ML20236X588

Safety Evaluation Supporting Amend 245 to License DPR-59

ML20236X588
Person / Time
Site:	FitzPatrick
Issue date:	07/29/1998
From:	NRC (Affiliation Not Assigned)
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Shared Package
ML20236X578	List: ML20236X576 ML20236X583 ML20236X588
References
NUDOCS 9808100123
Download: ML20236X588 (2)

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A' p k* UNITED STATES 4 g NUCLEAR REGULATORY COMMISSION 4 p, WAaHINGToN, D.C. 30e06 4001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 245TO FACILITY OPERATING LICENSE NO. DPR-59 l POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333

1.0 INTRODUCTION

By letter dated February 6,1998, the New York Power Authority (the licensee) requested the approval of changes to the Technical Specifications (TS) revising the Reactor Protection System (RPS) normal supply Electrical Protection Assembly (EPA) undervoltage trip setpoints. Each of the two Reactor Protection System (RPS) divisions may be supplied from its respective RPS motor generator (MG) set or from an attemate power source which derives power from same electrical division. The MG sets and l altemate sources for both divisions are provided with redundant, seismic qualified, Class

, 1E electrical protection assemblies (EPA) between the power source and the RPS bus.

- Any abnormal output type failure in either of the MG sets or altemate sources (if in  !

service) would result in a trip of the EPA producing a half scram on that RPS division and retaining full scram capability in the other RPS division. The RPS bus is a 120-vac power distribution bus which mainly supplies power to instrument power supplies and normally energized relay coils and solenoids. The EPA trip settings have time delays to prevent transients from deenergizing the bus. The licensee proposed to increase the undervoltage trip setpoints for the normal supply source from 2112.3 Vac for Channels "A" and "B" to 2112.5 Vac for Channel "A" and 2113.5 Vac for Channel "B."

2.0 EVALUATION The licensee performed a calculation to determine the total channel uncertainties associated with the normal RPS EPA trip setpoints over a 24-month operating cycle. The calculation analyzed the impact of voltage drop from the EPAs to the scram pilot valve solenoids and other relays, based on voltage measurements taken at RPS system loads.

The calculation concluded that the RPS scram pilot valve solenoids require the highest minimum voltage to ensure proper operation. Due to the location of the normal supply EPA (turbine building electric bays), the licensee discovered that the feeder cable run between the supply and the scram pilot valve solenoids will result in a significant voltage drop. The voltage drop assessment calculated the "A" and "B" channels separately due to their applicable differences. The licensee determined that the minimum undervoltage i trip values of 112.5 and 113.5 volts for the normal supply "A" and "B" EPAs, respectively, are required to assure minimum allowable voltage at the scram pilot valve solenoids. The licensee raised the field trip setpoint for the normal RPS EPA undervoltage trip to address the issue of the voltage drop. However, the setpoint specified in TS 4.9.G.2 was not revised at that time. Therefore, the licensee proposed to increase the TS undervoltage trip setpoints for the normal supply source from 2112.3 Vac for Channels "A" and "B" to 2112.5 Vac for Channel"A" and 2113.5 Vac for Channel "B." The time delay associated with this change is unaffected.

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k 2- j The NRC staff has evaluated the licensee's submittal and determined that the proposed instrument setpoint change to the TSs ensures that voltage drop is adequately factored into the EPA setpoints. The proposed change to the RPS normal supply EPA undervoltage trip setpoints provide adequate protection to the RPS power supplies.

Therefore, the proposed change is acceptable.

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 amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes the surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any emuents 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (63 FR 19976). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10.CFR 51.22(b) no environmentalimpact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

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 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: N. K. Trehan Date: July 29, 1998 I

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