ML20059D703
| ML20059D703 | |
| Person / Time | |
|---|---|
| Issue date: | 09/02/1993 |
| From: | Larkins J Advisory Committee on Reactor Safeguards |
| To: | Blaha J, Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| REF-GTECI-057, REF-GTECI-143, REF-GTECI-NI, TASK-057, TASK-143, TASK-57, TASK-OR ACRS-GENERAL, GL-92-08, GL-92-8, NUDOCS 9311020371 | |
| Download: ML20059D703 (5) | |
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UNITED STATES '
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September 2, 1993 4
MEMORANDUM FOR: James M. Taylor Executive Director for Operations ATTN:
James Blaha FROM:
John T. Larkins Executive Director, ACRS
SUBJECT:
400TH ACRS MEETING F0LLOW-UP ITEMS This memorandum is provided for follow-up action consistent with the Actions, Agreements, Requests, and Commitments made during the 400th ACRS meeting, August-5-6, 1993.
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John T. Larkins Executive Director, ACRS cc: w/ attachment:
E. L. Jordan, AE0D 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 N00bd 0
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SUMMARY
OF ACTIONS, AGREEMENTS, REQUESTS, AND COMMITMENTS 400TH ACRS MEETING AUGUST 5-6, 1993 During its 400th meeting, August 5-6, 1993, held at 7920 Norfolk Avenue, Bethesda, Maryland, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the reports and memoranda noted below.
REPORTS ProDosed Resolution of Generic Issue 57. " Effects of Fire Protection j
System Actuation on Safety-Related Eauioment" (Report to James M. Taylor, Executive Director for Operations, from J.
Ernest Wilkins, Jr.,
ACRS Chairman, dated August 11, 1993)
Proposed Resolution of Generic Issue 143. " Availability of Chilled Water System and Room Coolina" (Report to James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated August 11, 1993)
MEMORANDA Procosed Amendments to 10 CFR Parts 19 and 20: Controlled Area.
Occupational Dose and Trainina Criteria (Memorandum to C. J. Heltemes, Jr., Deputy Director for Generic Issues and Rulemaking, RES, from John T.
Larkins, Executive Director, ACRS, dated August 12, 1993.)
Consistent with the Committee's decision, Dr. Larkins informed Mr. Heltemes that the Committee had decided not to review these proposed rule changes.
Proposed NRC Generic letter " Removal of Accelerated Testina and Special ReDortina Recuirements for Emeraency Diesel Generators from Plant Technical Specifications" (Memorandum to Brian K.
Grimes, Director, Division of Operating Reactor Support, NRR, from John T. Larkins, Execu-tive Director, ACRS, dated August 13,1993.) Consistent with the Committ-ee's decision, Dr. Larkins informed Mr. Grimes that the Committee had decided to review the subject pronosed Generic Letter during its 401st meeting, September 9-11, 1993.
The Comm;ttee has no objection to the staff's proposal for issuing the proposed Generic Letter for public comment prior to this review.
Proposed NRC Suoolement I to Generic Lettfr 92-08. " Fire Endurance Test AcceDtance Criteria for Fire Barrier Systems Used to Separate Redundant Safe Shutdown Trains within the Same Fire Area" (Memorandum to Brian K.
Grimes, Director, Division of Operating Reactor Support, NRR, from John T.
Larkins, Executive Director, ACRS, dated August 16, 1993.)
Consistent with the Committee's decision, Dr. Larkins informed Mr. Grimes that the Committee had decided to postpone its review of the Supplement I to Generic Letter 92-08 until after the public comments have been reconciled by the staff.
2 RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The responses of the Executive Director for Operations (ED0) to previous ACRS reports were discussed as follows:
EDO letter, dated July 22, 1993, responding to the ACRS report dated June 18,
- 1993, concerning policy statement on technical specifications improvements for nuclear power plants
[pnclusion The above EDO letter satisfactorily addressed the Committee's comments.
ED0 letter, dated July 23, 1993, responding to the ACRS report dated July 15, 1993, concerning the regulatory review group report Conclusion The Committee did not raise any objections to the ED0's response.
However, Mr. Carroll believes that there are some questions that still remain to be discussed with Dr. Murley.
