ML20205F072
| ML20205F072 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/20/1984 |
| From: | Ebersole J Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0302, ACRS-SL-302, NUDOCS 8511040296 | |
| Download: ML20205F072 (3) | |
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o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION
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E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS P
WASHINGTON, D. C. 20555 September 20, 1984 H morable Nunzio J. Palladino Cnairman U.S. Nuclear Regulatory Comission Washington, D.C.
20555
Dear Dr. Palladino:
SUBJECT:
TWO-HUNDRED NINETY-THIRD MEETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, SEPTEMBER 6-8, 1984 293rd ACRS Meeting The Comittee met with representatives of the NRC Staff, Northeast Nuclear Energy Company (Applicant), Westinghouse Electric Corporation, and Stone &
Webster Engineering Corporation to review the application for an Operating License for the Millstone Nuclear Power Station Unit No. 3.
A report on this station has been sent to you.
The Comittee met with representatives of the NRC Staff, the Electric Power Research Institute (EPRI), and the Atomic Industrial Forum (AIF) to review and coment on the proposed EPRI Categorization of Generic Safety Issues and Licensing Issues regarding their applicability to future standardized nuclear power plant designs.
The Comittee took cote of its increasing involvement in NRC review and evaluation of DOE activities related to the identification, characterization, and licensing of geologic repositories for high-level waste disposal.
Members concluded that a specified procedure for conduct of this work would be helpful, The Comittee discussed the topic of steam generator overfill and the i
status of work related to this issue.
Additional comittee activity is l
planned with respect to this matter.
The Comittee's coments on the subjects noted above have been provided to the Executive Director for Operations.
Copies have been sent to you.
The Comittee discussed the request by H. B. Rosenthal, DOE, Office of Nuclear Safety, for suggestions regarding prominent experts for support to the DOE Assistant Secretary for Policy, Safety, and Environment (ASPE) on ASPE safety-related activities.
A reply to this request from the ACRS Executive Director has been sent to Mr. Rosenthal.
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The Comittee met with representatives of the NRC Staff to discuss the Interim Plan and Procedures for the Hanagement of Plant-Specific Backfitting of Operating Power Reactors (NRC Manual Chapter 0514). Action l
on this matter has been deferred to the 294th ACRS meeting (October 1984).
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r H:norable Nunzio J. Palladino September 20, 1984 i
I The Comittee discussed proposed ACRS coments in response to Comissioner J. K. Asselstine's inquiry regarding the frequency and severity of Class 9-type accidents related to the Staff's proposed Severe Accident Policy Statement. Additional discussion of this item is planned by the Comittee.
i The Comittee met with the Executive Director for Operations to discuss the relationship of the NRC Staff with organizations such as INPO, the need for a safety research base program, and the need for an NTSB type organization to evaluate nuclear power plant incidents / accidents.
t The-Comittee was briefed by representatives of the NRC Staff (IE) regarding recent operating occurrences at nuclear power plants including a refueling cavity water loss at the Haddam Neck Nuclear Plant, an overpressurization of the core spray system at Browns Ferry Unit 1, thermal transient damage to a feedwater line at Washington Public Power Supply _
System Nuclear Unit 2, a leak from the upper head injection system at McGuire Nuclear Station Unit 2, flooding of the component cooling water pump room at.Jndian Point Nuclear Facility Unit 2, a loss of decay heat removal at Arkansas huclear One Unit 2,
and a reactor vessel flaw indication at Indian Point Nuclear Facility Unit 2.
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The Comittees met with representatives of the NRC Staff to discuss the l
evaluation of hiiih-priority generic safety issues as potential new l
Unresolved Safety
,ssues.
Additional discussion of this matter is planned during the 294th ACR5 meeting.
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l Subcomittee Activities Since the last report of ACRS activities, the following subcomittee meetings have been held:
Combined Millstone Nuclear Power Station Unit 3/ Reliability and Prcbabilistic Assessment, in Windsor Locks, Hartford, CT on August 28-29, 1984 to' review the appitcation for an operating license by the Northeast Nuclear Energy Company for Millstone Unit No. 3 and the associated PRA Regulatory Policies and Practices, in Washington, D.C. on September 4,1984 to review experience with the interim backfit procedures now in effect and any revisions resulting from public coments l
Regulatory Policies and Practices, in Washington, D.C. on September 5, 1984 to consider recomendations to the Comission concerning the establishment l
of an NTSB-like body for nuclear power plant safety i
Safety Philosophy, Technology and Criteria, in Washington, D.C.
on September 5,1984 to discuss the EPRI categorization of the NRC Staff's Generic Safety and Licensing Issues and their application to standardized i
nuclear plants j
Future Agenda The following items are tentatively scheduled for consideration during the I
294th ACRS meeting, October 11-13, 1984:
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Honorable Nunzio J. Palladino Septemb:r 20, 1984 e Backfitting of nuclear power plants--ACRS coments regarding proposed changes to Manual Chapter 0514, NRC Program for Managerrent of Plant-Specific Backfitting of Operating Power Plants e Qualifications of nuclear power plant operators--ACRS coments regarding requirements for operator experience e Meeting with Director, NRR--Discuss items of mutual interest e Selection of new Unresolved Safety Issues--discuss NRC staff categorization of unresolved generic issues e PTS Research--NRC briefing on results of recent experiments regarding pressurized thermal shock and proposed NRC rule on PTS e Recent Occurrences at Operating Nuclear Facilities--reports and discussions with NRC representatives e Meeting with NRC Comissioners--need for an NTSB type board to investigate nuclear accidents Sincerely,
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Jesse C. Ebersole Chaiman
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