ML20205F034
| ML20205F034 | |
| Person / Time | |
|---|---|
| Issue date: | 05/30/1985 |
| From: | Ward D Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0310, ACRS-SL-310, NUDOCS 8511040174 | |
| Download: ML20205F034 (3) | |
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UNITED STATES v
NUCLEAR REGULATORY COMMISSION o
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- I ADVISORY COMMI'TTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 May 30,1985 Honorable Nunzio J. Palladino Chairman U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Dr. Palladino:
SUBJECT:
THREE HUNDRED AND FIRST MEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MAY 9-11, 1985 The Committee discussed the operational status of the Palo Verde Nuclear Generating Station Units 1, 2, and 3.
A letter regarding resolution of outstanding issues was approved and has been sent to you.
The Committee met with representatives of the NRC Staff to discuss a proposal from the National Academy of Sciences to conduct a study on human factors research needs in nuclear regulatory research.
Reports on the subjects noted above have been sent to you.
The Committee met with representatives of the NRC Staff to discuss the proposed amendment to 10 CFR 50 on " Emergency Planning and Preparedness for Production and Utilization Facilities" regarding the impact of earthquakes on emergency planning. ACRS coments regarding this matter have been scheduled for consideration during the 3C2nd ACRS meeting.
The Comittee met with representatives of the NRC Staff to review the adequacy of the proposed priority rankings of a remaining group of generic issues.
The Comittee's coments on the subject noted above have been provided to the Executive Director for Operations. A copy has been sent to you.
The Committee met with representatives of the NRC Staff, the Brookhaven National 1.aboratory, and the General Electric Company (GE) for a briefing on the application of GE for a forward-looking Final Design i
Approval for the GESSAR II design.
The Committee met with representatives of the NRC Staff to consider requirements for sabotage protection in future generation nuclear power plants.
The Committee was briefed by representatives of the Office of Inspection and Enforcement and NRC Regional Offices regarding recent operating occurrences at nuclear power plants, including a premature criticality event at the Virgil I.
Sumer Nuclear Plant, steam generator tube defects found during chemical cleaning of the secondary side of the steam generator at the Millstone Nuclear Plant, Unit 2, weld leaks in ultimate heat-sink piping at the Palo Verde Nuclear Generating Station, DESIGUATED GRIGIIIAL 8511040174 850530
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H:norable Nunzio J. Palladino '
Units 1, 2, and 3, and revisions to emergency diesel generator testing requirements for the North Anna Nuclear Plant, Unit 2.
The Committee met with representatives of the NRC Staff regarding the NRC Staff evaluation of the two-year trial period for quantitative safety goals and the related implementation plan.
The Comittee met with the Commissioners to discuss the proposed ACRS role in the civilian radioactive waste program.
The Committee discussed the issue of the reliability of PWR scram systems and assigned this matter to the ACRS Subcommittee on Scram System Reliability for further review and evaluation.
Subcommittee Activities Since the last report of ACRS activities, the following Subcommittee meetings have been held:
Combined Reactor Operations and Human Factors, in Atlanta, GA on April 17, 1985 to discuss INP0's evaluation of nuclear plant operations and incidents / accidents,
_ Reliability Assurance (valves?, in Washington, D.C. on April 23, 1985 to continue discussion from the March 19 meeting regarding methods to enhance the reliability of air-and motor-operated valves in nuclear plants.
Palo Verde, in Wintersberg, AZ on April 26, 1985 to review the final reports for various construction deficiencies and the results of the preoperational testing as requested in ACRS letter dated December 15, 1981, Class 9 Accidents, in Washington, D.C. on May 2, 1985 to be briefed on draft NUREG-0956, " Source Term Reassessment,"
Qualification Program for Safety-Related Equipment, in Washington, D.C. on May 6, 1985 to discuss RES programs for plant aging and equipment qualification, Reactor Operations, in Washington, D.C. on May 6,1985 to discuss recent operating occurrences, Safeguards and Security, in Washington, D.C. on May 7, 1985 to review the potential consequences of sabotage at nonpower reactors, be briefed by NMSS on sabotage protection at power reactors, and hear how the NRC Staff reviews and evaluates licensees' security plans.
Safety Research Program, in Washington, D.C. on May 8, 1985 to discuss the proposed NRC safety research program and budget for FY 1987 and gather information for use by the ACRS in its preparation of the annual report to the Commission on this matter,
Honorable Nunzio J. Palladino -
Safety Philosophy, Technology, and Criteria, in Washington, D.C. on May 8,1985 to review the status of the NRC Staff's evaluation of the trial use of the Consnission's proposed Quantitative Safety Goals.
Future Agenda l
l The following items are tentatively scheduled for consideration during the 302nd ACRS meeting, June 6-8, 1985:
Meeting with the E00 to discuss topics of mutual interest ACRS report on the proposed safety research program and budget for l
FY 1987 Proposed NRC Rules and Regulatory Guides--ACRS comments GESSAR II--Continue ACRS review for an FDA Evaluation of the Two Year Trial Use Period and Proposed Implementation of the NRC Safety Goals IE Inspection Program--General briefing on IE programs l
Consideration of Seismic Events in Emergency Planning ACRS Comments t
Decay Heat Removal Systems - ACRS comments regarding the decay heat removal system in CESSAR-80 type plants and its implementation S ncerel David A. Ward Chairman l
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