ML20217A638: Difference between revisions

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: 24. Proposed Generic Letter, " Potential for Degradation of the ECCS and the Containment Spray System after a LOCA Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment."
: 24. Proposed Generic Letter, " Potential for Degradation of the ECCS and the Containment Spray System after a LOCA Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment."
: 25.    ~ Proposed Regulatory Approach Associated with Steam Generator Integrity.
: 25.    ~ Proposed Regulatory Approach Associated with Steam Generator Integrity.
: 26. June 17,1997, letter regarding inclusion of a Containment Spray System in the AP600 Design.
: 26. {{letter dated|date=June 17, 1997|text=June 17,1997, letter}} regarding inclusion of a Containment Spray System in the AP600 Design.
22 Minutes of Plannino and Procedures Subcommittee Meetina. Auaust 27.1997 [ Handout
22 Minutes of Plannino and Procedures Subcommittee Meetina. Auaust 27.1997 [ Handout
                 #21.1]
                 #21.1]
Line 1,072: Line 1,072:
: 58.      Status Report, dated September 4,1997
: 58.      Status Report, dated September 4,1997
: 59.      Letter from John T. Lerkins, ACRS, to L Joseph Callan, EDO, dated July 31, 1997.                                                                              j
: 59.      Letter from John T. Lerkins, ACRS, to L Joseph Callan, EDO, dated July 31, 1997.                                                                              j
: 60.      ACRS letter dated December 30,1996, RE: ACRS Questions on Human Performance Program Plan
: 60.      ACRS {{letter dated|date=December 30, 1996|text=letter dated December 30,1996}}, RE: ACRS Questions on Human Performance Program Plan
: 61.      EDO Response dated February 4,1997, RE: ACRS Questions on Human                    I Performance Program Plan                                                            !
: 61.      EDO Response dated February 4,1997, RE: ACRS Questions on Human                    I Performance Program Plan                                                            !
: 62.      ACRS Report dated February 13,1997 RE: Human Performance Program Plan.
: 62.      ACRS Report dated February 13,1997 RE: Human Performance Program Plan.
Line 1,082: Line 1,082:
: 67.      ACRS letter to EDO dated December 13,1996, RE: ACRS Review of Generic l~                        Letters, Bulletins, and information Rsquests issued on an Expedited Bases.
: 67.      ACRS letter to EDO dated December 13,1996, RE: ACRS Review of Generic l~                        Letters, Bulletins, and information Rsquests issued on an Expedited Bases.
: 68.      EDO Response dated April 11,1997, to ACRS letter RE: Review by the ACRS of Generic Letters, Bulletins, and information Requests issued on an Expedited Basis.
: 68.      EDO Response dated April 11,1997, to ACRS letter RE: Review by the ACRS of Generic Letters, Bulletins, and information Requests issued on an Expedited Basis.
: 69.      ACRS letter dated November 22,1996, RE: NRC Programs for Risk-Based Analysis of Reactor Operating Experience.
: 69.      ACRS {{letter dated|date=November 22, 1996|text=letter dated November 22,1996}}, RE: NRC Programs for Risk-Based Analysis of Reactor Operating Experience.
: 70.      EDO Response dated December 19,1996, RE: NRC Programs for Risk-Based Analysis of Reactor Operating Experience.                                          j
: 70.      EDO Response dated December 19,1996, RE: NRC Programs for Risk-Based Analysis of Reactor Operating Experience.                                          j
: 71.      ACRS Report dated March 17,1997, RE: Proposed Standard Review Plan Sections and Regulatory Guides for Risk-Informed, Performance-Based Regulation.
: 71.      ACRS Report dated March 17,1997, RE: Proposed Standard Review Plan Sections and Regulatory Guides for Risk-Informed, Performance-Based Regulation.

Latest revision as of 05:12, 21 March 2021

Summary of 444th ACRS Meeting in Rockville,Md on 970903-05 Re Appropriate Action Items Listed in Attached Agenda.W/Fr Notice,Meeting Schedule & Outline,List of Attendees & List of Documents Provided to Committee
ML20217A638
Person / Time
Issue date: 11/06/1997
From:
Advisory Committee on Reactor Safeguards
To:
Advisory Committee on Reactor Safeguards
References
ACRS-3073, NUDOCS 9803250144
Download: ML20217A638 (73)


Text

__

, 2 Date issued: 11/6/97

@ Date s,igned: 11/14/97

  • a V 2ps-se 73 TABLE OF CONTENTS MINUTES OF THE 444TH ACRS MEETING SEPTEMBER 3-5, 1997 EREA I. Chairman's Report (Open) . . . .......... 1 II. Staff Action Plan to Improve the Senior Manmaement Meetina Process. SECY-97-072 (Open) . . 2 III. Draft Regulatorv Guide DG-1069; Fire Protection Procram for Permanently Shutdown and Decommissionina Nuclear Plants (Open) . . . . ... 4 IV. Proposed Generic Letter and Regulatorv Guide Associated With Steam Generator Intecrity Open) . . 6 V. Reoortino Reliability and Availability Information for Risk-Sienificant Systems and Equipment (Open) . . . . . .......... 8 VI. NRC Procrams for Rick-Based Analysis of Reactor Operating Experience and Snecial Studies (Open) . . 10 VII. Site-Specific Safety Goals (Open) . . . . . . . . 11 VIII. Use of Uncertainty Versus Point Values in the PRA-Related Decisionmakina Process (Open) . . . . . 12 IX. Meetino with the NRC Executive Director for Qpgrations (Open) . . . . . . . .......... 14 X. BWR Pressure vessel Shell Weld Insoections . . . . 19 f I

XI. Subcommittee Report (Open) . . .......... 20 XII. Subcommittee Renort . . . . . . .......... 21 R Sol XIII. Proposed Rule on Shutdown and Fuel Storage Pool Operations (Open) . . . . .......... 22 q

E( (f (/ Lls-9903250144 971106 h II PDR ACRS 3073 POR

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  • t XIV. Improper Control Rod Movement Durino Shutdown at Zion Unit 1. and Nonconservative Onerations Durino Isolation of Recirculation Pumn Seal Leak at Clinton (Open) . 26 XV. Executive Session (Open) . . . . . . . . . . . . . 30 A. Reports, Letters, and Memoranda REPORTS Staff Action Plan to Imorove the Senior Manacement Meeting Process (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated September 10, 1997.)

Procosed Rulemakino for Shutdown and Fuel Storace Pool Operations at heclear Power Plants (Report to Shirley Ann Jackson, Chairman, NRC, from R. L.

Seale, Chairman, ACRS, dated September 10, 1997.)

Reportino Reliability and Availability Information for Risk-Sionificant Systems and Ecuinment (Report to Shirley Ann Jackson, Chairman, NRC, from R. L.

Seale, Chairman, ACRS, dated September 11, 1997.)

Pronosed Generic Letter and Draft Reculatorv Guide DG-1074 Concernino Steam Generator Tube Integrity (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated September 15, 1997.)

  • Site-to-Site Variation in Risk-Based Reculatorv Ac-centance Criteria for Plant-Specific ADplication of Safety Goals (Report to Shirley Ann Jackson, Chair-man, NRC, from R. L. Seale, Chairman, ACRS, dated September 19, 1997.)

LETTERS

  • Drnft Regulatorv Guide DG-1069. Fire Protection Procram for Permanently Shutdown and Decommission-ino Nuclear Power Plants (Letter to L. Joseph 11

, s , ) g . ,, ,1 Callan, Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated September 10, .997) e Boilina Water Reactor Pressure Vessel Shell Wald Tnanection Recommandationn (B1MVIP- 05 ) (Letter to L. Joseph Callan, Executive Director for Opera-tions, NRC, from R. L. Seale, Chairman, ACRS, dated September 10, 1997)

MEMORANDA

  • Proposed Revision- to Reaulatorv Guide 5.62,

" Reporting of Safeauards Events" (Memorandum to L.

Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated September 9, 1997)

  • Pronomad Revision to Reculatorv Guide 8.7, "In-structione for Recordina and Renortina Occunational Radiation Ernosure Data" (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated September 9, 1997)
  • Proposed Final Generic Letter "Amaurance of Suffi-cient Net Positive Suction Head for Emergency Core Coolina and Containment Heat Removal Pumns" (Memo- I randum to L. Joseph Callan, Executive Director for I Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated September 9, 1997) )
  • ACRS Letter on the Senior Manacement Meetina Pro-cess, Sentember 11, 1997 (Memorandum to NRC Commissioners from John T. Larkins, Executive Director, ACRS, dated September 11, 1997)
  • Proposed Generic Letter, "T,ahoratory Testing of Nuclear-Grade Activated charcoal" (Memorandum to L.

Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated September 11, 1997) iii 1

]

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1 B. Reconciliation of ACRS Comments and Recommen-dations C. Report on the Meeting of the Planning and Proce-dures Subcommittee Held on August 27, 1997 (Open)

D. Future Meeting Agenda iv j

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APPENDICES I. Federal Register Notice II. M3eting Schedule and Outline III. Attendees IV.-Future Agenda and Subcommittee Activities V. List of Documents Provided to the Committee 9

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j 'S Date 1ssued: 11/6/97 j}sm Date signed: 11/14/97 dYg{:k MINUTES OF THE FOUR HUNDRED FORTY-FOURTH ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SEPTEMBER 3-5, 1997 ROCKVILLE, MARYLAND The 444th meeting of the Advisory Committee on Reactor Safeguards was held at Conference Room 2B3, Two White Flint North Building, Rockville, Maryland, on September 3-5, 1997. The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached agenda. A portion of the meeting was closed to discuss information of a personal nature, the release of which would constitute a clearly unwarranted invasion of personal The rest of the meeting was open to public attendance.

privacy.

There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.

A transcript of selected portions of the meeting was kept and is

.available in the NRC Public Document Room at the Gelman Building, 2120 L Street, N.W., Washington, D.C. [ Copies of the transcript are available for purchase from Neal R. Gross and Co., Inc., 1323 Rhode Island Avenue, N.W., Washington, D.C. 20005.]

ATTENDEES ACRS Members: Dr. Robert L. Seale (Chairman), Dr. Dana A. Powers (Vice-Chairman), Dr. George Apostolakis, Mr. John Barton, Dr. Mario H. Fontana, Dr. Thomas S. Kress, Dr. Don W. Miller, Dr. William J.

Shack and Mr. Robert E. Uhrig. [For a list of other attendees, see Appendix III.]

I. CHAIRMAN'S REPORT (Open)

[ Note: Dr. John T. Larkins was the Designated Federal Official for this portion of the meeting.)

Dr. Robert L. Seale, Committee Chairman, convened the meeting at 8:30 a.m. and reviewed the schedule for the meeting. He announced that Barbara Wade would be retiring on October 3, 1997, and that her considerable contributions to the Committee would be greatly missed.

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444th ACRS Meeting 2

. September 3-5, 1997 II. STAFF ACTION PLAN TO IMPROVE THE SENIOR MANAMRMENT MRETING PROPRRE. EECY-97-072 (Open)

[ Note: Mr. _ Paul A. Boehnert was the Designated Federal Official for this portion of the meeting.] -

Mr. Barton, Chairman of the Plant Operations Subcommittee, introduced the cognizant NRC staff represenmtatives present.

He noted that, as a result of the August 28, 1997 meeting of the Combined Subcommittees on this topic, a series of ques-tions were posed for staff response at this time. Mr.-Barton also said that the staff was asked to provide a status report on its efforts to perform an integrated review of; the NRC assessment process for operating plants.

Mr. Michael Johnson, Office of Nuclear Reactor Regulation (NRR), provided a status report on NRR's plans to perform an integrated review of the NRC plant assessment process. He discussed the central elements of the current assessment process: Systematic Assessment of Licensee Performance, the Senior Management Meeting (SMM), the Plant Performance Review, and the Plant Issues Matrix. Dr. Powers asked why the current process missed the problems seen at the Millstone plants. Mr.

Richard Barrett, Office for Analysis and Evaluation of Operating Data (AEOD), stated that, while problems were known to exist, there were no clear criteria available as to which type of regulatory action should be taken in this situation.

The staff noted that an integrated Review Plan is under development, partly in response to several Commission Staff Requirements Memoranda (SRM). The Plan will focus on ensuring that the assessment process emphasizes early identification of declining licensee performance and an open dialogue of assessment results with the industry and public. Efforts will be taken to minimize both the issuance of conflicting messages on plant performance and excessive administrative requirements to implement the assessment process, i

)

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444th ACRS Meeting 3 September 3-5, 1997 Dr. Apostolakis stated that the decisionmaking process used for plant assessment should reflect use of a risk-informed approach. Dr. Powers questioned the staff regarding the development of a specific list of requirements that will be addressed by the Review Plan. The staff indicated that they have not developed such requirements and they need to consider this point.

The staff is scheduled to develop the Review Plan by June 1998 for the Commission's consideration. The Plan is scheduled to be implemented in December 1998.

Mr. Barrett discussed improvements planned to the information base of the SMM. He discussed the performance assessment information, the SMM information flow, and the components of the performance Template. During discussion of these issues, Drs. Seale, Kreas and Apostolakis suggested that AEOD obtain information from the Institute of Nuclear Power Operations (INPO) and the International Atomic Energy Agency on what attributes contribute to a plant that is considered a " good performer." Dr. Powers also observed that the nuclear industry deserves praise for the extensive sharing of informa-tion that has become the norm. He expressed the Pope that such information sharing would not become a casualty of rate competition.

Comments and questions posed during the August 28 Combined Subcommittee Meeting were discussed by Mr. Barrett. He noted that the comments included suggestions that AEOD develop a model basis for its Template and an examination of a sample of significant plant events to determine if prior performance foreshadowed these events. AEOD agreed with these sugges-tions. Mr. Barrett acknowledged that the Subcommittee was also uncomfortable with NRC's use of economic performance indicators.

Specific questions posed by the Subcommittee and Mr. Barrett's responses (in parentheses) were:

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O 444th ACRS Meeting 4 September 3-5, 1997 How will the revised SMM process focus on organizational culture and management competency? (The staff will infer the effectiveness of the organization.)

How do indicators assess the timeliness of corrective action programs? (This issue will be addressed via the Template development activities.)

How is the staff assuring that new performance standards are " objective?" (The staff will not be using subjective information to develop performance standards.)

Will the new standards reduce reliance on event-driven assessments? (Yes, the staff will evaluate plant-performance-related data through use of the Template.)

What is being done about consistency among NRC assessment processes? (This is being evaluated via the integrated review process.)

The staff is scheduled to brief the Commission on September 19, 1997 on this matter. Draft reports will be made available for ACRS review in the Fall of 1997, and a Commission Paper is due by the end of 1997.

Conclusion The Committee issued a report to Chairman Jackson, dated September 10, 1997, on this matter.

III. DRAFT REGULATORY GUIDE DG-1069; FIRE PROTECTION PROGRAM FOR PERMANENTLY SHUTDOWN AND DECOMMISSIONING NUCTMR PLANTS (Open)

[ Note: Mr. Amarjit Singh was the Designated Federal Official for this portion of the meeting.]

