ML19297C802
| ML19297C802 | |
| Person / Time | |
|---|---|
| Issue date: | 11/21/1980 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0256, ACRS-SL-256, TAC-46140, NUDOCS 8101080071 | |
| Download: ML19297C802 (3) | |
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t Honorable John F. Ahearne Chai rman U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
TWO-HUNDRED-FORTY-SEVENTH MEETING UF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, NOVEMBER 6-8, 1980
Dear Dr. Ahearne:
The Advisory Committee on Reactor Safeguards held its 247th meeting in Washington, DC on November 6-8, 1980.
Items considered at this meeting are summarized belcw:
The 2mmittee met with Governor Sruce Babbitt, Chairman of the Nuclear Safety Oversight Committee, to discuss methods to strengthen the ACRS' role in the regulatory process.
The Committee met with you and the other Commissioners to discuss clarifica-tion of Commissioner Gilinsky's reauest for ACRS' comments regarding procosed changes in the residual heat removal systn of the North Anna Power Station Unit 2, new safety concepts for future nuclear power plant designs, and de facto use cf cuantitative safety goals in the regulatory process.
The Committee met with representatives of the NRC Staff and the General Electric Comoany to discuss the seismic modifications and procosed operation of the General Electric Test Reactor (GETR).
The Committee met with members of the NRC Staff and representatives of Pacific Gas and Electric Company to discuss the study of potential systems interactions inducec by cossible seismic events performed for the Diablo Canyon Nuclear Power Plant.
The Committee continued its consideration of the proposed Nuclear Data Link.
The Committee responded to. Commissioner Gilinsky's memorandum of October 2, 1980 regarding the format of findings in ACRS reports on license applications.
The Ccamittee comcleted its review of Regulatory Guide 1.97, Instrumentation for Licnt-Water-Cooled Nuclear Pcwer Plants to Assess Plant and Environs conc;tions Dur nc anc -ollowinc an Accident.
Cocies of ne letters and memoranda pertaining to the above have been provided to you.
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2:e:-atle John F.
Ahearne November 21, 1980 The : mmittee me with members of the NRC Staf# to discuss the status Of the ef#crt Oc develop, a system to control ccmbustible gases for the Secucyah Nuclear Pcu=r :lant Uni Ore.
Additional v!ork on this matter is :lanned for future meetings.
Since the las: recor: of ACRS Activities, the folicwing site visits anc subccmmit-tee meetings have been held:
Site Visit
' Idaho Nuclear Engineering Laboratory, Idaho Falls, ID on October 21, 1980 ECCS, in Idaho Falls, ID cn October 22-23, 1980 Trans:cr:ation of Racicactive Materials, in Washing:cn, DC on October 27, 1980 7.eneral Electric Test Reactor in h' ashing: n, DC on November 4,1980 92;ulatory Activities, in Washing:On, DC on November 5, 19E0 P-ccedures and Administration, in 9?ashington, DC on Novem er 5,1980 The folicwing items are tentatively scheduled for consideratico during tne 248th ACPS eeting, December 4-6, 1980.
Three Mile Island "uclear Station Unit 1 -- Restart Regulatory Guides regarding Utilities Management Structure and Technical Suppor:
" orth Anna Power Station Unit 2 -- Consider installation of a heat exchanger in the High Pressure Injection System and environmental qualification of the Residual Heat Removal System, Plant Staffing, results of Augmented Low Power Test Program, Steam 3enerator Tube Integrity, and Probabilistic Assessment of the Plant Clarification of ACRS Report on ATWS per GE Request ACRS Generic Items List -- Update of list Hydraulic Scram System for BWR Nuclear Plants New Safety Concepts for future reactor designs NRC a'aste Confidence Droceeding -- Items needing further consideration
Honorable Jonn
. Ahearne November 21, 1980 Indian Point Station Unit 2 -- Cavity flooding incident / plant status Meeting with NRC Commissioners ACRS Review of Procedures for certification of shipping containers for radioactive materials.
ACRS Review cf Long Range Safety Research Program.
Sincerely yours,
/
Milton S. Plesset Chairman
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