ML20059D480
| ML20059D480 | |
| Person / Time | |
|---|---|
| Issue date: | 10/05/1993 |
| From: | Wilkins J Advisory Committee on Reactor Safeguards |
| To: | Selin I, The Chairman NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0410, ACRS-SL-410, NUDOCS 9311020283 | |
| Download: ML20059D480 (6) | |
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NUCLEAR REGULATORY COMMISSION SL-0410.
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.:,i ADVISORY COMMITTEE ON REACTOR SAFEGUARDS PDR/4/g O,
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October 5, 1993 The Honorable Ivan Selin Chairman U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
Dear Chairman Selin:
SUBJECT:
SUMMARY
REPORT - FOUR HUNDRED FIRST MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, SEPTEMBER 9-10, 1993, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 401st meeting, September 9-10,
- 1993, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and memorandum:
Reports Proposed Generic Letter Recardina Removal of Accelerated Testina and Special Reportina Recuirements for Emercency Digjlyel Generators from Plant Technical Soecifications (Report to Chairman Selin, from J. Ernest Wilkins, Jr., ACRS Chairman, dated September 22, 1993)
Proposed Priority Rankings of Generic Issues: Eiahth Group (Report to James M. Taylor, Executive Director for Operations, from J.
Ernest Wilkins, Jr.,
ACRS Chairman, dated September 16, 1993)
Proposed Rule Amendina Fracture Touchness Reauirements for Licht Water Reactor Pressure Vessels. ProDosed Rule Recardina Reauirements for Thermal Annealina of Reactor Pressure Vessels, and Draft Reculatory Guide on Format and Content of Acolication for ADoroval for Thermal Annealina of Reactor Pressure Vessels (Report to James M. Taylor, Executive Direc-tor for Operations, from J.
Ernest Wilkins, Jr., ACRS Chair-man, dated September 20, 1993) liemorandum Proposed generic letter 93-XX. Research Results on Generic Safety Issue 106. "Pioina and the Use of Hichly Combustible Gases in Vital Areas" (Memorandum to Brian K.
Grimes, Direc-tor, Division of Operating Reactor Support, NRR, from John T.
Larkins, Executive Director, ACRS, dated September 15, 1993.)
Consistent with the Committee's decision, Dr. Larkins informed Mr. Grimes that the Committee had decided not to review the subject proposed generic letter.
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HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE 1.
Proposed Gqidelines for Dicital Instrumentation and Control (I&C) Systems Uocrades The Committee heard a briefing by and held discussions with representatives of the NRC staff on the diversity for advanced and operating reactor digital I&C systems and the status of the efforts to develop guidelines for implementing digital instrumentation and control system retrofits under 10 CFR 50.59.
Conclysion The Committee decided to defer further consideration of this matter until representatives of the Nuclear Utilities Man-agement and Resource Council (NUMARC) brief the Committee on the latest progress of the joint staff /NUMARC effort to develop guidelines for the performance of 10 CFR 50.59 reviews on digital I&C system upgrades. The Committee plans to report on this matter at that time.
No other action was taken by the Committee.
2.
Insiahts Gained from Foreion Trios and U.S.
Military Sources Recardina Dicital I&C Issues (Open/ Closed)
The Committee heard a briefing by and held discussions with representatives of the NRC staff on basic reactor protection system (RPS) architecture, regulatory goals for acceptance of RPS designs, and the star.dards and methods used to demonstrate the adequacy of safety-critical systems in the United Kingdom, France, Canada, and Germany.
Conclusion This briefing was for information only.
No action was taken by the Committee.
3.
Reconciliation of ACRS Comments and Recommendations The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows:
EDO letter, dated July 23, 1993, responding.to the ACRS report dated July 15, 1993, concerning ACRS Comments on the Regulatory Review Group Report Conclusion The above EDO letter satisfactorily addressed the Commit-tee's comments.
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2 BIGHLIGHTS QF KEY ISSUES CONSIDERED BY THE COMMITTEE 1.
ProDosed Guidelines for Dicital Instrumentation and Control 111Q) Systems Unarades t
The Committee heard a briefing by and held discussions with representatives of the NRC staff on the diversity for advanced and operating reactor digital I&C systems and the status of the efforts to develop guidelines for implementing digital instrumentation and control system retrofits under 10 CFR 50.59.
Conclusion The Committee decided to deter further consideration of this ratter until representatives of the Nuclear Utilities Man-l agement and Resource Council (NUMARC) brief the Committee on the latest progress of the joint staff /NUMARC effort to develop guidelines for the performance of 10 CFR 50.59 reviews on digital I&C system upgrades. The Committee plans to report on this matter at that time.
No other action was taken by the Committee.
2.
Insichts Gained from Foreion Trios and U.S. Military Sources Recardina Diaital I&C Issues (Open/ Closed)
The Committee heard a briefing by and held discussions with representatives of_the NRC staff on basic reactor protection system (RPS) architecture, regulatory goals for acceptance of RFS designs, and the standards and methods used to demonstrate the adequacy of safety-critical systems in the United Kingdom, France, Canada, and Germany.
ponclusion This briefing was for information only.
