ML20059D425
| ML20059D425 | |
| Person / Time | |
|---|---|
| Issue date: | 07/12/1993 |
| From: | Wilkins J Advisory Committee on Reactor Safeguards |
| To: | Selin I, The Chairman NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0407, ACRS-SL-407, NUDOCS 9311020250 | |
| Download: ML20059D425 (6) | |
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July 12, 1993 The Honorable Ivan Selin Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Chairman Selin:
SUBJECT:
SUMMARY
REPORT - THREE HUNDRED AND NINETY EIGHTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, JUNE 10-11, 1993, AND OlHER RELATED ACTIVITIES OF THE COMMITTEE During its 398th meeting, June 10-11, 1993, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and memorandum:
Reports SECY-93-ll3. Additional Implementation Information for 10 CFR Part 54.
"Reauirements for Renewal of Operatinq 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 Perf' rmance (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)
Memorandum information from International Meetinas on Dioital Instrumentation and n
Control Systems (Memorandum for Mr. James M. Taylor, Executive Director for Operations, from J. Ernest Wilkins, Jr., ACRS Chairman, dated June 18, 1993) i 1
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2 HJGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE i
1.
SECY-93-ll3. Additional Implementation Information for 10 CFR Part 54.
"Reouirements for Renewal of Operatina Licenses for Nuclear Power Plants" The Committee heard a briefing by and held discussions with represent-atives of the NRC staff on SECY-93-ll3 and related documents.
Although representatives from NUMARC were not present during this session, the NRC-staff expects to receive industry views in the near term.
The Committee expressed interest in reviewing the public comments and the staff's resolution of these comments.
Conclusion The Committee provided a report on this matter, dated June 18, 1993, to Chairman Selin.
2.
Public Comments on Advanced Liaht-Water Reactor Severe Accident Pl ant-Performance The Committee was briefed by a representative of RES on the public comments received on the Advance Notice of Proposed Rulemaking (ANPR) on ALWR Severe Accident Performance. Also, the staff's proposed approach for proceeding with rulemaking was discussed which, in part, involves continuing interaction with the Committee during the developmental phase.
l Conclusion The Committee provided a report on this matter, dated June 18, 1993, to the Executive Director for Operations, Mr. James M. Taylor.
3.
Reconciliation of ACRS Comments and Recommendations The responses of the Executive Director for Operations (EDO) to previous ACRS reports were discussed as follows:
EDO letter, dated June 3, 1993, responding to the ACRS report dated
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April 22,1993, concerning Definition of a large Release for Use with Safety Goal Policy.
The above EDO letter satisfactorily addressed the Committee's comments.
1 EDO letter, dated May 28, 1993, responding to the ACRS report dated i
April 30,
- 1993, concerning Staff Initiatives to ' Revise the Systematic Assessment of Licensee Performance Program.
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.
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1 ED0 letter, dated May 28, 1993, responding to the ACRS report dated.
April 27,1993, concerning Review of Organizational Factors Research' l
Program.
J The above ED0 letter satisfactorily addressed the Committee's comments.
ED0 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, o
i EDO 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 comments that need further discussion with the NRC staff.
It was agreed that these issues would be itemized and discussed with the staff during the Improved Light Water Reactors Subcommittee meeting on August 4, 1993.
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.
4.
" Final Policy Statement on Technical Specifications Improvements" i
The Committee reviewed and commented on the staff's proposed final policy statement on Technical Specifications Improvements for Nuclear Power Plants.
Representatives of the NRC staff participated.
Conclusion The Committee provided a report on this matter, dated June 18, 1993, to Chairman Selin.
5.
Reactor Oneratina Experience The Committee heard presentations by and held discussions with representatives of the NRC staff regarding recent operating events involving computer malfunctions.
o A representative of the NRC Region I Office described the loss of control i
room annunciators event that occurred at the Salem Nuclear P.wer Plant l
Unit 2 and the inoperable ATWS mitigating system actuation circuitry
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I 4-l (AMSAC) event that occurred at the Indian Point Nuclear Power Plant Unit
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i 3 and the findings of the NRC staff inspections of these events.
i A representative of NRR discussed the NRC staff's preparation of Information Notices (IN) on recent industry events involving computer problems, including yet to be issued ins on two research reactor digital control system problems, and software problems with the Maine Yankee ATWS system and the Fitzpatrick torus temperature monitoring system.
He also noted that Region I is developing an inspection procedure for assessing the adequacy of software integration at nuclear power plants.
Conclusion This briefing was for information only.
No action was taken by the Committee.
6.
Risk-Based Regulation The Committee was briefed by Dr. Vojin Joksimovich on risk-based l
regulation.
Conclusion This briefing was for information only.
No action was taken by the Committee.
7.
Unauthorized forced Entry at Three Mile Island Unit 1 k
i The Committee heard a presentation by and held discussions with representatives of the NRC staff regarding the unauthorized forced-entry into the protected area at Three Mile Island Unit 1 that occurred on February 7, 1993.
Conclusion This briefing was for information only.
No action was taken by the Committee.
8.
BWR Vessel Water Level Instrumentation 4
Dr. Catton provided a brief report on the status of the issue of the reliability of BWR vessel water level instrumentation.
This issue was discussed during the Joint Core Performance / Thermal Hydraulic Phenomena
'i Subcommittee meeting of May 12, 1993. Specifically, Dr. Catton noted that i
Mr. Paul Blanch, who had requested time to make a presentation to the Committee on the subject, withdrew his request for time for an oral statement but had submitted written material for the Committee's consideration.
Dr. Catton noted that the HRR staff has issued an Emergency Bulletin that orders the affected licensees to institute a hardware fix.
Mr. Blanch is apparently satisfied that his concerns have been addressed.
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Conclusion This briefing was for information only.
No action was taken by the Committee.
9.
ACRS Report on the Staff Anoroach for Asst;..no the -Consistency of the Present Reaulations with Resoect to the Commission's Safety Goals Dr. Lewis observed that the ACRS report entitled, " Staff Approach for Assessing the Consistency of the Present Regulations with Respect to the Commission's Safety Goals," dated May 26, 1993, contains an oversight in the last paragraph that may cause some confusion. The Committee agreed to isst.a a revised report clarifying the Committee's intent.
The' revised report was issued on June 25, 1993.
10.
Subcommittee Meetina During the period from May 14, 19b3 to June 9, 1993, the - following Subcommittee meeting was held:
Plannina and Procedures - June 9, 1993 The Subcommittee discussed proposed ACRS activities, practices, and-procedures for conducting Committee business and related matters.
11.
Future 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.
Apolication of Probabilistic Risk Assessment Methods for Rankina Motor-Operated Valves (MOV)
Hear a briefing by and hold discussions with 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.
Draft Requlatory 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.
6 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 Emeraency 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 this issue as a result of the lessons learned from the Barseback event.in Sweden. Representatives of the industry will participate, as appropriate.
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 steem
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Resolution of ACS 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.
Sincerely, i
J. Ernest Wilkins, r.
Chairman n
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