ML20034H231
| ML20034H231 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/08/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034H229 | List: |
| References | |
| NUDOCS 9303160207 | |
| Download: ML20034H231 (2) | |
Text
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UNITED STATES s-
., i NUCLEAR REGULATORY COMMISSION u
WASHINGTON, D.C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482
1.0 INTRODUCTION
By application dated June 11, 1992, Wolf Creek Nuclear Operating Corporation (the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. NPF-42) for the Wolf Creek Generating Station. The proposed changes would revise Technical Specification. (TS).
4.8.1.1.2 by removing the numerical value of 1352 kW associated with the verification of the emergency diesel generators capability to reject the largest single load, the essential service water pump motor, while maintaining-required voltage and frequency.
In lieu of the numerical value, the revised TS denotes the actual load, the essential service water pump motor, which is to be rejected during the emergency diesel generator load rejection surveillance.
2.0 EVALUATION The licensee has proposed the TS change as part of the corrective actions discussed in Licensee Event Report (LER) 91-022-00. On November 12, 1992, the licensee discovered that the existing requirements of TS 4.8.1.I'.2.g(2) had not been satisfied regarding the emergency diesel generators capability to reject a load of 1352 kW while maintaining voltage and frequency within acceptable limits. The value of 1352 kW is thought to be derived from the original diesel generator sizing calculations and was therefore not' the appropriate value for the load rejection surveillance requirement.
In order to satisfy the TS requirements prior to restarting from the last refueling outage, the essential service water _(ESW) system flow alignment was changed in order to maximize flow and result in a motor loading above the TS value of 1352 kW. The proposed change deletes the specific numerical value of 1352 kW and requires confirmation that the emergency diesel generators have the capability to reject the ESW pump motor, the largest single load.
The Bases for TS 3/4.8.1 refer. to Regulatory Guides (RG) 1.9, " Selection, Design, and Qualification of Diesel-Generator Units Used as Standby-(Onsite)'
Electric Power Systems at Nuclear Power Plants," and 1.108, " Periodic Testing of Diesel Generator Units.Used as Onsite-Electric Power Systems at Nuclear Power. Plants," with regard to the load rejection surveillance requirements.
The guidance provided by RG 1.9 and RG 1.108 require the diesel generator's output to remain within acceptable ranges following the loss _ of the _ largest 9303160207 930308 PDR ADOCK 05000482 l
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single load. The proposed change would continue to satisfy the positions stated in the RGs by requiring the diesel generators to withstand the loss of electrical load associated with the ESW pump motors with the ESW system aligned in its emergency configuration. The proposed change to.the Bases section adds additional details and updates the applicable revision of RG 1.9.
A clarification was added to the Bases section describing the surveillance requirements. The change was discussed with and agreed to by representatives of the licensee.
The staff has reviewed the information provided and concludes that the proposed TS surveillance requirement meets the positions of RG 1.9 and RG 1.108. The ability of each emergency diesel generator to reject the largest single load while maintaining voltage and frequency within acceptable limits will continue to be demonstrated at least every 18 months. The proposed changes to the Bases add clarifying information and do not change the intent.
Therefore, the staff finds the proposed TS changes to be acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Kansas State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 JNVIRONMENTAL CONSIDERATION The amendment changes a surveillance requirement. 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 consid-eration, and there has been no public comment on such finding (57 FR 34592).
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 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:
W. Reckley, NRR, PDIV-2 Date:
March 8, 1993
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