ML20065L643

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Safety Evaluation Supporting Amend 210 to License DPR-59
ML20065L643
Person / Time
Site: FitzPatrick 
Issue date: 04/13/1994
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20065L641 List:
References
NUDOCS 9404210197
Download: ML20065L643 (2)


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UNITED STATES

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% u; p SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 210 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333

1.0 INTRODUCTION

By letter dated December 29, 1993, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A.

FitzPatrick Nuclear Power Plant Technical Specifications (TSs).

The requested changes would revise TS 3.6.D.4 to eliminate an inconsistency between the operability requirements for the reactor coolant system (RCS) leakage detection and the specified requirements for monitoring RCS leakage.

In addition, the requested changes would also revise the TSs to make numerous editorial corrections which are administrative in nature.

2.0 EVALUATIOR 2.1 Reactor Coolant System Leakaae Monitorina The licensee has proposed to revise TS 3.6.D.4 to eliminate an inconsistency between the RCS leakage detection operability requirements and the requirements for monitoring leakage.

TS 3.6.0.1 currently requires that RCS leakage be below specified limits when there is irradiated fuel in the reactor vessel and reactor coolant temperature is greater than 212 'F.

TS 3.6.D.4 requires the leakage detection systems to be operable during power operation (any time the reactor is at a power level greater than 1 percent ~ rated power, even at temperatures less than 212 *F).

The proposed change would require the leakage detection system to be operable consistent with the requirements for monitoring leakage.

Although the change relaxes the requirement for the leakage detection system to be operable under certain power conditions, at temperatures of 212 *F and below, there are no TS requirements to monitor RCS leakage under these conditions. Therefore, the change would not decrease the margin of safety that is currently provided by-the existing TSs.

The change, however, would require the system to be operable whenever leakage monitoring is required.

Currently, the leakage detection system is not required to be operable when the plant is shutdown but reactor coolant temperature is greater than or equal to 212 'F, although monitoring of RCS leakage is required under these conditions.

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.' The NRC staff finds that the proposed change would improve the consistency of the TSs while maintaining adequate RCS leakage monitoring capability.

Based on the fact that adequate RCS leakage monitoring capability is maintained and there would be no decrease in the margin of safety currently provided the existing TSs, the NRC staff finds the proposed change to be acceptable.

2.2 Administrative Chanaes The licensee has proposed miscellaneous typographical and editorial corrections to Appendix A TSs.

The staff has reviewed these proposed changes and determined that they are acceptable since they do not involve any substantive changes to requirements.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.

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 Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public coment on such finding (59 FR 4945). 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 CONCLUSI0t(

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 Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

G. Replogle Date: April 13, 1994