ML20245J548
| ML20245J548 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1989 |
| From: | Remick F Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0354, ACRS-SL-354, NUDOCS 8903090154 | |
| Download: ML20245J548 (3) | |
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- ,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASM
- 4GTON, D. C. 20555 l
January 31, 1989 The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Comission 1-Washington, D.C. 20555
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED FORTY-FIFTH MEETING 0F THE ADVISORY COMMITTEE ON
' REACTOR SAFEGUARDS, JANUARY 12-14, 1989 The Advisory Comittee on Reactor Safeguards held its 345th meeting in Bethesda, Md., on January 12-14, 1989.
ACRS REPORTS The Committee was briefed by representatives of the NRC staff and prepared a report on the proposed Mark I Containment Performance Im-provement Program.
(Report to Chairman Zech, dated January 19, 1989)
The Committee was briefed by representatives of the NRC staff and prepared a report Resolution of Generic Issue 43, " Air Systems Reliabil-ity."
(Report to Chairman Zech dated January 19, 1989)
The completed its report on the Safety Evaluation Report for the Sodium Advanced Fast Reactor (SAFR) Design.
(Report to Chairman Zech dated January 19, 1989)
The Comittee prepared a report on NUREG-1150:
Resolution of ACRS Coments.
(Report to Chairman Zech dated January 23, 1989)
The Committee completed its report on Code Scaling, Applicability, and Uncertainty (CSAU) Methodology for Determination of Uncertainty Assoc 1-ated with the Use of Realistic ECCS Evaluation Models.
(Report to Chairman Zech dated January 19, 1989)
The Comittee was briefed by representatives of the NRC staff and prepared a report on Draft Final Rule on Standardization and Licensing Reform,10 CFR 52, "Early Site Permits; Standard Design Certifications; and Combined License for Nuclear Power Reactors." (Report to Chairman Zech dated January 19, 1989)
The reports on these subjects have been sent to you.
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. e The Honorable Lando W. Zech, Jr. January 31, 1989 OJi3 ACTIONS, AGREEMENTS, AND REQUESTS The Committee continued its discussion of its draft report on the Safety Goal Policy Implementation Plan but was unable to complete the. report during this meeting.
Additional time will be scheduled during the--
February 9-11, 1989 ACRS meeting to complete this report.
4 The Committee decided not to comment on the proposed 10 CFR Parts 50 and 55 rule on " Education and Experience Requirements for Senior Reactor Operators and Supervisors at Nuclear Power Plants" until after the public comments have been received and resolved by the NRC staff.
The EDO has been informed of this decision.
(See letter from R. Fraley to V. Stello dated January 23,1989.)
I The Committee discussed tre status of new members and plans to publish a public announcement calling for nomination of candidates for ACRS mem-bership.
Since the last report of ACRS activities, the following subcommittee meetings have been held:
Regional Programs, January 5-6, 1989 - The Subcommittee discussed the activities being carried out by the Region IV Office.
Improved Light Water Reactors, January 10, 1989 - The Subcommittee reviewed the proposed final version of 10 CFR Part 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants."
Auxiliary and Secondary Systems, January 11, 1989 - The Subcomit-tee discussed the design of air systems, problems experienced by utilities with these systems, industry activities to improve the performance of such systems, and the proposed resolution of Generic Issue 43, " Air Systems Reliability."
Mechanical Components, January 11, 1989 - The Subcommittee con-tinued its discussions of air-operated valve testing and operating experience.
FUTURE AGENDA The following items have been scheduled for consideration during the ACRS meeting on February 9-11, 1989:
l Nuclear Safety Research Program - Discuss the proposed ACRS annual report to the U.S. Congress regTr' ding the NRC safety research program.
Severe Accident Policy for Future LWRs - Briefing by NRC staff regarding implementation of severe accident policy for future light-water reac-tors.
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.The Honorable Lando W. Zech,.Jr. January 31, 1989 Decay Heat Removal _ - Briefing and discussion regarding the proposed-resolution of ACRS comments related to' the provisions' for containment closure during..mid-loop operation at nuclear power plants.
Resolution of Generic Issues - Review and report on the proposed resolu-tion of Generic Issue 70, "PORV Reliability," and Generic Issue 94, " Low Temperature. 0 overpressure Protection."
NRC Safety Goal Implementation Plan _ - Discuss 'the proposed ACRS report regarding.the proposed position of the staff for the implementation of the NRC safety goals.
Containment Design Criteria - Discuss the ACRS' position on containment design criteria.
' Application of the Leak-Before-Break Concept - Discuss the proposed NRC position on the limitation regarding. application of the Leak-Before-Break concept.
Sincerely, Forrest J. Remick Chairman
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