ML20133Q131

Summary of ACRS Subcommittee on Safety,Philosophy,Technology & Criteria 851009 Meeting in Washington,Dc Re NRC Development of Containment Performance Guidelines.Plan for Developing Design Objective Encl

ML20133Q131
Person / Time
Issue date:	10/11/1985
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
Shared Package
ML20133Q134	List: ML20133Q131 ML20133Q138
References
ACRS-2364, NUDOCS 8511010399
Download: ML20133Q131 (4)

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oyhg DATE ISSUED: 10/11/85 ACRS SUBCOMMITTEE MEETING MINUTES ON SAFETY PHILOSOPHY, TECHNOLOGY, AND CRITERIA OCTOBER 9, 1985 WASHINGTON, DC The ACRS Subccmmittee on Safety Philosophy, Technology, and Criteria met on October 9, 1985 at 1717 H Street, N.W., Washington, D.C. The purpose of this meeting was to discuss the status of the work performed by the NRC Staff in developing containment performance guidelines. The Subcom-mittee heard presentations from representatives of RES ard NRR. The meeting was began at 3:00pm and adjourned at 5:00pm. The principle attendees were:

D. Okrent, Subcommittee Chairman J. Ebersole, Member F. Remick, Member C. Wylie, Member W. Kerr, Member C. Michelson, Member R. Savio, ACRS Staff M. Ernst, RES Staff Z. Rosztoczy, NRR Staff J. Rosenthal, NRR Staff Highlights

1. The NRC Staff has been directed by Chairman Palladino to develop containment performance design objectives for incorporation into a Safety Goal Policy. The NRC Staff intends to develop proposed objectives and, after Commission approval, to seek public comment and publish revised guidelines. The design objectives would be then evaluated over a trial use and implementation period. At the end of the trial use, the design objectives would be reevaluated and final recommendations made to the Commission. The proposed budgeting is as follows:

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SPT&C Meeting Minutes October 9,'1985 PSY T/A FY 86 3.5 275K FY 87 4.0 400K FY 88 4.0 275K } Proposed use and FY 89 4.0 175K J implementation period Issuance of the containment performance design objectives and implementation guidelines is scheduled for September 1987. A copy the NRC Staff plan for achieving this is included as Attachment A.

3. The NRC Staff is just beginning the work containment performance design objectives and is not yet recommending any specific guide-lines. Some of the alternatives being considered are:

(a) The proposal put forth in NUREG-0739 ("A Approach to Quantita-tive Safety Goals for Nuclear Power Plants," October 1980) specifying an operating limit of 0.1 conditional probability and a safety goal of 0.01 conditional probability for contain-ment integrity given a severe accident.

(b) Requiring some specified reduction in the released fission products via containment performance.

(c) Establishing an acceptable probability for a large scale release and a minimum level of containment performance and then allowing tradeoff between core melt frequency and  !

containment failure in achieving this probability for a large scale release.

3. It would be the NRC Staff's intention to develop a preliminary performance objective and to evaluate this performance objective through trial use. Development and evaluation of this goal would l

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SPT&C Meeting Minutes - 3- October 9, 1985 relay heavily on reference plant analysis. The NRC Staff could relay significantly on the following' work:

4 (a) NUREG-0956, " Reassessment of the Technical Bases for Estimat-ing Source Terms," draft report for ccmment.

(b) NUREG-1037, " Containment Performance Working Group Report,"

draft report for comment.

(c) NUREG-1079, " Estimates of Early Containment Loads from Core

Melt Accidents," draft.

i (d) SARRP Reports and the subsequent draft of NUREG-1150.

(e) Past PRAs and their reviews with emphasis on Indian Point / Zion, Limerick, Millstone 3, GESSAR.

(f) Seismic Studies completed to date.

(g) Safety Goal Evaluation Steering Group Report.

l (h) PRA Reference Document (NUREG-1050).

It was noted that a useful concept to be considered in this process was j the use of a containment performance design objective which was dependent on the class of site under consideration. It was additionally noted that containment performance may well be very dependent on plant specific details of the containment design. This could limit the usefulness of the conclusions drawn from reference plant analysis.

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SPT&C Meeting Minutes October 9, 1985 NOTE: Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 1717 H Street, N.W., Washington, D.C., or can be purchased from ACE-Federal Reports, 444 florth Capitol Street, Washing-ton, D.C. 20001, (202) 347-3700.

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