ML20059D305
| ML20059D305 | |
| Person / Time | |
|---|---|
| Issue date: | 07/13/1993 |
| From: | Larkins J Advisory Committee on Reactor Safeguards |
| To: | Blaha J, Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| ACRS-GENERAL, NUDOCS 9311020204 | |
| Download: ML20059D305 (4) | |
Text
{{#Wiki_filter:t k fh [&* "'%q'o, t UNITED STATES NUCLEAR REGULATORY COMMISSION n { .E ADVISORY COMMITTEE ON REACTOR SAFELUARDS o, g WASHINGTON, D. C. 20555
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July 13, 1993 MEMORANDUM FOR: James M. Taylor Executive Director for Operations ATTN: J. Blaha, EDO FROM: John T. Larkins Executive Director, ACRS
SUBJECT:
398TH ACRS MEETING FOLLOW-UP ITEMS This memorandum is provided for follow-up action consistent with the Actions, Agreements, Requests, and Commitments made during the 398th ACRS Meeting, June 10-11, 1993. a/Z 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 j S. Chilk, SECY J. Johnson, OCM/IS J. Scarborough, OCM/KR J. Guttmann, OCM/FR E. McKenna, OCM/GD 1 $b i i 020053 trs:c urtn carct ut [,9f \\\\ - m,, ~'~ 9311020204 930713 PDR ACRS CENERAL PDR
SUMMARY
OF ACTIONS, AGREEMENTS, REQUESTS, AND COMMITMENTS 398TH ACRS MEETING JUNE 10-11, 1993 During its 398th meeting, June 10-11, 1993, held at-7920 Norfolk ' Avenue, Bethesda, Maryland, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and' completed the reports and memorandum noted below. REPORTS t SECY-93-ll3. Additional Implementation Information for 10 CFR Part S42 "Reauirements for Renewal of Ooeratina Licenses for Nuclear Power Plants" (Report to the Honorable Ivan Selin, NRC Chairman, from J. Ernest Wilkins,- Jr., ACRS Chairman, dated June 18,1993) Public Comments on Proposed Rule on ALWR Severe Accident Performance (Report to Mr. James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated June 18,1993) Policy Statement on Technical Specifications Improvements 'for Nuclear Power Plants (Report to the Honorable Ivan Selin, NRC Chairman, from J. Ernest Wilkins, Jr., ACRS Chairman, dated June 18,1993) MEMORANDVJ Jnformation from International Meetinas on Diaital Instrumentation and i Control Systems (Memorandum for Mr. James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated June 18, 1993) ANTICIPATED ACRS ACTIVITIES The Committee agreed to consider the following during the 399th ACRS Meeting, July 8-10, 1993, Bethesda, Maryland: NRC Reaulatory Review Group' Report - Review and comment on the report of the NRC Regulatory Review Group. Representatives of the NRC staff will participate. -{ Acolication of Probabilistic Risk Assessment Methods for Rankina Motor-Operated Valves (MOV) Hear a briefing by and hold discussions with i representatives of the NRC staff on the preliminary results from a-- research program to prioritize the risk importance of MOVs. Representatives of the industry will participate, as appropriate. Plans for Completina the Review of the Advanced Boilina Water Reactor Standard Safety Analysis Report (SSAR) Discuss the schedule for completing the ACRS review of the SSAR for the ABWR design. Representatives of the NRC staff will participate, as appropriate. .i
i r 2 Draft Reaulatory Guide. DG-1025. Calculational and Dosimetry Methods for Determinina Pressure Vessel Neutron Fluence - Review and comment on a draft regulatory guide on the methodology for determining pressure vessel neutron fluence. Representatives of the NRC staff will-participate. P Draft Reaulatory Guide. DG-1023. Evaluation of Reactor Pressure Vessels with Charov Upper-Shelf Enerav less Than 50 ft-lb - Review and comment on a draft regulatory guide on the evaluation of reactor pressure vessels with Charpy upper-shelf energy less than 50 ft-lb. Representatives of the NRC staff will participate. Debris Pluaaina of Emeroency Core Coolina Suction Line Strainers - Hear a briefing by and hold discussions with representatives of the NRC staff on the potential for debris plugging of emergency core cooling suction line strainers. In addition, the NRC staff will provide an update on its activities to evaluate the need for action by U.S. licensees to address 1 this issue as a result of the lessons learned from the-Barseback event in Sweden. Representatives of the industry will participate, as appropriate. 'I Reactor Operatina Experience - Hear a briefing by and hold discussions with representatives of the NRC staff on a recent event at _Sequoyah Nuclear Power Plant Unit 2 that involved a rupture of an extraction. steam header line. Resolution of ACRS Comments and Recommendations - Discuss responses from the NRC Executive Director for Operations to recent ACRS comments and recommendations. ACRS Subcommittee Activities Hear reports and hold discussions regarding the status of ACRS subcommittee activities, including a report of the Planning and Procedures Subcommittee. Other Committee 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. RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows: ED0 letter, dated June 3, 1993, responding to the ACRS report dated i April 22, 1993, concerning Definition of a large Release for Use with Safety Goal Policy. j The above EDO letter satisfactorily addressed the Committee's comments. ED0 letter, dated May 28, 1993, responding to the ACRS report dated-April 30, 1993, concerning Staff Initiatives to Revise the Systematic Assessment of Licensee Performance Program. -l
~ 3 4 The Committee did not raise any objections to the ED0's response. However, the Committee expressed interest in discussing in more detail the formal appeal process with Dr. Thomas Murley, NRR Director, during his next meeting with the ACRS. EDO letter, dated May 28, 1993, responding to the ACRS report dated April 27, 1993, concerning Review of Organizational Factors Research i Program. The above EDO letter satisfactorily addressed the Committee's comments. EDO letter, dated May 25, 1993, responding to the ACRS' report dated April 23, 1993, concerning SECY-93-049,- Implementation of 10 CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants. The above EDO letter satisfactorily addressed the Committee's comments. ED0 letter, dated May 19, 1993, responding to the ACRS report dated = April 26, 1993, concerning SECY-93-087, " Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs." The Committee noted that the ED0's response did not address several ACRS concerns that needed further discussion with the NRC staff. It was agreed 3 that these issues would be itemized and discussed with the staff during the Improved Light Water Reactors Subcommittee meeting on August 4, 1993. i EDO letter, dated June 8,1993, responding to the ACRS report dated April 23, 1993, concerning Prioritization of Generic Issue 152, " Design Basis for Valves That Might be Subjected to Significant Blowdown loads." The above EDO letter satisfactorily addressed the Committee's comments. l
SUMMARY
/ LIST OF FOLLOW-UP AND OTHER MATTERS Dr. Wilkins met with Dr. Murley and his senior staff on July 7,
= 1993, to discuss ACRS interfaces with the NRR staff. 1 The Committee agreed to discuss the IPE Program and !the Severe Accident Management Program at a future meeting. i -}}