ML20129G492

Summary of 433rd ACRS Meeting on 960808-10 Re Design Changes Proposed by Asea Brown Boveri - C-E Re Certification of Sys 80+ Design,Secy 96-128,proposed Rev 3 to Reg Guide 1.8,revs to Reg Guides 1.84,1.85 & 1.147 & Rev 3 to Reg Guide 1.105

ML20129G492
Person / Time
Site:	Indian Point, Arkansas Nuclear, 05200002
Issue date:	08/29/1996
From:	Kress T Advisory Committee on Reactor Safeguards
To:	Shirley Ann Jackson, The Chairman NRC COMMISSION (OCM)
References
RTR-REGGD-01.008, RTR-REGGD-01.084, RTR-REGGD-01.085, RTR-REGGD-01.147, RTR-REGGD-1.008, RTR-REGGD-1.084, RTR-REGGD-1.085, RTR-REGGD-1.147 ACRS-SL-0442, ACRS-SL-442, SECY-96-128-C, NUDOCS 9610070199
Download: ML20129G492 (10)

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ADVISORY COMMITTEE ON REACTOR SAFEGUAPOS POR /t/3/ff o, & WASHINGTON, D. C. 20555

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August 29, 1996 i

j The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 )

SUMMARY

REPORT - FOUR HUNDRED THIRTY-THIRD MEETING OF THE i ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, AUGUST 8-10, i 1996, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE '

During its 433rd meeting, August 8-10, 1996, the Advisory Committee 3 on Reactor Safeguards (ACRS) discussed several matters and completed the following reports. In addition, the Committee autho-rized Dr. Larkins, Executive Director, to transmit the memoranda noted below:

REPORTS e Desian Chances Proposed by ASEA Brown Boveri -

Combustion Encineerina Relatina to the Certification of the System 80+

Desian (Report to Shirley Ann Jackson, Chairman, NRC, from T.S. Kress, Chairman, ACRS, dated August 14, 1996.)

e SECY-96-128. " Policy and Kev Technical Issues Pertainina to the Westinchouse AP600 Standardized Passive Reactor Desian" (Report to Shirley Ann Jackson, Chairman, NRC, from T.S.

Kress, Chairman, ACRS, dated August 15, 1996.) j e Desian Chances Procosed by General Electric Nuclear Enerav Relatina to the Certification of the U.S. Advanced Boilina {;

ifater Reactor Desian (Report to Shirley Ann Jackson, Chairman, NRC, from T.S. Kress, Chairman, ACRS, dated August 15, 1996.)

e Risk-Informed, Performance-Based Reculation and Related I

Matters (Report to Shirley Ann Jackson, Chairman, NRC, from T.S. Kress, Chairman, ACRS, dated August 15, 1996.)

MEMORANDA e Procosed Revision 3 to Reculatory Guide 1.8, "Oualification and Trainina qf Personnel for Nuclear Power Plants" (Memoran-dum to James M. Taylor, Executive Director for Operations, from John T. Larkins, Executive Director, ACRS, dated August 13, 1996) - Consistent with the Committee's decision, Dr.

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.' The Honorable Shirley Jackson 2 4

i l Larkins informed Mr. Taylor that the Committee decided to i

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review the proposed final version of the subject Regulatory j Guide following reconciliation of public comments by the l staff. The Committee has no objection to the NRC staff l proposal to issue the proposed Regulatory Guide for public j comment.

• Draft Standard Review Plans on Antitrust and Power Reactor l Licensee Financial Oualifications & Decommissionina Fundina l Assurance (Memorandum to James M. Taylor, Executive Director >

'for Operations, from John T. Larkins, Executive Director,  !

ACRS, dated August 14, 1996) - Consistent with the Committee's l' l

decision, Dr. Larkins informed Mr. Taylor that the Committee 4

decided not to review the subject Standard Review Plans.

J e Proposed Revisions to Reaulatory Guides 1.84, 1.85, and 1.147 Pertainina to ASME Code Cases (Memorandum to James M. Taylor, Executive Director for Operations, from John T. Larkins, i

Executive Director, ACRS, dated August 14, 1996) - Consistent with the Committee's decision, Dr. Larkins informed Mr. Taylor that the Committee decided not to review the proposed revi-sions to the subject Regulatory Guides. The Committee would i like to have the opportunity to review future regulatory guides that pertain to ASME Division 1 Code Cases.

o Rulemakina Plan for Amendments to 10 CFR 73.55, Chances to Nuclear Power Plant Security Reauirements (Memorandum to James M. Taylor, Executive Director for Operations, from John T.

