ML20138P969

Summarizes ACRS 296th Meeting W/Nrc & Util to Review Application for OL for Hope Creek Generating Station,Unit 1.Clarification of ACRS Congressional Testimony Re Proposed Rule to Limit Use of Highly Enriched U Also Discussed

ML20138P969
Person / Time
Site:	Hope Creek
Issue date:	12/20/1984
From:	Ebersole J Advisory Committee on Reactor Safeguards
To:	Palladino N NRC COMMISSION (OCM)
References
ACRS-SL-0305, NUDOCS 8511140197
Download: ML20138P969 (3)

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$b $$d5 sm p%r gy.rf m'o, UNITED STATES 89 e NUCLEAR REGULATORY COMMISSION 3- $ ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 0 .[ W ASHINGTON, D. C. 20555

%,*****/ December 20, 1984 Honorable Nunzio J. Palladino Chairman U.S. Nuclear Regulatory Comission Washington, D.C. 20555

SUBJECT:

TWO-HUNDRED NINETY-SIXTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS 296th ACRS Meeting The Co=ittee met with representatives of the NRC Staff and the Public Service Electric and Gas Company (the Applicant), acting on behalf of itself and acting as agent for the Atlantic Citj Electric Company, to review the application for an Operating License for the Hope Creek Generating Station, Unit 1. A report on this matter has been sent to you.

The Comittee discussee the request by F. P. Gillespie. Director, Division of Risk Analysis and Operations, Office of Nuclear Regulatory Research, for clarification of ACRS Congressional Testimony relating to the proposed rule te limit the use of highly enriched uranium in research and test reactors.

A reply to this request has been sent to F. P. Gillespie. A copy has been sent to you.

The Committee discussed the fact that Regulatory Guide 1.52 on design, testing, and raintenance for post-accident HVAC systems ooes not cover the full range of problems involved, nor does it provide adequate coverage of the specific issues associated with control roons. Tne Comittee's cements on this subject have been provided to the Executive Director for Operations. A copy has been sent to you.

The Cemittee was briefed by representatives of the NRC Staff on the recomendations of the Fire Protection Policy Steering Cemittee on fire protection in nuclear power plants.

The Comittee ret with representatives of the NRC Staff to discuss the results of the two-year trial use of quantative safety goals.

The Comittee selected D. A. Ward and H. W. Lewis as its Chairman and Vice Chairmar., respectively, for CY 1985.

Subcomittee Activitics Since the last repcrt of ACRS activities, the following Subcomittee rieetings have been held:

. Metal Components, in Washington, D.C. on Noverber 8-9,19C4 to review a craf t report entitled, " Report of the U.S. NuclearJg,ulatory MAI c.ct m a er P '

Honorable Nunzio J. Palladino December 20, 1984 Commission Piping Review Committee, Vol. III: Evaluation of Potential for Pipe B reaks ," t.UREG-1061, Vol. III, dated September 1984; to discuss degraded bolting; and to review the RES materials and metallurgy program and budget e Combined Reactor Operations / Reliability and Probabilistic Assessment, in Washington, D.C. on November 14, 1984 to discuss the current status cf work related to steam generator overfill and systems interaction, and of the NRC Staff's work on the generic issue related to " piping and use of highly combustible gases in vital areas" e San Onofre Unit 1, in Washington, D.C. on November 26, 1984 to discuss tne NRC Staff's review of the seismic upgrade of the San Onofre Nuclear Generating Station Unit 1 e Hope Creek Generating Station Unit 1, in Philadelphia, PA on hovember 28-29, 1984 to review the operating license application of the Public Service Electric and Gas Company for the Hope Creek Generating Station e Emergency Core Cocling Systems in Washington, D.C. on November 28-29, 1984 to review: (1) hhC's thermal-hydraulic research programs, (2) the Yankee Atomic Electric Cenpany's request for an exemption to Appendix K to 10 CFR 50.46, (3) analysis work performed on behalf of NRR as part of the ATWS resolution effort, (4) the Westinghouse Owners Group Steam Generator Tube Rupture Program, (5) the hRR review of Westinghouse and Exxon Nuclear Corporation Evaluation Models for Westinghouse upper plenun injection plants, and (6) the status of resolution efforts for USI A-43, "Containrent Emergency Sump Performance " and the development of associated Regulatory Guide 1,82 o Air Systems, in Washington, D.C. on November 29, 1984 to review the repcrt of the hRC Horking Group on Control Room Habitability e Combined Reactor Radiological Effects and Waste Management, in Washington, D.C. on Noverber 30 and December 1,1954 to review research programs in the areas of: chemical engineering (process con t rol ) ,

occupational raciation protection, high- and low-level waste management, emergency planning, health effects, and meteorology and hydrology c Ccr.bined GESSAR II/ Reliability and Prctabilistic Assessment, in Los Angeles, CA on Decenber 4-5, 19E4 to review the General Electric Standard Safety Analysis Report to extend the Final Design Approval so that it will be applicable to future plants e Human Factors, in Washington, D.C. on December 11, 1984 to review the status of Huran Facters Research and the results of the kRR Human Factors Program Plan e Safety Philosophy, Technoloqy, and Criteria, in Washington, D.C. on Decerter 12, 1964 to discuss the i,R6 Staf f's draf t report on the results of the two-year trial use period for the proposed safety goals

t Honorable Nunzio J. Palladino December 20, 1984 Future Agenda The following items are tentatively scheduled for consideration during the 297th ACRS meeting, January 10-12. 1985:

e Regulatory Guide 1.28, Rev. 3, Quality Assurance Program Requirements (Design and Construction)--ACRS coments e Rulemaking regarding 10 CFR 50.47, Emergency Preparedness and Appendix E Consideration of seismic events and tornadoes--ACRS concents e Backfitting Requirements--ACRS comments regarding proposed NRC backfitting requirements for nuclear power plants e Discuss proposed ACRS report to the U.S. Congress on the NRC Safety Research Program and Budget for FY 1986-87 e Discuss recent events at operating reactors--ACRS comments e Chilled water systems in nuclear plants--ACRS comments regarding the basis for design, construction, and operation of chilled water systems in nuclear plants e Meeting with the Director, NMSS--Briefing regarding NMSS activities e Briefing by IE regarding its Vendor Inspection Program o Fire Protection Task Force Report (tentative)--ACRS comments e Meeting with NRC Commissioners (tentative)--Topics to be determined Sincerely.

• f W Jesse C. Ebersole Chairman

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