Pro.iect FSER Completion Date EPRI's Passive URD November 1993 GE/ABWR March 1994 CE/ System 80+ June 1994 W/AP-600 November 1995 GE/SBWR March 1996 The members and staff discussed the feasibility of meeting the proposed schedule and the individual documents needed by the Committee for review. Conclusions The members agreed that the proposed schedule is achievable provided that the document submittals are in reasonably final form and delivered to the Committee on time. 2. Backfit Considerations Representatives from the Office of Nuclear Regulatory Research (RES) and the Office of the General Counsel (0GC) briefed the Committee regarding SECY-93-086, "Backfit Considerations." The four options described in SECY-93-086 were discussed as well as whether rulemaking, subject to the Backfit Rule, can be justified as~ providing substantial benefits and yet 1
3 not result in substantial improvement in the margin of protection to public health and safety. Conclusions The Comittee prepared a report on this matter to Chairman Selin, as noted above. 3. PRA Workina Group Activities The Comittee was briefed by a representative of RES on the draft report by the PRA Working Group. This report documented the activities of the Working Group during the past year and provided recomendations to the NRC staff on the use of PRA. Conclusions The Committee prepared a report on this matter to Mr. James M. Taylor, as noted above. 4. Proposed NRC Staff Plan for Comparina Safety Goals with Reaulations Th's Comittee was briefed by a representative of RES on a draft SECY paper in regard to the proposed staff's approach for assessing the consistency of the present regulations with respect to the NRC safety goals. The recomended approach involved the use of existing programs. No new specific programs were anticipated. Dr. Kress, Chairman of the Safety Philosophy, _ Technology and Criteria Subcomittee, introduced this topic and noted that the Comittee had recomended a comparison of the body of current regulations against the NRC safety goals, in its reports regarding ' the implementation of the Safety Goal Policy. A representative of RES discussed the staff's approach for assessing the consistency of the present regulations with respect to the safety goals. He discussed the three approaches that had been considered. These were as follows: Use of IPE data in evaluating the effectiveness of regulations Use of PRA models to do detailed sensitivity studies related to specific regulations Include the evaluation as a part of existing programs, such as the programs for the elimination of requirements marginal to safety and IPE/IPEEE data base insights and other ongoing staff activities He discussed the details of these approaches and stated that the NRC staff recomended the use of the third approach. This would not entail any new program.
L, 1 i a j 1 4 Conclusions The Comittee prepared and issued a report on this matter to Chairman Selin, as noted above. 5. Meetina with the Director of the Office of Nuclear Reactor Reaulations The Comittee was briefed by Dr. Thomas Murley, Director, NRR, on items of mutual interest, including the following: Organizational factors research Computers in nuclear power plant operations Erosion / corrosion program Conclusions This briefing was for information only. No action was taken by the Comittee. 6. Form and Content of Combined license The Comittee was briefed by a representative of NRR on a preliminary SECY paper that reflects the staff's position on the contents of a combined operating license (COL) application; the COL form and content; COL /ITAAC; the concept of trarsition from high-level certified design information to detailed design a.J construction drawings; the quality assurance (QA) program's role in ITAAC; and the role of the PRA beyond design certification. The staff expects to continue to interact with the industry on many of these items. Conclusions This briefing was for information only. The Comittee will continue to follow such matters as progress is being made. 7. Meetino with the NRC Comissioners The Comittee met with the NRC Comissioners on Friday, May 14, 1993, to discuss items of mutual interest, including the following: Status of ACRS review of evolutionary and advanced light water reactor designs Digital instrumentation and control systems License renewal The Comission requested that the ACRS review and respond to the new Branch Technical Position dealing with metal fatigue. (The NRC staff
4 5 expects to submit this Branch Technical Position for ACRS teview in late 1994.) 8. ProDosed Resolution of Generic Issue 105. "Interfacino Systems LOCA in LWRs" The Committee was briefed by a representative of RES on the proposed NRC staff resolution position for Generic Issue 105, " Interfacing Systems LOCA in LWRs." The NRC staff proposes to resolve this issue by relying on the results of the licensee's ongoing IPE program, pursuant to the ACRS recommendation of same, made in January, 1990. Conclusions The Committee prepared and issued a report on this matter to Mr. James M. Taylor, as noted above. 9. Quadricartite Meetino of Advisory Committees The Committee discussed and approved a letter to Chairman Adolph Birkhofer, German RSK, and Chairman Francois Cogn6, French GPR proposing a list of five topics for the Quadripartite Meeting of Advisory Committees on October 11-15, 1993. The members also discussed who would attend the meeting and tentative traveling arrangements. [ Subsequent to the meeting, a memorandum was sent to Chairman Selin from J. Ernest Wilkins, Jr., ACRS Vice Chairman, dated May 26, 1993, regarding the participants in the Quadripartite Meeting of Advisory Committees.] 10. Election of New Member-at-Larae The Committee elected Mr. William Lindblad to replace Mr. James Carroll as the Member-at-Large for the remaining period of calendar year 1993. 11. ACRS Report on Imolementation Guidance for the Maintenance Rule It was brought the Committee's attention that a phrase had been inadvertently omitted from a recent ACRS report on implementation guidance for the maintenance rule, dated April 26, 1993. The Committee agreed to reissue the letter with the additional wording. 12. Review of the Generic Issue 153. " Loss of Essential Service Water in LWRs" Reoort Mr. Steven Mays, ACRS Senior Fellow, discussed the findings of his review of the Generic Issue 153 report requested by Mr. Carroll. He indicated. general agreement with the final conclusions of the report that Service Water System contributions to core damage frequency tended to be plant-specific and that IPE analysis and existing SWSOPI would be likely to identify problem areas. He indicated that the analysis relied heavily on older NRC sponsored risk analyses such as the Calvert Cliffs IREP and the TAP A-45 studies rather than the numerous and more recent IPE and other PRA submittals available to the Staff. While noting that there is
a 6 sufficient evidence to conclude that generic action is unwarranted for this topic, he indicated that the supporting analysis could have been more substantial. Conclusiont The Committee agreed not to review and comment on the proposed resolution of Generic Issue 153. 13. Reconciliation of ACRS Comments and Recommendations The responses of the Executive Director for Operations (ED0) to previous ACRS reports were discussed as follows: ED0 letter, dated April 28, 1993, responding to the ACRS report dated November 12,
- 1992, concerning Revised Guidelines for Prioritization of Generic Safety Issues.