Larkins, Executive Director, ACRS, dated August 14, 1996) -

Consistent with the Committee's decision, Dr. Larkins informed Mr. Taylor that the Committee decided not to review the subject Rulemaking Plan.

o Proposed Revision 3 to the Reculatory Guide 1.105, " Instrument Setooints for Safety Systems" (Draft Reculatory Guide DG-1045)

(Memorandum to James M. Taylor, Executive Director for Opera-i tions, from John T. Larkins, Executive Director, ACRS, dated August 16, 1996) - Consistent with the Committee's decision, Dr. Larkins informed Mr. Taylor that the Committee decided to review the proposed final version of the subject Regulatory Guide following reconciliation of public comments by the staff. The Committee has no objection to the NRC staff proposal to issue the proposed Regulatory Guide for public comment.

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! HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE i

1. Suoo_ lemental Safety Evaluation Reports for Evolutionary Plant I Desians l The Committee reviewed recent design changes proposed by-j General Electric Nuclear Energy and ASEA Brown Boveri -

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j Combustion Engineering relating to the certification of the i j U.S. Advanced Boiling Water Reactor (ABWR) and the System 80+ l

j. designs, respectively.

s The design changes consisted of both modifications to the  !

i designs and corrections to- the documentation to remove  !

!- inconsistencies and typographical errors.

l As a result of its review, the committee continues to believe j l that acceptable bases and requirements have been established i

in the applications to ensure that the U.S. ABWR and System j 80+ Standard Designs can be used to' engineer and construct

} plants that with reasonable assurance can be operated without undue risk to the health and' safety of the public.

4 Conclusion

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The Committee issued two reports to Chairman Jackson, dated August 14, 1996 and August 15, 1996, on this matter.

2. SECY-96-128. " Policy and Kev Technical Issues Pertainina to the Westinahouse AP600 Standardized Passive Reactor Desian" The Committee heard presentations by and held discussions with representatives of the NRC staff and Westinghouse Electric Corporation concerning the proposed staff positions related to three policy issues pertaining to the AP600 design: prevention and mitigation of severe accidents, external reactor vessel cooling, and post-72-hour actions. The Committee also discussed the status of resolution of seven technical issues listed in SECY-96-128, especially the new technical issue on spent fuel pool cooling. The Committee plans to discuss the  ;

resolution of these technical issues during future meetings. j conclusion I

The Committee issued a report to Chairman Jackson, dated August 15, 1996, on this matter.

3. Risk-Informed and Performance-Based Reaulations and Related Matters The Committee heard presentations by and held discussions with representatives of the NRC staff regarding issues identified

The Honorable Shirley Jackson 4 in the Staff Requirements Memorandum dated May 15, 1996, including: the use of the Commission's safety goals for plant-cpecific applications, accounting for uncertainty in risk-informed and performance-based regulations, requirements for risk neutrality versus allowance for acceptable increase in risk, pilot applications for risk-informed and performance-based regulations, and the role of performance-based regula-tion in the PRA Implementation Plan.

The ACRS plans to continue its interaction with the staff in the development of regulatory guidance and a standard review plan for performing and reviewing PRAs. The Committee will also continue its discussion of the application of the safety goals on a plant-specific basis and other issues related to risk-informed and performance-based regulations during future meetings.

. Conclusion The Committee issued a report to Chairman Jackson, dated )

August 15, 1996, on this matter.

4. Scent Fuel Pool Coolina Issues Representatives of the Office of Nuclear Reactor Regulation (NRR) briefed the Committee regarding the resolution of tha issues included in the spent fuel pool cooling action plan.

The NRR staff presented the conclusions of a survey conducted by NRR, assisted by the regions, regarding the spent fuel pool i cooling issues. This survey covered two activities that j measured the extent to which problems encountered at Millstone i Unit 1, regarding compliance with the Final Safety Analysis Report (FSAR), occurred at other facilities. The first activity, which was the focus of the survey, compared current refueling practices against the licensing basis (drawn from the FSAR, Technical Specifications, license amendments, and other docketed correspondence) for decay heat removal from spent fuel pools for all operating plants. The second activity was to review the licensees' compliance with other revised NRC inspection guidance.

Based on the survey, the staff concluded that spent fuel pool cooling systems and backup cooling capability at the existing plants are adequate. System design features and licensee operating practices were found to be adequate in ensuring protection of public health and safety.

Representatives of the Office for Analysis and Evaluation of Operational Data (AEOD) stated that AEOD is performing a study on the spent fuel pool cooling issues at the request of the Executive Director for Operations and it is scheduled to be

1 The Honorable Shirley Jackson 5 completed by the end of September 1996. The Conmittee plans to discuss the results of this study when they are available.

Conclusion This briefing was for information only. No Committee action was required.

RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS i

e The Committee discussed the response from the NEC Executive l Director for Operations dated June 21, 1996, responding to ACRS comments and recommendations included in the ACRS report dated June 6, 1996, concerning Regulatory Guidance Documents related to Digital Instrumentation and Control Systems.