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  • 444th ACRS Meeting 5 September 3-5, 1997 Introduction Dr. Powers, Chairman of the Fire Protection Subcommittee, stated that the purpose of this session was to discuss the proposed Draft Regulatory Guide on the fire protection program for permanently shutdown and decommissioning nuclear plants.

On July 29, 1996, the NRC amended its regulations on the decommissioning of nuclear power reactors by amending Part 50,

" Domestic Licensing of Production and Utilization Facilities,"

of Title 10 of the Code of Federal Regulations (CFR). These changes included in the amendment to 10 CFR 50.48, " Fire Protection," which added paragraph 50.48(f). Paragraph 50.4 8 (f) refers to licensees that have submitted the necessary certifications required by the amended 10 CFR 50.82, "Termina-tion of License." Paragraph 50.48(f) requires that the licensee of a permanently shut down nuclear power plant maintain a fire protection program to address the potential for fires that could result in the release or spread of radioactive materials. This proposed draft regulatory guide is to provide guidance to licensees for maintaining fire protection programs for nuclear plants that are permanently shut down and defueled and are in the process of being decommissioned. Such guidance has not heretofore been available.

The staff stated that a licensee may develop a performance-based fire protection program to meet the requirements of 10 CFR 50.4 8 (f) . The performance goals and measures established by the licensee should be based on established industry standards and practices and should provide reasonable assur-ance that the fire objectives of 10 CFR 50.48 will be met.

Conclusion The Committee issued a letter to the Executive Director for Operations, dated September 10, 1997, on this matter. j i

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444th ACRS Meeting 6 1

I September 3-5, 1997 i

IV. PROPOSED GENERIC LETTER AND REGULATORY GUIDE ASSOCIATED WITH STEAM GENERATOR INTEGRITY (Open)

[ Note: Mr. Noel Dudley was the Designated Federal Official for this portion of the meeting.]

Introduction Dr. Seale, Acting Chairman of the Materials and Metallurgy subcommittee, noted that there is a long history related to the proposed generic letter and draft regulatory guide regarding steam generator tube integrity. He noted that during a recent meeting of the Subcommittees on Materials and Metallurgy and on Severe Accidents, the staff announced a revised approach to ensuring steam generator tube integrity.

This alleviated the need for rulemaking. He stated that there are still several unresolved issues, such as what constitutes a viable regulatory policy with regard to steam generator tube integrity and the relative rigidity of proposed technical specifications.

Staff Presentation Mr. Jack Strosnider, NRR, noted that during the June 12, 1997 ACRS full Committee meeting, the staff presentcd the results of the risk assessment and regulatory analysis, which the staff had developed in support of the proposed rulemaking regarding steam generator tube integrity. He explained that subsequently, in accordance with the directions in a June 30, 1997 SRM, the staff prepared a proposed generic letter that:

a requested licensees to modify technical specifications to address inspection requirements, condition monitoring, and operational assessment; e provided licensees the option for proposing new repair criteria; and

o 444th ACRS Meeting 7 September 3-5, 1997

  • - provided model technical specifications. I Mr. Strosnider provided details -of the model technical specifications, which are perfomance-based and focused on the condition of steam generator tubing at the end of the operat-ing cycle. He outlined Draft Regulatory Guide DG-1074, " Steam Generator Tube Integrity," that provides guidance on quantification of inspection methods, perfomance of condition monitoring, and operation assessments. He noted that' the staff plans to brief the ACRS on the resolution of a Differing Professional Opinion and the development of a Draft Regulatory Guide regarding risk guidance: DG-1073, "An Approach to Plant-Specific, Risk-Informed Decision Making: Induced Steam Generator Tube Rupture," when these documents are completed.

Mr. Timothy. Reed, NRR, provided the following responses to issues that had been raised at previous ACRS meetings:

  • the use of a safety factor of 3 is correct, e exceeding the operationel leakage performance criteria will not automatically result in enforcement actions,
  • defense-in-depth is an attribute of a compliance-based approach and is not a component of - a regulatory risk approach, and
  • sufficient guidance exists in the steam generator tube Draft Regulatory Guide for licensees to develop processes to meet the performance criteria.

Mr. Reed stated that many of the issues identified by the ACRS were associated with risk assessments and would be addressed in DG-1073.

The ACRS Members and the staff discussed the relationships among the different documents associated with steam generator integrity, the schedule for completing DG-1073, ind'astry

444th ACRS Meeting 8 September 3-5, 1997 4

involvement in developing the requirements and guidelines, the adequacy of the proposed regulatory structure, and the flexibility provided by the model technical specifications.

Nuclear Enercrv Institute Presentation Mr. Clive Callaway, Nuclear Energy Institute (NEI), stated that he could not constructively contribute to the discussion since neither the proposed generic letter nor DG-1074 were available for industry review. He described the guideline documents that the Electric Power Research Institute (EPRI),

NEI, and the PWR Owners Groups have developed in the areas of nondestructive examination, condition monitoring, and operat-ing experience. He suggested that, based on the industry guidelines, the staff could monitor licensee programs using tube integrity performance criteria. Mr. Callaway stated that there is a need for NEI to meet with the staff to better understand its approach and schedule, and to identify differ-ences between the NRC regulatory guides and the industry guidance documents.

The ACRS Members and Mr. Callaway discussed the existing industry guidelines and the exchange of information between the staff and NEI. Dr. Seale encouraged NEI, as a major stakeholder, to take full advantage of the public comment period for the proposed generic letter.

Conclusion The ACRS issued a report to Chairman Jackson, dated September 15, 1997, on this matter.

V. REPORTING RELIABILITY AND AVAILABILITY INFORMATION FOR RISK-SIGNIFICANT SYSTEMS AND EOUIPMENT (Open)

[ Note: Mr. Michael T. Markley was the Designated Federal Official for this portion of the meeting.)

. i

, 444th ACRS Meeting 9 September 3-5, 1997 Intreduction Dr. Apostolakis, Chairman of the ACRS Subcommittee on Proba-bilistic Risk Assessment (PRA) introduced the topic to the Committee. He noted that the joint Subcommittees on PRA, Plant Operations, and Fire Protection had met with representa-tives of the NRC staff and of the industry to discuss these matters on August 28, 1997. He stated that AEOD had provided documents related to the NRC control of proprietary materials.

He added that these documents govern the public availability of information provided to the staff by INPO.

NRC Staff Presentation Mr. Steve Mays, AEOD, provided a brief presentation to the Committee. He' summarized the agreements between the NRC and INPO for sharing reliability and availability information provided by INPO. member utilities. He also discussed the regulatory requirements for controlling proprietary informa-tion and limits for sharing this information with the public.

Significant points made during the discussion include:

  • 10 CFR Section 2.790 (a) (4) provides for mandatory disclosure of agency documents, with some exceptions, including confidential commercial or proprietary materi-als.

The NRC has established written agreements with INPO that acknowledge the proprietary nature of plant reliability and availability data.

Plant-specific INPO data can be released to the public if the information is the basis for a regulatory decision such as an individual licensing action.

Generic analyses of INPO data can be released where individual plants are not identified.

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444th ACRS Meeting 10 i September 3-5, 1997 _l

  • - Equipment Performance and Information Exchange will be controlled under the same format and requirements as the

-earlier Nuclear Plant Reliability Data System (NPRDS).

Dr. Powers reiterated his concerns from the August 28, 1997 joint Subcommittee meeting, regarding the availability of " raw 1 INPO data" for public scrutiny and evaluation. Drs. Seale and l Fontana also questioned the practice of controlling this information when it is the basis for governmental action or

' decisions.- Dr. Kress questioned the prudence of the staff entering into agreements where the availability of information l to the public is constrained. The staff stated that the i agreement with INPO was essentially the same as that which l controlled access to NPRDS data. Mr. Mays also stated that  !

these agreements exist to protect the financial interests of l sponsoring organizations such as those for thermal-hydraulic computer code development.

l At the conclusion of the meeting, Dr. Apostolakis stated that the Committee expects to prepare a report to'the Commission regarding this matter. ,

conclusion The Committee provided a report to Chairman Jackson dated September 11, 1997, on this matter.

VI. NRC PROGRAMS FOR RISK-BASED ANALYSIS OF REACTOR OPERATING EXPERIENCE AND SPECIAL STUDIES (Open)

(Note: Mr. Amarjit Singh was the Designated Federal Official for this portion of the meeting.)

Introduction Dr. Apostolakis, Chairman of the Probabilistic Risk Assessment Subcommittee, stated that the purpose of this session was to hear a briefing by representatives of the NRC staff regarding

444th ACRS Meeting 11 September 3-5, 1997 the NRC programs for risk-based analysis of reactor operating experience as well as the results of several special studies performed by the staff, including those related to auxiliary feedwater, Westinghouse reactor protection systems, loss of offsite power, initiating events, reactor core injection cooling, high pressure core injection, and fire events.

NRC Staff Presentation The staff briefed the Committee regarding the accident sequence precursor (ASP) program. The ASP program was originally a research project developed by RES. The responsi-bilities were later transferred to AEOD. This program is now a specific task action in the PRA Implementation Plan where AEOD conducts and manages the ASP program. During the August 29, 1997 Subcommittee meeting, representatives from RES discussed their efforts to support AEOD through ASP model development.

Conclusion This session was information only and no Committee action was required.

VII. SITE-SPECIFIC SAFETY GOATA (Open)

(Note: Mr. Noel Dudley was the Designated Federal Official for this portion of the meeting.)

Dr. Thomas Kress, Chairman of the Safety, Technology, and Criteria subcommittee, led a discussion concerning the development of site-specific large, early release frequency (LERF) criteria for nuclear plants. He explained that Mr.

Richard Sherry, Jt CRS Senior Fellow, had helped to develop a methodology for calculating site-specific LERF criteria from the individual early fatality quantitative health objective (QHO). The methodology was sent out to three national laboratories for peer review.

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I 444th ACRS Meeting 12 September 3-5, 1997 Dr. Kress explained that the site-to-site variability of the site-specific LERF values, compared to the uncertainties associated with the methodology, were small enough so that site-specific LERF criteria were not necessary. He noted that I based on the methodology results, total early fatality risk or societal risk, which is strongly effected by the population density near nuclear plants, should be considered as a metric l for making regulatory decisions. I i

Dr. Kress read a draft ACRS report on this subject. Dr. l Powers raised the issue of the uncertainties associated with the radionuclide dispersion model used in the methodology.

The ACRS Members and the staff discussed the relationship between population density and societal risk, the historical debates regarding societal risk, the difficulty in redefining a QHO, and the consequences of having plants operating outside a newly defined safety goal. l Conclusion The ACRS issued a report to Chairman Jackson, dated September 19, 1997, on this matter.

VIII.USE OF UNCERTAINTY VERSUS POINT VALUES IN THE PRA-RELATED DECISIONMAKING PROCESS (Open)

[ Note: Mr. Michael T. Markley was the Designated Federal Official for this portion of the meeting.)

Dr. Apostolakis, Chairman of the ACRS Subcommittee on PRA, provided a report of the meeting of the joint Subcommittees on PRA, Plant Operations, and Fire Protection regarding the use of uncertainty versus point values in the PRA-related decisionmaking process. He noted that joint Subcommittees had met with representatives of the NRC staff and of the industry on August 28-29, 1997, to discuss these matters. He stated that the Commission had approved the Committee and staff's

. 444th ACRS Meeting 13 September 3-5, 1997 request for an extension in responding to the SRM dated May 27, 1997.

Dr. Apostolakis noted that the staff had conducted a workshop to solicit industry and public feedback on the draft Standard Review Plan (SRP) and associated guidance for risk-informed, performance-based regulation. He summarized a few points raised by participants at the workshop including completeness of PRAs and implications for risk-informed changes to the current licensing basis, types of uncertainty and approaches for addressing them, concern that acceptance criteria would be implemented as limits, and concern over the implications for plants that already exceed the Commission's Safety Goals. He also noted that Dr. Harry Martz of Los Alamos National Laboratory had given a presentation on the consideration of uncertainty in the application of Safety Goals.

NRC Staff Presentation Mr. Thomas King, Office of Nuclear Regulatory Research (RES),

led the discussions for the NRC staff. Messrs. Mark Cunningham, RES, .nd Gareth Parry, NRR, provided supporting discussion. The staff summarized key considerations in the treatment of uncertainty, guidelines for assessing complete-ness, and the schedule for completion of the SRP and associ-ated guidance for risk-informed, performance-based regulation.

Significant points made during the discussion include:

The state of the art in risk analysis has uncertainty (completeness, model, and parameter), variability in analysis assumptions, and quantifiable and unquantifiable uncertainty.

Acceptance guidelines and definitions of change have inherent difficulties in numerical values and decision guidelines, direction and magnitude of change, and bundling of proposed changes.

i', .,',.

. 444th ACRS Meeting.

14 September 3-5, 1997 The staff philosophy for addressing uncertainty is presented in Draft Regulatory Guide DG-1061 (General Guidance) including the use of mean values, use of sensitivity ' analysis and qualitative arguments, and qualitative or bounding analysis to address completeness.

  • Meetings with the'ACRS Subcommittee on PRA are scheduled for October 21-22 and November 13-14, 1997, to address potential policy issues and the proposed final.SRP and associated guidance.

Dr. Apostolakis expressed the view that the Commission may have considered the. issue of completeness and uncertainty in establishing its Safety Goals.- Drs. Kress and Powers stated that there was still a need for assessment of the risks for other modes of operation. (e .g. , low-power and shutdown operations). Dr. Apostolakis stated that requiring quantifi-cation of uncertainty analysis may unnecessarily limit risk-informed initiatives. He suggested that trore consideration be given to unquantifiable benefits of proposed changes.

Ennelusion The Committee expects to provide a report to the Commission l during a future meeting.

IX. MFFTING WITH THE NRC FYFCUTIVE DIRECTOR FOR OPERATIONE (Open)

[ Note: Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.)

Dr. Seale welcomed Mr. L. Joseph Callan, Executive Director for Operations, and his staff. Dr. Seale stated ACRS appreci-ation for the willingness and cooperation of Mr. Callan and his staff to discuss with the Committee items of mutual interest.

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, 444th ACRS Meeting 15 September 3-5, 1997 Mr. Callan noted that he received a memorandum from the ACRS Executive Director indicating six items of interest to the  ;

committee. The Committee, however, chose to discuss only three items. These were the Senior Management Meeting (SMM) process, NRC oversight of Department of Energy (DOE) nuclear facilities, and NRC Research Program activities.

Mr. Callan stated that the SMM is an important part of l

the NRC process for evaluating licansee performance.

Decisions regarding the appropriate level of regulatory attention to plants exhibiting performance problems are made at the semiannual SMM. Throughout the process, the information regarding the performance of the plants is provided primarily by the regions and NRR. The AEOD ;

staff also provides independent insights based on the NRC l Performance Indicators. The Office of Enforcement (OE) and the Office of Investigations (OI) provide additional insights. The SMM process is described in detail in SECY-96-093 anti in Management Directives 8.13 and 8.14.