No action was taken by the Committee.
3.
Reconciliation of ACRS Comments and Recommendations The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows:
EDO letter, dated July 23, 1993, responding to the ACRS
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report dated July 15, 1993, concerning ACRS Comments on the Regulatory Review Group Report Conclusion The above EDO letter satisfactorily addressed the Commit-tee's comments.
3 EDO letter,. dated August 18, 1993, responding to the ACRS ~
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report dated June 18, 1993, concerning Public Comments on Proposed Rule on ALWR Severe Accident Performance Conclusion The above EDO letter satisfactorily addressed the Commit-tee's comments.
4.
Meetina with the NRC Commissioners v
On Thursday afternoon, the Committee traveled to the One White Flint North building, Pockville, Maryland, for a meeting with the NRC Commissioners.
The NRC Commissioners were briefed by the Committee on the following topics:
Status of ACRS review of evolutionary and advanced light water reactor designs Selected ALWR policy issues Regulatory Review Group Report 5.
ProDosed Priority Rankinos of Generic Safety Issues: Eichth Group The Committee reviewed and commented on the NRC staff's priority rankings to 31 generic safety issues (eighth. group).
Conclusion The Committee provided a report on this matter dated September 16, 1993, to James M.
Taylor, Executive Director for Opera-tions.
6.
Proposed Generic Letter on Removal of Accelerated Testina and Hoecial Reportina Reauirements for Emercency Diesel Generators from Plant Technical Soecifications The Committee reviewed and commented on the proposed generic letter en remova) of accelerated testing and special reporting requirements for emergency diesel generators.from plant technical specifications.
Representatives of the NRC staff
'I participated.
A representative of NUMARC commented that NUMARC is generally satisfied with the proposed GL, but believes some clarification is needed.
Conclusion The Committee provided a report on this matter dated September 22, 1993, to Chairman Selin.
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Pronosed Rule Amendino Fracture Touchness Reauirements for-Licht Water Reactor Pressure Vessels Proposed Rule RecaDliDE Recuirements for Thermal Annealina of Reactor Pressure' Vessels; and Draft Reculatory Guide on Format-and Content of Aeolication for Acoroval _ for Thermal Annealina of Reactor Pressure Vessels The Committee reviewed and commented on the proposed rulemak-ing on the fracture toughness requirements for reactor pressure vessels for protection against pressurized thermal shock events.
Also, the Committee reviewed and commented on a new rule on thermal annealing of the reactor pressure vessel.
Conclusion The Committee provided a report on this matter dated September r
20, 1993, to James M. Taylor, EDO.
'1he Committee requested an opportunity to review the proposed final version of these rules and the guide after the public comments.. have been reconciled and before publication.
8.
Report of the Plannina and Procedures Subcommittee Dr. Wilkins stated that the ACRS staff will meet with the Technical Assistants from the Chairman's office and others to discuss the ACRS/ACNW budget.
9.
Subcommittee Meetinas During the period from August 8 to September 9,
1993, the following Subcommittee meetings were held:
Materials and Metallurav - August 16, 1993 The Subcommittee reviewed a proposed rulemaking on fracture toughness requirements for reactor pressure vessels, revisions to 10 CFR 50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal l
Shock Events," Appendix G,
" Fracture Toughness Require-ments," Appendix H,
" Reactor Vessel Materials Surveil-lance Program Requirements," and a new rule, and an-implementing draft regulatory guide on reactor vessel thermal annealing, 10 CFR 50.66 and DG-1027, respective-l lY-
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Pronosed Rule Amendina Fracture Touchness Recuirements for Light Water Reactor._ Pressure Vessels. Procosed Rule Recardina Recuirements for Thermal Annealina of Reactor Pressure Vessels, and Draft Reculatorv Guide on Format and Content of Acolication for Accroval for Thermal Annealinq of Reactor Pressure Ve_gsels The Committee reviewed and commented on the proposed rulemak-ing on the fracture toughness requirements for reactor pressure vessels for protection against pressurized thermal shock events.
Also, the Committee reviewed and commented on a new rule on thermal annealing of the reactor pressure t
vessel.
Conclusion The Committee provided a report on this matter dated September 20, 1993, to James M. Taylor, EDO.
The Committee requested an opportunity to review the proposed final version of these rules and the guide after the public comments have been reconciled and before publication.
8.
ReDort of the Plannina and Procedures Subcommittee Dr. Wilkins stated that the ACRS staff will meet with the Technical Assistants from the Chairman's office and others to discuss the ACRS/ACNW budget.
9.
Subcommittee Meetinas During the period from August 8 to September 9,
1993, the following Subcommittee meetings were held:
Materials and Metallurcy - August 16, 1993 The Subcommittee reviewed a
proposed rulemaking on fracture toughness requirements for reactor pressure vessels, revisions to 10 CFR 50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," Appendix G,
" Fracture Toughness Require-ments," Appendix H, " Reactor Vessel Materials Surveil-lance Program Requirements," and a new rule, and an implementing draft regulatory guide on reactor vessel thermal annealing, 10 CFR 50.66 and DG-1027, respective-ly.
