ML20205P797
| ML20205P797 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/09/1986 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20205P802 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 3206F, NUDOCS 8605220007 | |
| Download: ML20205P797 (2) | |
Text
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GPU Nuclear QgI f
100 interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
May 9, 1986 Mr. John A. Zwolinski, Director BWR Project Directorate No.1 Division of BWR Licensing U.S. Nuclear Regulatory Comission Washington, D. C. 20555
Dear Mr. Zwolinski:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Supplement 1 to NUREG-0737 Regulatory Guide 1.97 Response Section 6.2 of Supplement 1 to NUREG-0737, pertaining to Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident", requires each licensee to submit a report describing how it meets the specific recomendations of the Regulatory Guide.
GPU letter dated June 13, 1984 transmitted a report on Oyster Creek's implementation of the requirements of Regulatory Guide 1.97.
As we indicated in discussions with your staff (Project Manager for Oyster Creek), GPU has subsequently updated the report to revise certain variables and to reflect the recent plant modifications made since our last submittal.
Table III of the attached Topical Report No. 028 proposes the following modifications for certain variables, a.
Installation of new components:
1.
Emergency Service Water System flow indicators.
2.
Redundant torus water temperature indicators.
3.
Drywell high radiation monitors.
4.
Manual sampling capability to Radioactive Gas Effluent Monitoring System.
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Upgrading existing components:
1.
Torus pressure instrument.
2.
Core Spray flow instrument.
3.
Neutron monitoring instrument.
Table III also provides justification for those variables listed below for which GPU does not believe upgrading is required.
1.
Boron grab sample 2.
Drywell sump level 3.
Standby liquid control flow 4.
Equipment drain tank level 5.
High radioactivity liquid tank level The modifications recommended in Table III, except those indicated to be completed during the upcoming 11R refueling outage, will be incorporated into the Integrated Living Schedule for Oyster Creek Nuclear Generating Station, which will be negotiated with members of your staff.
Topical Report 028 is based on the current Oyster Creek Emergency Operating Procedures (EOPs) which were prepared on the basis of revision 2 of BWR Owners Group emergency procedure guidelines. We are in the process of revising the E0Ps based on revision 4 of the BWR Owners Group emergency procedure guidelines.
If you have any questions, please contact M. Laggart, Manager, BWR Licensing, at (201) 299-2341.
Very trul yours, dier Vice President and Director Oyster Creek PFB/pa Attachment cc: Administrator, Region I NRC Resident Inspector l
U.S. Nuclear Regulatory Commission 0.C. Nuclear Generating Station l
631 Park Avenue Forked River, New Jersey 08731 King of Prussia, Pennsylvania 19406 l
Mr. Jack N. Denohew, Project Manager l
U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue l
Bethesda, Maryland 20014 l
3206f t