In an SRM dcted June 28, 1996, the Commission directed the staff to assess the SMM process and evaluate the 1 development of indicators that can provide a basis for l judging whether a plant should be placed on or deleted j from the watch list. In response to this SRM, a study was perfomed with the assistance of a contractor (Arthur Andersen) and a report was issued on December 30, 1996.

The Arthur Andersen report addressed two major areas:

the SMM information base and the SMM process. The first ;

area involves the inputs to the SMM decision process, including performance indicators and the criteria used by NRC senior managers. The second area involves the roles of SMM participants, the method of reaching consensus, the presentation of information, and the documentation of meeting results. Based on the Andersen study and the staff's independent evaluation, a set of nine recommenda-tions and actions were proposed. These are:

A 444th ACRS Meeting 16 September 3-5, 1997 Assess leading indicators, such as management and operational effectiveness on an ongoing basis.-

Re-engineer assessment.information to better sup-port the SMM decisionmaking process.

  • Shift from use of subjective to objective factors.

Restrict format and volume of information provided to senior managers for the SMM.

Initiate continued ' effort to improve information access through automation.

  • Use new economic indicators (to gauge licensees' economic stress) outside the SMM process.
  • Attain a better balance in SMM participant's roles in the decision process and include consideration of consensus decisionmaking techniques.
  • Present information in a rigorous and structured manner.
  • Develop a better process for completing the public record of SMM meetings.

Mr. Callan noted that the Arthur Andersen report is only a starting effort and the staff is continuing to work on SMM implementation. AEOD issued a memorandum that provides guidance on the implementation of the above recommendation, including a corresponding milestone schedule. By June 1998, the majority of the recommenda-tions are scheduled to be implemented.

  • Mr. Hugh Thompson,Jr. , Deputy Executive Director for Regulatory Programs, described the status of NRC over -

sight of DOE nuclear facilities. He noted that the NRC

444th ACRS Meeting 17 September 3-5, 1997 position regarding the regulation of nuclear safety, safeguards, security, and radiation protection at DOE facilities requires careful consideration. Among the issues to be considered are the magnitude of the poten-tial workload, the types of DOE facilities and opera-tions, NRC's current statutorf authority, overlapping regulatory authority with other Federal agencies, and NRC's funding requirements and the mechanism that could 1

be employed to recover the cost of its oversight.

]

Direction Setting Issue #2 addressed options for NRC's position on the regulation of DOE facilities. In March 1997, after considering public comments, as well as the December 1996 DOE decision to seek transfer of oversight to NRC, the Commission endorsed seeking the transfer to NRC of responsibility for the regulatory oversight of l

certain DOE nuclear facilities, contingent on adequate l funding, staffing, and a clear delineation of the authority NRC would exercise over these facilities. In addition, the Commission directed the staff to convene a high-level NRC Task Force to identify, in conjunction with DOE, the policy and regulatory issues needing analysis and resolution. In June 1997, both DOE Secretary Pefia and NRC Chairman Jackson agreed to pursue J NRC regulation of DOE nuclear facilities, on a pilot program basis.

  • In FY 1998, the Task Force plans to conduct a pilot program of simulated regulation at three facilities. These are Lawrence Berkeley National Laboratory, the Spent Fuel Dry Transfer and Storage Facility (Idaho), and the Radiochemical Engineering Development Center (Tennessee). In FY 1999, additional pilot facilities of a different nature will be added.
  • Mr. Ashok Thadani, Deputy Executive Director for Regula-tory Effectiveness, stated that one of the general objectives of the NRC Strategic Plan is to " supply research needed to regulate effectively." The supporting strategy for accomplishing this objective states that the

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444th ACRS Meeting- 18 September 3-5, 1997 NRC "will maintain a core research capability required

' now and in the future to support NRC's regulatory mission." The Commission decision on Direction Setting Issue #22' (Research) RES to develor rit'eria for deter-RES has developed mining core research capabilitie.

l these criteria, which are embedded in a methodology for  !

assessing where core research capabilities will be needed in the foreseeable future, and to determine their size and composition.

In an SRM dated March 28, 1997, the Commission'Anstructed j the staff to develop and submit-to-the Commission a plan for implementing the Commiesion's-decision that "...the preparation and coordination of rulemaking should move from RES to the Program Offices, and that most confirma-tory research activities now in the Program Offices should move to RES." In addition, the Commission noted in the SRM that there are many-key questions raised in DSI #22, and the staff should provide an integrated set of recommendations for Commission consideration. In order to respond to the SRM, the Directors of NRR, NMSS, AEOD, and RES have formed an ad hoc steering group. The steering group noted that, of the.202 issues identified by the Strategic Assessment and Rebaselining Steering Committee, the issue of the future role, scope, and organization of NRC's generic issues program remains an open issue, the resolution of which also affects the role and function of RES. Hence, it would seem appropriate to pursue resolution of these issues simultaneously.

Mr. Thadani noted that the agency needs to stay abreast of national 'and international nuclear safety develop-L ments, emerging technologies, and design concepts.

l In conclusion, Dr. Seale thanked Messrs. ' Callan, Thompson, and Thadani, and the NRC staff regarding the information provided to the Committee, and invited Mr. Callan and his staff to a l-

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4 444th'ACRS Meeting 19 September 3-5, 1997 semi-annual discussion . with the ACRS of items of mutual interest. I Conclusion This briefing was for information only. No Committee action-was required.

X. BWR PRESSURE VESSEL SHELL WELD INSPECTIONS (Open)

-[ Note: Mr. Amarjit Singh was the designated Federal Official for this portion of the meeting.)

Introduction Dr. seale, Acting Chairman of the Materials and Metallurgy and Severe Accidents Subcommittees, stated that the purpose of this session was to hear presentations by representatives of the NRC staff regarding the interim Safety Evaluation Report on a report, "BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations (BWRVIP-05)," submitted by on the Boiling Water Reactor Vessel and Internals Project (BWRVIP). -

NRC Staff Presentatlon The NRC staff provided the background and the results of its independent assessment of the BWRVIP-05 report, The staff performed an independent assessment of the BWRVIP-05 report. i The staff concluded that the BWRVIP-05 report did not include l a risk-informed analysis, nor did it adequately consider beyond design basis transients, which appear to dominate the estimated frequency of BWR reactor vessel failures. On the basis of the independent assessment of the BWRVIP-05 report, the. staff also concluded that any significant reactor pressure vessel vulnerability to failure would not be expected until relatively late in the life of the reactor vessel, when higher j levels of embrittlement are reached. Based on this conclu-  !

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e 444th ACRS Meeting 20 l September 3-5, 1997 i

sion, the staff will consider plant-specific requests, if technically justified, to delay inspections of the circumfer-ential welds for up to 40 months. I i

The staff is expected to complete its review of the BWRVIP-05 report and issue a final Safety Evaluation Report by December 1997, concluJion l

The Committee issued a letter to the Executive Director for Operations, dated September 10, 1997, on this matter.

XI. SUBCOMMITTEE REPORT (Open)

[Notm : Mr. Paul A. Boehnert was the' Designated Federal Official for this portion of the meeting.)

i The Chairman of the Thermal-Hydraulic Phenomena Subcommittes '

provided a report on the meeting that was held to continue its review of the Westinghouse Test and Analysis Program being conducted in support of the AP600 design certification. The Subcommittee reviewed the modifications made to the H NOTRUMP small-break loss-of-coolant accident (LOCA) code to support its use for AP600 evaluation model analyses. The Subcommittee concluded that Westinghouse needs to address the following issues:

  • A number of specific items need to be examined to ensure that the code meets the requirements stipulated in Appendix K to 10 CFR 50.46.

The documentation associated with the AP600 version of NOTRUMP requires improvement.

  • A stronger tie needs to be demonstrated between the Phenomena Identification and Ranking Table and verifica-

444th ACRS Meeting 21 September 3-5, 1997 tion and validation testing to show that the tests have appropriately covered the ranges of important phenomena.

A proposed fix to the code (taking an initial arbitrary

  • penalty" in the in-containment refueling water storage tank. level) to compensate for poor performance on drain flow from the pressurizer needs to be justified with regard to its meeting the intent of Appendix K.

Conclusion The Subcommittee will hold a follow-on meeting to address these issues.

XII. SUBCOMMITTEE REPORT (Open)

[ Note: Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.)

Dr. Kress, Chairman of the Regulatory Policies and Practices subcommittee, provided a report to the full Committee regard-ing a meeting on August 27, 1997. The purpose of the Subcom-mittee meeting was to explore the subject of defense-in-depth.

The Subcommittee discussed the formal definition of defense-in-depth, how it has been used historically and if there is a need for a new policy statement, and if necessary and suffi-ciency limits could be established.

Dr. Kress summarized the main points of the Subcommittee discussion as follows:

  • Defense-in-depth (DID) historically has been defined mostly by example and is generally unclear.
  • DID is a philosophy and not a requirement.
  • DID is structurally scattered throughout the body of the regulations, and thus, the necessary and sufficiency

'. . . ~

'444th ACRS Meeting 22 September 3-5, 1997 (N&S) limits are already set by the existing regulations.

PRA is a tool that measures the effectiveness of imple-mentation of the DID philosophy.

A new policy statement on DID is probably not needed.

If a new policy statement is to be developed, it should be part of a new policy on PRA and Safety Goals.

DID can be defined in terms of three " levels:" preven-tion, mitigation, and emergency response.

  • It seems impractical to establish N&S limits for levels 1 and 3, because the requirements for these are perfor-mance in nature.

It would be useful to develop technical risk-based NES lim 3ts for level 2 requirements. The most important need is to establish the appropriate regulatory balance between core damage frequency and conditional containment failure probability.

Conclusion The Subcommittee concluded that the experience that will be gained in the near future by implementing the defense-in-depth portions of the risk-informed decision process on requested changes to the licenses basis should be very useful. It might be reasonable to await this experience before developing any policy statement. i XIII. PROPOSED RULE ON SHUTDOWN AND FUEL STORAGE POOL OPERATIONS (open)

[ Note: Dr. M. El-Zeftawy was the Designated Federal Official for this portion of the meeting.]

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f '444th ACRS Meeting 23

. September- 3-5,-1997 Introduction Dr. Powers stated that the NRC is proposing to amend its regulations regarding.the Shutdown Rule. On April 18,1997, the ' ACRS; issued its report to the Commission expressing concerns regarding the existing understanding of risk during shutdown operations. The staff sees a need for an enforceable rule to ensure safety during shutdown operations.

NRC Staff Presentation Mr. Eric Weiss, NRR, stated that the objective of the propci..ad rule is t.o establish a clear regulatory framework for ensuring that cold shutdown, refueling outages, and fuel pool opera-tions continue to be conducted in a safe manner. To accom-plish the objective for fuel pool operations, licensees would be required to document factors important to safety in their Final Safety Analysis Report and incorporate these factors'in fuel pool operating procedures.

The proposed rule consists of three parts: Shutdown Opera-tions, Fire Protection,-and Spent Fuel Pool Operations. The proposed rule also allows licensees to enhance' operational flexibility by . the use of PRA methods as a complement to traditionel analyses.

The Shutdown Operation section of the proposed rule was structured with the objectives of reducing the frequency of events that can lead to loss of the decay heat removal function, assuring that mitigative equipment is available for those events that do occur, providing a measure of performance

~

through monitoring of parameters that represent necessary I safety functions, and facilitating inspection and enforcement l activities. These goals are to be achieved through'a combina-tion of procedural, monitoring, and mitigation capability requirements.

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444th ACRS Meeting 24 September 3-5, 1997 The Fire Protection section is intended to extend the fire protection provisions already provided during power operation to shutdown operation. The proposed rule would require licensees to implement measures to minimize the frequency of fires during shutdown operations. It would also require that the decay heat removal function be maintained free of fire damage, or that fire damage be limited by promptly detecting.

controlling, and extinguishing fires that do occur.

)

l The Fuel Storage Pool Operhtions section is intended to establish clearly defined regulatory controls for current  ;

operational practices in spent fuel pool operations and to facilitate inspection and enforcement.

In support of the shutdown operation requirements of 10 CFR Section 50.67, conforming changes would have to be made to other regulations. The most significant of these are:

Adding the structures, systems, and components necessary for compliance with the shutdown operation requirements of Section 50.67 to the Maintenance Rule (Section 50.65) and the License Renewal Rule (10 CFR Part 54),

  • Providing for notification and submitting reports to the NRC in accordance with Section 50.72 and Section 50.73, of any event that results in actuation of the mitigation j equipment, and
  • Adding a definition of shutdown operations to Section 50.2 which makes it clear that normal operation includes shutdown operation.

I Nuclear Enerev Institute Presentation j Mr. Anthony Pietrangelo stated that the Nuclear Energy ,

Industry (NEI) is concerned that the proposed rule will not I raise the current level of safety, yet will conservatively l cost the industry an estimated $200 million to implement. In

1 444th ACRS Meeting 25 September 3-5, 1997 addition, the proposed rule overlooks the regulatory oversight and safety benefits provided by 10 CFR 50.65, the Maintenance Rule.- The implementation burden associated with the proposed rule would only increase economic pressure and divert licensee attention from outage . management to regulatory compliance without an attendant benefit in safety.

Mr. Pietrangelo noted that since 1991, when the industry developed and implemented' NUMARC 91-06, Guidelines for Industry Actions to Assecs Shutdown Management, there has been a significant decrease in both the frequency and severity of events during shutdown. In addition to the substantial improvement in safety, there has been an equally impressive productivity improvement resulting in a 40% reduction in the median refueling outage duration. Therefore, it is in the industry's self interest to continue the practices that have been successful in achieving safer, shorter outages.

The industry believes that the Maintenance Rule and other existing regulations adequately address NRC concerns over the potential for licensees to withdraw from current practice, and that a separate shutdown rule is unnecessary. In addition, the industry and the NRC have worked for several years to develop a practical model to demonstrate risk-informed, performance-based regulation through the maintenance rule. As such, the maintenance rule provides a regulatory framework that encompasses both shutdown and power operations. The potential for achieving a more consistent and cohesive risk-informed, performance-based regulatory framework cannot be realized if overlapping and inconsistent requirements are added that impose regulatory burden without improving safety..

conclusion The Committee issued a report to Chairman Jackson, dated September 10,'1997, on this matter. It recommended that the proposed rule not be issued for public comment. The Committee recommended that the NRC satff explore other methods and work L

I 444th ACRS Meeting 26 l

September 3-5, 1997 j I

with the industry to find ways to achieve enforceability without penalizing industry practices. The Committee also recommended that fuel storage pool operatione and fire protection requirements for shutdown operations not be included in the proposed rule.

XIV. IMPROPER CONTROL ROD MOVEMENT DURING SHUTDOWN AT ZION UNIT 1. j AND NONCONSERVATIVE OPERATIONS DURING ISOLATION OF RECIRCULA-TION PUMP SEAL TRAK AT CLINTON (Open)

[ Note: Mr. Michael T. Markley was the Designated Federal Official for this portion of the meeting.)

