ML20205F077
| ML20205F077 | |
| Person / Time | |
|---|---|
| Issue date: | 10/29/1984 |
| From: | Ebersole J Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR ACRS-SL-0303, ACRS-SL-303, NUDOCS 8511040303 | |
| Download: ML20205F077 (3) | |
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NUCLEAR REGULATORY COMMISSION o
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E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS Y
WASHINGTON, D. C. 20555
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October 29, 1984 Honorable Nunzio J. Palladino Ch innan U.S. Nuclear Regulatory Comission Washington, D.C.
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Dear Dr. Palladino:
SUBJECT:
TWO-HUNDRED NINETY-FOURTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, OCTOBER 11-13, 1984 294th ACRS Meeting The Comittee met with representatives of the NRC Staff and its contractor, the Oak Ridge National Laboratory, to review the NRC final rule on the analysis of potential pressurized thermal shock (PTS) events.
The Comittee met with representatives of the NRC Staff to discuss experience levels required for reactor operators.
The members expressed concern that probabilistic risk analyses (PRAs) submitted in connection with applications for future final design approvals and standardized nuclear power plant designs are controlled as proprietary documents.
The Committee met with representatives of the NRC Staff to discuss a proposed backfit rulemaking to replace the current Backfit Rule (50.109) and draf t Manual Chapter 0514 designed to control backfits on operating reactors.
Reports on the subjects noted above have been sent to you.
The Comittee continued its review of the NRC Staff's evaluation of generic safety issues to identify new unresolved safety issues.
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The Comittee heard a report of its Subcomittee on Reactor Radiological Effects concerning the NRC Staff response to earlier Comittee coments regarding residual contamination limits for decomissioned nuclear facilities.
A supplement to its report of May 14, 1984 regarding this topic was completed.
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 Comittee was briefed by representatives of the NRC Staff (IE) regarding recent operating occurrences at nuclear power plants including a reactor coolant pump failure at the Palisades Nuclear Power Plant, thermal transient damage to the feedwater piping support system at WNP 2, and the effects of Hurricane Diana at the Brunswick Steam Electric ' Plant Units 1 and 2.
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7 H:n:rable Nunzio J. Palladina
- s The Comittee was briefed by H. Denton, Director, NRR, regarding NRR activities associated with near term operating licenses, INP0 accreditation of utility training programs, fire protection, and technical specifications.
Subcommittee Activities Since the last report of ACRS activities, the following subcommittee meetings have been held:
Combined Reactor Radiological Effects /Humboldt Bay, in Eureka, CA on September 10, 1984 to visit the Humboldt Bay site and review the plant's decommissioning plans and procedures Quality and Quality Assurance in Design and Construction, in Washington, D.C. on September 11, 1984 to discuss the adequacy of quality assurance and quality control personnel at nuclear power plants during construction, and the use of designated representatives in QC practices Metal Components, in Washington, D.C. on September 14, 1984 to review the status of BWR pipe cracking, aging of metal components, and other related matters Fire Protection, in Washington, D.C. on September 26, 1984 tc discuss the potential for damage to safety related equipment from inadvertent actuation of the fire protection system Reactor Radiological Effects, in Washington, D.C. on September 27-28, 1984 to be briefed on (1) the status of USI 111.D.3.1, Radiation Protection Plan and other generic safety issues; and (2) NRC Staff's evaluation of TMI-2 cleanup endpoint alternatives. KRC Staff proposed amendments to 10 CFR 20 to specify residual radioactive contamination limits were also discussed Maintenance Practices ano Procedures, in Seattle, WA on October 2,1984 to review a Battelle Human Factors Division review of maintenance practices in Japan Reactor Operations, in Washington, D.C. on October 9,1984 to review recent experiences at operating nuclear power plants
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Combined Reliability and Probabilistic Assessment / Limerick, in Washington, l
D.C. on October 9-10, 1984 to begin the review of probabilistic risk assessment (PRA) for the Limerick plant and to complete the review of outstanding items on the Limerick operating license (OL) review Human Factors, in Washington, D.C. on October 10, 1984 to explore experience levels of reactor operators, especially at new plants scheduled to come on line. Updates on activities such as the training and qualifications package and the Human Factors Program Plan were also discussed I
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l Honorablo Nunzio J. Palladino.
Future Agenda The following items are tentatively scheduled for consideration during the 295th ACRS meeting, November 1-3, 1984:
IE Activities--Briefing by Director, Office of Inspection and Enforcement Limerick Nuclear Power Station--Complete OL review and discuss PRA ACRS response to inquiry from Comissioner Asselstine regarding Class-9 Accidents Briefing by NRC Staff on water chemistry control in BWR nuclear plants erel
% y,6. GLA Jesse C. Ebersole Chairnan
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