ML20210P177
| ML20210P177 | |
| Person / Time | |
|---|---|
| Issue date: | 08/09/1999 |
| From: | Travers W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Powers D Advisory Committee on Reactor Safeguards |
| References | |
| RTR-REGGD-01.181 NUDOCS 9908120106 | |
| Download: ML20210P177 (7) | |
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665-0001 4....
August 9, 1999 Dr. Dana A. Powers, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
PROPOSED REGULATORY GUIDE 1.181," CONTENT OF THE UPDATED FINAL SAFETY ANALYSIS REPORT IN ACCORDANCE WITH 10 CFR 50.71(e)"
Dear Dr. Powers:
By letter to NRC Chairman Greta Joy Dicus dated July 21,1999, the Advisory Committee on Reactor Safeguards recommended approval of Regulatory Guide (RG) 1.181 for use by the industry. RG 1.181 endorses the industry guideline document developed by the Nuclear Energy Institute (NEI), NEl 98-03, Revision 1, " Guidelines for Updating Final Safety Analysis Reports," dated June 1999, without exception.
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in your letter, you indicated that as part of its efforts to develop risk-informed regulation, the staff should anticipate how the safety analysis report will evolve. As an example, you indicated that it may be necessary to include information crucial to the conduct of probabilistic risk assessments in the safety analysis report. I have forwarded your recommendation to the managers responsible for risk-informed initiatives.
Sincerely, AA.
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l Willia
. Tra e Executive Director w
for Operations cc: Chairman Dicus g
Commissioner Diaz Commissioner McGaffigan Commissioner Merrifield SECY f ll $Ut 4i 9908120106 990809 PDR REGGD 01.181 C PDR n i
August 9, 1999 Dr. Dana A. Powers,' Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
PROPOSED REGULATORY GUIDE 1.181," CONTENT OF THE UPDATED FINAL SAFETY ANALYSIS REPORT IN ACCORDANCE WITH 10 CFR 50.71(e)"
Dear Dr. Powers:
~
By letter to NRC Chairman Greta Joy Dicus dated July 21,1999, the Advisory Committee on Reactor Safeguards recommended approval of Regulatory Guide (RG) 1.181 for use by the industry. RG 1.181 endorses the industry guideline document developed by the Nuclear Energy Institute (NEI), NEl 98-03, Revision 1, " Guidelines for Updating Final Safety Analysis
- Reports," dated June 1999,'without exception.
In your letter, you indicated that as part of its efforts to develop risk-informed regulation, the staff should anticipate how the safety analysis report will evolve. As an example, you indicated that it may'be necessary to include information crucial to the conduct of probabilistic risk assessments in the safety analysis report. I have forwarded your recommendation to the managers responsible for risk-informed initiatives.
OriginalSigned by
' Sincerely, William D. Travers William D. Travers Executive Director for Operations cc: Chairman Dicus Commissioner Diaz Commissioner McGaffigan Commissioner Merrifield SECY DISTRIBUTION: See attached page DOCUMENT NAME: G:\\RGEB\\FSAR\\GT990368.WPD
- See previous concurrence OFFICE RGEB: DRIP TECH EDITOR
- SC:RGEB: DRIP
- C:RGEB: DRIP NAME J. Birmingham:sw B.Calure*
F.Akstulewicz C. Carpenter DATE 08/03/99 07/ 30 /99 08/03/99 08/03/99 OFFICE.
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08/ b /99 08/h/99 08/E/99 DATE 08/
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August 9. 1999 Distribution: Green Ticket 19990368 Dated AUS 0a me Central File (w/ incoming)(GT 19990368) l PUBLIC (w/ incoming)(GT 19990368).
EDO r/f (w/ incoming)(GT 19990368)
NRR MAILROOM (w/ incoming)(GT 19990368)
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SCollins RZimmerman BSheron WKane GHolahan
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Dr. Dana A. Powers, Chairman Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission.