Introduction Mr. Barton, Chairman of the ACRS Subcommittee on Plant Operations, introduced the topic to the Committee. He briefly summarized the operating events at Zion Unit 1 and Clinton.

He noted that the ACRS had requested the staff presentation to focus on the human and organizational performance issues. He also noted that licensee representatives from each utility were in attendance and would be willing to answer questions as ,

needed. Mr. Barton introduced cognizant NRC representatives I in attendance.

NRC Staff Presentation Mr. Robert Dennig, NRR, introduced the presenters from the NRC staff. Mr. Marc Dapas, Region III, presented the findings of-the Augmented Inspection Team (AIT) for the event at Zion. l Mr. Geoffrey Wright, Region III, presented the findings of the Special Inspection Team (SIT) at Clinton. Mr. Greg Galletti, NRR, discussed the human factors aspects of the Clinton and ,

Zion events. Mr. Jay Persensky, RES, provided supporting l discussion regarding human performance modeling and methodolo-  :

gies.

444th ACRS Meeting 27 September 3-5, 1997 Mr. Dapas reviewed the sequence of events for the Zion incident and summarized the findings of the AIT assessment.

He noted that on February 21, 1997, a control room operator improperly inserted control rods too far into the core, taking the reactor suberitical. The operator continuously withdrew rods to restart the reactor without direction from shift management. At the onset of this incident, the plant was approaching the end of allowed outage time (AOT) for a containment spray pump (CS) pump that was out of service (inoperable with maintenance ongoing) and operators had commenced a controlled shutdown of the unit. Operating shift l management w.s focused on restoring the CS pump and there were l approximately 39 people in the control room envelope including senior station management. Significant points made during the discussion include:

i Operations supervision did ne maintain a proper level of  ;

oversight to ensure that operating shift activities were l conducted in a controlled manner.

Direction was not provided to operations supervision to correct command and control deficiencies, communications problems, lack of teamwork, and control room distrac-tions. l Actions of the nuclear station operator reflected a lack of understanding of reactor physics and of proper control rod manipulations for approach to criticality.

  • The significance of the event was not communicated to management in a timely manner. Operations management returning of the operating shift to licensed duties reflected a lack of appreciation for the significance of the event.
  • The operating shift was newly formed and the licensed operator requalification program was deficient in

444th ACRS Meeting 28

' September 3-5, 1997 assessing shift capability in conducting the shut-down/ prompt restart evolution.

  • The - Zion event did not pose a risk to the health and safety v2 the public. However, the event revealed significant w fety insights regarding human performance.

Mr. Wright reviewed the sequence of events for the Clinton incident'and summarized the findings of.the SIT assessment. ,

He noted that on September 5, 1996,. operators at Clinton were attempting to place the unit in single-loop operation by isolating the . "B" reactor recirculation pump (RRP-B)- At the time, the licensee believed the seal package for RRP-B was the source of unidentified reactor coolant leakage. Ineffective-planning resulted in operators taking nonconservative action to isolate the seal flow to RRP-B. The seal failed and the leak rate increased from about 5 gpm-to approximately 38 gpm.

Significant points made during the discussion include:

  • Inappropriate operator action resulted in the failure of the "B" reactor recirculation pump seal and extended shutdown of the unit.

Management failed to put economic expectations in proper i perspective with safety. Emphasis had been placed on  !

maintaining power production in attaining single loop operations.

Operator actions reflected an attitude of procedural ,

compliance through intent rather than adherence to actions defined in procedures.

i Mr. Galletti discussed the human factors analysis framework, noted the significant findings of the inspection teams, and reviewed the actions relative to each of the findings.

Significant points made during the discussion include:

s .

j 444th ACRS Meeting 29 September 3-5, 1997 The Clinton incident did not have the same command and control issues observed at Zion. However, management tolerance for. procedural deviations and a lack of sensitivity to removing performance barriers.was evident at Clinton but not at~ Zion. Also, Clinton'had longer-term problems with effectiveness of past corrective actions.

  • - Both incidents provide valuable input for the NRC's Human Performance and Human Reliability Implementation Plan -

including information for the HFIS database and Senior Management Meeting (SMM) .

  • The staff plans to use the ATHEANA model to assess human performance.

Dr. Apostolakis questioned how proper control room communica-tions are defined. The staff stated that the protocol is an announcement of planned actions by the reactor operator, a repeat-back acknowledgement by the cognizant shift supervisor or senior reactor operator that the message is understood, and.

an announcement by the operator when the subject' action is being taken.

Mr.. Barton stated that fundamental operator knowledge of reactivity changes is an industry-wide problem, He added that most operator training programs are symptom-based and that this training focuses on transients rathur than reactivity control. Mr. Barton also questioned operating shift composi-tion at Zion. In particular, he questioned -why the subject operating crew had not worked together before or trained as a working unit. The licensee stated that this crew was formed as a sixth operating shif t (from five existing shifts) to support outage activities.

Dr. Seale questioned when the human performance assessment--

would move more toward PRA. The staff stated that the ATHEANA

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444th ACRS Meeting 30 l September 3-5, 1997 model would be used and the Seabrook Nuclear Plant was participating as a pilot plant.

l l

At the conclusion of the meeting, Mr. Barton thanked the i participants and stated that he was not recommending the l Committee to prepare a letter or report regarding these matters.

l Conclusion This briefing was for information only. No Committee action was required. i XV. EXECUTIVE SESSION (Open) l

[ Note: Dr. John T. Larkins was the Designated Federal j official for this portion of the meeting.) ,

I A. Reports, Letters and Memoranda  !

l l

REPORTS l e Staff Action Plan to Imorove the Senior Manacement Meetino Process (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated September 10, 1997.)

l l

  • Proposed Rulemakinc for Shutdown and Fuel Storace I Pool Operations at Nuclear Power Plants (Report to j Shirley Ann Jackson, Chairman, NRC, from R. L.

Seale, Chairman, ACRS, dated September 10, 1997.) l l

l

  • Reportino Reliability and Availability Information

]

for Risk-Sionificant Systems and Eculpment (Report to Shirley Ann Jackson, Chairman, NRC, from R. L.

Seale, Chairman, ACRS, dated September 11, 1997.) l i

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)

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444th ACRS Meeting 31 September 3-5, 1997 Pronosed Generic Letter and Draft Reculatorv Guide DG-1074 Concernine Steam Generator Tube Intecrity j (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated September 15, 1997.)

e Site-to-Site Variation in Risk-Based Reculatorv Ac-centance Criteria for Plant-Snecific Apolication of l Safety Goals (Report to Shirley Ann Jackson, Chair- l man, NRC, from R. L. Seale, Chairman, ACRS, dated September 19, 1997.)

LETTERS

  • Draft Reculatorv Guide DG-1069. Fire Protection Procram for Permanently Shutdown and Decommission-

)

ine Nuclear Power Plants (Letter to L. Joseph '

Callan, Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated September 10, 1997)

Boiline Water Reactor Pressure Vessel Shell Weld Insnection Recommendations (BWRVIP-05) (Letter to L. Joseph Callan, Executive Director for Opera-tions, NRC, from R. L. Seale, Chairman, ACRS, dated September 10, 1997)

MEMORANDA

  • Proposed Revision to Reculatorv Guide 5.62.

"Reportino of Safecuards Events" (Memorandum to L.

Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated September 9, 1997) e Proposed Revision to Reculatorv Guide 8.7. "In-structions for Recordinc and Reportino Occunational Radiation Exoosure Data" (Memorandum to L. Joseph

444th ACRS Meeting 32 September 3-5, 1997 Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated September 9, 1997)

  • Pronosed Final Generic Letter " Assurance of Suffi-cient Net Positive Suction Head for Emeroency Core Cooline and Containment Heat Removal Pumns" (Memo-randum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive  !

Director, ACRS, dated September 9, 1997)

  • ACRS Letter on the Senior Management Meetino Pro-cess. Sentember 11. 1997 (Memorandum to NRC commissioners from John T. Larkins, Executive Director, ACRS, dated September 11, 1997)
  • Proposed Generic Letter.
  • Laboratory Testino of Nuclear-Grade Activated Charcoal" (Memorandum to L.

Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated Sept. ember 11, 1997)

B. Reconciliation of ACRS Comments and Recommendations (Note: Mr. Sam Duraiswamy was the Designated Federal Official for this portion of the meeting.]

  • The Committee discussed the response from the Executive Director for Operations (EDO) dated July 15, 1997, responding to ACRS comments and recommendations included in the ACRS report dated June 20, 1997, concerning the proposed regulatory approach associated with steam generator integrity.

The Committee decided that it was satisfied with the EDO's response.

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444th ACRS Meeting 33 September 3-5, 1997

  • The Committee discussed the response from the EDO dated July 15, 1997, responding to ACRS comments and recommen-dations included in the ACRS report dated June 17, 1997, concerning inclusion of a containment spray system in the AP600 design. '

The Committee decided that it was satisfied with the EDO's response.

  • The Committee discussed the response from the.EDO dated July 16, 1997, responding to ACRS comments and recommen-dations included in the ACRS report dated June 18, 1997, concerning the. proposed Generic Letter: " Potential for Degradation of the Emergency Core Cooling System and the_ l Containment Spray System after a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficien-cies and Foreign Material in the Containment."

The Committee decided that it was satisfied with the EDO's response.

  • The Committee discussed the response from the EDO dated August 1, 1997, responding to ACRS comments and recommen-dations included in the ACRS report dated July 14, 1997, concerning the proposed final revisions to 10 CFR Part'  ;

26, Fitness-for-Duty Program Requirements.

The Committee decided that it was satisfied with the l EDO's response.

  • The Committee discussed the response from the EDO dated .

August 6, 1997, responding to ACRS comments and recommen .

dations_ included in the ACRS report dated July 14, 1997, concerning the proposed Regulatory Guide and. Standard Review Plan chapter for risk-informed, performance-based inservice inspection.

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I 444th ACRS Meeting 34 September 3-5, 1997 l i

The - Committee decided that it was satisfied with the EDO's response.

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The Committee discussed the response from the EDO dated  !

August 15, 1997, responding to ACRS comments and recom-mendations included in the ACRS report dated June 17, 1997, concerning the proposed final Generic Letter,

" Assurance of Sufficient Net Positive Suction Head for  !

Emergency Core Cooling and Containment Heat Removal l

Pumps."  !

The Committee authorized the Executive Director, ACRS, to issue a memorandum, dated September 9, 1997, requesting j further discussion of this issue during a futste meeting ,

and accepting the staff's offer to brief the Committee on  !

the NRC power reactor inspection program. '

C. Report on the Meeting of the Planning and Procedures Subcommittee (Open)

The Committee heard a report from Dr. Seale on the Plan-ning and Procedures Subcommittee meeting held on August 27, 1997. The following items were discussed:

1) EXECUTIVE DIRECTOR MFFTING WITH NRC CHAIRMAN (Open)

The Executive Director briefed the Committee on his meeting with Chairman Jackson on August 21, 1997.

The recent budget cut and schedule for ACRS re-sponse to the Commission on uncertainty vs. point values were some of the topics discussed. The Chairman has agreed to extend the due date for ACRS response associated with uncertainty vs. point values until January 1998.

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444th ACRS Meeting 35 September 3-5, 1997

2) REPLY TO COMMISSION ON ACRS SUBCOMMITTEE STRUCTURE (Open)

Revision 5 of the reply to the Commission's Staff Requirements Memorandum concerning ACRS Subcommit-tee structure was submitted for approval.

RECOMMENDATION The Subcommittee recommended that the draft letter be distributed at the 444th meeting, so that Mem-bers could review and comment on it before the end ,

of the meeting. The Full Committee approved the letter as drafted.

3) NPP ASSIGNMENTS TO MEMBERS (Open)

A list of plants will be provided to each Member to identify the plants he wishes to be assignad.

Plants not chosen will be randomly assigned to Members by the ACRS Chairman.

l RECOMMENDATION  :

The Subcommittee recommended that a statement be drafted to explain to Members about what they need to do on those plants that were assigned to them.

The Subcommittee also recommended that Members identify the plants they wish to have assigned to them.

4) ACRS RETREAT (Open)

The Subcommittee has agreed to recommend for Com-mittee approval potential dates, location, and an agenda for a fall retreat. A memorandum from Dr.

Powers on this subject was distributed.

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l 444th ACRS Meeting 36 l September 3-5, 1997 l I

RECOMMENDATION l

The Subcommittee recommended that the Committee look at the significant issues facing the Agency and issues included in the NRR Director's bimonthly I reports and develop an approach to review and l comment on these issues in a timely manner. The Subcommittee also recommended that the revised ACRS Bylaws be discussed. Dates for the retreat were discussed at the 444th meeting. The Full Committee 1 agreed on the dates of January 30-31, 1998, for the I retreat, assuming that a Quadripartite Meeting l would not be held the previous week in Japan.

1

5) TOPICS OF JOINT INTERFAT (Open) 1 A memorandum from Dr. Powers proposed that Dr.

Seale appoint Dr. Apostolakis to work with Dr. John Garrick (ACNW) to identify topics of joint inter-est. A memorandum from Dr. Apostolakis proposed a slightly different method for identifying these I topics.

RECOMMENDATION The Subcommittee recommended that Dr. Seale meet with Dr. Garrick to identify topics of joint inter-est and suggest how each topic should be addressed by the two Committees. '

6) LICENSE RENEWAL AND OTMER TOPICS OF INTERPRT (Open)

A memorandum from Dr. Fontana discusses license renewal activities and a memorandum from Dr. Powers raises license renewal as one of several topics of interest to the ACRS. Both memoranda suggest ways for the ACRS to review activities associated with license renewal.

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444th ACRS Meeting 37 l September 3-5, 1997 l

l RECOMMENDATION 1

The Subcommittee recommended that the ACRS staff l provide the Committee with the current staff sched-

{

ule for developing regulatory guidance associated )

with license renewal.

7) LETTER ON RUTPMAKING ACTIVITIES (Open)

During the June 1997 meeting, the Committee re- l viewed the staff proposal for not developing a l severe accident rulemaking for future plants.

Although the Committee agreed with the staff pro-l posal, it did not issue a letter documenting its l position. When the staff submitted a SECY paper to !

the Commission on this matter, some of the Commis-l sioners' Technical Assistants called the ACRS '

Office to find out the Committee position regarding

this matter. It is recommended that, in the fu-ture, the Committee document its position on a specific rulemaking activity in a letter to the EDO or in a report to the Commission.

RECOMMENDATION The Subcommittee recommended that t'ne ACRS document all its decisions by letter to the Commission or the EDO.

8) DRAFT PERFORMANCE REVIEW REPORT (Open)

Several ACRS members commented en the draft Perfor-mance Report distributed after the July 9-11, 1997 meeting. The staff will continue to track the performance measures and will prepare an operating i i plan in anticipation of a requirement to produce a plan and a performance report in the next fiscal year.

l l

l l

l

i

. ' '

  • f.

l

' l 444th ACRS Meeting 38  ;

September 3-5, 1997  !

