ML20116K531
| ML20116K531 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/10/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116K523 | List: |
| References | |
| NUDOCS 9211170245 | |
| Download: ML20116K531 (3) | |
Text
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UNITED STATES i
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%,.....f SAFETY EVALVATION BY THE OFFICE OF NVCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. i n T0 FACILITY OPERATING LICENSE NO. DPR-20 CONSUMERS POWER COMPANY PAllSADES PLANT D_0CKET NO. 5Q-2H
1.0 INTRODUCTION
By letter dated June 12, 1992. Consumers Power Company (CPCo or the licensee) requested an amendment to the Technical Specifications (TS) appended to Facility Operating License No. DPR-20 for the Palisades Plant.
The amendment deletes the qualifying phrase "after the reactor has been made critical" from TS 3.7.2.
This change allows testing flexibility when tFe plant is abova 325*F, but not yet critical.
2.0 EVALUATION The existing Electrical System TS, Section 3.7.1, is applicable when the primary coolant system is above 325'F.
The existing associated action statement, 3.7.2, applies only when the reactor is critical. A strict.
interpretation of these two specifications would allow required electrical components to be inoperable for specified time periods, when the reactor is at power, but not when the reactor is_at Hot Shutdown or Hct Standby. This limitation precludes test loading of the diesel generators when the plant is subcritical above 325'F and could require an entry into TS 3.0.3 while in Hot Shutdown for a condition which would be allowable while at full power.- Based on the above considerations, the licensee proposes that the qualifying phrase
...after the reactor has been made critical." be deleted from TS 3.7.2.
The NRC staff has reviewed the information provided by the licensee in support of the proposed TS change and, based on-our review, we find the proposed change to TS 3.7.2 acceptable. The proposed change is consistent with the equivalent Action Statements of the Standard Technical Specifications (STS) for Combustion Engineering Pressurized Water Reactors.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendment. The State official had no comments.
9211170245 921110 PDR ADOCK 05000255 P
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4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The 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 (57 FR 37564).
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 t' amendment.
5.0 CONCLUSION
The staff 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:
A. Masciantonio Date:
hvember 10, 1992