Washington, DC 20555-0001
SUBJECT:
PROPOSED REGULATORY GUIDE 1.181,'" CONTENT OF THE UPDATED FINAL SAFETY ANALYSIS REPORT IN ACCORDANCE WITH 10 CFR 50.71
Dear Dr. Powers:
1 By letter to NRC Chairman Greta Joy Dicus dated July 21l 1999, the Advisory Com ettee on Reactor Safeguards recommended approval of Regulatory Guide (RG) 1.181 for se by the industry. RG 1.181 endorses the industry guideline document developed by th Nuclear Energy
- Institute (NEI), NEl 98-03, Revision 1, " Guidelines for Updating Final Safety alysis Reports,"
dated June 1999, without exception.
In your letter, you indicated that as part of its efforts to develop risk-i rmed regulation, the staff should anticipate how the safety analysis report will evolve. As an xample, you indicated that it may be necessary to include information crucial to the conduct probabilistic risk assessments in the safety analysis report. I have forwarded your recomm dation to the managers responsible for risk-informed initiatives.
Sincerely Willia
. Travers Exe ive Director or Operations cc: Chairman Dicus
-Commissioner Diaz Commissioner McGaffigan Commissioner Merrifield SECY DISTRIBUTION: See attac d page DOCUMENT NAME: G:
EB\\FSAR\\GT990368.WPD
- See previous concurre ce
/
OFFICE RGEBjdRIPg g TECH EDITOR SC:%@P C:RGEB: DRIP NAME J.Bibingham:sw B.Calurei F.Akstulewicz C.Carpented DATE'
,d8/ 03 /99 07/30/99 08/ 3 /99 M08/
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D: DRIP ADIP D:NRR EDO NAME D.Matthews W.Kane S. Collins W. Travers DATE-08/'
/99 08/
/99 08/
/99 08/
/99 OFFICIAL RECORD COPY
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Dr. Dana A. Powers, Chairman l
Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 i
SUBJECT:
PROPOSED REGULATORY GUIDE 1.181, " CONTENT OF THE UPDATED s
FINAL SAFETY ANALYSIS REPORT IN ACCORDANCE WITH 10 CFR 50.71(e)"
)
Dear Dr. Powers:
By letter to NRC Chairman Greta Joy Dieus dated July 21,1999, the Advisory Committee on i
Reactor Safeguards recommended approval of Regulatory Guide (RG) 1.181 for use by the industry. RG 1.181 endorses the industry guideline document developed by the Nuclear Energy Institute (NEI), NEl 98-03, Revision 1, " Guidelines for Updating Final Safety Analysis Reports,"
dated June 1999, without exception.
l In your letter, you indicated that as part of its efforts to develop risk-informed regulation, the staff should anticipate how the safety analysis report will evolve. As an example, you indicated that it 4
may be necessary to include information crucial to the conduct of probabilistic risk assessments in the safety analysis report. I have forwarded your recommendation to the managers responsible for risk-informed initiatives.
