ML20078K059
| ML20078K059 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/09/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078K056 | List: |
| References | |
| NUDOCS 9411220237 | |
| Download: ML20078K059 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 151 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT N0. 133 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY HCGUIRE NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 1.0 JETRODUCTION By letter dated August 25, 1994, Duke Power Company (the licensee) submitted a request for changes to the McGuire Nuclear Station, Units 1 and 2, Technical Specifications (TS).
The requested changes would revise the testing interval for auxiliary feedwater (AFW) system pumps from monthly to quarterly on a staggered test basis.
The amendments are consistent with the guidance in NUREG-1366, " Improvements to Technical Specifications Surmillance Requirements" and Generic Letter 93-05,"Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation."
In addition, a note is incorporated from NUREG-1431, " Revised Standard Technical Specifications, Westinghouse Plants" into the TS clarifying that the turbine-driven AFW pump cannot be tested until the required pressure exists in the secondary side of the steam generator.
2.0 ilALVATION The NRC has completed a comprehensive examination of surveillance requirements in the TS that require testing during power operation. The evaluation is documented in NUREG-1366, " Improvements to Technical Specification Surveillance Requirements," dated December 1992.
The staff found that while the majority of testing at power is important, safety can be improved, equipment degradation decreased, and an unnecessary burden on personnel resources eliminated by relaxing a small fraction of the TS testing intervals.
Based on the results of the evaluations documented in NUREG-1366, the NRC issued Generic letter 93-05.
Section 9.1 of NUREG-1366 discusses the potential advantages of reduced surveillances for the auxiliary feedwater pumps. As noted in the report, although performance of surveillances is an important mechanism in the identification of problems with the auxiliary feedwater pumps, the testing also contributes to the degradation of the pump and system unavailability.
The analyses used in the report found that a monthly surveillance test interval may be contributing to AFW pump unavailability through failures and equipment degradation.
The report recommended a change in the testing frequency to a quarterly interval.
Another advantage of the quarterly testing is that it is consistent with the requirements of the ASME Code. As discussed 9411220237 941109 PDR ADOCK 05000369 P
. in Generic Letter 93-05, the licensee has indicated that the change in surveillance frequency is compatible with observed plant operating experience and is consistent with the NRC guidance on this issue.
The requested changes to the testing frequency in consistent with the guidance in Generic Letter 93-05 and is therefore acceptable. The requested addition of a footnote to TS 4.7.1.2.b.2) clarifies when the subject testing is required to be performed.
This clarification is consistent with the NRC guidance in NUREG-1431 and is acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the North Carolina State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ENVIRONMENTA1. 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.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that uay 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 (59 FR 49426). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR Sl.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 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 (wration in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: R. E. Martin, PD 11-3 Date: November 9, 1994
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