ML20059E025
| ML20059E025 | |
| Person / Time | |
|---|---|
| Issue date: | 09/02/1993 |
| From: | Wilkins J Advisory Committee on Reactor Safeguards |
| To: | Selin I, The Chairman NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-057, REF-GTECI-143, REF-GTECI-NI, TASK-057, TASK-143, TASK-57, TASK-OR ACRS-SL-0409, ACRS-SL-409, NUDOCS 9311030071 | |
| Download: ML20059E025 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION SL-0409 i
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S September 2, 1993 The Honorable Ivan Selin Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Chairman Selin:
SUBJECT:
SUMMARY
REPORT - FOUR HUNDREDTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, AUGUST 5-6, 1993, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 400th meeting, August 5-6, 1993, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and memoranda:
Reports Prooosed Resolution of Generic Issue 57. " Effects of Fire Protection System Actuation on Safety-Related Eouioment" (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 Cooling" (Report to James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated August 11, 1993)
Memoranda Proposed Amendmr /. to 10 CFR Parts 19 and 20: Controlled Area. Occuoa-tional Dose. ar, Mino Criteria (Memorandum for C. J. Heltemes, Jr.,
Deputy Director
. neric Issues and Rulemaking, RES, from John T.
Larkins, Executive c wector, ACRS, dated August 12, 1993.)
Consistent with the Committee's decision, Dr. Larkins informed Mr. Heltemes that the Committee had decided not to review the subject proposed rule changes.
Proposed NRC Generic letter " Removal of Accelerated Testino and Special Reportira Reouirements for Emeroency Diesel Generators from Plant Technical Soecifications" (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 proposed Generic Letter during its 401st meeting, September 9-11, 1993.
The Committee has no objection to the staff's proposal for issuing the proposed Generic Letter for public comment prior to this review.
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Prooosed NRC Sucolement 1 to Generic letter 92-08. " Fire Endurance Test Acceotance Criteria for Fire Barrier Systems Used to Seoarate Redundant Safe Shutdown Train; within the Same Fire Area" (Memorandum to Brian K.
Grimes, Director, Division of Operating Reactor Support, NRR, from John T.
i 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.
HIGHLIGHTS OF KEY ISSVES CONSIDERED BY THE COMMITTEE 1.
Proposed Resolution of Generic Safety Issue 57.
" Effects of Fire Protection System Actuation on Safety-Related Eouioment." and the lessons Lgarned from the La Salle Fire PRA The Committee heard a briefing by and held discussions with representa-tives of the NRC staff and Sandia National Laboratories on the proposed resolution of Generic Safety Issue 57 and the lessons learned from the La Salle Fire PRA.
Conclusion The Committee provided a report on the proposed resolution of Generic Safety Issue 57 dated August 11, 1993, to James M. Taylor, Executive Director for Operations.
2.
Reconciliation of ACRS Comments and Recommendations The responses of the Executive Director for Operations (ED0) to previous ACRS reports were discussed as follows:
ED0 letter, dated July 22, 1993, responding to the ACRS report dated a
June 18, 1993, concerning policy statement on technical specifica-tions improvements for nuclear power plants Conclusion The above EDO letter satisfactorily addressed the Committee's comments.
EDO 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. Carrol? believes that there are some questions that still remain to be discussed with Dr. Murley.
q The Honorable Ivan Sel.*
3 September 2, 1993 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.
3.
Remainina Policy Issues for Passive Plant Desions The Committee heard a briefing by and held discussions with representa-tives 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 E00'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, but 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.
I Conclusion The Committee decided to defer consideration of a report until the resolu-tion of the public comments are completed by the staff and a revised SECY is made available to the Committee.
4.
Advanced Liaht Water Reactor Policy Issue on Emeraency Plannino The Committee heard a briefing by and held discussions with representa-tives of the NRC staff on a draft Commission paper related to emergency planning for advanced light water reactors.
ConclusiQD This briefing was for information only.
No action was taken by the Corrai ttee.
5.
Proposed Resolution of Generic Issue 143. " Availability of Chilled Wat_tt System and Room Coolina" The Committee heard a briefing by and held discussions with representa-tives 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.
