ML20059D682
| ML20059D682 | |
| Person / Time | |
|---|---|
| Issue date: | 08/03/1993 |
| From: | Larkins J Advisory Committee on Reactor Safeguards |
| To: | Blaha J, Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| TASK-1.D.3, TASK-TM ACRS-GENERAL, NUDOCS 9311020363 | |
| Download: ML20059D682 (6) | |
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1 NUCLEAR REGULATORY COMMISSION
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1 August 3, 1993 MEMORANDUM FOR: James M. Taylor Executive Director for Operations ATTN: James Blaha FROM:
John T. Larkins Executive Director, ACRS
SUBJECT:
399TH ACRS MEETING FOLLOW-UP ITEMS This memorandum is provided for follow-up action consistent with the Actions, Agreements, Requests, and Commitments made during the 399th ACRS meeting, July 8-9, 1993.
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John T. Larkins Executive Director, ACRS cc: w/ attachment:
E. L. Jordan, AE00 R. M. Bernero, NMSS T. E. Murley, NRR E. S. Beckjord, RES S. Chilk, SECY J. Johnson, OCM/IS J. Scarborough, OCM/KR J. Guttmann, OCM/FR E. McKenna, OCM/GD f$6 x
020055 i) m 9311020363 930803
SUMMARY
OF
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ACTIONS, AGREEMENTS, REQUESTS, AND COMMITMENTS 399TH ACRS MEETING JULY 8-9, 1993 During its 399th meeting, July 8-9, 1993, held at 7920 Norfolk Avenue,.Bethesda, Maryland, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the reports, memorandum, and letter noted below.
REPORTS Reaulatory Review Group ReDort (Report to the Honorable Ivan Selin, NRC Chairman, from J. Ernest Wilkins, Jr., ACRS Chairman, dated July 15,1993)
Proposed Draft Reaulatory Guides. DG-1023. " Evaluation of Reactor Pressure Vessels with Charov Vocer-Shelf Enerav less Than 50 Ft-lb." and DG-1025.
" Calculational and Dosimetry Methods for Determinina Pressure Vessel Neutron Fluence" (Report to James M. Taylor, Executive Director for Opera-tions, from J. Ernest Wilkins, Jr., ACRS Chairman, dated July 15,1993)
MEMORANDUM Procosed Resolution of Generic Issue I.D.3.
" Safety System Status Monitorina" (Memorandum for Warren Minners, Director, Division of Safety Issue Resolution, RES, from John T. Larkins, Executive Director, ACRS, dated July 16, 1993.)
Consistent with the Committee's decision, Dr.
Larkins informed Mr. Minners that the Committee had decided not to review the proposed resolution of Generic Issue I.D.3.
LETTER Process for Expeditina the Issuance of Information Notices (Letter to Mr.
l Steven Sholly, Senior Consultant, MHB Technical Associates, from John T.
Larkins, Executive Director, ACRS, dated July 16,1993.) Consistent with the Committee's decision, Dr. Larkins informed Mr. Sholly that the Committee forwarded his request for an investigation of the process for expediting the issuance of Information Notices to the NRC Executive Director for Operations for consideration and disposition.
RECONCILIATI0fi 0F ACRS COMMENTS AND RECOMMENDATIONS The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows:
EDO letter, dated May 19, 1993, responding to the ACRS report dated April 26,1993 (revised June 24, 1993), concerning implementation guidance for the Maintenance Rule.
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()nclusion The above ED0 letter satisfactorily addrassed the Committee's comments.
EDO letter, dated June 8,1993, responding to the ACRS report dated April 23, 1993, concerning the prioritization of Generic Issue 152,
" Design Basis for Valves that Hight Be Subjected to Significant Blowdown Loads."
Conclusion The Committee did not raise any objections to the ED0's response.
However, Mr. Michelson believes that there are some questions that still need to be discussed with the staff during the Mechanical Components Subcommittee meeting scheduled for August 17, 1993.
If these questions are not adequately resolved, Mr. Michelson will advise the Committee as to what additional actions should be taken.
EDO letter, dated June 15, 1993, responding to the ACRS report dated May 10,1993, concerning Proposed Resolution of Generic Issue 105, "Intert'actrg Systems LOCA in LWks."
Concluilon The above ED0 letter satisfactorily addressed the Committee's comments.
ED0 letter, dated June 28, 1993, responding to the ACRS report dated May 26, 1993 (revised June 16,1993), concerning the staff approach for assessing the consistency of the present regulations with respect to the Commission's Safety Goal Policy.
Conclusion The above ED0 letter satisfactorily addressed the Committee's comments.
ED0 letter, dated June 30, 1993, responding to the ACRS report dated June 18, 1993, concerning information relevant to a number of international meetings on digital instrumentation and control in which the NRC staff were participants.
Conclusion The Committee noted that the material provided did not seem to address the NRC staff's lessons learned from these meetings.
Dr.
Lewis suggested that the members would learn more from Mr. Russell, Associate Director, NRR, who offered to appear before the Committee to discuss the information on digital instrumentation and control issues that was acquired during these meetings.
