ML20059E490
| ML20059E490 | |
| Person / Time | |
|---|---|
| Issue date: | 09/29/1993 |
| From: | Larkins J Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| REF-GTECI-023, REF-GTECI-NI, TASK-023, TASK-23, TASK-OR ACRS-GENERAL, NUDOCS 9311030236 | |
| Download: ML20059E490 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION e
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o.
g WASHINGTON, D. C. 20555
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September 29, 1993 i
MEMORANDUM FOR:
James M. Taylor Executive Director for Operations ATTN:
James Blaha FROM:
John T.
Larkins Executive Director, ACRS
SUBJECT:
401ST ACRS MEETING FOLLOW-UP ITEMS This memorandum is provided for follow-up action consistent with the Actions, Agreements, Requests, and Commitments made during the 401st ACRS meeting, September 9-10, 1993.
John T.
Larkins Executive Director, ACRS cc: w/ attachment:
E.
L. Jordan, AEOD R. M.
Bernero, NMSS T.
E. Murley, NRR E.
S.
Beckjord, RES S.
Chilk, SECY J. Johnson, OCM/IS l
J.
Scarborough, OCM/KR l
J.
Guttmann, OCM/FR E.
McKenna, OCM/GD l
C20cng go 9311030236 930929 PDR ACRS CENERAL PDR
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SUMMARY
OF ACTIONS, AGREEMENTS,-ASSIGNMENTS, AhD REQUESTS 401ST AC'RS MEETING - SEPTEMBER 9-10, 1993 During i' s 401st meeting, September 9-10,
- 1993, held at 7920 Norfolk Au nue, Bethesda, Maryland, the Advisory Committee on Reactor $3*.eguards (ACRS) discussed several matters and completed the reports and memoranda noted below.
REPORTS Proposed Generic Le_tter Recardina Removal of Accelerated Testina and Special Reportina Reauirements for Emeraency Diesel Generators from Plant Technical Soecifications (Report to Chairman Selin, from J. Ernest Wilkins, Jr., ACRS Chairman, dated September 22, 1993)
Proposed Priority Rankinos of Generic Issues: Elahth Group (Report to James M. Taylor, Executive Director for Operations, from J.
Ernest Wilkins, Jr.,
ACRS Chairman, dated September 16, 1993)
Proposed Rule Amendi.no Fracture Touchness Reauirements for-Licht Water Reactor Pressure Vessels. Proposed Rule Recardina Recuirements for Thermal Annealina of Heactor Pressure Vessels, and Draft Reculatory Guide on Format and Content of Application for Acoroval for Thermal Annealina of Reactor PIgagMre Vessels (Report to James M. Taylor, Executive Direc--
tor for Operations, from J.
Ernest
- Wilkins, Jr.,
ACRS Chairman, dated September 20, 1993)
MEMORANDUM Proposed Generic Letter 93-XX. Research Results on Generic Safety Issue 106. "Ploina and the Use of Hichly Combustible Gases in Vital Areas (Memorandum to Brian K. Grimes, Director, 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.
RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows:
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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
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Conclusion The above EDO letter satisfactorily addressed the Commit-tee's comments.
EDO letter, dated August 18, 1993, responding to the ACRS 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.
SUMMARY
/ LIST OF FOLLOW-UP MATTERS 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.
During the discussion, Mr. William Russell, NRR, offered to provide copies L; the SER for the Diablo Canyon Retrof for Eagle 21 (Westinghouse) to the Committee.
The Committee agreed to provide ACRS consultant reports from the computers in Nuclear Power Plant Operations Subcommittee meeting, July 21, 1993, to the staff.
The Committee decided to defer further consideration of this matter until representatives of the Nuclear Utilities Management and Resource Council (NUMARC) brief the Committee on the latest progress of the joint staff /NUMARC ef fort to develop guidelines for the perfor-mance 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 Commit-tee.
On Thursday afternoon, the Committee traveled to the one White Flint North building, Rockville, 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
3 Le Committee reviewed and commented on the proposed rulemaking on the fracture toughness requirements for reactor pressure vessels for protection against pressurized thermal shock events and on a new rule on thermal annealing of the reactor pressure vessel.
i 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.
Dr. Wilkins announced that Dr. Shack is the new chairman of the Materials and Metallurgy Subcommittee and that Dr.
Seale, the former Chairman, will continue to be a member.
Also, Dr. Shack is the new Chairman of the Structural Engineering Subcommittee and Mr. Lindblad, the former Chairman, will continue to be a member.
The Committee discussed a letter from Mr. Robert J.
Talbert, a concerned citizen, on the issue of emergency operating procedures for dealing with BWR ATWS/ Core power stability. The Committee agreed to forward the letter to the Mr. James M. Taylor, EDO, for review and response.
The Committee agreed that the 402nd ACRS meeting should be scheduled for two days only, October 7-8, 1993.
AtITICIPATED ACRS ACTIVITIES The Committee agreed to consider the following during the 402nd ACRS Meeting, October 7-8, 1993, Bethesda, Maryland:
Engposed Resolution of Qejle_ tic Issue-23. " Reactor Coolant Pump
- l Egal Failure" - Review and comment on the proposed rule to j
address the resolution of Generic Issue-23.
Representatives i
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 radioactive dose due to releases from a design basis steam l
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generator tube rupture. Representatives of the NRC staff will participate.
Proposed Final Amendments to 10 CFR Part 55 Review and 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 participate, 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.
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 generator tube rupture event that occurred at Palo Verde Unit 2 on March 14, 1993.
Representatives of the industry will participate, as appropriate.
Resolution of ACRS Comments and Recommendations Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations.
Beoort of the Plannina and Procedures Subcommittee (Open/ Closed) - 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 I
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.
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5 Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of matters and specific issues that were not completed during previous meetings as time and availability of information permit.
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