I

9) REVISIONS TO ACRS BYLAWS (Open) j The ACRS Bylaws are being revised to reflect ,

changes in Committee practice and to incorporate  !

new Commission procedures. A draft of the revised j Bylaws will be made available to the Committee l subsequent to review by this subcommittee. I RECOMMENDATION The subcommittee recommended that a draft copy of the revised Bylaws be given to its members before the October 2-4, 1997 meeting so that it can be given to the ' Full Committee at that meeting and discussed at the Fall Retreat. .

10) ACRS REVIEW OF NRC REREARCH ACTIVITIES (Open)  !

New procedures are being developed to implement an expanded review of the NRC research program. This review will be performed in two phases: Phase I will be a programmatic review, similar to past Reports to Congress, and will be prepared by- the end of this calendar Year. Phase II will be a I detailed review of the appropriateness, timeliness,  !

and quality, and management of the specific re-  ;

search programs to be carried out in FY 98. A l draft memorandum describing this process in more j detail was submitted.

RECOMMENDATION The Subcommittee recommended that comments on this draft memorandum be given to Senior Fellow Gus Cronenberg by September 5, 1997.

_ , ,f, ,

444th ACRS Meeting 39 September 3-5, 1997

11) SITE-SPECIFIC APPLTCATION OF SAFETY GOATR (Open)

The paper on a simplified methodology using expo-sure index data to calculate a site-specific risk and population distribution has been forwarded to BNL, ORNL, and SNL for external review. Comments from ORNL and SNL were received and comments from BNL and SNL were expected to arrive prior to the ACRS full Committee meeting in September 1997.

During that meeting, the Committee reviewed and factored these comments into its report to the Commission on this subject. ,,

RECOMMENDATION The Subcommittee recommended that Senior Fellow Rick Sherry assess the comments and discuss with the Full Committee those comments that he feels would have an impact on the conclusions or the Committee approach discussed in the paper.

12) FUTURE FOREIGN AND DOMESTIC TRAVEL (Open)

Dr. Powers notified the Subcommittee of a CSNI meeting on Nuclear Aerosols on June 16-18, 1998, in Cologne, Germany. The Subcommittee also has de-ferred from the July meeting a decision on atten-dance at a Halden meeting in Norway in March 1998.

Dr. Apostolakis requested approval to attend a Specialists' Meeting in Chattanooga, TN on Oct. 14-17, 1997 on Human Performance in Operational Events.

There is also a travel request from Dana Powers to attend the International Symposium on Upgrading the Fire Safety of Operating Nuclear Power plants, to i

e 444th ACRS Meeting 40 September 3-5, 1997 be held November 15 to November 22, 1997 in Vienna Austria.

RECOMMENDATION The Subcommittee recommended that the full Commit-tee approve the following international travel requests: Dr. Kress to attend the CSNI meeting in Germany, Dr. Miller to attend the Halden meeting in Norway, and Dr. Powers to attend the Fire Safety meeting in Austria. The Subcommittee also recom-mends thar. travel be approved for Dr. Apostolakis to attend the Specialists' Meeting in Tennessee.

13) STATUS OF APPOINTMENT OF MEMBERS (Open)

We expect to have the final approval on the ap-pointment of Bob Uhrig by the end of this week, and we are planning on sending a slate of candidates to the Commission for a replacement for. Ivan Catton during September.

14) Member Issues There were no Member issues.

D. Future Meetine Acenda Appendix IV wummarizes the proposed items endorsed by the Committee for the 445th ACRS Meeting, October 2-3, 1997.

The 444th ACRS meeting was adjourned at 4:28 p.m. on Friday, September 5, 1997.

7 w

,,- , [.

=

EavironsmentalIsapacts of the Proposed Flading of No S3==88t~-t Impact ~

Acdon

, the action plan to improve the Based upon the foregoing Senior Management Meeting The Commissiou has completed its environmental assessment, the .

evaluauon of the proposed action and Process.

concludes that there is no signiacant Commission concludes that the 9:45 am-f 0:45 omaDmA Regulatory environmentalimpact if the proposed amendments wiu not have a Guide DG-1069: Fin Pmtection amendments are signiacant effect on the quality of the ProgmmforPermanentlyShutdown will be made to thesited.No changes human environment. Accordingly, the and Decommissioning Nuclear bases, or procedures of the two units atand Heensing t'ammialon has determined Plants (Openbh not toConunittee wul the McGuire Nuclear Station. Other than Pr*Pam an environmentalimpact h*er Presentations by and hold statement for the proposed ons with rue ta of the name change, no other changes will amendments. g be made to the facility operating .

licenses, including the T=chnical For further details with respec..t to the Regulatory Guife DG-1069 on the SpeciScations, PmPosed action, ese thelimnsee's fire Protection p for request for the amendments dated June Permanentl shut ownand The change wiu not increase the 12,1997, which is available for public probability or consequences of inspection at the Commluion's Public 'C0"$"JO 8#~ i g nuclear plants.

accidents, no changes are being made in Document Room, b Gelman Building, g,, ,'f,g,,,Q[Po8 the types of any emuents that may be 2120 L Street, NW., Washington DC, and CuMeAn d hd released offsite, and there is no Steam signi$ cant increase in the snowable at the local public document room Generate 'ty(OSTh located at the J. Murrey Atkins Library, Commithe erpre nudou individual or cumulative occupational . Univenity of North Carolina at by and hold discussions with radiation arposure. Accordingly, the Charlotte,9201 University City representatives of the NRC staff Commission concludes that there am no Boulevard, Charlotte, North Carolina. mgarding b propomd Guede significant radiological environmental Letter and Regulatory Guide impacts ==ananted with the proposed Dated at Rockville, Maryland, this ath day of August toer. asociated with steam generator --

action. Integdty.

For the Nuclear Regulatory -'"

With regard to potential Naec R. la, 2JO pm-2.00 p.m.: Reporting nonradiological impacts, the proposed ReliabilityandAvailability Actfng Duvetor, hefect D(redorate D-#,

action does not affect nonradiological InformationforRisk.Significant plant efnuents and has no other DMsJon ofReactorFrelseteJD. Ofpas of. S NuclearReactorW- JrtemsandEqui ment (Open)--

environmentalimpact. Accordingly,the Ine Committee hear Commiulon concludes that there are no IFR Doc. 87-21680 Filed 8-14-47; 8:45 aml presentations by and hold saases ones 'reew signincant nonradiological discussions with representatives of environmental impacts amociated wit theWRC staff, as needed, the proposed action. 2 NN

  • the voluntary approach proposed th d for ility ,

Since e m I o l co uded Addowy Commmee h ~

there is no measuroble environmental Weguarde; Meethe Nou" - t. -.

impact associated with the proposed 2. cop.m 2:30p.nuNRCPmgramsfor action, any alternatives with equal or In accordance with the of rusk. Rased Analysis ofReactor poster environmental impact need not - Sections 29 and 182b. of a tomic Opem tie evaluated. As an alternative to the Energy Act (42 U.S.C. 2039,2232b), the Advisory Committee on Reactor Studler( Exp)erience n -N Committeeand Special,

. Proposed action, the sta5 considered will hear presentations by and hold denial of the proposed action. Denial of Safeguards will hold a meeting on discussions with representatives of the application would result in no - Septembe/ 3-5,1997,in Conference Room T-2B3,11545 Rockville Pike, the NRC staH, as naaded,regarding change in current environmental the NRC Programs for Risk Based impacts. N environmentalimpacts of Rockvine, Maryland.b date of this Analysis of Reactor Operating I

the proposed action and the alternative meeting was previously pubushed in Experience as well as the results of action are similar. the Federal Register on Thursdsy, January 23,1997 (52 FR 3539). several special studiseperformed

\

by the staH. Including tnose related Afternatin Use ofResomtes Wedneeday, September 3,1997 '

This action does notinvolve the use g, 'pto%cdon of any resources not pavlously s:30 am4:45 a.m.: Remarts j '. bythe ACRS Chairman systems, loss of offsite power, .

considered in the Final Environmental )- - initiating events, reactor core The ACRS Chairman will Statement related to the McGuire opening remarks regarding conduct injection cooling, high pressure -

Nuclear Station, core inloction, and fire events.

ngencies andPomons Contacted- of the meeting regarding and comment items of cunent interest. brie 0y 2:30 p.m.-130 pm.r Site.Speeffic I Goals During this session, the Committee ,, . hear esentations pr(Open)-b Committee In accordance with its stated policy, will discuss priorities for by and hold '

l on August 1,1997, the staff consulted '

discussions with an ACRS Senior with the North Carolina State of5cial, preparation of ACRS reporta. FeDow, and representatives of the  !

, Richard Frys of the Division of 8:45 a.m.-9:45 a.m.:StaffAction Plan to ,

Improve the SeniorManagement NRC staH, as needed,regarding the '

Protection, North Carolina Department Meeting Procese, SECY-97-072 use of site-speciBc safety goals.

of Environment Health, and Natural 3:45 p.m.-d:25 p.m.:Use of Uncertainty Resources, regar, ding the environmental (Open)--N Committee will beer-presentations by and hold Versus Point Valuesin the PRA-impact of the proposed amendments. Related Decisionmaking Process discussions with representatives of N State official had n'o comments. (Open)--N Committee wiu hear a the NRC sta!!, as noeded, regarding report by the Chairman of the s

M'

... . _ : n FedeM Register / Vol. 62, N;.'158 t' Friday, August'15.1997 f Notices

. P-- - ,

43759 PtobabillsdeRisk Assessment the NRC staff regarding the Subcommittee regarding matters Committee will complete its pp"- rule on shutdown and discussed at tb August 28-29, ' discussion cf proposed ACRS ruel storage pool operations. nports on matters considered 1997 Subcommittee meeting. 2:00p.me7.00 p.m.:PrepamUon of

  • pne7.90 pm.:PnpamUon of during this meeting.

ACRSReports (Open)-The ACRSReports ( n)-The Committee will discuss proposed 2:45 pa.-430pm.:Stmtegic Planning Committee will (Open)-The Committee wiu proposed ACRS reports on matters considered ACRS reports on matten considered during this meeting continue its discussion ofitems of during this meeting. signiBeant importance to NRC, Pdday, Septemhef s,2997 including rebase of the Thursday, September 4,2097 ***I"**** 0** *' N ' ***'

820 a.m:-825 an.:Openin Remarks ###

SJO ca425 an.: Opening Remarks bythe ACRS Chairman LOpen)~

by the ACRS Chairman The ACRS chah== will

}- .

&" Rf*'h*""* j The ACRS Chairman will make opening remarks regarding the discuss matters related to the opening remarks regarding conduct condyct of the meeting conduct of rammttree medvities and of the meeting _ specific issues that were not Contml 835 ane20d5 a.ni.: with the 825 ca.-20J0 ca.:Improhtdown at

.RodMovementDudng cmpleted during pavious NRCEnecutive Director Zion Unit 2, andNanconsonative ***'i"C** ** 'A"* **0 *'*II*blII'7 0I OpemUons(Open)-Th Committee Operations Duringleolation of infamedon permit, will meet with b NRC Executive Recirculation Pump Sea 1Isakof Procedures for the maduct of and Director for Operations regarding Cunton (Open)-The Committee . Partidpation in ACRS meetings wars items of mutualinterset, including wiU haar pmentations by and hold published in the Federal Register on the following: discussions with representatives of. October 1,1996 (61 FR 51310). In o Human Performance Program Plan the NRC staff regarding im roper acemdance with these procedures, oral I o Research control rod movement d , or written statements may be presented l o Oversightof E fadlities/ shutdo en at Zion Unit 1 . by members of the public and )

Direction Setting lesue r2 monconservative operations during representatives of the nuclearindustry.

. o Developmentofrisk-informed isolation of recirculation puinp esal electronic recordings w!!! be permitted l regulation .

leak at the Clinton Nuclear Power only during the open portions of the o Role of ACRS ta resolving tachabal Plant, and human /orfsntvaHonal meeting, and questions may be asked differenme between NRC staff and performace issues associated with only by members of the Committee,its industry j thue incidents. consultants, and staff. Persons desiring

'9JO ca.-!!:00 ca.:BWR Fieseure 20:45 ca.-Jiro am.:Reconculation of to make oral statements should notify

, Vesse!SheU Weldinspections ACRS Comments and Mt. Sam Duralswamy, Chief. Nuclear (Open)-The Committee will hear a Recoewe Suons(Open)-b Reactors Branch, at least five days report by the Chairman of the Committe wiU discuss responses before the inuting,if possible, so that

, Materials and Metallurgy from the NRC Executive Director for appropriate arrangements can be made Subcommittee regarding issues )

Operations to comments and to allow the nar===ary time during the discussed / raised at the August 28, recommendations included in. meeting for adth statementa. Use of still, 1997 Subcommittee meeting recent ACRS reports, including motion picture, and television cameras nasociated with BWR pressure those on the Proposed Regulatory during this meeting may be limited to vessel shell weld inspections. Approach associated with Stum selected portions of the meeting as

!!JD0 a.m.-2 225 cm.: Subcommittee GeneratorIntegrity, Inclusion of a determined by the Phai man Report (Open)-The Committee will Containment Spny Systamin the Inforation regarding the time to be set hear a report by the Chairman of the AP600 design, and propoeed Final aside for this purpose may be obtained =

Thermal-Hydraulic Phenomena Revisions to to CFR Part 26,- by contacting the Chief of the Nuclear Sea-ittee regarding the items Fitnes-For Duty Program Roactors Brsnch prior to the meeting. In discussed during the July 29-30, Requirements. view of the possibility that the schedule 1997 Subcommittee meeting. ~ 22::00 a.m.-!!JO o.m.: Report of the for ACRS meetings may be adjusted by l 22as c.n>22J0 am.: Subcommittee Planning andProceduise the Chnirman as necessary to facilitate Report (Open)-The Committee will Subcommittee (Open/ Closed)-b the conduct of the meeting, persons haar a report by the Chairman of the Committee wiu hear a report of the pl'nnInf to attend should check with #

tory Pelicies and Practices Plening and Procedures the Chief of the Nuclear Reactors Branch SLa=='ttee regarding matters Subcommittee on matters related to if such roscheduling would result in discussed during the August 27, the conduct of ACRS businesa, ma}orinconvenience.

1997 Subcommittee meeting. qualifications of candidates In accordance with Subsection 10(d) 22J0 a.m.-22:00 Noon: Artum ACRS nominated for appointment to the P.I.92-463,I have determined that it is Activities (Open)-The Committee ACRS, and orgah(sational and necessary to close portions of this will discuss the recommendations. personnelmattere solating to the meeting noted above to discuss matters of the Planntng and Procedures '

ACRS. that relate solely to the internal Sub committee regarding items (Note: A portion of this asulos as be Per*onnel rul*8 and Practices of this proposed for consideration by the closed to discuss organizational and Advisory enmmittee per 5 U.S.C.

full Committee during future pareonnel matters that relate solely to the 552b(c)(2), and to discuss information meetings. tatsmal personnel rules and practices of this the release of which would constitute a

  • "10 pm.-2:45 p.m.: Proposed Rule on Advisory Committee, and information the clearly unwarranted invasion of Shutdown andFuelStoroLee Poof retsase of which would constitute e clearly personal privacy per 5 U.S.C. 552b(c)(o).

