ML20072L399
| ML20072L399 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/23/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072L398 | List: |
| References | |
| NUDOCS 9408310245 | |
| Download: ML20072L399 (2) | |
Text
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UNITED STATES yq
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,o SAFETf EVALUATION BY THE OFFICE OF NVCLEAR REACTOR REGULATIO_t{
RELATED TO AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE N0. NPF-57 PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION. UNIT 1 DOCKET NO. 50-352
1.0 INTRODUCTION
By letter dated June 6,1994, the Philadelphia Electric Company (the licensee) submitted a request for changes to the Limerick Generating Station (LGS), Unit 1, Technical Specifications (TS).
The requested changes would remove the controls for a remote shutdown system control valve and delete the isolation signal for certain primary containment isolation valves from TS Tables 3.3.7.4-1 and 3.6.3-1 respectively, as a result of eliminating the steam condensing mode of the Residual Heat Removal (RHR) system.
2.0 EVALUATION The RHR system steam condensing mode has never been used at LGS, Unit 1.
Further, the remainder of the steam condensing mode components have been removed from service at LGS, Unit 1, during the fifth refueling outage, as authorized by. Amendment No. 65. Currently, valve HV-51-1F0llA, is in the i
locked closed position with its electrical power source removed. The valve's handswitch does not perform any function, and will be removed from the remote shutdown panel.
Therefore, the licensee has revised Table 3.3.7.4-1 to reflect this change.
Similarly, valves HV-C-51-lF103A and HV-C-51-lF104B, are locked closed in their safety-related position with their electrical power source removed.
These valves are no longer required to receive an isolation signal or meet valve closure time, but provide manual containment isolation.
The proposed TS changes reflect the current physical condition in the plant.
The components associated with steam condensing mode have been removed during the Unit 1 fifth refueling outage as per staff authorization in Amendment No.
65, dated January 12, 1994.
Therefore, the staff concludes that the proposed TS changes will not impact the performance of the safety-related function of the RHR system components, and are acceptable.
1 9408310245 940023 PDR ADOCK 05000352 P
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment.
The State of ficial had no comments.
4.0 ENVIRONMENTAL CUSIDERATION 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 comment on such finding (59 FR 37076). 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 Contributors:
T. Liu F. Rinaldi Date:
August 23, 1994