ML20217A958
| ML20217A958 | |
| Person / Time | |
|---|---|
| Issue date: | 08/11/1997 |
| From: | Seale R Advisory Committee on Reactor Safeguards |
| To: | Shirley Ann Jackson, The Chairman NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0452, ACRS-SL-452, SECY-97-072-C, SECY-97-72-C, NUDOCS 9803250309 | |
| Download: ML20217A958 (9) | |
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'o UNITED STATES SL-0452 NUCLEAR REGULATORY COMMISSION n.
,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS PDR WASHINGTON, D. C. 20555 August 11, 1997 The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, D.C.
20555-0001
Dear Chairman Jackson:
SUBJECT:
SUMMARY
REPORT - FOUR HUNDRED FORTY-THIRD MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, JULY 9-11, 1997, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 443rd meeting, July 9-11, 1997, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following report and letter.
In addition, the Committee authorized Dr. Larkins, Executive Director, to transmit the memoranda noted below:
FEPORT Procosed Reculatorv Guide and Standard Review Plan Chaoter for Risk-Informed. Performance-Based Inservice Insoection (Report to Shirley Ann Jackson, Chairman, NRC, from R.
L.
- Seale, Chairman, ACRS, dated July 14, 1997.)
t LETTER e
ProDosed Final Revisions to 10 CFR Part 26, Fitness-For-Duty Procram Recuirements (Letter to L.
Joseph Callan, Executive Director for Operations, NRC, from R.
L.
Seale, Chairman, ACRS, dated July 14, 1997) l MEMORANDA e
Procosed Final Revision 3 to Reculatorv Guide 5.44. " Perimeter Intrusion Alarm Systems" (Memorandum to L.
Joseph Callan,
/d)O[
/
Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated July 15, 1997) e Procosed Direct Final Rulemakino: Chances to Paracraoh (h) of 10 CFR 50.55a. " Codes and Standards" (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T.
Larkins, Executive Director, ACRS, dated July 15, 1997) 2., d C'
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The Ilonorable Shirley Jackson 2
i HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE 1.
Meetina with the Director of the NRC Office of Nuclear Reactor Reculation Mr. Samuel J. Collins, Director, Office of Nuclear Reactor Regulation (NRR), briefed the Committee on items of mutual a broad view of current interest.
Mr. Collins presented issues that are under consideration by NRR.
NRR priorities are articulated in three major categories:
oversight of operating reactors, allegation follow-up, and event response.
Current issues include allegations, employee concerns, a
safety-conscious work environment, plant evaluation and assessment, and design bases and 10 CFR 50.59 process improve-Other issues which are the subject of ongoing ACRS/NRR ments.
interactions are spent fuel storage, steam generator integri-ty, license renewal, core performance and reactor fuel, and industry deregulation and restructuring.
CONCLUSION This was an information briefing.
No Committee action was required.
2.
Acceotance Criteria for Plant-Soecific Safety Goals and Derivina Lower-Tier Accentance Criteria The Committee heard a briefing by and held discussions with an ACRS Senior Fellow regarding the results of an analysis he performed to determine the site-specific changes in core damage frequency and large, early release frequency when these lower-tier criteria are derived from the prompt fatality quantitative health objectives.
The Committee discussed the Commission's request related to these matters as stated in the Staff Requirements Memorandum dated May 27, 1997.
Conclusion The Committee expects to prepare a report to the Commission during the September 3-5, 1997 ACRS meeting.
The Committee decided to submit the study completed by the ACRS Senior Fellow for external peer review.
3.
Procosed Standard Review Plan Chaoter and Reculatory Guide for Risk-Informed, Performance-Based Inservice Insoection The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the proposed Regulatory Guide DG-1063 and Standard Review Plan Chapter 3.9.8 for risk-informed, performance-based inservice inspec-tion for piping.
The ACRS Subcommittee on Probabilistic Risk
The Honorable Shirley Jackson 3
A'ssess' ment also met with the staff, industry representatives, and other interested parties on July 8,1997, to discuss these documents and industry initiatives.
