ML20206S737
| ML20206S737 | |
| Person / Time | |
|---|---|
| Issue date: | 03/03/1999 |
| From: | Powers D Advisory Committee on Reactor Safeguards |
| To: | Shirley Ann Jackson, The Chairman NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0468, ACRS-SL-468, SECY-98-244-C, NUDOCS 9905210206 | |
| Download: ML20206S737 (11) | |
Text
SL-0468
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION PDR n
l ADVISORY COMMITTEE oN REACTOR SAFEGUARDS g
wash m oTow,p.c. noses March 3,1999 The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555 0001
Dear Chairman Jackson:
SUBJECT:
SUMMARY
REPORT-FOUR HUNDRED FIFTY-NINTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, FEBRUARY 3-6, 1999, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 459th meeting, February 3-6, 1999, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and letters. In addition, the Committee authorized Dr. Larkins, Executive Director, to transmit the memoranda noted below.
REPORTS List of Questions to be Addressed for Possible Resolution of Kev lasues Associated with the Proposed Revision to 10 CFR 50.59 (Chances. Tests and Exoeriments)
(Report to Shirley Ann Jackson, Chairman, NRC, from Dana A. Powers, Chairman, ACRS, dated February 18,1999)
NFPA 805. " Performance-Based Standard for Fire Protection for Liaht Water Reactor Electric Generatina Plants"(Report to Shirley Ann Jackson, Chairman, NRC, from Dana A. Powers, Chairman, ACRS, dated February 18,1999)
Proposed imorovements to the NRC Insoection and Assessment Proarams (Report to Shirley Ann Jackson, Chairman, NRC, from Dana A. Powers, Chairman, ACRS, dated Fnbruary 23,1999)
LETTERS SECY-98-244. "NRC Human Performance Plan" (Letter to William D. Travers, Executive Director for Operations, NRC, from Dana A. Powers, Chairman, ACRS, i
dated February 19,1999)
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The Honorable Shirley Jackson 2
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Resolution of Generic Safety issue B-61. " Allowable ECCS Eauioment Outaae Periods"(Letter to William D. Travers, Executive Director for Operations, NRC, from
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Dana A. Powers, Chairman, ACRS, dated February 19,1999)
MEMORANDA Draft Reaulatory Guide DG-1076. " Service Level I. II. and lil Protective Coatinas Apolied to Nuclear Power Plants"(Memorandum to William D. Travers, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, l
dated February 11,1999) l l
Draft Reaulatorv Guide DG-1080. " Nuclear Power Plant Simulation Facilities for Use in Operator Trainina and License Examinations" (Memorandum to William D.
Travers, Executive Director for Operations, NRC, from John T. Larkins, Executive l
Director, ACRS, dated February 16,1999)
HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE 1
1.
Status of the Proposed Final Revision to 10 CFR 50.59 (Chances. Tests and Experiments)
The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the status of the proposed final revision to 10 CFR 50.59.
The Committee and staff discussed the status of activities associated with the l
l proposed near-term revision to 10 CFR 50.59, including the planned reconciliation of public comments, options for revising the current 50.59 process, and the schedule for completion. Most public comments were provided by nuclear power plant licensees, industry organizations, and law firms. Key issues discussed in the public comments and in ACRS deliberations were those associated with margin of safety, " minimal" increase in probability and consequences, screening of changes, clarification of definitions, NRC Enforcement Policy, and the status of industry guidance development in NEl 96-07, " Guidelines for 10 CFR 50.59 Safety l
Evaluations."
l l
The Committee plans to review the proposed Commission paper on the summary of public comments and staff recommendations for revising 10 CFR 50.59 during its March 10-13,1999 meeting. The Committee also plans to review the proposed final revision to 10 CFR 50.59 during its May 5-8,1999 meeting.
The Honorable Shirley Jackson 3
Conclusion During the February 3,1999 ACRS meeting with the Commission, the Commission requested that the ACRS provide a list of questions which, if answered, would aid
- in the resolution of key issues associated with the near-term revision to 10 CFR 50.59. In response, the Committee provided a report to Chairman Jackson dated February 18,1999.
2.
Proposed Improvements to the NRC Insoection and Assessment Proarams The Committee heard presentations by and held discussions with representatives of the NRC staff concerning the status of activities related to proposed improvements to the NRC Inspection and Assessment Programs (SECY-99-007).
The staff has identified eight candidate plants (two in each region) to participate in the proposed pilot program. These plants will be named following additional consultation with the nuclear industry and the Commission.
The staff stated that two documents are under preparation: one to ensure that high-risk events are not eliminated by the screening methodology, and the other to facilitate the use of the inspection results. Both documents are expected to be completed in the near future. The staff also discussed the issues raised during the January 26,1999 joint meeting of the ACRS Subcommittees on Plant Operations and on Reliability and Probabilistic Assessment. These issues included the selection, assessment, and the schedule for implementing the pilot program; high-level objectives of the assessment process; the implications associated with the use of thresholds for the performance indicators; proposed revisions to the enforcement program; oversight of the transition process; and policy issues associated with the revised assessment process.
