ML20009B401
| ML20009B401 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, North Anna  |
| Issue date: | 05/18/1981 |
| From: | Mark J Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0262, ACRS-SL-262, NUDOCS 8107150373 | |
| Download: ML20009B401 (3) | |
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NUCLEAR REGUi.ATORY COMMISSION
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- c ADVISORY COMM11 TEE ON REACTOR SAFEGUARDS 8'
O WASHINGTON, D. C. 20555 g
May 18,1981 1
Honorible Joseph M. Hendrie Chairman U. S. Nuclear Regulat1ry Commission Washington, DC 20555
Subject:
TWO-HUNDRED-FIFTY-THIRD FIETING 0F THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, MAY 7-9, 1981
Dear Dr. Hendrie:
This report summarizes Committee activities since my last report to you of April 20,1981.
253rd ACRS Meeting The Advisory Committee on Reactor Safeguards held its 253rd meeting in Washington, DC on May 7-9, 1981.
Items considered at this meeting are summarized below.
The Committee completed its review of control system failures that could cause or exacerbate nuclear power plant accidents, responding to Commissioner Ahearne's Tetter of Decemt,W % 1980, and has provided its comments to you.
The Committee completed its review of the causes and implications of the Browns Ferry Nuclear Power Station Unit 3 partial-failure-to-scram, responding to Commissioner Ahearne's letter of December 12, 1980, and has provided its comments to you.
The Committee completed its review of the proposed modification to the North Anna Power Station Unit 2 Low Pressure In.iection and Residual Heat Removal Systems that were suogested in Commissioner Gilinsky's statement on the full power author-ization for that plant, dated August 20, 1980, and has provided its comments to you.
The Committee noted, in a memorandum to the Executive Director for Operations, its awareness of the need to develop requirements for an infrastructure of support-ing capabilities at nuclear plants including gocedures, infomation, and trained personnel.
The Executive Director for Operations has been infomed that the Committee has no objection to the NRC Staff's plan to increase the licensed power level for the Crystal River Nuclear Plant Unit 3 to levels up te 2544 MWt,.
l 8107150373 810518 PDR ACRS SL-0262 PDR
Honorable Joseph M. Hendrie May 18,1981 The Committee heard a report from members of the NRC Staff regarding the consideration of natural events in emergency planniqq for nuclear power plants.
The Committee heard a report from members of the NRC Staff regarding NRC interim requirements related to hydrogen control and certain degraded core conditions for nuclear power plants.
The Committee heard a report from an NRC Interoffice Steering Group representa-tive regarding the proposed NRC program for the development of quantitative risk criteria.
The Committee heard a report from representatives of the NRC Staff regarding the use of probabilistic assessment in support of licensing activities.
The Committee discussed with members of the NRC Staff the proposed scheduling of ACRS projec c reviews and the impact of such schedules on the NRC licensing /
hearing process.
The Cunmittee discussed the scope of and procedures for preparation of its annual report to the Commission on the FY 1983 Reactor Safety Research budget.
This matter will require further discussion and has been scheduled for the 254th ACRS Meeting, June 4-6, 1981 and the 255th ACRS Meeting, July 9-11, 1981.
The Committee briefly discussed a proposed response to questions frora Senator Alan Simpson, Chairman, Subcommittee on Nuclear Regulation regarding the NRC safety research program. Additional discussion of this reply has been scheduled for the 254th ACRS Meeting.
ACRS Subcommittee Activity Since the last report of ACRS activities, the following subcommittee meetings have been held:
Advanced Reactors, in Des Plaines, IL, on April 21-22, 1981 Fluid Dynamics, in San Francisco, CA on April 28-29, 1981 Shoreham Station (site visit only), in Riverhead, LI, NY on April 30, 1981 Site Evaluation, in Washington, DC on April 30-May 1,1981 Reactor Fuels and ECCS, in Washington, DC on May 5,1981 Decay Heat Removal Systems, in Washington, DC on May 5,1981 Safety Philosophy, Technology, and Criteria, in Washington, DC on May 6,1981 Babcock and Wilcox Weter Reactors, in Washington, DC on May 6,1981 l
I Honorable Joseph M. Hendrie May 18,1981 Future Schedule The following items are tentatively scheduled for consideration during the 254th ACRS Meeting, June 4-6, 1981:
ACRS comments regarding proposed rule on nuclear power plant siting, ACRS report to NRC on proposed FY-83 reactor safety research budget, Application of TMI-2 Lessons Learned to DOE Plants, Briefing regarding OTA report on standardization of nuclear facilities, Briefing by NRC Staff on thermal shock t.o reactor pressure-vessels from overcooling transients, Briefing by NRC Staff on the technical issues being considered in the Class-9 l
l accidents rulemaking, Reply to U. S. Senate Subcommittee on Nuclear Regulation regarding NRC research activities, Meeting with Commissioners to discuss OPE recommendation that generic studies should be deferred ir, favor of licensing actions and impact of Congressional action regarding FY-81 supplemental budget request, Briefing by NRC Staff on Westinghouse Corp. proposal regarding " leak-before-break" criteria in lieu of the instantaneous double-ended pipe break.
Sincerely yours, J. Carson Mark Chairman l
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