ML20246F933
| ML20246F933 | |
| Person / Time | |
|---|---|
| Issue date: | 01/09/1989 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Zech L NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-043, REF-GTECI-NI, TASK-043, TASK-43, TASK-OR ACRS-SL-0353, ACRS-SL-353, NUDOCS 8905150143 | |
| Download: ML20246F933 (3) | |
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20655 January 9, 1989 The Honorable Lando W. Zech, Jr.
Chairman U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Chairman Zech:
SUBJECT:
THREE HUNDRED FORTY-F0URTH MEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, DECEMBER 15-16, 1988 The Advisory Committee on Reactor Safeguards held its 344th meeting, in Bethesda,-Md., on December 15-16, 1988.
ACRS REPORT The Committee prepared its report on the Equipment Qualification-Risk Scoping Study.
(Report to Chairman Zech. dated December 20,1988,)
The report on this subject has been sc.nt to you.
OTHER ACTIONS, AGREEMENTS, ASSIGNMENTS AND REQUESTS The Committee was briefed by Mr. Harold Denton and Mr. James Taylor on the status of the activities being carried out under the Memorandum of Cooperation between the U.S. and the U.S.S.R. for matters relating to civilian nuclear reactor safety. Mr. Denton invited the ACRS to partic-ipate in this information exchange and to identify an ACRS liaison to work with the U.S. team.
Dr. Forrest J. Remick has been assigned to act as the ACRS liaison.
The Committee decided to review the NRC staff's proposal for a Commis-sion policy statement on additional applications of leak-before-break technology and provide comments on this matter.
A subcommittee meeting will be scheduled during February 1989 for discussion of this topic.
Committee action on this matter is expected to be completed during the February or March 1989 ACRS meeting.
The Committee was briefed by the NRC staff on the scope of and schedule for the issues associated with GE reactor core power oscillations. The Committee expressed concern as to the possibility of an ATWS combined with a power oscillation and will continue to follow the progress of the NRC staff's work.
The election of Committee officers for 1989 was held.
Dr. Remick was k50I elected as Chairman and Mr. Michelson was elected as Vice Chairman.
DESIGNATED ORIGIEAL Certitled By f/#0 o
Q' The Honorable Lando W. Zech, Jr. January 9, 1989 The Committee discussed the status of appointment of new members to the ACRS. A separate memorandum regarding the status of appointment of new members has been sent to you by the ACRS Executive Director.
(See memorandum from R. Fraley to Chaiman Zech, dated December 27,1988)
Since the last report of ACRS activities, the following subcommittee meetings have been held:
Containment Systems, December 6,1988 - The Subcommittee reviewed I
the NPC staff's recommendations for BWR Mark I containment perform-ance and improvements.
Thermal Hydraulic Phenomena, December 7.1988 - The Subcommittee reviewed the NRC-RES Technfcal Program Group on the Code Scaling, Applicability, and Uncertainty (CSAU) Evaluation Methodology and the report of the joint NRC/B&W Technical. Advisory Group on the need for follow-on research pertaining to thermal hydraulic phenom-ena associated with the B&W once-through steam generator.
Reliability Assurance, December 12, 1988 - The Subcommittee contin-ued its review of the Equipment Qualification-Risk Scoping Study with emphasis on the peer-review comments.
Advance Reactor Designs, December 13, 1988 The Subcommittee reviewed the draft Safety Evaluation Report for the SAFR design.
The Subcommittee Safeguards and Security, December 14, 1988 discussed safeguards at nuclear reactors and fuel facilities.
FUTURE AGENDA The following items were tentatively scheduled for consideration during the ACRS meeting on January 12-14, 1989:
Sodium Advanced Fast Reactor (SAFR) - Complete the ACRS discussion on and report on the preapplication review of this standardized plant.
Fitness for Duty - Review and report on the proposed NRC rule regarding fitness for duty of nuclear power plant operators.
Standard Design Certification and Combined Licenses for Nuclear Power Plants - Review and report on the proposed final version of 10 CFR Part 52 regarding Early Site Permits, Standard Design Certifications, and Combined Licenses for nuclear power plants.
Meeting with NRC Commissioner James Curtiss - Discuss topics of mutual interest regarding ACRS and NRC activities.
l ECCS - Complete the ACRS discussions and report on the proposed NRC Code TcaTing Applicability and Uncertainty Evaluation Methodology.
'The Honorable Lando W. Zech,'Jr. January 9, 1989 Containment Systems - Complete the ACRS discussion on and report on the NRC staff's proposed recommendations for a BWR Mark ~ I containment performance improvement program.
' NRC Quantitative iatety Goals - Complete the ACRS discussion on and report on the NRC staff's proposed plan for implementation of the NRC's Safety Goal Policy.
Generic Issue 43, " Air Systems Reliability" - Review and report on the proposed resolution of Generic Issue 43, " Air Systems' Reliability."
Nuclear Safety Research Program - Discuss the ACRS annual report to the U.S. Congress on the NRC safety research program.
New Members - Discuss qualifications of candidates proposed for consid-eration as nominees for appointment to the ACRS.
Accident 14anacement - Briefing regarding NRC staff's development of a program plan on severe accident management.
Sincerely, William Kerr Chairman
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