ED0 letter, dated July 27, 1993, responding to the ACRS report dated July 15, 1993, concerning proposed draft Regulatory Guides, DG-1023 and DG-1025 Conclusion The above EDO letter satisfactorily addressed the Committee's comments.
As stated in the response, the Committee expects to schedule another meeting for review of the proposed final versions of the draft guides.
EUMMARY/ LIST OF FOLLOW-UP MATTERS The Committee heard a briefing by and held discussions with representatives of the NRC staff on the draft SECY, " Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems in Passive Plant Designs," dated July 1993, and outstanding issues related to the ED0's responses to ACRS concerns.
In the draft SECY, the staff identified eight issues specific to the regulatory treatment of non-safety systems for passive light water reactors.
The Committee generally agreed with the staff's positions, however, it had some concerns. The staff stated that the draft SECY will be placed in the Public Document Room and the public will be given an opportunity to submit comments.
The Committee decided to defer consideration of a report until the resolution of the public comments is completed by the staff and a revised SECY is made available to the Committee.
3 The Committee heard a briefing by and held discussions with representatives of the NRC staff and Pacific Northwest Laboratory on the NRC staff's proposed resolution of Generic Issue 143 and the value-impact assessment in support of GI-143.
The Committee provided a report on this matter dated August 11, 1993, to James M.
Taylor, Executive Director for Operations.
The Committee also intends to address its concern that there appears to be no process in place to ensure that licensees give appropriate attention to this issue as part of their IPE and IPEEs.
ANTICIPATED ACRS ACTIVITIES The Committee agreed to consider the following during the 401st ACRS Meeting, September 9-11, 1993, Bethesda, Maryland:
Proposed Rulemakina on the Fracture Touahness Reauirements for Reactor Pressure Vessel (RPV) - Revisions to 10 CFR 50.61. Accendix G and Aooendix H. and a New Rule on Thermal Annealina (10 CFR 50.66) - Review and comment on the proposed rulemaking on the fracture toughness requirements for RPV for protection against pressurized thermal shock events and on a new rule on thermal annealing of the RPV. Representatives of the NRC staff will participate. Representatives of the industry will participate, as appropriate.
Proposed Priority Rankina of Generic Issues Review and comment on the priority rankings proposed by the NRC staff for a number of generic issues.
Representatives of the NRC staff will participate.
Proposed Generic Letter on Removal of Accelerated Testina and Special Reportina Reauirements for Emeroency Diesel Generators from Plant Technical Soecifications
- Review and comment on the proposed generic letter on removal of accelerated testing and special reporting requirements for emergency diesel generators from plant technical specifications. Representatives of the NRC staff will partici-pate.
Representatives of the industry will participate, as appropriate.
Proposed Guidelines for Diaital Instrumentation and Control (I & C) Systems U_ parades - Review and comment on the guidelines proposed by NUMARC for 10 CFR 50.59 evaluations of digital instrumentation and control systems upgrades.
Representatives of the NRC staff and the industry will participate.
SECY-93-143. "NRC Staff Actions to Address the Recommendations in the Report on the Reassessment of the NRC Fire Protection Proaram" - Hear a briefing by and hold discussions with representatives of the NRC staff regarding SECY-93-143.
Representatives of the industry will participate, as appropriate.
Status of Individual Plant Examination (IPE) Proaram - Hear a briefing by and hold discussions with representatives of the NRC staff on the status of the IPE Program, including how generic issues are addressed in the IPE program. Repre-sentatives of the industry will participate, as appropriate.
Periodic Meetina Between the ACRS and the Commissioners Meet with the Commissioners to discuss matters of mutual interest.
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4 Insiahts Gained from Foreion Trios and U.S. Military Sources Recardina Dioital Instrumentation and Control Issues - Hear a briefing by and hold discussions with representatives of the NRC staff regarding insights gained by the staff from its interactions with foreign regulatory authorities and nuclear utilities as well as U.S. military sources on digital instrumentation and control issues.
Resolution of ACRS Comments and Recommendations - Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recom-mendations.
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.
ACRS Subcommittee Activities - Hear reports and hold discussions regarding the status of ACRS subcommittee activities, including reports from the Subcommittees on Materials and Metallurgy, Mechanical Components, 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.