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The Honorable Ivan Selin 4
September 2, 1993
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Conclusion The Comittee 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 j
place to ensure that licensees give appropriate attention to this issue as part of their IPEs.
6.
Reoort of the Plannina and Procedures Subcommittee As a result of tSe Planning and Procedures Subcommittee meeting held on August 4,1993, the following item was brought to the attentica of.the Committee:
Dr. Wilkins reported on his meeting with Chairman Selin on August 4,1993.
Items discussed during the meeting included the interaction between the Committee and the NRC staff, the Quadripartite meeting of Advisory Groups in France, the impact of FTE reductions on the ACRS, and the ACRS/ACNW Fellowship program.
7.
Subcommittee Meetinos During the period from July 8 to August 5,1993, the following Subcommit-tee meetings were held:
Comouters in Nuclear Power Plant Ooerations - July 21, 1993 The Subcommittee heard from the NRC staff and the Nuclear Utilities Management and Resource Council (NUMARC) on the progress of joint staff /NUMARC effort to develop guidelines for the performance of 10 CFR 50.59 reviews on digital instrumentation and control system upgrades. In addition, the Subcommittee heard from representatives of two utilities regarding their implmentation of digital retro-fits for the replacement of analo?
instrumentation systems.
Finally, a brief presentation by the NRC Office of Regulatory Research was given on the status of digital system environmental qualification research.
Thermal Hydraulic Phenomena - July 22-23, 1993 The Subcomittee began its review of the Westinghouse analytical and separate effects program being conducted in support of the AP600 design certification effort.
i Auxiliary and Secondary Systems - July 27-28, 1993 I
The Subcommittee heard a briefing by and held discussions with representatives of the NRC staff and Sandia National Laboratories on the proposed resolution of Generic Safety Issue 57, " Effects of Fire Protection System Actuation on Safety Related Equipment," and the lessons learned from the internal fire analysis for the LaSalle Nuclear Power Plant, Unit 2.
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The Honorable Ivan Selin 5
September 2, 1993 Imoroved Licht Water Reactors - August 4, 1993 The Subcomittee reviewed the status of resolution of the open items in the draft safety evaluation report for the EPRI Passive LWR Utility Requirements document. The Subcomittee also discussed the NRC staff response to ACRS coments on recommendations related to certain policy, technical, and licensing issues pertaining to evolutionary and advanced reactor designs, and certain remaining policy issues for passive plant designs.
Plannina and Procedures - August 4,1993 The Subcommittee discussed proposed activities, practices, and procedures relating to ACRS and related matters.
8.
Future ACRS Activities The Comittee agreed to consider the following during the' 401st ACRS Meeting, September 9-11, 1993, Bethesda, Maryland:
Proposed Rulemakina on the Fracture Touchness Reouirements for Reactor Pressure Vessel (RPV) - Revisions to 10 CFR 50.61. Accendix G and Accendix H.
and a New Rule on Thermal Annealina (10 CFR 50.651 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.
j Proposed Priority Rankina of Generic Issues - Review and comment on the priority rankings propcsed by the NRC staff for a number of generic issues.
Representatives of the NRC staff will participate.
Proposed Generic Le.tter on Removal of Accelerated Testina and Soecial Reportina Reauirements for Emeraency Diesel Generators from Plant Technical Soeci uc;tions Review and comment on the proposed generic letter on removas of accelerated testing and special reporting require-ments for emergency diesel generators from plant technical specifications.
Representatives of the NRC staff will participate. Representatives of the industry will participate, as appropriate.
Procosed Guidelines for Diaital Instrumentation and Control (I&C) Systems i
Uoorades - Review and coment 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.
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September 2, 1993 SECY-93-143. "NRC Staff Actions to Address the Recommendations in the Reoort 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.
1 Status of Individual Plant Examination (IPE) Proaram Hear a briefing by ar.d 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.
Representatives of the industry will participate, as appropriate.
Pgriodic Meetina Between the ACRS and the Commissioners - Meet with the Commissioners to discuss matters of mutual interest.
Insiahts Gained from Foreian Trios and U.S. Military Sources Recardina Diaital 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 recommendations.
Reoort 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.
Sincerely,
%dn J. Ernest Wilkins, Jr.
Chairman
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