Opeintions (Open)-The Committee unwansnted invssion of permal primy.! Further information regarding topics wiu hear presentations by and hold 2220 p.m.-320 pm.: Prv on of to be discussed, whether the meeting tiscussions with repmentatives of ACRS Reports (Open The has been canceHed or roscheduled, the o

y

_ _ _ _ _ _ _ _ . . . .. _..s

      • ,' . '48700 Federal Regleter / Vel. 62. Ns.158 / Friday, August 15,1997 [ Notices Chairman's ruling on requests br the Desed c Rockvills. Maryload. this 113 de7 premiums are being paid (the " premium opportunity to t oral statements of Augut, see?. ' payment year").N yield Sgure is and the time therefor,can be For the Nuclear Eggulatory Commission, reported in Pederal Reserve Statistical obtained by contacting Mr. Sean n=amon A.poseII, galeases G.13 and H.15.

Duraiswamy, Chief. Nuclear Reactors Cksf,Fseedoeno#n W Puhue Branch (telephone 301/415-7384), tha===# Asem Spench. O p ,pg ,I* w I"II between 7:30 a.m. and 4:15 p.m. EIFT. Aqbemotion Assemess" fflarof . 1,1M7, the opp le percentage of the ACRS g noom.m.s.g m e tsre ,,is. w emi ~,,-g,m-;r,ga;- =,

Y,'Se#dWorldNee %

s (RPA) amended ERISA section .

MAIN MENU."N Direct Did Acosas 4006(aX3XEXillXH) to provkle that the museber to PedWorld is (800) 308-4872 11 able is as pescent for P years PEfd000N BEldEPtTSIARAffTV on or aAerJuly 1, or 'tp.fedworld.Nos documents and CORPORATION the meeting agenda me also eveilable for .

- s. 1997, through (atleast) plan years downloading or reelewing on the interest Amoumpden for Determiedng beginning befuse January 1,2000.

laternet at http://www.asc. gov / Verteble. Rete Premiurn; interest However,under section 774(c) of the ACRSACNW.. . Assumptione for beidesasuployer Plan RFA, the lication of the ====d--*

Duned:/.esent 11, seer.

Volustions Pollowing besos WIlhdrawal is deferred certain regulated public pahaC.Boyle,-  : utility (RPU) plans for es long as six w Ad,ges,y- u , , Aemsev %BunSt%

.g- months.N applicable penantage for offles, e RPU plans will therefore reinain 80 IFR Dec. er-steet Filed 6-14 er; a4s esel ACfiole Nation ofintmet reens and t for plan years beginning before

, emme om. - "umPhas. ,

uary 1,1998. (N ruimperning

'autessurf: 'Ihis notice infonos the public the applicable pereen er " partial" of the laterest mess and - - "-- to RPU plans are in 54006.5(g)

NUCl. EAR REGULATORY be used under corten Pension'BeneSt of the psomim rates . .- ' tion.) -

00mS800N ,. Guaranty Corporation . ; '"- These For plans forwhich the appikable .

lpesentsees.es estand as easj rates and assusaptions em published percentage is se pescent, the assumed elsewhere (or are derivable from rates interest rete to be used in f-Washington Nuoleer Units 8 and s'

  • published elsewhere),but ano collected variable-rate pruniusas for premium '
Closing of 1. coal Public Document and published in this notico for the payment years beginning in August '

Room convenience of the public. Interest mies 1997 is 5.53 percent (Le., as percent of Notice is hemby given that the ",,

p Y,ff ,,, 8[1 Percent yield Sgure forJuly j """

sAfss:N interest rate for I __-- " -

&e varia mt* Pmmlusa under part g g, g y ,,, g room R) for acords to ipterest rates to be used in ' ^

the Washington Public Supply

- 4"' *'t* P m miuss pe years variable-rate pruniums for premiums '

p L System's Washington Nuclear Units a h A"E" g y* Payment years beginning between phas fw September 1996 and August 1997,h

, and 5 (WPPSS) located at the W.H. Abel g ,g Memorial Library,Montemano, ,gg,p[p fou wiedmwd &^g- # rates for July and August 1997 in the Washington, e5setive August is,1997. - -

table mSect an a plicable percentage of 1

. N W.H. Abel Memorial Libsary has 4281 ePP { to valuation dates -

as puernt and us ap ly only to non-served as the LPDR for WPPSS Units 3 g,'usen- erom*antion 00stract: . ,,,,,[lans.

RPU rates for and 5 for 23 yens. In a letter dated May Fon P s However before July 1997,which resect 2s,1997,the community librarian Haro! . Ashner, ht Geners!

.OfBos of the GeneralCounsel, en applicable tage of 80 percent, ofBelally informed the NRC that they no apply to RPU partial" RPU) plans Pension BeneSt Corposetion, longerwish to serve as the LPDR.NRC DC m4 -RPU plum has made the dadata= to ofHeially close 1200 K Street, NW., W .

the WPPSS Units 3 and 5 LPDR because 20005,203-326-4034 (302-33H179 .

none of the libmries la the vicinity og forTIT and EDL ,

the Sa , Washington alte are suppuneestastr bromeAviest - Per premium permera years to. sumes tre.

in in maintaining the docenant . .

9tnrun0 in terest collection, no locility was ever Variable. Rate Premisens- -

reas is ,

constructed on the site, and these bas- Section 400e(aX3XEX111XII)of the 8#7 been no demonstrated local public Erantoyee Retirement laceae Security 8'8"'"* " .

" E#

interest in the LPDR materials for a

  • number of years. Therafore, eSective ' " idof 1974 of the PSGC's regulation on Premdum (ERISA) and $ 4008.4(bX1) 8'"

August 15,1997, the 1XDR will be ' ' Rates (39 CPR part 4006) preemibe use Sm closed. of an assumed interest rete in M 1997-Persons now laterested in infonnation determining a single-essployer plan's to this facility or any other vanable. rete premiums. The rete is the ,,gg7

[ gy I activity may contact the NRC " applicable percentags" (described in '

j

  • Public Document Room by calling tou- the statute and the regulation) of the g ,,iggy

.auns t307 g,gy sm free 1-400-397-4209 or writing to NRC annual yield on 30 year Treasury . .My 1997 5.75

.( Public Document Roosa, Washington, DC 30555-4001.

securities for the month proceding the beginning of the plan year for which August 1997 6.83 em

. q#wg#o, UNITED STATES

/ Appendix II

]

$ o NUCLEAR REGULATORY COMMISSION

. 3  :

ADVISORY COMMITTEE ON REACTOR SAFE 2UARDS o WASHINGTON, D. C. 20666 August 8, 1997 SCHEDULE AND OUTLINE FOR DISCUSSION 444th ACRS MEETING SEPTEMBER 3-5, 1997 WEDNESDAY SEPTEMBER 3, 1997, COhrsk MCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND

1) 8:30 - 8:dhA.M. Onenino Remarks by the ACRS Chairman (Open) 1.1) Opening Statement (RLS/SD) I 1.2) Items of current interest (RLS/JTL/SD) 1.3) Priorities for preparation of ACRS reports (RLS/SD) 55 {
2) 8:45 - 9: 45 A.M. Staff Action Plan to Imorove the Senior Manacement Meetino Process, SECY-97-072

'(Open) (JJB/PAB) 2.1) Report by the Subcommittee Chairman.

2.2) Discussions with representatives of the NRC staff, as needed, '

regarding the action plan to improve the Senior Management Meeting process.

SS o

3) 9: 46 - 10:45 A.M. Draft Reaulatory Guide DG-1069; Fire l Protection Procram for Permanently

)

Shutdown and Decommissionina Nuclear Plants (Open) (DAP/AS) 3.1) Remarks by the Subcommittee Chairman.

3.2) Briefing by and discussions with representatives of the NRC staff regarding the draft '

Regulatory Guide on the fire protection program for permanently shutdown and decommissioning nuclear g plants.

10:4h-11:00A.M. *** BREAK ***

4) 11:00 - 12:b p.M.

Procosed Generic Letter and Reculatorv Guide Associated with Steam Generator Intecrity (Open) (RLS/NFD)

' 4.1) Remarks by the Subcommittee Chairman.

( & nsc ri bt S' f>o rlNns of +he meebng h l

..,t .,.-

2

( 4.2) Briefing by and discussions with ,

representatives of the NRC staff regarding the proposed Generic j

Letter and Regulatory Guide associated with steam generator integrity.

]

Representatives of the nuclear industry will participate, as appropriate.

13 s j 12:30 - 1:30 P.M. ***LUNCE***

5) 1:30-2:$[P.M. Reoortina Reliability and Availability 1 Information for Risk-Sionificant Systems and Ecuinment (Open) (GA/MTM) ,

5.1) Report by the Subcommittee <

Chairman.

5.2) Discussions with representatives of the NRC staff, as needed, regarding the voluntary approach proposed by the industry for reporting reliability and availability information for risk-significant systems and equipment.

t Representatives of the nuclear, industry will participate, as appropriate.

O c~ 2S 6)' 2: N - 2:D9 P.M. NRC Procrams for Risk-Based Analysis of Reactor Ooeratina Ernerience and Soecial Studies-(Open) (GA/AS) 6.1) Report by the Subcommittee Chairman.

6.2) Discussions with representatives of the NRC staff, as needed, ,

regarding the NRC Programs for Risk-Based Analysis of Reactor Operating Experience as well as-the results of several special studies performed by the staff, including those related to auxiliary feedwater, Westinghouse reactor protection systems, loss of offsite. power, initiating events, reactor core injection cooling, high pressure core injection, and fire events.

N t

~

3 2r 25

7) 2:M- 3:30 P.M. Site-Soecific Safety Goals (Open)

(TSK/NFD/RRS) 7.1) Remarks by the Subcommittee Chairman.

, 7.2) Briefing by and discussions with an ACRS Senior Fellow, and representatives of the NRC staff, as needed, regarding the use of site-specific safety goals.

2.5 SI 3:M - 3:45 P.M. *** BREAK ***

57 35

8) 3:46 - 4:35 P.M. Use of Uncertainty Versus Point Values in the PRA-Related Decisionmakina Process (Open) (GA/MTM)

Report by the Subcommittee Chairman regarding issues discussed / raised on the use of uncertainty versus point values in the PRA-related decisionmaking process at the August 28-29, 1997 Subcommittee meeting.

Representatives of the NRC staff will sParticipate, as appropriate.

9 l 3g , q . gg f h. -- B C ORK

9) 4 :15 -

1:29 P.M. Precaration of ACRS Recorts (Open) 56 4. / 5' Discussion of proposed ACRS reports on:

9.1) Action Plan to Improve the Senior Management Meeting Process (JJB/PAB) 9.2) Draft Regulatory Guide DG-1069, Fire Protection Program for Permanently Shutdown and Decommissioning Nuclear Plants j (DAP/AS) '

9.3) Site-Specific Safety Goals (TSK/NFD/RRS) 9.4) Proposed Generic Letter and Regulatory Guide associated with l Steam Generator Integrity (RLS/NFD) 9.5) Reporting Reliability and Availability Information for Risk-Significant Systems and Equipment (tentative) (GA/MTM)

TEURSDAY. SEPTEMBER 4, 1997. CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, ROCKVILLE, MARYLAND 3 -

10) 8:30 - 8:35 A.M. Onenina Remarks by the ACRS Chairman 4 (Open) (RLS/SD)

/

I 11) . 8:35 - 10:15 A.M. Meetino with the NRC Executive Director for Ooerations (Open) (RLS/MME) 11.1) Remarks by the ACRS Chairman.

11.2) Briefing by and discussions with the NRC Executive Director for l Operations regarding items of mutual interest, including the following:

e Human Performance Program Plan e Research Program o DOE Oversight / Direction Setting Issue #2 e NRC staff procedures for providing the ACRS with generic letters, bulletins, and other regulatory guidance issued on an expedited basis e Development of risk-informed regulation e Role of ACRS in resolving technical differences between NRC staff and industry T

[ 10:15 - 10:30 A.M. *** BREAK ***

3 5~ '

12) 10:30 - 11: M A.M. BWR Pressure Vessel Shell Weld Inscections (Open) (RLS/AS)

Report by the Subcommittee Chairman regarding issues discussed / raised at the August 26, 1997 Subcommittee meeting associated with BWR pressure vessel shell weld inspections.

Representatives of the NRC staff and nuclear industry will participate, as appropriate.

I t ' 3.T - (l '+4 A.H. - Furt6u de scottom of Ite m fwltk UR(St ff-

13) 11:09 - 11:35 A.M. Subcommittee ReDort (Open) (TSK/PAB) 44 55 Report by the Subcommittee Chairman regarding matters discussed at the July 29-30, 1997 meeting of the Thermal Hydraulic Phenomena Subcommittee.

Representatives of the NRC staff will participate, as appropriate.

3

5 g .Sr /A: 07

14) 11: N - itste A.M. Subcommittee Reoort (Open) (TSK/MME)

Report by the Subcommittee Chairman regarding matters discussed during the August 27, 1997 Regulatory Policies and Practices Subcommittee meeting associated with the defense-in-depth approach.

Representatives of the NRC staff will participate, as appropriate.

4:o4 4: 50

15) 2ms90 - 19e@0 Noon Future ACRS Activities (Open)

(RLS/JTL/SD)

Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed for consideration by the full Committee during future meetings.

67 D1 12 : M - 1:M P.M. ***LUNCE***

16) 1:he - 2: P.M. Procomed Rule on Shutdown and Fuel Storace Pool Doerations (Open) (DAP/MME) 16.1) Remarks by the Subcommittee Chairman.
16.2) Briefing by and discussions with .

representatives of the NRC staff regarding the proposed rule on shutdown and fuel storage pool operations.

Representatives of the nuclear industry j will participate, as appropriate. I 2:h[ - Side P.M. *** BREAK ***

17) 3:N M P.M. Prenaration of ACRS Recorts (Open)

(5:00-5:15 P.M. BREAK) 17.1) Action Plan to Improve the Senior Management Meeting Process See .r+4 vn is (JJB/PAB) 17.2) Draft Regulatory Guide DG-1069, g go -/, ! y 7 g H.

  • Fire Protection Program for Rie"**"#3 MM "*""*"*"*1Y 'h"'d "" *"d Decommissioning Nuclear Plants (DAP/AS) 17.3) Site-Specific Safety Goals (TSK/NFD/RRS) 17.4) Proposed Generic Letter and Regulatory Guide associated with Steam Generator Integrity 1 (RLS/NFD)

I I

1 i

6 1

(

17.5) Proposed Rule on Shutdown and Fuel Storage Pool Operations (DAP/MME) 17.6) Reporting Reliability and Availability Information for Risk-Significant Systems and Equipment (tentative) (GA/MTM)

FRIDAY, SEPTEMBER 5, 1997, CONFERENCE ROOM 2B3, TWO WHITE FLINT NORTH, Rouav1LLE, MARYLAND

18) 8:30 - 8:35 A.M. Qpgpino Remarks by the ACRS Chairman (Open) (RLS/SD) 27
19) 8:35 - 10:30 A.M. Imoroner Control Rod Movement Durino Shutdown at Zion Unit 1, and Nonconservative ODerations Durino Isolation of Recirculation Pumo Seal Leak at Clinton (Open) (JJB/MTM) 19.1) Remarks by the Subcommittee Chairman.

