ML20045A438
| ML20045A438 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/07/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045A437 | List: |
| References | |
| NUDOCS 9306100258 | |
| Download: ML20045A438 (2) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20586 4001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.164 TO FACILITY OPERATING LICENSE NO. DPR-16 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY
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0YSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 i
1.0 INTRODUCTION
ByletterdatedMarch3,1993,theGPUNuclearCorporation,thelicenseeforf the Oyster Creek Nuclear Generating Station, submitted a request to reduce the setpoint on the ninth (highest) safety valve from 1230 to 1221 psig. The v '
licensee also included a licensing basis analysis in support of the Technical Specification (TS) change request.
2.0 EVALUATION The reduction in setpoint of the ninth safety valve from 1230 to 1221 psig is based on licensing basis analysis presented in the amendment request. The safety valves are not actuated during normal operations. The system satisfies the overpressure protection requirement of the ASME Code. However, Oyster Creek has not had transients in which a safety valve has been actuated. A plant performance evaluation showed a low probability of a safety valve-opening due to an anticipated transient.
The most limiting overpressure event that was analyzed in the Final Safety Analysis Report (FSAR) was re-analyzed, and the results were presented in the amendment request. The event was the main steam isolation valve closure with scram on high neutron flux and failure of electromatic relief valves, turbine bypass valves,~ isolation condensers and recirculation pump trip.
In the re-analysis, the-single (ninth) safety valve was assigned an analysis setpoint of 1236 psig which was the same setpoint used for the four safety valves that are set at 1221 psig. The remaining four safety valves were assigned an analysis setpoint of 1227 psig and are set at 1212 psig. The resulting peak pressure at the bottom of the reactor vessel was 1368 psig which is below the ASME Code limit of 1375 psig (110% of design pressure). This is lower than the peak pressure of 1369 psig that was the result in the original FSAR analysis. The recirculation piping had a peak pressure of 1376.5 psig which is also below l
the Code limit of 1380 psig (115% of design pressure).
9306100258 930607 PDR ADOCK 05000219 p
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c Since the event acceptance limits have been satisfied with peak pressures that are below the Code limits, the analysis is acceptable.
3.0 STATE CONSULTATION
In accordance with the Comission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment. 7he State official had no coments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public coment on such finding (58 FR 16861). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributor:
A. Wilford Date:
June 7, 1993