ML20246F903
| ML20246F903 | |
| Person / Time | |
|---|---|
| Issue date: | 02/27/1989 |
| From: | Remick F Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0355, ACRS-SL-355, NUDOCS 8905150133 | |
| Download: ML20246F903 (3) | |
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,E - ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
, $ WASHINGTON, D. C. 20666 February 27, 1989 ;
The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED FORTY-SIXTH MEETING 0F THE ADVISORY COMMITTEE ON '
REACTOR SAFEGUARDS, FEBRUARY 9-11, 1989-ACRS REPORTS The Committee prepared its annual ACRS Report to the Congress on the Safety Research Program of the Nuclear Regulatory Commission (reports to the Hon. J. Danforth Quayle and the Hon. Jim Wright dated February 17, 1989).
The Committee prepared its report on Further ACRS Coments on Implemen-tation of the Safety Goal Policy (report to Chairman Zech dated February 16, 1989).
The Comittee prepared its repor_t on the Final Rule on Standardization and Licensing Reform, 10 CFR Part 52, "Early Site Permits; Standard ,
I Design Certifications; and Combined Licenses for Nuclear Power Plants" (report to Chairman Zech, dated February 15, 1989).
The Committee prepared its report on the Proposed Resolution of Generic Issues 70, " Power Operated Relief Valve and Block Valve Reliability,"
and 94, " Additional Low-Temperature Overpressure Protection for LWRs" (report to Chairman Zech dated February 16, 1989).
The Committee provided Further ACRS Comment on Proposed Resolution of Generic Issue 99, "Im) roved Reliability of RHR Capability in PWRs" (report to Chairman Zeci dated February 16, 1989).
l Copies of these reports have been sent to you.
OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS The Committee discussed a request from Cleveland Electric Illuminating Company to postpone completion of its Seismic Margins Evaluation Program for the Perry Nuclear Power Plant to the end of the third refueling f Sol t i g 51 g 3 890227 DESIGNATED caror3AL SL-0355 PDC ,, g l
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1 The Honorable Lando W. Zech, Jr. February 27, 1989 1
outage. (The Committee had previously recomended that this be done by the end of the second refueling outage in its July 13, 1982 report.)
The Committee the Seismic Marginshad no objection Evaluation to this Program p(postponement memorandum of thetocompletion from R. Fraley V. of Stello dated February 21,1989).
The Committee discussed the NRC staff's proposed Policy Statement on the application of leak-before-break technology (SECY-88-325, dated November _
22, 1988). The . Committee expects to continue these discussions and report to the Commission during the March 9-11, 1989 ACRS meeting (letter to you from Forrest J. Remick dated February 15,1989).
The Committee endorsed a recommendation to reappoint Dr. Paul Shewmon to the ACRS upon expiration of his current term. A memorandum recommending his reappointment has been forwarded to you.
Your request that the Committee prepare a report on the composition and personnel needs of the ACRS in light of the issues to be considered by the Committee over the next year is scheduled for discussion during the March 9-11, 1989 ACRS meeting.
Since the last report of ACRS activities, the following subcommittee meetings have been held:
Human Factors, January 26, 1989 - The Subcommittee discussed the Human Factors Research Program Plan.
- Mechanical Components, January 27, 1989 - The Subcommittee dis-cussed the NRC staff-proposed resolution of Generic Issues 70,
" Power Operated Relief Valve and Block Valve Reliability," and 97,
" Additional Low-Temperature Overpressure Protection for LWRs."
Safety Research, February 8,1989 - The Subcommittee discussed the ongoing and proposed NRC safety research program and budget.
FUTURE AGENDA The following items are scheduled for consideration during the ACRS meeting on March 9-11, 1989:
Severe Accident Research Program - ACRS review and comment regarding i
proposed NRC Severe Accident Research Program Plan. ,
Application of Leak-Before-Break Technology - ACRS review and comment on the proposed NRC policy regarding application of the leak-before-break i technology to ECCS design and environmental qualification of components.
Peach Bottom Nuclear Plant - Review and comment on the proposed restart of this plant, i
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The Honorable Lando W. Zech,' Jr. February 27, 1989 i
Use of Safety Goals - Discuss proposed ACRS comments / recommendations regarding the use of Safety Goals for evaluation of the effectiveness of NRC regulations in protecting the'public health and safety.
Containment Design Criteria - Discuss proposed ACRS activities regarding development of containment design criteria for future ~ nuclear power plants.
Meeting with ED0 - Discuss peer review /use of NUREG-1150, " Reactor Risk 1 Reference Document," and other items of mutual interest.
Sincerely, Forrest J. Remick Chairman 1
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