19.2) Briefing by and discussions with representatives of the NRC staff regarding improper control rod movement during shutdown at Zion Unit 1, nonconservative operations during isolation of recirculation pump seal leak at the Clinton Nuclear Power Plant, and human / organizational performance issues associated with these incidents.

Representatives of the nuclear industry will participate, as appropriate.

\

10thh-10:45A.M. *** BREAK ***

20) 10:45 - 11:00 A.M. Reconciliation of ACRS Comments and Recommendations (Open) (RLS, et.al./

SD, et.al.)

Discussion of the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports.

21) 11:00 - 11:30 A.M. Recort of the Plannino and Procedures

/ Dissi - / : o o F M. Subcommittee (Open/ Closed) (RLS/JTL) cteub Report of the Planning and Procedures o c c / FA A /2: +o - / J N' Subcommittee on matters related to g

f) w H e e ben M n 1: @

the conduct of ACRS business, l

A

- 1

,. j 7 l qualifications of candidates nominated for appointment to the ACRS, and organizational and personnel matters relating to the ACRS.

[ Note: A portion of this session may be closed to discuss organizational and personnel matters that-relate solely to the internal personnel rules and practices of this Advisory Committee, and information the release of which would constitute a clearly unwarranted invasion of personal privacy.]

45 11:30 - 12:34 P.M. *** LUNCH ***

22) M- P.M. Prenaration of ACRS Ren s (Open)

Continue discussion of proposed ACRS reports on:

22.1) Action Plan to Improve the Senior Management Meeting Proceso (JJB/PAB) 22.2) Draft Regulatory Guide DG-1069, Fire Protection Program for Permanently Shutdown and

' Decommissioning Nuclear Plants (DAP/AS) 22.3) Site-Specific Safety Goals (TSK/NFD/RRS) 22.4) Proposed Generic Letter and Regulatory Guide associated with Steam Generator Integrity (RLS/NFD) 22.5) Proposed Rule on Shutdown and Fuel Storage Pool Operations (DAP/MME) 22.6) Reporting Reliability and }

Availability Information for )

Risk-Significant Syste'ms and Equipment (tentative) (GA/MTM) 3:30 - 3:45 P.M. *** BREAK ***

23) 3:45 - 4: P.M. Stratecic Plann'ina (Open) ( S/JTL) i Dis asion of it s of signi cant impor ance to NRC, including rebase ning of the ommittee a ivities for FY 1 8.

1 l

l

8

. 24) 4:30 - 4 45 P.M. Mikcellaneous\gpen) (RL JTL/SD)

Dis ssion of mi cellaneou matters rela d to the co duct of C mittee activi ies, and ma ers/ spec ic issues that we e not compl ed durin ~ previous meetings, as time an availabil'ty of informati permit.

NOTE:

  • Presentation time should not exceed 50 percent of the total time allocated for a specific item. The remaining 50 percent of the time is reserved for discussion.

I o Number of copies of the presentation materials to be provided to the ACRS - 35.

I I

1 i

l

APPENDIX lli: MEETING ATTENDEES 444TH ACRS MEETING I, September 3,1997 NRC STAFF P. Castleman, OCM/ND T. Hsia, OCM/ND J. Mitchell, OEDO B. Borchardt, NRR M. Johnson, NRR A. Markley, NRR L. Thonus, NRR S. Weiss, NRR J. Hyslop J. Schif,~ gens, NRR J. Strosnider, NRR K. S. West, NRR E. Connar, NRR -

T. Reed, NRR J. Flack, NRR A. Levin, NRR P. Wilson, NRR D. O'Neal, NRR G. Parry, NRR i N. Siu, RES T. King, RES J. Perensky, RES A. Ramey-Smith, RES C. Tinkler, RES E. Rodrick, RES H. Vandermolen, RES T. Wolf, AEOD A. Madison, AEOD l P. O'Reilly, AEOD ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC S. D. Floyd, NEl K. Umerstall, MLB F. Emerson, NEl L. M. Muntzing, MLB A. Nelson, NEl P. E. Troy, MLB C. Callaway, NEl P. Negas, GE B. Bradiey, NEl L. Allenbach, Arthur Andersen T. Sutter, Bechtel M. Neal, NUS J. Fulford, NUS .

i l

I l

Appendix ill 444th ACRS Meeting APPENDIXlil: MEETING ATTENDEES 444TH ACRS MEETING September 4,1997 NRC STAFF T. Hsia, OCM/ND J. Callan, OEDO A. Thadeni, DEDE J. Mitchell, OEDO J. Thoma, DEDR R. Eckenrode, NRR J. Schiffgens, NRR C. Thomas, NRR C. E. Carpenter, NRR S. Lee, NRR K. Wichman, NRR M. Khanna, NRR A. Lee, NRR R. Hermann, NRR S. Sheng, NRR K. Kavanagh, NRR r i J. Strosnider, NRR B. Elliot, NRR E. Weiss, NRR S. West, NRR M. Pohida, NRR W. Lyon, NRR T. Tjader, NRR R. Latta, NRR P. Balmain, NRR J. Monninger, NRR D. Jackson, NRR G. Hubbard, NRR D. Serig, NMSS J. Persensky, RES R. Meyer, RES L. Abramson, RES S. Malik, RES G. Mizuno, OGC ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLlO F. Galpin, Rogers & Assoc. Eng.

P. Negus, GE M. Neal, NUS g D. Modeen NEl i i

Appendix lil 444th ACRS Meeting T. Pietrengob, NEl

. F. Emerson, NEl S. Rockford, BGE L. Weil, McGraw Hill D. Raleigh, Bechtel

)

i

Appendix lil j 444th ACRS Meeting APPENDIXlil: MEETING ATTENDEES 444TH ACRS MEETING September 5,1997 l

NRC STAFF j P. Castleman, OCM/ND

{

J. Mitchell, OEDO '

G. Galletti, NRR E. Goodwin, NRR R. Dennig, NRR L. Rossbach, NRR C. Shiraki, NRR R. Capra, NRR i

T. Koshy, NRR  !

G. Marcus, NRR R. Eckenrode, NRR S. Rubin, NRR J. Hopkins, NRR C. Thomas, NRR j E. Adensam, NRR L. Spessard, NRR M. Depas, Rlli i G. Wright, Rill J. Persensky, RES J. Kauffman, AEOD J. Rosenthal, AEOD ATTENDEES FROM OTHER AGENCIES AND GENERAL PUBLIC J. Cook, Illinois Power M. Lyon, Illinois, Power R. Godley, Commonwealth Edison L. Holden, Commonwealth Edison J. Eenigenberg, Commonwealth Edison l

l I

I l

l

APPENDIX IV: FUTURE AGENDA I

The Committee agreed to consider the following during the 444th ACRS Meeting, September 3-5, 1997; 1

h

e ., * . , ,

( September 5, 1997 PROPOSED SCHEDULE ANK OUTLINE FOR DISCUSSION 444bh ACRS MEETING October 2-4, 1997 THURSDAY, OCTOBER 2, 1997, COlisinnCE ROOM 2B3, TWO WRITE FLiliT NORTH, ROCKVILLE, MARYLAND

1) 8:30 - 8:45 A.M. Doenine Remarks by the ACRS chairman (open) 1.1) Opening Statement (RLS/SD) 1.2) Items of current interest (RLS/JTL/SD) 1.3) Priorities for preparation of ACRS reports (RLS/SD)
2) 8:45 - 10:45 A.M. Human Performance and Reliability Imolementation Plan (Open) (GA/NFD) 2.1) Remarks by the Subcommittee Chairman.

2.2) Briefing by and discussions with representatives of the NRC staff regarding the proposed Human Performance and Reliability Imple-mentation plan.

Representatives of the nuclear industry will participate, as appropriate.

10:45 - 11:00 A.M. *** BREAK ***

3) 11:00 - 12:30 P.M. Emercenev Core coolina System Strainer Blockage (Open) (JJB/AS) 3.1) Remarks by the Subcommittee Chairman. .

3.2) Briefing by and discussions with representatives of the NRC staff and the BWR Owners Group regarding the NRC staff Safety Evaluation Report on BWR Owners Group Utility Resolution Guide for Emergency Core Cooling System Strainer Blockage, and related matters.

12:30 - 1:30 P.M. ***LUNCR***

i l

1

.. i.

2

4) 1:30 - 3:30 P.M. Procomed Final Reaulatorv Guidance t

Related to Imolementation of 10 CFR

~

50.54 and Prooosed Revision 1 to Generic Lettdr 91-18 (Open) (DAP/MTM) 4.1) Remarks by the cognizant ACRS 1 Member. I 4.2) Briefing by and discussions with l representatives of the NRC staff and Nuclear Energy ,

)

Institute regarding proposed i final revisions to 10 CFR 50.59  !

(Changes, Tests, and Experiments) and the proposed revision 1 to Generic Letter 91-18, "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions."

3:30 - 3:45 P.M. *** BREAK ***

5) 3:45 - 4:45 P.M. Prooosed Resolution of a Differina Professional Ooinion Concernino Steam Generator Intecrity (Open) (RLS/NFD) 5.1) Remarks by the Subcommittee Chairman.

5.2) Briefing by and discussions with representatives of the NRC staff regarding the proposed resolution of a Differing Professional opinion Associated with the steam Generator integrity.

6) 4:15 - 7:00 P.M. Precaration of ACRS Reoorts (Open)

(5:45-6:00: Break) Discussion of proposed ACRS reports on:

6.1) Human Performance and Reliability Implementation Plan. (GA/NFD) 6.2) Emergency Core Cooling System Strainer Blockage. (JJB/AS) 6.3) Proposed Final Version of 10 CFR 50.59 and Revision 1 to Generic Letter 91-18. (DAP/MTM) '

6.4) Proposed Resolution of A Differing Professional Opinion Concerning Steam Generator Integrity. (RLS/NFD)

I

3 FRIDAY, OCTOBER 3, 1997. CONFERENCE ROOM 2B3, TWO WHITE FLINT

NORTH, ROCKVILLE, MARYLAND
7) 8:30 - 8:35 A.M. Oneniha Remarks by the ACRS Chairman (Open) S/SD)
8) 8:35 - 10:00 A.M. Cacability nd Anolication the EPRI CHECKWORKS dade (Open/Cl ed) (TSK/PAB) 8.1) Remark by the committee Chairman.

8.2) Briefing b and discussions with represe ati s of the the NRC staff nd Elec ic Power Research Ins tute (EPRI) egarding the e ability and app cation of the PRI CHECKWORKS Code

(.No : A portion of this se ion may be c sed to discuss EPRI proprietary nformation applicable to this matter.)

10:00 - 10:15 A.M. *** BREAK ***

9) 10:15 - 11:45 A.M. Meetino with the Director of the NRC Office for Analysis and Evaluation of Operational Data (AEOD) (Open) (RLS/MME) 9.1) Remarks by the ACRS Chairman 9.2) Briefing by and discussions with the AEOD Director on items of mutual interest, including Accident Sequence Precursor Program, and other AEOD Programs.
10) 11:45 - 12:00 Noon Subcommittee Recort (Open) (TSK/PAB)

Report by the Chairman of the Thermal Hydraulic Phenomena Subcommittee regarding matters considered during the September 29-30, 1997 Subcommittee meeting.

12:00 - 1:00 P.M. ***LUNCE***

11) 1:00 - 1:15 P.M. Reconciliation of ACRS Comments and Recommendations (Open) (RLS, et. al./SD, et al.)

Discussion of the responses of the NRC Executive Director for Operations to commente and recommendations included in recent ACRS reports.

12) 1:15 - 1:45 P.M. Future ACRS Activities (Open) .

(RLS/JTL/SD)

o. .. ., .

4 Discussion of the recommendations of the Planning and Procedures Subcommittee regarding items proposed-for consideration by the full Committee during future meetings. '

13) 1:45 - 2:15 P.M. Renort of the Plannina and Procedures Subcommittee (Open/ Closed) (RLS/JTL)  !

Report of the Planning and Procedures (

Subcommittee on matters the conduct of ACRS related to' business, qualifications of candidates nominated for appointment to the ACRS, and organizational and personnel matters relating to the ACRS. '

[ Note: A portion of this session may be closed to discuss organizational and personnel _ matters that relate solely to ,

the internal personnel rules and '

practices of this Advisory Committee, and information the release of which i

would constitute a clearly unwarranted invasion of personal privacy.]

14) 2:15 - 7:00 P.M. Prenaration of ACRS Renorts (Open)

(3:15-3:30: BREAK) 14.1) Human Performance and Reliability Implementation Plan (GA/NFD) 14.2) Emergency Core Cooling System Strainer Blockage (JJB/AS) 14.3) Proposed Final Version of 10 CFR 50.59 and Revision 1 to Generic Letter 91-18 (DAP/MTM) 14.4) Proposed Resolution of A Differing Professional opinion Concerning Steam Generator Integrity (RLS/NFD)

E KS od )

BATURDAY, OCTOBER 4, 1997. C(C7ERENCE R00K. 2332 TNO MEITE FLINT NORTH, ROCKVILLE, MARYLAND

15) 8:30 - 12:00 Noon Prenaration of ACRS Renorts (Open)

Continue discussion of proposed ACRS reports listed under Item 14.

16) 12:00 - 12:30 P.M. Stratecie Plannina (Open) (RLS/JTL)

Discussion of items of significant importance to NRC, including rebaselining of the Committee activities i

1 i

5 for FY 1998.

17) 12:30 - 1:00 P.M. Miscellaneous (Open) (RLS/JTL/SD)

Discussion of miscellaneous matters related to the conduct of Committee l activities, and matters / specific issues l that were not completed during previous meetings, as time and availability of i information permit.

NOTE: e Vresentation time should not exceed 50 percent of the total time allocated for a specific item. The rammining 50 percent of the time is reserved for discussion.

  • Number of copies of the presentation materials to be provided to the ACRS - 35.

l l

l 1

APPENDIX V

(

LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE

[ Note: Some documents listed below may have been provided or prepared for Committee use only. These documents must be reviewed prior to release to the public.]

MEETING HANDOUTS AGENDA DOCUMENTS ITEM NO.

