ML20010D771
| ML20010D771 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/13/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20010D768 | List: |
| References | |
| NUDOCS 8108310227 | |
| Download: ML20010D771 (2) | |
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UNITED STATES 8
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g NUCLEAR REGULATORY COMMISSION
.E WASHINGTON D. C. 20555 v
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 55 TO PROVISIONAL OPERATING LICENSE NO. DPR-16 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. S0-219
1.0 INTRODUCTION
By letters dated October 10, 1978 and August 11,1980, as modified l
March 19,1981, Jersey Central Power & Light Company (the licensee) requested an amendment to Provisional Operating License No. OPR-16 for the Oyster Creek Nuclear Generating Station. This amendment would provide a change to the Appendix A Technical Specifications by modifying Section 3.7 to be consistent with the 125V DC plant modifi-cation installed during the 1978 refueling outage. This change would l
also clarify the surveillance requirements of Section 4.7 to show consistency with current 125V DC system surveillance practices of IEEE STD. 450.
The changes requested with regard to grid undervoltage protection remain under NRC review; this request will be addressed in a subsequent license amendment.
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l 2.0 DISCUSSION AND EVALUATION l
The Oyster Creek Technical Specification Section 3.7 applies to the operating status of the auxiliary electrical power to assure adequate powfr supply for operation of equipment required for safe plant shutdown.
The licensee has performed a plant modification which included changing the 125V DC power distribution for safety related loads from distribution center A to C.
The safety related loads previously powered from panel E are now powered from panel DC -F.
We have reviewed the proposed changes to the Technical Specification and find them to be administrative in nature. Thus, we conclude that these changes are acceptable, Section 4.7 applies to the surveillance requirements for the Auxiliary l
Electrical Power System. The change request basically updates the battery surveillance practices as presented in IEEE STD. 450. The change also requires that the batteries be tested only when the reactor is' shutdown. When the plant is operating both batteries are at full capacity.
Based on the above, we find the proposed changes acceptable.
8108310227 810813 DR ADOCK 05000219 PDR
3.0 ENV1dONMENTAL CONSIDERATION We have determined 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 determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 951.5(d)('4), that an environmental impact statement or negt. 'va feclaration and environmental impact appraisal need not be pie 3 in connection with the issuance of this amendment.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) becaure 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 safety 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 common defense and security or to the health and safety of the public.
Date:
August 13, 1981 9
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