Sincerely, William D. Travers Executive Director for Operations cc: Chairman Dicus Commissioner Diaz Commissioner McGaffigan Commissioner Merrifield SECY DISTRIBUTION: See attached page DOCUMENT NAME: G:\\RGEB\\FSAR\\GT990368.WPD
- See previous concurrence OFFICE RGEB: DRIP Q TECH EDITOR SC:RGEB: DRIP C:RGEB: DRIP J. Birmingham (
NAME B.Calure*
F.Akstuleriez C. Carpenter i
l DATE 08/03/99 07/30/99 08/
/99 08/
/99 OFFICE D: DRIP ADIP D:NRR EDO NAME D.Matthews W.Kane S. Collins W. Travers DATE_
08/
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Norry Blaha Burns DATE: 07/22/99 Thadani, RES Mitchell, OEDO ASSIGNED TO:
CONTACT:
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G t4990SG,8 OFFICE OF THE SECRETARY-CORRESPONDENCE CONTROL TICKET PAPER NUMBER:
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EDO AUTHOR:
DANA POWERS AFFILIATION:
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS ADDRESSEE:
CHAIRMAN'DICUS LETTER DATE:
Jul 21 99 FILE CODE: OM-7 ACRS
SUBJECT:
PRO FINAL REG GUIDE 1.181, CONTENT OF THE UPDATED FINAL SAFETY ANALYSIS REPORT IN ACCORDANCE WITH 10 CFR 50.71 ACTION:
Appropriate DISTRIBUTION:
RF SPECIAL HANDLING: NONE CONSTITUENT:
NOTES:
DATE DUE:
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DATE SIGNED:
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS Q
WASHINGTON, D. C. 20555 July 21,1999 The Honorable Greta Joy Dieus Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Chairman Dicus:
SUBJECT:
PROPOSED FINAL REGULATORY GUIDE 1.181, ' CONTENT OF THE UPDATED FINAL SAFETY ANALYSIS REPORT IN ACCORDANCE WITH 10 CFR 50.71(e)"
During the 464* meeting of the Advisory Committee on Reactor Safeguards, July 14-16,1999, we reviewed the proposed final Regulatory Guide 1.181, which endorses NEl 98-03, Revision 1,
" Guidelines for Updating Final Safety Analysis Reports," without exception. During this review, we had the benefit of discussions with representatives of the NRC staff and the Nuclear Energy Institute (NEI). We also had the benefit of the documents referenced.
Recommendation We recommend approval of proposed final Regulatory Guide 1.181 for use by the industry.
Discussion As a result of industry experience and other initiatives related to updated Final Safety Analysis i
Reports (FSARs), the NRC has determined that additional guidance regarding compliance with 10 CFR 50.71(e) is necessary. This regulation requires licensees to periodically update their FSARs. Revisions must be filed either annually or 6 months following each refueling outage, provided that the interval between successive updates does not exceed 24 months.
Although 10 CFR 50.71(e) specifies the type of new information that must be evaluated to determine if the FSAR must be opdated, experience has shown that additional guidance is necessary. The staff has worked with NEl and other stakeholders to develop this additional guidance. We believe that the guidance resulting from this joint effort, which is documented in NEl 98-03, Revision 1, is sufficient for licensees to demonstrate compliance with the requirements of 10 CFR 50.71(e).
The Commission is now encouraging an evolution in the regulations that will lead to changes in the assessment of safety system performance and the types of accidents that are considered.
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The information in the FSAR (e.g., which describes the facility, presents the design bases and
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the limits on its operation, and presents a safety analysis of the structures, systems, and I
components) must reflect these changes. As part of its efforts to develop risk-informed regulation, the staff should anticipate.how the safety analysis report will evolve. It may be necessary, for example, to include in the safety analysis report information crucial to the conduct of probabilistic risk assessments.
Sincerely, Dana A. Powers -
Chairman
References:
1.
Memorandum dated June 10,1999, from David B. Matthews, Office of Nuclear Reactor Regulation, to Robert L Seale, Chairman, ACRS,
Subject:
Request for Review and Endorsement of Regulatory Guide 1.181, " Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)."
2.
10 CFR 50.71, Maintenance of Records, Making of Reports.
3.
10 CFR 50.34(e), Final Safety Analysis Report.
4.
Nuclear Energy Institute, NEl 98-03, Revision 1, " Guidelines for Updating Final Safety Analysis Reports," June 1999.
~
5.
Memorandum dated Febnaary 16,1999, from Annette Vietti-Cook, Secretary of the Commission, to William D. Travers, Executive Director for Operations, NRC,
Subject:
i Staff Requirements - SECY-99-001 - Proposed Guidance for Updated Final Safety Analysis Reports in Accordance with 10 CFR 50.71(e).
6.
Memorandum dated June 30,1998, from John C. Hoyle, Secretary of the Commission, to L. Joseph Callan, Executive Director for Operations, NRC,
Subject:
Staff Requirements - SECY-98-087 - Proposed Generic Letter 98-XX: Interim Guidance for Updated Final Safety Analysis Reports in Accordance with 10 CFR 50.71(e).
I
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