ML20199L956
| ML20199L956 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/04/1986 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| TASK-07-01.A, TASK-08-03.B, TASK-7-1.A, TASK-8-3.B, TASK-RR NUDOCS 8604110010 | |
| Download: ML20199L956 (2) | |
Text
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Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:
April 4,1986 Mr. John A. Zwolinski, Director BWR Project Directorate No. 1 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Zwolinski:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 SEP Topic VII-1 A, Isolation of Reactor Protection System from Nonsafety Systems; and SEP Topic VIII-3B, DC Power System Bus Voltage Monitoring and Annunciation GPUN letters dated August 13, 1984 and July 8,1985 transmitted the results of GPUN's evaluation concerning SEP Topic VII-1 A.
GPUN letter dated June 7,1985 forwarded the results of our investigation regarding SEP Topic VIII-38.
Subsequently, the NRC staff requested further clarifications before resolving these SEP Topics.
Provided below are our responses to questions raised by the staff.
The staff raised a concern regarding the adequacy of the electrical isolation feature (SEP Topic VII-1 A) between the Power Shape Monitoring System (PSMS) computer and the Reactor Protection System (RPS).
Please note, the Oyster Creek PSMS computer is dedicated to monitor the core reactivity profile.
The following RPS sensors are presently read by the PSMS at Oyster Creek:
1.
Local Power Range Monitors 2.
Average Power Range Monitors 3.
Reactor Recirculation Flow These RPS signal inputs are protected by isolation amplifiers on the " front end" of the PSMS computer thereby preventing propagation of a failure in the h
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. PSMS into the RPS. This isolation feature is described in Amendment 68 to Qyster Creek Facility Description and Safety Analysis Report (Response to Question 3 and Question SC of Supplement 8).
The staff also asked if Qyster Creek had ever experienced a high resistance connection between the station batteries and the 125 volt D.C. buses (SEP Topic VIII-38). Our investigation indicates tnat Qyster Creek has not experienced a failure of the D.C. power supply system which can be attributed to a high resistance connection between the station battery chargers and the buses nor between the buses and the station batteries.
Very truly yours, r _ _ _ - --)
1 iedler Vice President & Director Qyster Creek PBF:gpa 3039f/0160A cc: Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Jack N. Donohew, Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Mail Stop #314 NRC Resident Inspector Qyster Creek Nuclear Generating Station Forked River, New Jersey 08731
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