ML20052G025

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Forwards Proposed Agenda for 820518-20 Site Visit & 820521 Visit to Gpu Nuclear Corp Headquarters to Discuss SEP Integrated Assessment Program
ML20052G025
Person / Time
Site: Oyster Creek
Issue date: 05/11/1982
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Fielder P
JERSEY CENTRAL POWER & LIGHT CO.
References
TASK-***, TASK-RR LSO5-82-05-016, LSO5-82-5-16, NUDOCS 8205140244
Download: ML20052G025 (3)


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May 11,1932 DISTRIBUTION Docket NRC PDR Docket No. 50-219 LS05-82-05-016 Local PDR ORB Reading NSIC DCrutchfield HSmith Mr. P. B. Fiedler JL mbardo Vice President & Director - Oyster Creek OELD Oyster Creek Nuclear Generating Station OI&E Post Office Box 388 forked River, New Jersey 08731 (10)

Dear Mr. Fiedler:

SUBJECT:

VISITS TO THE OYSTER CREEK NUCLEAR GENERATING STATION AND GPU NUCLEAR CORPORATION HEADQUARTERS As discussed with Mr. J. Mnubel of your staff, we and our contractors will be conducting visits to the Oyster Creek Nuclear Generating Station on May 18,19 and 20, and to GPU Nuclear Corporation Head-quarters on May 21, 1982 to discuss the SEP Integrated Assessment Program. The meetings will include, (1) a review of the licensee's position on differences (2) discuss factors pertinent to back-fitting decisions, and (3) close out differences where agreements can be reached. The proposed agenda for the meeting is contained in the enclosure.

The attendees for May 18,19 and 20,1982 are:

t-co C. Grimes 576-52-9171 de

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R. Fell 378-42-6083 c

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M. Rubin 558-90-6787 gI, l

J. Lombardo 093-24-0211 2

e R. Spulak (Sandia) 480-76-2665 y

P.Amico(Sandia) 075-48-1882 II The attendees for May 21, 1982 are:

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W. Russell h k S6d

, pei J. Lombardo si g

Sincerely.

Original signed by

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8205140244 820511 Dennis M. Crutchfield, Chief fDRADOCK05000 Operating Reactors Branch #5 Division of 1,1censina D G:g #5 DL: ORB #5 i

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' Mr. P. B. Fiedler May11,1962 cc G. F. Trowbridge, Esquire Resident' Inspector Shaw, Pittman, Potts and Trowbridge c/o U. S. NRC 1800 M Street, N. W.

Post Office Box 445 Washington, D. C.

20036 Forked River, New Jersey 08731 J. B. Lieberman, Esquire Commissioner Berlack, Israels & Lieberman New Jersey Department of Energy 25 Broadway 101 Commerce Street New York, New York 10004 Newark, New Jersey 07102 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 J..Knubel BWR Licensing Manager GPU Nuclear 100 Interplace Parkway Parsippany, New Jersey 07054 Deputy Attorney General

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State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 Lacey Road Fo.rke,4, River, New Jersey 08731 U. S. Environmental Protection Agency Region II Office ATTN:

Regional Radiation Representative 26 Federal Plaza New York, New York 10007 Licensing Supervisor Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731 e

AGENDA TOPICS WHICH DO NOT MEET CURRENT CRITERIA OR EQUIVALENT AS OF MARCH 1982 III-5.A Effects of Pipe Break on Structures, Systems and Components Inside Containment.

III-5.B Pipe Break Outside Containment III-6 Seismic Design Considerations III-8.A Loose Parts Monitoring III-10. A Thermal-Overload Protection for Motors of

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Motor-Operated Valves V-5 Reactor Coolant Pressure Boundary (RCPB) Lea'kage Detection V-6 Reactor Vessel Integrity V-10. B RHR Reliability V-ll.A Requirements for Isolation of High and Low Pressure Systems V-12. A Water Purity of Boiling Water Reactor Primary Coolant VI-4 Containment Isolation System VI-7.A.3 ECCS Actuation System VI-7.C.1 Appendix K - Electrical Instrumentation and Control (EIC) Re-reviews VI-10. A Testing of Reactor Trip System and Engineered Safety Features Including Response Time Testing VII-1.B Trip Uncertainty and Setpoint Analysis VII-2 Enginee. red Safety Features (ESF) System Control Logic and Design VII-3 Systems Required for Safe Shutdown VIII-2 Onsite Emergency Power Systems - Diesel Generator VIII-3.B D.C.. Power' System Bus Voltage Monitoring and Annunciation VIII-4 Electrical Penetrations of Reactor Containment

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