Conclusion The Committee issued a report to Chairman Jackson, dated February 23,1999, on this matter.
3.
Meetina with the NRC Commissioners. Commissioners' Conference Room. One j
White Flint North The Committee met with the Commissioners on February 3,1999, to discuss items of mutual interest including: proposed (near-term) revision to 10 CFR 50.59 (Changes, tests and experiments); proposal for the development of a risk-informed framework for 10 CFR 50.59; options to make 10 CFR Part 50 risk informed; proposed rulemaking on the use of revised source term; status of ACRS activities i
The Honorable Shirley Jackson 4
associated with license renewal; impact of PRA results and insights on the regulatory system; elevation of CDF to a fundamental safety goal and possible revision of the Commission's Safety Goal Policy Statement; and NRC Safety Research Program.
4.
Proposed Final Revision to 10 CFR 50.65 (a)(3) of the Maintenance Rule The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the proposed final revision to the Maintenance Rule, which would require the licensees to perform safety assessments prior to performing maintenance activities. The briefing included a discussion of the following provision of 10 CFR 50.65(a)(3): "In performing monitoring and preu ntive maintenance activities, an assessment of the total plant equipment that is out of service should be taken into account to determine the overall effect on performance of safety functions." The Committee and the staff discussed whether the word "should," used in the current rule, imposes a requirement.
The proposed final rule requires licensees to perform maintenance activities on structures, systems or components within the scope of 10 CFR 50.65(a)(3)
(including but not limited to surveillance, post-maintenance testing, corrective and preventive maintenance). This rule also requires that the licensee assess and manage any increases in risk that may result from proposed maintenance activities.
Conclusion The proposed final revision to 10 CFR 50.65 (a)(3) provided to the Committee is still being revised by the staff. Consequently, the Committee decided to defer its comments, pending receipt of the proposed final version of the rule.
5.
SECY-98-244. NRC Human Performance Plan The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the current version of the Human Performance Plan (HPP) contained in SECY-98-244. The staff explained the prioritization process used in the current version of the HPP and presented its strategy for completing the development of the HPP, which includes formulation of a disciplined process to develop a more technically defensible plan. The process is expected to identify agency needs in the human performance area and define, quantitatively where possible, the requirements and closure conditions for activities associated with such needs.
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The Honorable Shirley Jackson 5
The Committee and staff discussed the lack oflinkage between the HPP's mission statements and goals, use of high-level human performance models and risk l
metrics, cooperation with the institute of Nuclear Power Operations, and the scrutability of decisions based on expert judgment.
Conclusion The Committee issued a letter to the NRC Executive Director for Operations dated February 19,1998, on this matter. The Committee plans to discuss the progress made by the staff in completing the development of HPP during future meetings.
6.
Proposed Resolution of Generic Safety issue (GSI) B-61. Allowable ECCS Eauioment Outaae Periods The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the proposed resolution of Generic Safety issue (GSI)
B-61," Allowable ECCS Equipment Outage Periods." The two primary issues of GSI relate to the risk impact of surveillance test ir.tervals and allowable equipment outage times, and the need for a limit on cumulative outage time (COT) on systems during unscheduled or corrective maintenance. The first issue was considered l
resolved with the issuance of Regulatory Guide 1,177, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications." Regarding the second issue, the staff performed a limited regulatory analysis to evaluate the impacts of COT on systems during unscheduled or corrective maintenance. Based on the results of the analysis the staff concluded that implementation of a limit on COTS did not meet the substantial added protection criterion specified in the NRC regulatory analysis guidelines.
Since this issue will be addressed through l
implementation of the Maintenance Rule, the staff considers GSI B-61 resolved.
Conclusion l
l The Committee issued a letter to the NRC Executive Director for Operations, dated February 19,1999, on this matter.
1 7.
Fire Protection Issues The Committee heard presentations by and held discussions with representatives of the National Fire Protection Association (NFPA), Nuclear Energy Institute (NEI),
I and NRC staff regarding the draft NFPA-805,' Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," and the proposed outline for developing a comprehensive regulatory guide on fire protection.
The Honorable Shirley Jackson 6
4 Th'e NFPA-805 Standard is intended to be an akemative method to meet the existing fire protection requirements. The scope of the Standard is limited to establishing the minimum requirements for existing light-water reactors during all phases of plant operation (e.g., power operation, refueling, shutdown, decommissioning, and degraded conditions). Within the framework of NFPA-805, the plant owner / operator is provided the option of selecting a deterministic approach (e.g., Appendix R to 10 CFR Part 50 and NFPA Life of Safety Code) or a performance-based approach (e.g., engineering analysis, fire modeling, and probabilistic safety assessment) for satisfying the performance criteria specified in the Standard. The staff plans to hold a public meeting to discuss the comments received from the industry in the near future.
