ML19312C532

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Safety Evaluation Supporting Amends 46,46 & 43 to Licenses DPR-38,DPR-47 & DPR-55,respectively
ML19312C532
Person / Time
Site: Oconee  
Issue date: 09/09/1977
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19312C528 List:
References
NUDOCS 7912160091
Download: ML19312C532 (2)


Text

' UNITED STATES NUCLEAR REGULATORY COMMISSION

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CASHINGToN, o. c. 20655

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS. 46, 46 AND 43 TO FACILITY LICENSE N05. OPR-38, DPR-47 AND DPR-55 DUKE POWER CCMPANY OCONEE NUCLEAR STATION, UNIT NOS. 1, 2 AND 3 DOCKET N05. 50-269, 50-270 AND 50-287_

Introduction By letter dated July 5, 1977, Duke Power Company (licensee) requested in the changes to the common Technical Specifications incorporated operating licenses of Units 1, 2 and 3 of the Oconee Nuclear Station.

The changes would pennit the extended operation of Oconee Unit 3 Cycle 2 from 265 effective full power days (EFPD) to 282 EFPDs.

Discussion The Oconee Unit 3, Cycle 2 reload was approved on October 22, 1976, for a cycle length of 265 EPFDs. To provide flexibility in the scheduling of refueling operations at Oconee Nuclear Station, the licensee has proposed to extend Cycle 2 by 17 EFPDs to 282 EFPDs.

Evaluation The Oconee Unit 3 Cycle 2 was approved by NRC on the basis of a review of an analysis performed by the licensee which justified Cycle.2 operation at the rated core power of 2568 MWt.

Based on the Cycle 2 reload analysis, Technical Specifications were proposed which provided operational control rod position limits and power intalance limits for a cycle of 265 EFPDs. These limits assured that operation of Cycle 2, would not result in any Technical Specifications Safety Limits or Limiting Conditions for Operation being exceeded.

The licensee assessed the applicability of the existing Technical Specifi-cation limits for the extended Cycle 2 in a manner similar to that performed As a result of this assessment, it was detenained for the Cycle 2 reload.

that the operational control rod position limits (Technical Specification Figures 3.5.2-lC3 and 3.5.2-2C3) and the power imbalance limits (Technical 7 912160 O?J-

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a Specification Figure 3.5.2-3C3) would require slight mooifications to account for limiting conditions which would exist in the extended part of the cycle.

We have reviewed the licensee's submittal and base concluded that with the slight modifications proposed by the licensee the Technical Specifica-tions for Oconee Unit 3 will remain valid for the 17 EFPD extension of Cycle 2 to 282 EFPDs.

Environmental Consideration We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any environmental impact.

Having made this deter-mination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 51.5(d)(4) that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.

Conclusion We have concluded, based on the considerations discussed above, that:

(1) because the amendments do not involve a significant increase in the probability of consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do 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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Date:

September 9,1977

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