ML20080B890
| ML20080B890 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/02/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080B888 | List: |
| References | |
| NUDOCS 9412060343 | |
| Download: ML20080B890 (2) | |
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UNITED STATES il NUCLEAR REGULATORY COMMISSION
\\.....,8 WASHINGTON. D.C. 2055 % 0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 81 AND 42 TO FACILITY OPERATING LICENSE NOS. NPF-39 AND NPF-85 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353
1.0 INTRODUCTION
By letter dated September 16, 1994, the Philadelphia Electric Company (the licensee) submitted a request for changes to the Limerick Generating Station (LGS), Units 1 and 2, Technical Specifications (TS).
The requested changes would revise TS Surveillance Requirement (SR) 4.7.4.e, and the associated Bases Section 3/4.7.4, to extend the snubber functional testing interval from 18 months ( 25 percent) to 24 months (i 25 percent), and increase the sample plan size, as described in SR 4.7.4.e.1, from 10 percent to 13.3 percent.
2.0 EVALUATION The current LGS, Units 1 and 2, TS SR 4.7.4.e requires that at least every 18 months a representative sample of each type of snubber be tested using either of the sample plans described in TS Sections 4.7.4.e.1 or 4.7.4.e.2.
These sample plans are used to determine the population of snubbers or compensating struts that will be tested for functionality during the testing interval.
TS Section 4.7.4.e.1 identifies the testing requirements for a percent of the total population of snubbers and compensating struts, whil TS Section 4.7.4.e.2 establishes the representative sample size of 37 restraints.
These functional tests incorporate the recommendations of the American Society of Mechanical Engineers (ASME) and the American Nuclear Standards Institute (ANSI) Operations and Maintenance (0M) standards for snubber and compensating strut testing.
Amendments Nos. 54 and 19 to LGS, Units 1 and 2, Facility Operating License Nos. NPF-39 and NPF-85, endorsed ASME/ ANSI OM-1990 Addenda to ASME/ ANSI OM-1987, Part 4, " Examination and Performance Testing of Nuclear Power Plant Dynamic Restraints." However, the staff did not approve the extension of the restraints' functional testing interval from 18 months to 24 months in conjunction with a 10 percent sample plan size.
Based on available results from testing data, the staff determined that a 15-year period can be accepted as the expected service life for most snubbers, particularly those exposed to a harsh environment. The 18-month period and the 10 percent sample plan size was considered acceptable, because it meant that all snubbers in the plant were likely to be functionally tested every 15 years.
9412060343 941102 PDR ADOCK 05000352 P
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- However, the 24-month period and the 10 percent sample plan size would not achieve this goal.
The staff has recently approved, based on the recommendations of Generic Letter 91-04, " Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle," TS amendments authorizing changes in the frequency of various SRs to accommodate the outages dictated by the new 24-month fuel cycle.
Therefore, the licensee has proposed to revise the sample plan size to assure that all the snubbers in the plant would be functionally tested every 15 years.
The licensee has determined that a change in the sample plan size from 10 percent to 13.3 percent would assure that all snubbers in the plant would be tested every 15 years for the requested testing frequency interval of 24 months.
The staff concurs with the licensee's determination and finds that the proposed TS changes are acceptable to the staff.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 [NVIRONMENTAL CONSIDERATION The amendment changes 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 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (59 FR 50019). 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 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 operation 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:
F. Rinaldi Date:
November 2, 1994
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