Conclusion The Committee issued a report to Chairman Jackson on July 14, 1997, on this matter.
4.
Meetina with NRC Commissioner McGaffican Commissioner Edward McGaffigan offered his views on how the NRC could operate more efficiently and effectively and discussed a number of technical and regulatory issues.
These included the restructuring of ACRS subcommittees, possible rulemaking to improve the 10 CFR 50.59 process, the PRA imple-mentation plan, NRC and licensee resources, oversight of Department of Energy facilities, AP600 design issues, and the role of the ACRS in NRC research activities.
Conclusion The Committee meets occasionally with individual NRC Commis-sioners.
No Committee action was required.
5.
Proposed Final Revisions to 10 CFR Part 26. Fitness-For-Duty Procram Recuirements The Committee heard presentations by and held discussions with representatives of the NRC staf f regarding the proposed final revisions to 10 CFR Part 26, Fitness-For-Duty (FFD) Program Requirements.
The purpose of the proposed amendment is to improve the effectiveness of licensees' FFD programs, reduce unnecessary burdens, and to ensure continued protection of public health and safety.
The staff prepared a draft NUREG document which summarizes public comments and associated staff responses on the proposed amendment to 10 CFR Part 26.
The draft NUREG document also discusses the comments and responses in relation to other Federal FFD programs.
The staff concluded that the proposed final modifications would not impose any additional burden on the industry;
- moreover, some modifications would reduce licensees' administrative burden and provide increased clarity and consistency to 10 CFR Part 26 requirements.
Conclusic_D The Committee issued a letter to the Executive Director for Operations dated July 14, 1997, on this matter.
The. Honorable Shirley Jackson 4
6.
Mal' den Reactor Proiect The NRC staff briefed the Committee regarding the activities at-the Halden Reactor Project (HRP) which is an international-ly funded cooperative effort. The NRC has participated in the HRP since 1958.
During this period, the NRC received the benefit of numerous research products. The NRC staff uses the Halden-generated products and information in the~ development of analytical tools and regulatory guidance.
The staff plans
-to continue participation in the HRP in 1997-1999 in accou dance with the agreement and also because of the benefits received.
The main HRP activities address nuclear fuels and materials performance and improved operational safety and efficiency through improvements in control room design.
The HRP main-
'tains comprehensive facilities and research staf f for perform-ing experimental research on issues regarding the human-system interfaces for advanced technology.
These f acilities include the Halden Man-Machine Laboratory (HAMMLAB), which contains a full-scope PWR simulator, a modifiable CRT-based operator interface, and an extensive automated system for recording and analyzing experimental data.
The HRP conducts research to ensure and enhance the quality of computer-based systems.
The research addresses topics covering various types of instrumentation and control systems.
The development and application of both formal and convention-al methods to verify and validate high integrity software are also subjects of research.
In addition, HRP research activities in the areas of fuels and materials performance have become preeminent with advanced in-reactor instrumentation and testing methods.
The research program explores the regime of high burnup fuels. The results are now used to update NRC analytical codes such as FRAPCON and to support licensing reviews for extended fuel burnup.
CONCLUSION This briefing was for information only.
The Committee, however, plans to follow-up on the progress of this project.
7.
Use of RASCAL Code Durina Incident Resoonse The Committee was briefed by representatives of the Office for Analysis and Evaluation of Operational Data (AEOD) on the use of the RASCAL computer code in support of the Emergency Dose Projection System employed in support of incident response actions.
This briefing was held in response to questions raised during an AEOD presentation to the Committee in
The Honorable Shirley Jackson 5
December 1996 on modifications made to the Emergency Response Program.
Specifically, Committee members requested details concerning the capabilities of RASCAL, with regard to its use for dose projection.