1 Onenino Remarks by the ACRS Chairman

1. Items of Interest, September 3-5,1997 2 Meetina with the Divialan of Inanne+ ion and Snanart Procreiiis. C#,m of Nn*= R== Mar Regulation (NRR)
2. Integrated Review of the NRC Assessment Process for Operating Commercial Nuclear Reactors [Viewgraphs) i 3 Meetina with the Office for Analvais and Evmin=+ ion of Ooerm+ianal D=*= (AEOD) i
3. Improvements to the Information Base of the Senior Management Meeting '

[Vowgraphs) 4 Draft Rennlainrv Guide 1089

4. l July 29,1996 Decommissioning Amendment 50.48(f) for 50.82(a)(l) Reactors l

Maintain Fire Protection Programs 5 *':dnc with the Division of Enaineerina. Office of Noelaar Rametor Raanistian (NRR)

5. Steam Generator Generic Letter SG Tube Integrity [Vowgraphs) 6 Nuclear Enery Instnute
6. Clive Callaway [Viewgraphs) 7 Public Availability of Data from Voluntarv Anorameh [Viewgraphs) i 8 Accident Seauence Precursor (ASP) Proaram Mand ='a (Vowgraphs) 9 Considerations for Site-Soncific Derivation of Suhaldiarv Risk Au20 tens Criteria -

Resoonse to Comments [Viewgraphs) f 7. Presentation, Rick Sherry, ACRS, Senior Fellow

Appendix V 444th ACRS Meeting 10 Site Snecific Safetv Goals [ Handout #7-1]

8. Letter dated August 29,1997, to J. Larkins, Executive Director, ACRS, from W. T.

Pratt, Brookhaven National Laboratory,

Subject:

Considerations for Plant-Specific Application of Safety Goals and Definition of Subsidiary Criteria

9. Draft letter from R. L. Seale, Chairman, ACRS, to Shirley Ann Jackson, Chairman, NRC,

Subject:

Risk-Based Regulatory Acceptance Critoria for Plan-Specific Application of Safety Goals, Part ll 11 Pronosed Schadnia for Comoletion of Risk-infear,ed R.G.s/SRPs [Vowgraph] .

12 Treatment of Uncertainties [Vowgraphs) 13 BWR Reactor Pressure Va===l Shell Wald insoantian Recommer.d=drs (BWRVIP-05)

[Vowgraphs) 4 14 I Thermal-Hvdraulie Phenomena [ Handout #13-1]

( 10. Chairman's Report to ACRS on the Thermal-Hydraulic Phenomena Subcommittee Meeting of July 29-30,1997.

j

11. Memorandum, T. R. Quay, NRR, to N. J. Liparulo, Westinghouse,

Subject:

Request for Additional Information (RAI) Related to Validation of the Notrump Small-Break LOCA Code for AP600, dated August 13,1997.

15 Reanl=+nry Polielas and Practica= [ Handout #14-1]

12. Summary and Some Thoughts on Defense-in-Depth.
13. Future ACRS Activities [ Handout #15-1] Memorandum dated September 4,1997,

Subject:

Future ACRS Activities - 445th ACRS Meeting, October 2-4,1997.

16 Office of the insoector General (Handout, OlG/97A-01, dated August 21,1997]

14. NRC Needs Comprehensive Plan to Resolve Regulatory issues 17 Presentation by the Office for Analysis and Evmination of Ooerational Data [Vmwgraphs]
15. Development of 50.67 Shutdown and Fuel Storage Pool Operations at Nuc'sar Power Piants.

l

Appendix V j 444th ACRS Meeting 18 Presentation by the Nuclaar Enerov institute [Vmwgraphs)

16. Industry Perspective on Proposed Shutdown Rule
20. Presentation on Operatina Pane +nr Events [Viewgraphs]
17. Introduction
18. Zion, Unit 1 i
19. Clinton
20. Human Performance 21.

Reconciliation of ACRS Comments and Recommendations (Handout #20.1]

21. Proposed Final Generic Letter " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps"
22. Proposed Standard Review Plan Section 3.9.8 & RG DG-1063 for Risk-Informed Inservice inspection of Piping.
23. Proposed Final Revisions to 10 CFR Part 26, Fitness-for-Duty Program Requirements.
24. Proposed Generic Letter, " Potential for Degradation of the ECCS and the Containment Spray System after a LOCA Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment."
25. ~ Proposed Regulatory Approach Associated with Steam Generator Integrity.
26. June 17,1997, letter regarding inclusion of a Containment Spray System in the AP600 Design.

22 Minutes of Plannino and Procedures Subcommittee Meetina. Auaust 27.1997 [ Handout

  1. 21.1]

.4 Appendix V 444th ACRS Meeting

{

MEETING NOTEBOOK CONTENTS

' I 6 11 DOCUMENTS 2 Staff Action Plan to Imorove Senior Manmaament E'_ _^Ais Prc===

1. Table of Contents
2. Proposed Schedule
3. Status Report, dated September 3,1997
4. SECY-97-072, " Staff Action Plan to improve the Senior Management Meeting Process, dated April 2,1997.
5. Memorandum, dated May 23,1997, D. F. Ross, AEOD, Subject, improvements to the Information Base for the Senior Management Meeting (Predecisional Draft -

Provided for ACRS Use Only).

6. Memorandum to L. Joseph Callan, EDO, J. T. Larkins, ACRS,

Subject:

Staff Requirements - Briefing on Staff Response to Arthur Andersen Study 1 Recommendations and SECY 97-072, dated June 24,1997.

7. Memorandum to L. Joseph Callan, EDO, Subject, Staff Requirements - Briefing on j Analysis of Quantifying Plan Watch List Indicators (Arthur Andersen Study), dated March 14,1997.
8. Excerpt of Committee Briefing on Arthur Andersen Study, Minutes of 439th ACRS Meeting, March 6-8,1997, dated May 1,1997.
9. SECY-97-192, " Peer Review of the Arthur Andersen Methodology and Use of Trending Letters," dated August 21,1997.
10. Management Directive 8.14, Senior Management Meeting 3 Draft Reaulatory GnN DG-1089
11. Table of Contents
12. Proposed Schedule
13. Status Report, dated September 3,1997
14. Draft Regulatory Guide DG-1069, Fire Protection Program for Permanently Shutdown and Decommissioning Nuclear Power Plants.

4 P,Lx::d Generic Letter and RaaiMarv nua A==c ' ^ -! with 9-- n Generator Inhav

15. Table of Contents
16. Proposed Schedule
17. Status Report, dated September 3,1997 j
18. Memorandum to J. T. Larkins, ACRS, from T. T. Martin, NRR, dated August 12, i 1997,

Subject:

ACRS Review of the Proposed Steam Generator Generic Letter. I

! 19. DG-1074, Draft Steam Generator Regulatory Guide " Steam Generator Tube l

_ ________ a

r Appendix V 4 -444th ACRS Meeting integrity." -

5 Reoortina P=H-hili +v and Av".:'N lnf,,rn.*n for Risk-SianifL -n; Svet ins' and Equipment

20. Table of Contents
21. Proposed Schedule
22. Status Report, dated September 3,1997
23. Staff Requirements Memorandum dated June 12,1997.
24. ' SECY-97-101, Proposed Rule,10 CFR 50.76, " Reporting Reliability and Availability information for Risk-Significant Systems and Equipment," dated May 7,1997.
25. Report dated April 12,1995, from T. Kress, ACRS Chairman, to 1. Selin, NRC Chairman,

Subject:

Proposed Rulemaking on Reporting Reliability and Availability Information for Risk-Significant Systems and Equipment.

26. Letter dated May 12,1997, from J. Taylor, EDO, to T. Kress, ACRS Chairman,

Subject:

Proposed Rulemaking on Reporting Reliability and Availability information for Risk-Significant Systems and Equipment.

6 NRC Prescerns for Risk R==ad Analvais of Pandar Ooeratina Fvnariance and A =!=l Studiet i

27. Table of Contents

- 28. Proposed Schedule

29. Status Report, dated September 3,1997 '
30. Letter dated November 22,1996, from T. Kress, ACRS Chairman to J. Taylor, EDO,

Subject:

NRC Programs for Risk-Based Analysis of Reactor Operating Experience.

31. Letter dated December 19,1996, from J. Taylor, EDO, to T. Kress, ACRS Chairman,

Subject:

NRC Programs for Risk-Based Analysis of Reactor Operating Experience.

32. Memorandum dated June 19,1997, from E. Rossi, AEOD, to R. Zimmerman, T.

Martin, B. Sheron, F. Gillespie, B. Boger, M. Slosson, and G. Holahan, NRR,; L.

Shao, B. Morris, and W. Hodges, RES; J. Wggins, Rl; J. Jaudon, Ril; J. Grobe, Rill; and A. Howell, RIV; Subject, "Special Study: Fire Events - Feedback of U.S.

Operating Experience - Final Report," w/o attached proprietary materials.

33. Memorandum dated June 17,1997, from E. Rossi, AEOD, to B. Sheron, F.

Gillespie, B. Boger, M. Slosson, and G. Holahan, NRR; L. Shao, B. Morris, and W. Hodges, RES; C. Hohl and J. Wiggins, Rl; J. Jonson and J. Jaudon, Rll; G.

Grant and J. Grobe, filll; and P. Gwynn and A. Howell, RIV; Subject, "Special Report: - Reactor Core isolation Cooling System Reliability 1987-1993, AEOD/S97-02 (INEL-950196)," w/o attached report.

7 Site-Soecific Safety Goals

( 34. Table of Contents

f

.O Appendix V g 444th ACRS Meeting

35. Proposed Schedule
36. Status Report, dated September 3,1997
37. Staff Requirements Memorandum dated May 27,1997
38. Note dated August 16,1997, from M. Linn, ORNL, to T. Kress, ACRS,

Subject:

Peer Review of Analysis Prepared by ACRS Senior Fellow, Rick Sherry

39. Letter dated August 18,1997, from A. Camp, SNL, to D. Powers, ACRS,

Subject:

Considerations for Plant-Specific Site-Specific Applications of Safety Goals and Definition of Subsidiary Criteria, Rick Sherry, June 27,1997.

40. Draft input to 444th ACRS meeting minutes, M. Markley.
41. Memorandum dated June 27,1997, from R. Sherry, ACRS Fellow, to ACRS Members,

Subject:

Consideration for Plant-Specific Site Specific Application of Safety Goals and Definition of Subsidiary Criteria.

42. Report dated April 11,1997, from R. Seale, ACRS Chairman, to S. Jackson, NRC Chairman,

Subject:

Risk-Based Regulatory Acceptance Criteria for Plant-Specific Application of Safety Goals.

43. Letter dated July 23,1997, from J. Colvin, NEl, to S. Jackson, NRC Chairman,

Subject:

Proposed SRP/RG for risk-informed, performance-based regulation.

44. {

Note dated August 17,1997, from D. Powers, ACRS, to G. Apostolakis, ACRS, i

Subject:

NEl Objections to the CDF Safety Goal.

45. Written comments dated August 26,1997, from S. Levinson, B&W Owners Group, g to G. Apostolakis,

Subject:

Comments on Uncertainty and Safety Goals.

8 Use of Uncertaintv Versus Point Vah== in the PRA-Ral='ad Denialanmakino Prc-==

46. Table of Contents
47. Proposed Schedule
48. Status Report, dated September 3,1997
49. Staff Requirements Memorandum dated May 27,1997.
50. Staff Requirements MemorandumDATED June 5,1997.
51. Memorandum dated July 2,1997, from S. Jackson, NRC Chairman, to J. Callan, EDO,

Subject:

"The Statement of Core Damage Frequency of 10E-4 as a Fundamental Commission Goal.

52.' Note dated July 15,1997, from 1. Catton, ACRS Consultant, to M. Markley, ACRS Staff,

Subject:

Meeting Report for July 7-8,1997 PRA Subcommittee. 1

)

53. List of questions to be addressed at the PRA Subcommittee meeting on July 7, 1997.
54. Letter dated July 23,1997, from J. Colvin, NEl, to S. Jackson, NRC Chairman,

Subject:

Comments on SRP/RGs for risk-informed, performance-based regulation.

55. Written comments dated August 26,1997, from S. Levinson, BWROG, to M.

q Markley, ACRS Staff,

Subject:

Request for written comments to be read into the public record during joint PRA, Plant Operatens, and Fire Protection Subcommittee meeting, August 28-29,1997.

56. Note dated August 17,1997, from D. Powers, ACRS, to G. Apostolakis, ACRS,

Subject:

NEl Objections to CDF Safety Goal.

l Appendix V 1

444th ACRS Meeting I

i 11 ':..a ;Jh the NRC Fr=>ive Dir=:= for Cse,-.::=s

56. Table of Contents
57. Proposed Schedule
58. Status Report, dated September 4,1997
59. Letter from John T. Lerkins, ACRS, to L Joseph Callan, EDO, dated July 31, 1997. j
60. ACRS letter dated December 30,1996, RE: ACRS Questions on Human Performance Program Plan
61. EDO Response dated February 4,1997, RE: ACRS Questions on Human I Performance Program Plan  !
62. ACRS Report dated February 13,1997 RE: Human Performance Program Plan.
63. EDO Reponso dated April 10,1997 RE: Human Performance Program Plan.
64. ACRS Report dated November 19,1996, RE: Position on Direction Setting issue 22-Future Role of NRC Research. j
65. ACRS Report to Congress dated February 21,1997, RE: Safety Research  !

Program.

66. Staff Requirements, COMSECY-96-066, Research (DSl#2).
67. ACRS letter to EDO dated December 13,1996, RE: ACRS Review of Generic l~ Letters, Bulletins, and information Rsquests issued on an Expedited Bases.
68. EDO Response dated April 11,1997, to ACRS letter RE: Review by the ACRS of Generic Letters, Bulletins, and information Requests issued on an Expedited Basis.
69. ACRS letter dated November 22,1996, RE: NRC Programs for Risk-Based Analysis of Reactor Operating Experience.
70. EDO Response dated December 19,1996, RE: NRC Programs for Risk-Based Analysis of Reactor Operating Experience. j
71. ACRS Report dated March 17,1997, RE: Proposed Standard Review Plan Sections and Regulatory Guides for Risk-Informed, Performance-Based Regulation.
72. SRM dated January 22,1997, RE: SECY-96-218.
73. ACRS Report dated July 14,1997, RE: Pres-:::d Regulatory Guide and Standard Review Plan Chapter for Risk-Informed, Performance-Based Inservice inspection.

12 BWR Pressure Vessel Shell Wald ineaardians BWRVIP-05 Rana.1

. 74. Table of Contents

75. Proposed Schedule
76. Project Status Report, dated September 4,1997 13 Report on 7/29-30/97 T/H Phenomena Suh=ri,rr.ittee d;,,s- Use of '.'.';;urish an==

Notrumo SBLOCA Code for AP600 Analvana

77. Table of Contents I. 78. Proposed Schedule

9 I Appendix V 444th ACRS Meeting

79. Status Report, dated September 4,1997  ;

16 Prooosed Rule on Shutdown and Fuel Storane Pool Ooerations

80. Table of Contents.
81. Proposed Schedule. i
82. Status Report, dated September 4,1997.

19 Imoroner Control Rod Movement Durino Shutdown at Zion Unit 1. and Noncensarvative Ooerations Durina isolation of Recirculation Pumo See! Leak at Clinton

83. Table of Contents.
84. Proposed Schedule.
85. Status Report, dated September 5,1997.

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