NUREG-1184, Submits Comments on Isap,Discussed During 327th Meeting of ACRS on 870709-11.Recommends Extension of Isap Process to Other Plants.Listed Points Need Further Consideration

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Submits Comments on Isap,Discussed During 327th Meeting of ACRS on 870709-11.Recommends Extension of Isap Process to Other Plants.Listed Points Need Further Consideration
ML20235V940
Person / Time
Issue date: 07/15/1987
From: Kerr W
Advisory Committee on Reactor Safeguards
To: Zech L
NRC COMMISSION (OCM)
References
RTR-NUREG-1184 ACRS-R-1258, NUDOCS 8707230363
Download: ML20235V940 (2)


Text

' 68.8ICq o UNITED STATES'

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.n NUCLEAR REGULATORY COMMISSION

_ [' . ,$ _ ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 8

0, g WASHINGTON, D. C. 20555

%.v....J July 15, 1987 The Honorable Lando W. Zech, Jr.

Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Chairman Zech:

SUBJECT:

ACRS COMMENTS'ON THE INTEGRATED SAFETY ASSESSMENT PROGRAM During the 327th meeting of the ACRS, July 9-11, 1987, we reviewed the experience gained with .the NRC Staff's Integrated Safety Assessment Program (ISAP) pilot program. This topic was discussed during a Subcom-

<nittee meeting on July 7, .1987. The ISAP process had also been dis-cussed during our 279th meeting in July 1983, as reported in our letter to Chairman Palladino of July 12, 1983. In our review, . we had the benefit of discussions with the NRC Staff and industry representatives and of the documents referenced.

The ISAP is intended as a cooperative program, between the NRC Staff and a licensee, which provides for the optimized resolution 'of multiple.

safety issues. The program would ' permit a licensee- to develop an '

integrated plan for implementing plant' improvements in response- to outstanding safety issues. It would be based on'a comprehensive list of' issues, an assessment of the plant's operating experience, and a plant-The ISAP concept grew out of the Systematic specific Evaluationrisk analy(sis.SEP), which was highly successful in upgrading th Program ten oldest licensed plants to 'conformance with current regulatory requirements.

The ISAP pilot program was carried out for Millstone Unit 1 and Haddam

. Neck by Northeast Nuclear Energy Company (NNECO) and the NRC Staff. The NRC. Staff has-issued a draft Integrated Safety Assessment Report (ISAR)-

for Millstone Unit 1 and will soon issue the draft ISAR for Haddam Neck.

The NRC Staff is preparing reconsnendations. to the Commission for the future use of the ISAP process based on an analysis of the lessons.

learned from the pilot program.

}

j -A, \

The Honorable Lando W. Zech, Jr., '

July 15, 1987

1 Experience with' the ISAP pilot program demonstrates thst the process is ,

useful and provides an excellent mechanism for ~ the implementation of '

regulatory requirements. The_NRC Staff and NNECO appear to agree on the usefulness of ISAP. We recomend that the . ISAP process be extended to 1

other plants.

The NRC Staff has not yet completed the development of the procedures by-which the .ISAP process would be implemented more broadly. The methods used in the pilot program were successful. However, several points need l to be considered further.  ;

, i (1) the application of the process to plants that were not in the SEP 1 j

(2) the coordination with the Individual Plant Examination program.

under the Severe Accident Policy implementation ,

(3) the appropriate scope for the risk analysis to be used as part of '

ISAP e

We would like to review the NRC Staff's proposal for future use of the ,

i ISAP when it is available. 9, i Sincerely,I Il l

l William Kerr Chairman i

References:

1. U.S. Nuclear Regulatory Commission, NUREG-1184, " Integrated Safety l Assessment Report," Draft Report, April.1987 '

i

2. Northeast Utilities, " Integrated Safety Assessment Program, Haddam Neck Plant," Volumes 1 to 3, Final Report, December 1986 l
3. Northeast Utilities, " Integrated Safety Assessment Program, Mill-stone, Unit 1," Volumes 1 to 3, Final Report, July 1986
4. Northeast Utilities Service Company, NUSCO 149, " Connecticut Yankee-Probabilistic Safety Study," Volumes 1 to 4, February.1986
5. Northeast Utilities Service Company, NUSCO 147, " Millstone, Unit 1, Probabilistic Safety Study,". Volumes I to 3 July 1985 I

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