Two follow-on issues resulted from this discussion: (1) the recovery of areas that may have been judged to be unavailable based on initial dose projections that later turn out to be in error, and (2) the treatment of plant workers when a radiolog-ical release results in contamination in and around the immediate site (e.g., an event that occurs during a refueling outage).
Committee members expressed concern that the latter event may have implications for shutdown _ risk vis-a-vis the proposed rulemaking for shutdown and spent fuel pool operati-ons.
Conclusion This briefing was for information only.
The Committee will consider these issues further and may hold additional discus-sions on this matter during a future meeting.
8.
Recommendations for Probabilistic Seismic Hazard Analysis; Guidance on Uncertainty and Use of Excerts The Committee heard presentations by and held discussions with representatives of the NRC staff and its consultants regarding NUREG/CR-6372, which was prepared by the Lawrence Livermore National Laboratory for the NRC Office of Nuclear Regulatory Research.
This NUREG documents the recommendations resulting from a study performed by the Senior Seismic Hazard Analysis Committee (SSHAC), which was organized and co-sponsored by the NRC, the Department of Energy, and the Electric Power Research Institute.
The objective of the study performed by SSHAC was to develop implementation guidelines, including a recommended methodology, suitable for performing a Probabilistic Seismic Hazard Analysis (PSHA) for use in regulating nuclear power plants.
The SSHAC concluded that many of the major potential pitf alls in executing a successful PSHA are procedural rather than technical in character.
One of the most difficult challenges for the PSHA analyst is to properly represent the wide diversity of expert judgments about the technical issues in PSHA in an acceptable analytical result, including addressing the large uncertainties.
This conclusion was primarily based on strong emphasis on procedural guidance.
The Honorable-Shirley Jackson 6
Concithsion
)
This briefing was for information only.
No Committee action was required.
RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The Committee discussed the response from the NRC Executive e.
Director for Operations (EDO) dated June 12, 1997, responding to ACRS comments and recommendations included in the ACRS report dated May 7, 1997, concerning design basis verifica-tion.
The Committee decided that it was satisfied with the EDO's response.
e The Committee discussed the response from the EDO dated June 23, 1997, responding to ACRS comments and recommendations included in the ACRS report dated May 8, 1997, concerning the proposed final policy statement *on the restructuring and economic deregulation of the electric utility industry.
-The Committee decided that it was satisfied with the EDO's response.
e The Committee discussed the response from the EDO dated July 7,
1997, concerning stockpiling of potassium iodide.
The Committee decided that it was satisfied with the EDO's response.
e The Committee discussed the response from the EDO dated July 9,
- 1997, responding to ACRS comments and recommendations included in the ACRS report dated June 23, 1997, concerning regulatory guidance for implementation of digital instrumenta-tion and control systems.
The Committee decided that it was satisfied with the EDO's response.
OTHER RELATED ACTIVITIES OF THE COMMITTEE During the period from June 11 through July 9, 1997, the following Subcommittee meetings were held:
The' Honorable Shirley Jackson 7
Probabili~stic Risk Assessment - July 7-8, 1997-e The Subcommittee' on Probabilistic Risk Assessment (PRA) met on July 7, 1997, with representatives of the NRC staff tofreview-acceptance criteria for plant-specific safety goals ~and
. deriving lower-tier acceptance. criteria, and the use' -of uncertainty versus point values in the PRA-related decision-making process..
On July 8,>1997, the Subcommittee reviewed
' the-proposed Standard Review Plan'section and associated draft Regulatory Guide DG-1063 for risk-informed, performance-based inservice inspection for piping.
9-Plannina and Procedures - July 8 and 10, 1997 The. Planning and Procedures Subcommittee discussed proposed ACRS activities,. practices, and procedures for conducting Committee business and organizational and personnel matters relating to ACRS and its staff.
LIST OF FOLLOW-UP MATTERS FOR THE EXECUTIVE DIRECTOR FOR OPERATIONS e
The Committee considered the Proposed Direct Final Rulemaking:
. Changes to Paragraph (h) of 10 CFR 50.55a, " Codes and Stan-
-dards," and decided to review the changes, if any, resulting from the resolution of public comments.
