ML20138M806
| ML20138M806 | |
| Person / Time | |
|---|---|
| Issue date: | 11/09/1984 |
| From: | Ward D Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0304, ACRS-SL-304, NUDOCS 8511040426 | |
| Download: ML20138M806 (2) | |
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%*****p November 9, 1984 Honorable Nunzio J. Palladino Chairman U.S. Nuclear Regulatory Comission Washington, D.C.
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Dear Dr. Palladino:
SUBJECT:
TWO-HUNDRED NINETY-FIFTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, NOVEMBER 1-3, 1984 295th ACRS Meeting The Comittee met with representatives of the hRC Staff and Philadelphia Electric Company (Applicant) to review the application for an Operating License for the Limerick Generating Station, Units 1 and 2.
A report on this matter has been sent to you.
The Committee discussed Comissioner J. K. Asselstine's request for ACRS comments regarding the frequency and severity of severe core damaging accidents. The Committee's comments on this subject have been sent to you, to Commissioner Asselstine, and to the other Commissioners.
The Comittee was briefed by representatives of the NRC Staff regarding use of hydrogen addition for primary system water chemistry in boiling water rea ctor_s_.
The Comittee was briefed by J. M. Taylor, Deputy Director, IE, regarding the organizational status and activities of the NRC Office of Inspection and Enforcement.
The Comittee discussed with representatives of the NRC Staff proposed amendments to the Comission's emergency preparedness regulations (10 CFR Part 50, 50.47 and Appendix E) to explicitly state that consideration of potential impacts of earthquakes on energency planning for nuclear power plant sites is not required.
Additional ACRS consideration of this matter it planned.
The Comittee met with the Comissioners to discuss the proposed NRC policy statement on consideration of severe core damage in nuclear power plant regulation.
Subcommittee Activities Since the last report of ACRS activities, the following subcommittee meetings have been held:
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Certified By PDR
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Honorable Nunzio J. Palladino November 9,1984 Emergency Core Cooling Systems, in Washington, D.C. on October 16-17, 1984 to continue its review of the joint NRC/ Babcock and Wilcox Owners Group /B&W/EPRI integral test program Combined GESSAR II/ Reliability and Probabilistic Assessment, in Los 18-19, 1984 to review the General Electric Standard Angeles, CA on October Safety Analysis Report to extend the Final Design Approval so that it will be applicable to future plants Combined Reliability and Probabilistic Assessment and Limerick Station, in Los Angeles, CA on Octbber 20, 1984 to continue review of the probabilistic risk assessment for the Limerick Plant Future Agenda The following iteris are tentatively scheduled for consideration during the 296th ACRS meeting, December 13-15, 1984:
Hope Creek Generating Station--OL review Yankee Nuclear Power Station, Appendix K exemption--ACRS comments San Onofre Nuclear Generating Station Unit 1--ACRS comments regarding seismic upgrade RSR Report to Congress for FY 1986-87 Program and Budget--discuss proposed chapter NRC Staff Briefing on " Steam Generator" Overfill--ACRS comments NRC Task Force report on two-year trial use of the proposed safety goal--NRC Briefing /ACRS coments as appropriate NRC Staff briefing on Fire Protection Steering Comittee Report--NRC briefing /ACRS coments as appropriate Meeting with Director, NMSS, briefing regarding NMSS activities i
l Regulatory Guide 1.82, Rev.
- 1. Emergency Core Cooling and Containment i
Sumps--ACRS comments Fire protection in nuclear facilities--discuss report of NF. Steering Comittee, ACRS comments as appropriate Sincerely.
David A. Ward Vice-Chairman i
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