ML20205E948
| ML20205E948 | |
| Person / Time | |
|---|---|
| Issue date: | 09/24/1985 |
| From: | Ward D Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0314, ACRS-SL-314, NUDOCS 8511040044 | |
| Download: ML20205E948 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 3
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o, WASHINGTON, D. C. 20555 September 24, 1985 Honorable Nunzio J. Palladino Chairman U. S. Nuclear Regulatory Commission Washington, D.C.
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Dear Dr. Palladino:
SUBJECT:
THREE HUNDRED FIFTH MEETING 0F THE ADVISORY COMMITTE REACTOR SAFEGUARDS, SEPTEMBER 12-14, 1985 The Committee met with representatives of the NRC Staff and Gulf States Utilities, acting on behalf of itself and as an agent for the Cajun Electric Power Cooperative, to review the application for a license to operate the River Bend Station, Unit 1.
The Committee was briefed by representatives of the Office of Inspection and Enforcement regarding recent post-trip failures in the auxiliary feedwater system at Turkey Point, Unit 3.
Reports on the subjects noted above have been sent to you.
(I The Committee discussed the efforts of the NRC Staff to evaluate and resolve the technical concerns and allegations and the quality assurance and quality control issues raised in conjunction with construction practices at the Comanche Peak Steam Electric Station, Units 1 and 2.
The Committee met with representatives of the NRC Staff to review the proposed resolution for USI A-43,
" Containment Emergency Sump Performance" and Regulatory Guide 1.82, Revision 1, " Water Sources for Long Term Recirculation Cooling Following a Loss of Coolant Accident."
The Committee heard a report of its Subcommittee on Metal Components regarding proposed Revision 2 to Regulatory Guide 1.99, " Radiation Damage to Reactor Vessel Materials."
The Committee's comments on the subjects noted above have been provided to the Executive Director for Operations. A copy has been sent to you. '
The Committee met with representatives of the NRC Staff, the Brookhaven National Laboratory, and the General Electric Company (GE) to continue review of the application of GE for a forward-looking Final Design Approval for the GESSAR II design.
The Committee was briefed by representatives of the Office of Inspection and Enforcement and the Office of Nuclear Reactor Regulation regarding recent operating occurrences at nuclear power plants, including
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inadvertent actuation of the fire suppression system at the Hope Creek Generating Station, Unit 1, a post trip loss of auxiliary feedwater at the Turkey Point Nuclear Generating Plant, Unit 3 a potential main "3 N 8511040044 850924 p
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steam isolation valve failure at low steam flow at the Turkey Point Nuclear Generating Plant, Units 3 and 4, comon mode problems with steam generator pressure indication at the Maine Yankee Atomic Power Station,
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c.c.J c u pipe crack indications at the Peach Bottom Atomic Power Station.
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The Comittee was briefed by representatives of the NRC Staff regarding proposed changes in 10 CFR 50, Apaendix A entitled General Design Criterion 4, " Environmental and Missi'e Design Bases."
The Comittee met with representatives of the NRC Staff and experts in the field of natural aptitude selection testing to consider the use of natural aptitude selection testing in the nuclear power industry.
The Comittee met with Harold R. Denton, Director of the NRC Office of Nuclear Reactor Regulation (NRR) and was briefed on the recent reorganization of NRR.
The Comittee met with the Panel on ACRS Effectiveness Chaired by L.
Manning Muntzing, Doub & Muntzing, Chartered, to discuss the Panel's report, " Analysis and Recomendations Concerning the Scope, Methods, Manage, ment and Effectiveness of the Advisory Comittee on Reactor Safeguards" dated September 1985.
The Committee discussed the application of the PRA evaluation for the Indian Point nuclear plant to the design and operation of this station.
T The Comittee met with the NRC Comissioners to discuss ACRS participation in the DOE program to handle and dispose of civiTTaii radwaste, positive and negative human performance aspects associated with the N_RC Severe Accident Policy, and the need for human factors research relating to nuclear power plant operations.
Since the last report of ACRS activities, the following Subcommittee meetings, have been held:
Joint Emergency Core Cooling Systems and Fluid Dynamics, in Washington, D.C. on August 27, 1585 to (1) review the status of the hydrodynamic loads issue for plants with Mark I-III containment; (2) review the USI A-43, " Containment Emergency Sump Performance" implementation proposal; (3) review the results of calculations of the Davis-Besse feed-and-bleed capability; and (4) review ECCS-related issues of ongoing concern to NRR Metal Components, in Washington, D.C. on September 4-5, 1985 to review Regulatory Guide 1.99, Revision 2 and other related concerns, and discuss the status of the piping NDT program and HSST programs.
The Subcomittee also reviewed problems associated with steam generator girth weld cracks Reactor Operations. in Washington, D.C. on September 10,1985 to-discuss recent operating experience at nuclear power plants
River Bend Units 1 & 2, in Washington, D.C. on September 11, 1985 to continue its review of Gulf States Utilities Company's application for a full power operating license
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General Electric Standard Safety Analysis Report (GESSAR II), in Washington, D.C. on September 11, 1985 to continue its review of GESSAR II for final design approval applicable to future plants Future Agenda The following items are tentatively scheduled for consideration during the 306th ACRS meeting, October 10-12, 1985:
Consideration of extreme environmental phenomena in emergency planning per requests of Comissioners Asselstine, Bernthal, and Zech during the 303rd ACRS meeting Report of the ACRS Subcommittee on the State of Nuclear Power Plant Safety -- Discussion of the most significant safety-related issues in need of resolution NRC Policy Statement on Advanced Reactors -- discussion of revised o
Advanced Reactor Policy Statement dated August 21, 1985 General Electric Standard Safety Analysis Report (GESSAR II)
Continue ACRS review of the FDA for this standardized NSSS
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Report of the Subcommittee on Regulatory Activities regarding proposed changes in NRC Regulatory Guides on :
Meteorological Measurement Programs, Regulatory Guide 1.23 Revision 1 Criteria for Power, Instrumentation, and Control Portions of Safety Systems (Task No. IC 609-5)
Instrument Setpoints for Safety-Related Systems Meeting with NRC Comissioners to discuss ACRS coments on EPA Standards for Disposal of High Level Civilian Radwaste and. to discuss Comission guidance, if available, regarding the ACRS role in the NRC regulation of the DOE radwaste program and radwaste activities Safety Goal Policy -- Subcommittee report regarding containment performance guidelines Davis-Besse Restart Plan -- NRC Staff briefing regarding proposed restart of this facility TVA Nuclear Power Program Briefing regarding TVA's reorganization of its nuclear power program to deal with deficiencies both in operation and construction
NRC Staff reassessment and new position on accident source tems (NUREG-0956) - ACRS comments
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Repor t of the Procedures and Administration Subcomittee regarding '
proposed changes in ACRS procedures and implementation of the recomendations of the Panel on ACRS Effectiveness The Committee will also discuss proposed ACRS coments regarding use of natural ability selection for nuclear power plant operators, and the application of the _ Indian Point PRA to the design and operation of this station Sincerely, David A. Ward Chairman l4 t
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