EDO letter, dated April 23, 1993, responding to the ACRS report dated March 18, 1993, concerning Computers in Nuclear Power Plant Operations. ED0 letter, dated April 19, 1993, responding to the ACRS report dated March 19, 1993, concerning Human Performance in Operating Events. ED0 letter, dated April 9,1993, responding to the ACRS report dated December 18, 1992, concerning Resolution of Generic Safety Issue B-56, Diesel Generator Reliability. EDO letter, dated April 7,1993, responding to the ACRS report dated March 18, 1993, concerning ABWR Review Schedule. The above ED0 letters addressed the Committee's comments. No Committee action was taken as a result of this reconciliation review. 14. Subcommittee Meetinos During the period from April 17, 1993 to May 13, 1993, the fullowing Subcommittee meetings were held: Probabilistic Risk Assessment - May 11, 1993 The Subcommittee discussed a report of the PRA Working Group that summarizes the activities of this Group and provides guidance for the NRC staff regarding the application of PRA. Joint Thermal Hydraulic Phenomena / Core Performance - May 12, 1993 Dr. Catton, Chairman of the Ther' al Hydraulics Phenomena Subcommittee, m reported on the results of the Joint Subcommittee meeting. The purpose of the meeting was to discuss the issue of resolution of ATWS accompanied by a
,e + 1 4 7 core power instabilities for a BWR, and the issue of the reliability.of. BWR vessel water level instrumentation. Plannino and Procedures - May 12, 1993 The Subcommittee discussed proposed ACRS activities, practices, and-procedures for conducting Committee business and related matters. Qualifications of candidates nominated for appointment to the ACRS were also discussed. 15. Future ACRS Activities The Committee agreed not to review and comment on the proposed resolutions of Generic Issue HF 4.4, " Procedures Other than E0P" and Generic Issue HF 5.2, " Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation." The following activities were scheduled for the 398th ACRS Meeting, June 10-12, 1993, Bethesda, Maryland: SECY-93-067. " Final Policy Statement on Technical Soecifications Imorovements" The Committee will review and comment on the' staff's proposed final policy statement on technical specifications improvements. Representatives of the NRC staff and industry will ' participate, as appropriate. SECY-93-113. Additional Imolementation Information for 10 CFR Part 54. "Reouirements for Renewal of Operatino Licenses for Nuclear Power Plants" The Committee will review and comment on SECY-93-113, Additional. Implementation Information for 10 CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants. Representatives of the NRC staff and industry will participate, as appropriate. Public Comments on Severe Accident Plant Performance Criteria for Futurg LMB 1 The Committee will review and comment on a draft Commission paper regarding public comments on the 10 CFR Part 50 Advance Notice of Proposed Rulemaking on Severe Accidents for Future LWRs as well as the staff's recommendation regarding major policy issues resulting from the resolution of public comments. Representatives of the industry will participate, as appropriate. Unauthorized Forced Entry at Three Mile Island Unit 1 The Committee will be briefed by and hold discussions with representatives of the NRC staff regarding the unauthorized forced entry into the protected area'at Three Mile Island Unit I that occurred on February 7,1993. Represent-atives of the licensee will participate, as appropriate. Reactor Ooeratina Experience - The Committee will be briefed by and hold discussions with representatives of the NRC staff regarding recent operating events involving computer malfunctions. i
i 8 Risk-Based Reaulation The Committee will briefed by Dr. Vojin Joksimovich on risk-based regulation. BWR Vessel Water level Instrumentation - The Committee will be briefed by and hold discussions with Dr. Paul Blanch regarding his concerns with BWR vessel water level instrumentation. Resolution of ACRS Comments and Recommendations The Committee will discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations. ACRS Subcommittee Activities - The Committee will hear reports and hold discussions regarding the status of ACRS subcommittee activities, including status of issues associated with ABWR design. Committee Activities The Committee will discuss anticipated and proposed Committee activities, future meeting agenda, and organizational matters, as appropriate. Also, the members will discuss matters and specific issues that were not completed during previous meetings. Sincerely, M J. Ernest Wilkins, Jr. Chairman .}}