The development of a comprehensive regulatory guide for fire protection at nuclear power plants was approved by the Commission in an SRM dated June 30,1998.
The staff, with technical assistance from the Pacific Northwest National Laboratory, has prepared the draft outline to be used for developing the regulatory guide. The staff provided a draft copy of the outline to NEl on December 24,1998, reyiesting comments by February 24,1999.
Conclusions The Committee issued a report to Chairman Jackson dated February 18,1999, regarding the proposed NFPA-805 Standard.
8.
Follow-uo items Resultina from the ACRS Retreat A meeting of the ACRS Subcommittee on Planning and Procedures was held on January 27-29, 1999, in Bethesda, Maryland. A number of key issues were discussed and recommendations were made. The Committee will act on these recommendations and make periodic assessments of the effectiveness of the actions taken.
9.
NRC Safety Research Proaram The Committee discussed the format and content of its 1999 report to the Commission regarding the NRC safety research program. Several research areas were discussed, including PRA research for risk-informed / performance-based regulation; high burnup fuel performance; thermal-hydraulic code integration and in-house capabilities; advanced instrumentation and control; and research required for plant license renewal. The Committee plans to issue its report to the Commission in May 1999.
v-The Honorable Shirley Jackson 7
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1 RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The Committee discussed the response from the NRC Executive Director for Operations (EDO) dated December 11,1998~ to the ACRS comments and recommendations included in the ACRS ~ report dated November 19, 1998, concoming the proposed rule on use of an attemative source term at operating reactors.-
The Committee decided that it was satisfied with the EDO's response.
The Committee discussed the response from the EDO dated December 11,1998, to the ACRS comments and recommendations included in the ACRS report dated November 17,1998, conceming the proposed revision to the enforcement policy.
The Committee plans to continue its discussion of this matter during future meetings.
The Committee discussed the response from the EDO dated December 28,1998, to the ACRS comments and recommendations included in the ACRS letter dated November 23,1998, conceming the reprioritization and proposed resolution of Generic Safety lasue-171.
The Committee plans to continue its discussion of the issue regarding the i
development of appropriate tools for conducting risk-informed analysis for effective prioritization of GSis during its review of the reevaluation of the GSI process.
The Committee discussed the response from the EDO dated January 7,1999, to 1
ACRS comments and recommendations included in the ACRS letter dated j
November 20,1998, concerning the staff's Safety Evaluation Report on the Topical Report (WCAP-14572, Revision 1) regarding the Westinghouse Owners Group application of risk-informed methods to inservice inspection of piping.
The Committee plans to continue its discussion of this matter during future meetings. Specifically, the Committee noted that the staff's revised SER still does not sufficiently characterize the distinction between parameter and model uncertainties discussed during the Committee's deliberations. The Committee plans to review NUREG-1661, noted in the EDO's response, which summarizes the independent uncertainty and sensitivity studies performed by the Pacific Northwest National Laboratory.
The Committee discussed the response from the EDO dated January 8,1999, to the ACRS comments and recommendations included in the ACRS letter dated
The Honorable Shirley Jackson 8
December 14,1998, regarding the proposed Commission Paper conceming options for making risk-informed revisions to 10 CFR Part 50.
The Committee decided that it was satisfied with the EDO's response.
The Committee discussed the response fr$m the EDO dated January 29,1999, to i
ACRS comments and recommendations included in the ACRS letter dated December 11,1998, conceming options for incorporating risk insights into the 10 l
CFR 50.59 process.
The Committee decided that it was satisfied with the EDO's response.
The Committee discussed the response from the EDO dated January 19,1999, to the ACRS comments and recommendations included in the ACRS interim report dated December 16,1998 concerning the proposed improvements to the NRC inspection and assessment programs.
The Committee decided that it was satisfied with the EDO's response.
OTHER RELATED ACTIVITIES OF THE COMMITTEE During the period from December 3,1908 through February 2,1999, the following I
Subcommittee meetings were held:
Thermal-Hvdraulic Phenomena - December 16-17,1998 l
l The Subcommittee on Thermal-Hydraulic Phenomena discussed the application of I
the Westinghouse Electric Company's WCOBRA/ TRAC best-estimate large-break LOCA code to nuclear power plants with upper plenum injection; the NRC Thermal-Hydraulic Code Review Action Plan; the Electric Power Research Institute's RETRAN-3D transient analysis code; and the status of the NRC thermal-hydraulic l
l research program.
