ML20138M804

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Summarizes ACRS 280th Meeting on 840510-12 W/Nrc Seismic Qualification Utils Group & Senior Seismic Review & Advisory Panel Re Status of USI-46 Concerning Seismic Qualification of Equipment in Operating Plants
ML20138M804
Person / Time
Issue date: 05/29/1984
From: Ebersole J
Advisory Committee on Reactor Safeguards
To: Palladino N
NRC COMMISSION (OCM)
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR ACRS-SL-0298, ACRS-SL-298, NUDOCS 8511040425
Download: ML20138M804 (3)


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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS Q

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hay 29, 1984 Honorable Nunzio J. Palladino Chairman U.S. Nuclear Regulatory Commission Washington, D.C.

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Dear Dr. Palladino:

SUBJECT:

TWO-HUNDRED EIGHTY-NINTH NEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS,itAY 10-12, 1984 289th ACRS tieeting The Comittee met with representatives of the NRC Staff, the Seismic Qualification Utilities Group (SQUG), and the Senior Seismic Review and Advisory Panel (SSRAP) to discuss the status of USI A-46 (Seismic Qualification of Equipment in Operating Plants) and its proposeo resolution including the use of past earthquake experience data to show seismic ruggedness of certain classes of nuclear power plant equipment.

A report on the subject noted above has been sent to you.

The Committee discussed Proposed Amendments to 10 CFR Part 20 to Specify Residual Radioactive Contamination Limits for Decommissioning.

The Committee met with representatives of the NRC Staff and representatives of General Electric Company to discuss the General Electric SAFER /GESTR-LOCA ECCS Evaluation fiodel.

The Comittee reviewed the adequacy of the NRC Staff's assignment of priority rankings to a group of new generic issues.

The Comittee was briefed by representatives of the NRC's Office for Analysis and Evaluation of Operational Data (AE00) on AEOD's Trends and Patterns Program Plan. The ACRS wishes to be kept informed of the results of this program.

The Committee's comments on the subjects noted above have been provided to the Executive Director for Operations. Copies have been sent to you.

The Committee was briefed by representatives of the NRC Staff regarding the status of the NRC's Maintenance Program Plan.

The Comittee was briefed by representatives of the NRC Staff regarding operating experience dealing with stub tube leaks at Nine Mile Point 1, removal, replacement and examination of recirculation 3iping at !!onticello, and failure of a steam generator safety relief va' ve to close at the Davis-Besse Nuclear Plant.

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Honorable Nunzio J. Palladino May 29, 1984 The Comittee was briefed by representatives of the NRC Staff regarding the status of the implementation plan for Regulatory Guide 1.97, Revision 2, instrumentation to follow the course of a serious accident.

Subcommittee Activities Since the last report of ACRS activities, the following meetings have been held:

Emergency Core Cooling Systems (ECCS), in Washington, D.C. on April 24, 1984 to continue its review of the General Electric ECCS Evaluation Model Code known as SAFER Qualification Program for Safety-Related Equipment, in Washington, D.C. on April 25, 1984 to discuss qualification and maintenance of electrical teminal blocks and the proposed resolution of A-46, Seismic Qualification of Equipnent in Operating Plants Air Systems, in Washington, D.C. on April 26, 1984 to review general design provisions for chilled water systems, the NRC Staff's assignment of priority for resolution of Generic Safety Issue 43 regarding contamination of instrument air lines, NRC Staff proposed amendments to 10 CFR Part 20 regarding residual contamination limits for decommissioning, and other related topics Combined Extreme External Phenomena and Engineering / Seismic Design of Structural Piping, in Washington, D.C. on April 26, 1984 to discuss the NRR/RES plans for seismic design research programs Class 9 Accidents, in Washington, D.C. on April 27, 1984 to discuss the final Severe Accident Policy Statement, alternatives to the Power Burst Facility Phase II Test Program, and Quantitative Uncertainty Estimates for the Source Tem Emergency Core Cooling Systems, in Washington, D.C. on May 2, 1984 to continue its review of the joint NRC/B&W Owners Group /B&W/EPRI integral test program Reactor Operations, in Washington, D.C. on May 3, 1984 to review NRC's Office for Analysis and Evaluation of Operational Data's Trends and Patterns Program Plan.

Maintenance Practices and Procedures, in Washington, D.C. on May 8, 1984 to review the NRC Integrated Haintenance Task Action Plan and continue review of maintenance practices and procedures Safety Research Program, in Washington, D.C. on May 9,1984 to review the proposed NRC Safety Research Program and Budget for FY 1986 and 1987 and l

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Honorable Nunzio J. Palladino May 29, 1984 gather information for.use by the ACRS in preparation of its report to =the Commission on the program Future Agenda The following items are tentatively scheduled for consideration during the 290th ACRS meeting, June 14-16, 1984:

Severe Accident Policy--ACRS comments on revised policy statement Diablo Canyon huclear Power Plant--ACRS response to Commission request for comments on the proposco license condition concerning seismic reevaluation of the Diablo plant and on the nature of the Hosgri fault Proposed Amendment to Part 50 to Limit the Use of High-Enriched Uranium in Non-Power Reactors and Steps for Improving Security Measures at Non-Power Reactors--ACRS comments in response to the Commission request for Connittee views on these natters NRC Reactor Safety Research Program and Budget--ACRS Report to the Commission regarding the proposed FY 1986/87 RSR program and budget Regulatory Guide 1.35, Rev. 3, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments--ACRS comments Regulatory Guide 1.35.1, Determining Prestressing Forces for Inspection of Prestressed Concrete Conta, nent Structures--ACRS comments Sincerely,

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