ML20040G164
| ML20040G164 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/03/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040G163 | List: |
| References | |
| NUDOCS 8202110377 | |
| Download: ML20040G164 (2) | |
Text
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UNITED STATES 8
3 NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555 7
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR OYSTER CREEK NUCLEAR GENERATING STATION I
SUPPORTING AMENDMENT NO. 60 TO PROVISIONAL OPERATING LICENSE NO. DPR-16 GPU NUCLEAR CORPORATION AND i
JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219
1.0 INTRODUCTION
j By letter dated October 19, 1981 GPU Nuclear Corporation and Jersey Central Power & Light Company (the licensees) requested an amendment to Provisional Operating License No. DPR-16 for the Oyster Cree.k Nuclear Generating Station.
This amendment would authorize changes in the Diesel Generator Load Sequence Timers for the Service Water Pump and Closed Cooling Water Pump, and the requirements for protective instrumentation.
By letter dated October 26, 1981 the licensees also requested a change to the Diesel Generator inspection schedule to be performed at least once per 18 months during shutdown, rather than annually.
In addition the basis for Section 4.7 that appears on page 4.7-1 and is duplicated on page 4.7-2 has been removed.
2.0 DISCUSSION AND EVALUATION Our safety evaluation of Amendment 42 to the Licensing Application found it acceptable to automatically trip the RBCCW pump and SW pump during LOCA. A safety injection (SI) signal trips the RBCCW pump instantaneously while the SW pump trip is delayed for 10 sec + 15% after an SI signal. The delayed trip is accomplished by means of a D. C. relay power by the same class lE battery which supplies the control power to the starting relay of this pump.
These relays will have the design and surveillance requirements same as other load sequence times of the diesel generator listed in the licensee's technical specification. The load shedding feature and long time delay (120 sec) in restarting the service water pump ensures that the proposed time delay (10 sec +_15%) for tripping the SW pump after an SI signal shall not cause the pump to be inadvertently connected to the diesel generat6r..
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The proposed technical specification changes include the revised consumption of diesel generator fuel oil for the three days (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) requirements. The revised figures are due to addition of Security System Loads and removal of RBCCW pum'p and SW pump from the load requirement contained in Amendment 42 of the licensing application. The revised figures of fuel consumption, for various previously analyzed scenarios, are still within the specification requirement of the licensee's facility for 3 days consumption.
8202110377 820203 PDR ADOCK 05000219 P
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. Based on our evaluation, we conclude that the proposed changes to the technical specification (table 3.1.1, application section 3.1 and 3.7) are acceptable.
A thorough inspection of the diesel generators involves a rigorous check up of all its components in accordance with the manufacturer's recommendations. This necessitates taking the diesel generator out of service for a possible extended period of time.
During plant operation, taking one diesel generator out for inspection purposes, will curtail its availability when required for safety.
The proposed interval of at least once per 18 munths, during shutdown, enhances the reliability and ensures availability of the diesel generator when required during plant operation. The proposed time interval is in accordance with the standard technical specification requirements of boiling water reactors and thus provides added assurance of diesel generator availability during power-operation.
Based on our evaluation, we conclude that the proposed changes to the technical specification (page 4.7-1 and 4.7-2) are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
We have detendined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this detemination, we have further concluded that the amendment involves an action which is insignif.ican$ from the standpoint of environmental impact a'nd, pursuant to 10 CFR 551.5(d)(4), that an envirornental impact statement or negative declaration and envirornental impact
. appraisal need not be prepared in connection with the' issuance of this amendment.
4.0 CONCLUSION
We have conc 1'uded, based on the considerations discussbd above, that:
(1) because the amendment does not involve a significant. increase in the probability or consequences.of accidents previously considered and does not involve a significant decrease in a safetf margin, the amendment does not involve a significant hazards consideration, (2) there,
is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and-(3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the comhon defense and security or.to the health and safety of the public.
Date:
Fchruary 3,1902
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