ML20246F949
| ML20246F949 | |
| Person / Time | |
|---|---|
| Issue date: | 12/02/1988 |
| From: | Remick F Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| RTR-REGGD-01.009, RTR-REGGD-1.009 ACRS-SL-0352, ACRS-SL-352, NUDOCS 8905150146 | |
| Download: ML20246F949 (3) | |
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION 8[/S;/8 g
ay ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 0
WASHINGTON, D. C. 20555 December 2, 1988 The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED F0P.TY-THIRD MEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, NOVEMBER 17-18, 1988 The Advisory Committee on Peactor Safeguards held its 343rd meeting, in Bethesda, Md., on November 17-18, 1988.
ACRS REPORTS / ACTIONS The Committee prepared its report on the Safety Evaluation Report for the " Power Reactor Inherently Safe Module" (PRISM) Design.
(Report to Chairman Zech dated November 22, 1988)
The report on this subject has been sent to you.
l OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS, AND REQUESTS The Committee was briefed by rnresentatives of the Staff on the Pro-posed Regulatory Guide 1.9, Revisior. 3, and prepared its letter on ACRS Action on Proposed Regulatory Guide 1.9, Revision 3, " Selection, Design, Qualification, Testing, and Reliability of Diesel Generator Units as Onsite Electric Power Systems at Nuclear Power Plants," (letter to Mr.
Stello dated November 22, 1988).
The Committee concurred in the NRC Staf r's proposal to issue this Guide for public comment and stated that it would review the proposed final version of this Guide after the public conment period, together with the public comments and the Staff's response to them.
The Committee prepared a letter on ACRS Action on Proposed Regulatory Guide, Task No. EE-006-5, " Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants," (letter to Mr. Stello dated November 22, 1988).
The Committee concurred in the regulatory position of this Guide.
Dr. Siess briefed the Committee on the nature of the NRC Staff's pro-posed revisions to Standard Review Plan Sections 6.5.2, 6.5.4, and 6.5.5.
The Committee decided that there is no need for further ACRS action on this matter.
Mr. Fraley has informed Dr. Murley of the Committee's decision.
(See letter from R. Fraley to T. Murley, dated bg November 23,1988.)
DESIGNATED ORIGINAL f.f6SS1202 CeetLt1e$ 37 (h//~$
SL-0352 PDC
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The Honorable Lando W. Zech, Jr.
2 December 2, 1988 The Committee continued its discussion.of.the NRC Staff's proposed ex-panded program for the in-situ testing of safety-related motor-operated valves. 'This subject will be discussed further at a future meeting of the Mechanical Components Subcommittee at which Industry representatives will present their views on the proposed program.
The, Nominating Panel, composed of Dr. Kerr, Mr. Ward, and Mr. Carroll, reported its nomination for Committee officers for 1989.
The election will be scheduled during the December 15-17, 1988 ACRS meeting. Nomina-tions for the Member-at-Large appointment to the Planning Committee and election of new officers will be completed during the December election.
The Committee discussed the status of new members and has forwarded an additional nomination for the Commission's consideration.
Since 'the last report of ACRS activities, the following subcommittee meetings have-been held:
Mechanical Components, October 26-27, 1988 The Subcommittee reviewed recent work related to valve reliability as part of its discussion of the NRC Staff's proposed new requirements for in-situ testing and surveillance of safety-related motor-operated valves.
Advanced Boiling Water Reactors, November 15-16, 1988 - The Subcom-mittee continued its review of this proposed standard plant.
FUTURE AGENDA The following items have been scheduled for consideration during the ACRS meeting on December 15-17, 1988:
Meeting with Director, NRC Office of Nuclear Regulatory Research -
Discuss topics of mutual interest, including the status of implementa-tion of recommendations of the National Research Council on Revitalizing Nuclear Safety Research and on Human Factors Research.
Quantitative Safety Goals - Review and comment on proposed NRC Staff plan for implementation of NRC's Safety Goal Policy.
Containment Systems - Review and comment on the proposed NRC recommenda-tions for improvements to the BWR Mark I containment.
Thermal-Hydraulic Phenomena - Review NRC Code Scaling Applicability and Uncertainty (CSAU) Evaluation Methodology proposed for use with best-estimate ECCS evaluation models.
l Equipment Qualification-Risk Scoping Study - Review and comment on the Equipment Qualification-Risk Scoping Study.
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, The Honorable Lando W. Zech, Jr.
3 December 2, 1988 3LaSalle Power Oscillation Event - Briefing regarding status of programs to address implice tions of the core power oscillation event which occurred recently at the LaSalle Nuclear Power Plant.
Reactor Operator Requalification - Briefing regarding lessons learned from revised operator qualification methodology.
Sodium Advanced Fast Reactor (SAFR) - Initial sessim to discuss the SAFR design.
ACRS Subcommittee Reports - Reports regarding status of assigned ACRS subcommittee activities, including thermal-hydraulic phenomena regarding status of joint NRC/B&W OTSG follow-on research program, the interna-tional conference on quality and quality assurance, and the visit to the Fermi Nuclear Plant.
Discuss anticipated ACRS subcommittee Anticipated ACRS Activities activities and topics proposed for consideration by the full Committee
Election of ACRS Officers - Discuss qualifications of members proposed as candidates for ACRS Officers for CY 1989 and conduct elections.
Meeting with Director. 0GPA - Report regarding exchaage of safety-related information.
Sincerely,
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Forrest J. Remick Acting Chairman l
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