The Committee plans to follow-up on the research activities at the Halden Reactor Project.
The Committee plans to hold further discussions with the staff on the issues associated with the use of RASCAL Code during incident response at a future meeting.
PROPOSED SCHEDULE FOR THE 444TH ACRS MEETING
.The Committee agreed to consider the following during the 444th ACRS Meeting, September-3-5,-1997:
Staff Action Plan to Imorove the Senior Manaaement Meetina Process.
SECY-97-072 The Committee will hold discussions with representatives of the NRC staff, as needed, regarding the action plan to improve the Senior Management Meeting process.
Renortina-Reliability 'and Availability Infornation for Risk-
.Sionificant-Systems and Eauinment The Committee will hold discussions with representatives of the NRC t staf f, as needed, regarding the voluntary approach prcposed by the industry for reporting reliability and availability information for
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The Honorable Shirley Jackson 8
n risk-significant systems and equipment.
Represents 11ves of the nuclear industry will participate, as appropriate.
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~
NRC Procrams for Risk-Based Analysis of Reactor Operatina Exoeri-ence and Boecial Studies The Committee will hold discussions with representatives of the NRC staff, as needed, regarding the NRC programs for Risk-Based Ana-lysis of Reactor Operating Experience as well as the findings and conclusions of several special studies performed by the staff, including those related to auxiliary feedwater, Westinghouse reactor protection system, loss of offsite power, initiating
- events, reactor core isolation
- cooling, high pressure core injection, and fire events.
Draft Reaulatory Guide DG-1069:
Fire Protection Procram for Permanently Shutdown and Decommissionina Nuclear Plants The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the draft Regulatory Guide on fire protection program for permanently shutdown and decommissioning nuclear plants.
Site-Soecific Safety Goals The Committee will hold discussions with an ACRS Senior Fellow and representatives of the NRC staff, as needed, regarding the site-specific safety goals.
Use of Uncertainty Versus Point Values in the PRA-Related Decision-makino Process The Committee will hear a report by the Subcommittee Chairman regarding matters discussed at the August 28-29, 1997 Subcommittee meeting.
Representatives of the NRC staff will participate, as appropriate.
Meetina with the NRC Executive Director for Ooerations The Committee will hear a presentation by and hold discussions with the NRC Executive Director for Operations regarding items of mutual interest.
Procosed Generic Letter and Reaulatorv Guide Associated with Steam Generator Intecrity The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed Generic Letter and Regulatory Guide associated with steam generator integrity.
Representatives of the nuclear industry will partici-pate, as appropriate.
The Honorable Shirley Jackson 9
BWR Pressure Vessel Shell Weld Insoections The Committee will hear a report by the subcommittee Chairman regarding issues discussed at the August 26, 1997 Subcommittee meeting associated with BWR pressure vessel shell weld inspections.
Representatives of the NRC staff will participate as appropriate.
Subcommittee Reoort The Committee will hear a report by the Subcommittee Chairman regarding matters discussed at the July 29-30, 1997 meeting of the Thermal Hydraulic Phenomena Subcommittee.
Proposed Rule on Shutdown and Scent Fuel Pool Ooerations The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed rule on shutdown and spent fuel pool operations.
Reaulatorv Policies and Practices The committee will hear a report by the Subcommittee Chairman regarding matters discussed at the August 27, 1997 Subcommittee meeting Imoroner Control Rod Movement Durina Shutdown at Zion Unit 1, and Nonconservative Operations Durina Isolation of Recirculation Seal Leak at Clinton The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding improper control rod movement during shutdown at Zion Unit 1, nonconservative operations during isolation of recirculation seal leak at the Clinton Nuclear Power Plant, and associated organizational human performance issues.
Representatives of the nuclear industry will participate, as appropriate.
Sincerely, R. L. Seale Chairman
.