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5-Advanced Boilina Water Reactors - September 8, 1993 The Subcommittee discussed the status of resolution'of the remaining open issues in the ABWR Standard Safety Analsis Report and how the ABWR design satisfies ' the requirements resulting from the' resolution of certain-unresolved safety issues and generic safety issues.
Plannina and Procedures - September 8, 1993 The Subcommittee discussed proposed activities, practic-es, and procedures relating to ACRS and related matters.
8.
Future ACRS Activities The Committee agreed to consider the following during the
-l 402nd ACRS Meeting, October 7-8, 1993, Bethesda, Maryland:
Procosed Resolution of Generic Issue-23. " Reactor Coolant Pump Seal Failure" - Review and comment on the proposed rule to address the resolution of Generic Issue-23.
Representatives of the NRC staff will participate.
Representatives of the industry will participate, as appropriate.
EPRI Passive LWR Reauirements Document - Review and comment on the NRC staff's Safety Evaluation Report related to the EPRI Utility Requirements Document for Passive LWRs.
Representa-tives of the NRC staff and industry will participate.
Resolution of Generic Issue 67.5.1.
" Reassessment of SGTR Radioloaical Consecuences"
- Review and comment on the proposed resolution of Generic Issue 67.5.1 that addresses the validity of present techniques to calculate offsite radioac-tive dose due to releases from a design basis steam generator tube rupture.
Representatives of the NRC staff will partici-pate.
Review and Proposed Final Amendments to 10 CFR Part 55 comment on the proposed final amendments to 10 CFR Part 55 regarding renewal of license and requalification requirements for licensed operators. Representatives of the NRC staff will participate.
Representatives of the industry will.partici-pate, as appropriate.
Severe Accident /PRA Issues for the ABWR Desian - Hear pre-sentations by and hold discussions with representatives of the NRC staff and GE on the severe accident /PRA issues for the ABWR design.
Develop comments and recommendations for inclusion in the final ACRS report on the Final Design' Approval for the ABWR.
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Insiahts Gained from the NRC Staff Reassessment of the Fire' Protection Procram (tentative) - Hear a briefing by and hold discussions with representatives of the NRC staff on the lessons learned from the staff's recent reassessment of the fire protection program.
(Note:
This item has been deferred to a future ACRS meeting.]
Steam Generator Tube Ruoture Event at Palo Verde Unit 2 - Hear a briefing by and hold discussions with representatives of the NRC staff regarding the issues arising from the steam genera-tor tube rupture event that occurred _at Palo Verde Unit 2 on March 14, 1993. Representatives of the industry will partici-pate, as appropriate.
Discuss Resolution of ACRS Comments and Recommendations responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations.
Report of the Plannina and Procedures Subcommittee - Hear a report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business.
A portion'of this session may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational and personnel matters that relate solely to internal personnel rules and practices of ACRS and matters the release of which would represent a clearly unwarranted invasion of personal privacy.
ACRS Subcommittee Activities - Hear reports and hold discus-sions regarding the status of ACRS subcommittee activities, including reports from the Subcommittees on Thermal Hydraulic Phenomena, and Computers in Nuclear Power Plant Operations.
Future ACRS Activities - Discuss topics proposed for consider-ation by the full Committee during future meetings.
Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of matter and specific issues that were not completed during previous meetings as time and availability of information permit.
Sincerely,
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Ernest Wilkins, l
Chairman 1
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Insichts Gained from the NRC Staff Reassessment of the Fire Protection Proaram (tentative) - Hear a briefing by and hold discussions with representatives of the NRC staff on the lessons learned from the staff's recent reassessment of the fire protection program.
[ Note:
This item has been deferred to a future ACRS meeting.]
Steam Generator Tube Runture Event at Palo Verde Unit 2 - Hear a briefing by and hold discussions with representatives of the NRC staff regarding the issues arising from the steam genera-tor tube rupture event that occurred at Palo Verde Unit 2 on March 14, 1993. Representativen of the industry will partici-pate, as appropriate.
Resolution of ACRS Comments a..a Recommendations - Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations.
Esp _ oft of the Plannina and Procedures Subcommittee - Hear a report of the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business.
A portion of this session may be closed pursuant to 5 U.S.C. 552b(c) (2) and (6) to discuss organizational and personnel matters that relate solely to internal personnel rules and practices of ACRS and matters the release of which would represent a clearly unwarranted invasion of personal privacy.
ACRS Subcommittee Activities - Hear reports and hold discus-sions regarding the status of ACRS subcommittee activities, including reports from the Subcommittees on Thermal Hydraulic Phenomena, and Computers in Nuclear Power Plant Operations.
Future ACRS Activities - Discuss topics proposed for consider-ation by the full Committee during future meetings.
Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of matter and specific issues that were not completed during previous meetings as time and availability of information permit.
Sincerely,
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J. Ernest Wilkins, Chairman l
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