Fire Protection - January 20-21,1999 The Subcommittee on Fire Protection reviewed the insights gained, in the fire protection area, from the review of the licensee submittals of Individual Plant l
Examination of External Event reports, results of the Pilot Fire Protection Functional Inspections, electrical circuit analysis, proposed NFPA Fire Protection Standard, and related matters.
The Honorable Shirley Jackson 9
Reliability and Probabilistic Risk Assessment - January 25,1999 The Subcommittee on Reliability and Probabilistic Risk Assessment discussed the possible use of frequency-consequence curves in risk-informed decisionmaking.
Plant Operations and Reliability and Probabilistic Risk Assessment - January 26, 1999 The Subcommittees on Plant Operations and on Reliability and Probabilistic Risk Assessment continued their discussion of proposed improvements to the NRC inspection and assessment programs, including initiatives related to development of a risk-based inspection program and performance indicators.
Plannina and Procedures - January 27-29 and February 2,1999 The Planning and Procedures Subcommittee discussed proposed ACRS activities, practices, and procedures for conducting Committee business and organizational and personnel matters relating to ACRS and its staff.
LIST OF FOLLOW-UP MATTERS FOR THE EXECUTIVE DIRECTOR FOR OPERATIONS i
The Committee deferred its comments on the proposed final revision to 10 CFR 50.65 (a)(3) of the Maintenance Rule to a future meeting, pending receipt of the proposed final version of the rule and an associated draft regulatory guide. As requested by the staff, ACRS review of the proposed final rule and the draft regulatory guide will be scheduled for the April 7-10,1999 meeting.
The Committee plans to discuss the progress made by the staff in completing the development of a Human Performance Plan during future meetings.
The Committee plans to follow the progress in the development of the NFPA 805 Fire Protection Standard during future meetings.
During the discussion of the January 7,1999 EDO response to the ACRS letter regarding the Staff's Safety Evaluation Report (SER) on the Topical Report, WCAP 14572, Revision 1, Westinghouse Owners Group Application of Risk-Informed Methods to inservice Inspection of Piping, the Committee expressed concern that the staff's revised SER still does not sufficiently characterize the distinction between parameter and model uncertainties. The Committee plans to review NUREG-1661, noted in the EDO's response, which summarizes the independent uncertainty and sensitivity studies performed by the Pacific Northwest National Laboratory.
i The Honorable Shirley Jackson 10 The Committee plans to continue its discussion of issues raised in its November 17, 1998 report regarding proposed revisions to the Enforcement Policy during future meetings.
The Committee plans to continue its discussion of the issue, which was raised in its November 23,1998 letter on the proposed resolution of GSI-171, regarding the development of appropriate tools for conducting risk-informed analysis for effective i
prioritization of GSis during its review of the reevaluation of the GSI process.
PROPOSED SCHEDULE FOR THE 460TH ACRS MEETING i
The Committee agreed to consider the following during the 460th ACRS Meeting, March 10-13,1999:
Commission Paper on 10 CFR 50.59 (Chanaes. tests and experiments) (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed Commission Paper on the summary of public comments and staff recommendations for revising 10 CFR 50.59.
YLestinahouse Best-Estimate Laroe-Break LOCA Methodoloav (Open/ Closed)
The Committee will hear presentations by and hold discussions with representatives of the Westinghouse Electric Company and the NRC staff regarding the application of the Westinghouse best-estimate large-break LOCA methodology to upper plenum injection plants.
Phase 1 Standard for PRA Quality (Open)
The Committee will hear presentations by and hold discussions with representatives of the American Society of Mechanical Engineers (ASME) Task Force and the NRC staff regarding the proposed Phase 1 Standard, developed by the ASME Task Force, for PRA quality as well as industry programs for certifying PRAs.
Event Reportina Reauirements Rule (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed rule for event reporting requirements.
Reevaluation of the Generic Safety issue Process (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the results of the reevaluation of the Generic Safety issue process.
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The Honorable Shirley Jackson 11 o
Fuel Bumun Extension Licensino Framework /NRC Particination in the CABRI Reactor Fuels Research Proaram (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding' the proposed use of a systematic process, such as Phenomena identification and Ranking Table (PIRT) for fuel bumup extensions, and the status of the NRC participation in the CABRI reactor fuels research program.
Guidance for imolementina the Revised Enivicernent Policy (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding guidance for implementing the revised Enforcement Policy, as well as the staffs plans to make the Enforcement Policy risk informed.
Safetv Evaluation Reoort on the Toolcal Report Reaardina Tritium Production Core (Open)
The Committee will hear presentations by and hold discussions with representatives of the NRC staff and the Department of Energy (DOE) regarding the NRC staffs Safety Evaluation Report on the Topical Report associated with the tritium production core, which describes how the inclusion of a significant number of tritium-producing-burnable absorber rods affects the performance of nuclear plant systems and components for a representative commercial light-water reactor.
Sincerely, A c.. %
Dana A. Powers Chairman p
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