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

l e The Committee discussed the response from the NRC Executive Director for Operations dated June 28, 1996, responding to ACRS comments and recommendations included in the ACRS report l dated June 4, 1996, concerning Proposed Rule on Shutdown Operations.

The Committee decided that it would continue its discussion of this issue.

• The Committee discussed the response from the NRC Executive Director for Operations dated July 18, 1996, responding to ACRS comments and recommendations included in the ACRS report dated June 6, 1996, concerning Potential Use of IPE/IPEEE ,

Results to Compare the Risk of the Current Population of l Plants with the Safety Goals.

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

e The Committee discussed the response from the NRC Executive Director for Operations dated July 26, 1996, responding to ACRS comments and recommendations included in the ACRS report dated June 28, 1996, concerning Severe Accidant Research.

During its September 12-13, 1996 meeting, the Committee is ,

scheduled to discuss with the NRC staff the capability of NRC codes to assess the likelihood of steam generator tube ruptures during a severe accident. Subsequent to this discussion, the Committee plans to provide comments concerning this matter.

The Honorable Shirley Jackson 6 OTHER RELATED ACTIVITIES OF THE COMMITTEE During the period from June 13 to August 8, 1996, the following Subcommittee meetings were held:

o Probabilistic Risk Assessment & Plant Operations -

July 17-18, 1996 The Subcommittees on Probabilistic Risk Assessment (PRA) and Plant Operations discussed risk-based analysis of reactor

< operating events, the role of performance-based regulation in the PRA Implementation Plan, the plant-specific application of safety goals, the requirement for risk neutrality versus the allowance for an acceptable increase in risk, risk-informed inservice testing and inservice inspection requirements, the methods for judging the acceptability and unacceptability of assumptions and models used in performing PRAs, and the pilot applications for risk-informed and performance-based regula-tions.

e Westinahouse Standard Plant Desians - July 19, 1996 The Subcommittee on Westinghouse Standard Plant Designs I discussed SECY-96-128, " Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Standardized Passive Reactor Design," which contains proposed staff positions on l l

three policy issues: the prevention and mitigation of severe accidents, post-72-hour actions, and external reactor vessel  !

cooling, as well as the status of resolution of seven key I technical issues.

e Planninc and Procedures - August 6, 1996 The Planning and Procedures Subcommittee discussed proposed ACRS activities, practices, and procedures for conducting l Committee business and organizational and personnel matters relating to ACRS and its staff.

e Probabilistic Risk Assessment - August 7, 1996 The Subcommittee on Probabilistic Risk Assessment discussed risk-based inservice testing and inservice inspection require-ments, pilot applications for risk-informed and performance-based regulations, and related matters, as well as issues identified in the Staff Requirements Memoranda of May 15 and June 11, 1996.

LIST OF FOLLOW-UP MATTERS FOR THE EXECUTIVE DIRECTOR FOR OPERATIONS e The Committee decided to review the proposed final version of Revision 3 to Regulatory Guide 1.8, " Qualification and

The Honorable Shirley Jackson 7 Training of. Personnel for Nuclear Power Plants" after the staff has reconciled the public comments. The Committee has no objection to the NRC staff proposal to issue the proposed Regulatory Guide for public comment. [A memorandum was sent to James M. Taylor, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated August 13, 1996.]

e The Committee decided to review the proposed Revision 3 to Regulatory Guide 1.105, " Instrument Setpoints for Safety Systems" (Draft Regulatory Guide DG-1045) after the staff has reconciled the public comments. The Committee has no objec-tion to the NRC staff proposal to issue the proposed Regulato-ry Guide for public comment. [A memorandum was-issued to James M. Taylor, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated August 16, 1996.]

e The Committee decided not to review the proposed revisions to Regulatory Guides 1.84, 1.85, and 1.147 pertaining to ASME Code Cases. The Committee would like to have the opportunity to review future regulatory guides that pertain to ASME Code Cases. [A memorandum was sent to James M. Taylor, Executive Director for Operations, from John T. Larkins, Executive Director, ACRS, dated August 14, 1996.]

e The Committee decided not to review the Draft Standard Review Plans on Antitrust and Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance. [A memorandum was sent to James M. Taylor, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated August 14, 1996.]

e The Committee decided not to review the Rulemaking Plan for Amendments to 10 CFR 73.55, Changes to Nuclear Power Plant Security Requirements. [A memorandum was sent to James M.

Taylor, Executive Director for Operations, from John T.

Larkins, Executive Director, ACRS, dated August 14, 1996.]