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3 ED0 letter, dated July 6,1993, responding to the ACRS report dated May 20, 1993, concerning Draft Report of the PRA Working Group.
Conclusio.n The above ED0 letter satisfactorily addressed the Committ'ee's comments.
Dr. Wilkins recommended, and the Committee agreed, that the EDO should add subject headings to its future response letters to assist the ACRS members and staff in tracking and handling the responses more effectively.
SUMMARY
/ LIST OF FOLLOW-UP MATTERS As follow-up on to Dr. Wilkins' meeting with the NRR Director, Dr.
Thomas Murley, it was suguested that the ACRS Chairman meet with the NRC Office Directres (NRR, RES, and AE0D) and the Deputy Executive Director for Nuf. ear Reactor Regulation to discuss the relationship betgeen the Cummittee and the NRC staff. It was agreed that Messrs.
Carroll, Lindblad and Larkins also attend the proposed meeting.
l This meeting will be scheduled at an appropriate time in the future.
During the discussion of the schedule for completing the ACRS review of the GE Advanced Boiling Water Reactor (ABWR) design, it was noted that the ACRS review schedule is based on the assumption that GE will provide the final Standard Safety Analysis Report by July 31, 1993.
If ACRS does not receive the SSAR by this date, the review schedule may be adversely impacted. Also, the Committee decided to review the security aspects of the ABWR design, but not the technical specifications and SAMDA issues.
In its report, dated July 15, 1993, on Draft Regulatory Guides DG-1025, " Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence" and DG-1023, " Evaluation of Reactor Pressure i
Vessels with Charpy Upper-Shelf Energy less Than 50 Ft-Lb," the Committee stated that it would review the proposed final versions of these guides after the public comments have been reconciled and before they are published in final form.
'I During the discussion on the Perry BWR-6 Nuclear Power Plant event (where the suction strainers to the ECCS pumps became clogged due to ingestion of debris from the containment suppression pools), Mr.
Carroll asked if the licensee evaluated the impact of hydrodynamic loads on the larger replacement strainers which will be installed to deal with this problem. Mr. Richard Barrett, NRR, stated that the staff would provide a response.
Mr. Richard Barrett also agreed to keep the Committee informed regarding the outcome of its reevaluation of the containment emergency sump blockage issue and the decision regarding the need for additional regulatory action.
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The Committee agreed with a proposal by Mr. Carroll, Chairman of the Plant Operations Subcommittee, that the staff be invited to brief the Committee after the Augmented Inspection Team has completed its investigation of the concern whether the rod control system at the j
Salem Nuclear Power Plant, Unit 2, has met the design basis single 4
failure criteria.
The Committee agreed with a proposal by Dr. Kress that NVREG/CR-6075, "The Probability of Containment Failure by Direct Containment Heating in Zion," be considered during a future meeting of the Severe Accidents Subcommittee.
l The Committee expressed an interest in reviewing the proposed i
Generic Letter on Removal of Accelerated Testing 'and Special Reporting Requirements for Emergency Diesel Generators from Plant Technical Specifications and suggested that the NRC staff provide a copy of this generic letter to the Committee when possible, j
ANTICIPATED ACRS ACTIVITIES The Committee agreed to consider the following during the 400th ACRS Meeting, August 5-7, 1993, Bethesda, Maryland:
j Remainina Policy Issues for Passive Plant Desians - Review and comment j
on the draft Commission paper on the remaining policy issues related to the passive plant designs and outstanding issues related to the ED0's i
responses to ACRS concerns.
Representatives. of the NRC staff and the industry will participate.
Proposed Resolution of Generic Safety Issue 57. " Effects of Fire Protection System Actuation on Safety-Related Eauionent." and the Lessons i
Learned from the La Salle Fire PRA - Review and comment on the proposed
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resolution of Generic Safety Issue 57 and the L9ssons Learned from the La Salle Fire PRA.
Representatives of the NFJ staff will participate.
Representatives of the industy will participate, as appropriate.
Proposed Resolution of Generic Issue 143. " Availability of Chilled Water Systems and Room Coolina" Review and comment on the NRC staff's-proposed resolution of Generic Issue 143.
Representatives of the NRC staff will participate.
Advanced Liaht Water Reactor Policy Issue on Emeraency Plannina - Review and comment on a draft Commission paper related to emergency planning for ads anced light water reactors.
Representatives of the NRC staff will participate.
Resolution of ACRS Comments and Recommendations - Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations.
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5 Reoort of the Plannina and Procedures Subcommittee - Hear a report of I
the Planning and Procedures Subcommittee on matters related to the conduct of ACRS business.
ACRS Subcommittee Activities Hear reports and hold discussions regarding the status of ACRS subcommittee activities, including reports from the Subcommittees on Thermal Hydraulic Phenomena and Advanced Boiling Water Reactors.
Future Activities Discuss anticipated and proposed Committee activities, and organizational matters, as appropriate.
Also, discuss matters and specific issues that were not completed during previous meetings as time and availability of information permit.
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