PROPOSED SCHEDULE FOR THE 434TH ACRS MEETING The Committee agreed to consider the following during the 434th ACRS Meeting, September 12-13, 1996:

Adecuacy of the Codes to Analyze Steam Generator Tube Temoera-ture Distributions Durina Severe Accidents -

The Committee will hear presentations by and hold discussions with represen-tatives of the NRC staff regarding the adequacy of the NRC codes to analyze steam generator tube temperature distribu-tions during severe-accident conditions.

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The Honorable Shirley Jackson 8 Representatives of the industry will participate, as appropriate.

Indian Point Unit 3 - The Committee will hear presentations by and hold discussions with representatives of the Indian Point Unit 3 licensee (New York Power Authority) regarding the resolution of issues that led to.the shutdown of. Indian Point Unit 3, and the status of resolution of new issues since the restart of the plant in June 1995.

Representatives of the NRC staff will participate.

M9etino with the Director of the NRC Office of Nuclear B_eaulatory Research (RESL - The Committee will hear a presen-tation by and hold discussions with Mr. David Morrison, RES Director, on items of mutual interest including:

e Overview of the NRC research program and budget e Research priorities e NRC thermal-hydraulic code activities e International cooperative research program o RES plans and priorities for providing information necessary for the development. of risk-informed and performance-based regulations by expanding the scope of NUREG-1150 work to include a Level 3 PRA for shutdown modes of operation, fire, and other external events; the rationale for these plans and priorities; and ongoing and planned research for use in performing such PRAs for other modes of operation Loss of Feedwater Event at Arkansas Nuclear One Unit 1 - The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the findings and conclusions of the Augmented Inspection Team, which investi-gated the May 19, 1996, loss of feedwater event at Arkansas Nuclear One Unit 1.

Representatives of the licensee will participate, as appropriate.

Sincerely,

, 1 5. /W T. S. Kress Chairman 3

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uq'o UNITED STATES i

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j {, ,E ' ADVISORY COMMITTEE ON REACTOR SAFEGUARDS

& WASHINGTON, D. C. 20555 l

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l October 3,1996 1

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MEMORANDUM FOR: Jim McKnight I Document Control Branch FROM: Ethel Barnard Advisory Committe n Reactor Safeguards The attached ACRS Documents are being provided to you for listing on the accessions list. Please forward to the Public Document Room.

I Attachments:

As Stated l

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ACRS MEETING MINUTES AND OTHER DOCUMENTS (PDR 100396)

1) ACRS-2995 427thACRS Meeting, 12/7-8/95 '

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2) ACRS-3001 Probabilistic Risk Assessment Subcommittee Meeting, 2/27-28/96 l

3) ACRS-3002 Fire Protection Subcommittee Meeting,2/29/96 l

4) ACRS-3004 Instrumentation & Control Systems and Computers, Subcommittee Meeting, 3/6/96

- 5) ACRS-3006 429th ACRS Meeting,3/7-9/96

6) ACRS-3007 Extreme External Phenomena Subcommittee Meeting,4/3/96

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7) ACRS-3008 Severe Accidents Subcommittee Meeting,4/8/96 )

8) ACRS-3009 Reactor Fuels Subcomm;ttee Meeting,4/10/96 i

9) ACRS-3011 430th ACRS Meeting,4/11 13/96

10) ACRS-3013 Plant Operations Subcommittee Meeting,5/21/96

11) ACRS-3015 Planning and Procedures Subcommittee Meeting,5/22/96

12) ACRS-3016 431st ACRS Meeting, 5/23-25/96 l

13) ACRS-3017 Joint Materials & Metallurgy and Severe Accidents, Subcommittees Meeting, 6/3-4/96

14) ACRS-3018 Joint Probabilistic Risk Assessment and Westinghouse , Subcommittees f Meeting, 6/5/96  !

15) ACRS-3019 Planning and Procedures Subcommittee Meeting,6/11/96

16) ACRS-3021 432nd ACRS Meeting, 6/12-14/96

17) ACRS-3023 Westinghouse Standard Plant Designs, Subcommittee Meeting,7/19/96

18) ACRS-3024 Planning and Procedures Subcommittee Meeting,8/6/96

19) SL-0440 Kress ACRS ltr 06/26/96 to Jackson, Summary Report - Four Hundred Thirty-First Meeting of the ACRS, 05/23-25/96, and Other Related l Activities of the Committee

20) SL-0441 Kress ACRS ltr 07/25/96 to Jackson, Summary Report - Four Hundred Thirty-Second Meeting of the ACRS, 06/12-14/96, and Other Related Activities of the Committee

21) SL-0442 Kress ACRS ltr 08/29/96 to Jackson, Summary Report - Four Hundred Thirty-Third Meeting of the ACRS, 08/08-10/96, and Other Related Activities of the Committee

22) Summers memo 10/2/96, Release of Background Documents re the Review of Health Effects of Low-Levels of lonizing Radiation

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