ML17157B913
| ML17157B913 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/14/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17157B912 | List: |
| References | |
| NUDOCS 9207230099 | |
| Download: ML17157B913 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.122TO FACILITY OPERATING LICENSE NO.
NPF-14 PENNSYLVANIA POWER AND LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
SUS UEHANNA STEAM ELECTRIC STATION UNIT 1
DOCKET NO. 50-354
- 1. 0 INTRODUCTION By letter dated May 21, 1992, the Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (the licensees) submitted a request for changes to the Susquehanna Steam Electric Station, Unit 1, Technical Specifications (TS).
The requested changes would make changes to the Unit 1
Technical Specifications to correct the flow dependent MCPR Operating Limits to be consistent with the licensee's NRC-approved methodology.
Changes to the MCPR TS were approved as part of Amendment Number 118 to Operating License No.
Amendment 118 was issued on May 7, 1992.
- 2. 0 EVALUATION After issuance of Amendment 118, the licensee discovered an error in the calculation of the Unit 1 Technical Specifications flow-dependent MCPR operating limit curve.
The corrected MCPR Operating Limits were entered into the licensee's Powerplex core monitoring system on May 15, 1992 under administrative control and staff agreement.
The licensee is currently operating under these corrected limits and is making this change to the Technical Specifications to make the corrections to the calculational error permanent.
The single calculational error affected TS Figure 3.2.3-1.
The corrected Figure 3.2.3-1 is consistent with the proper implementation of the licensee's NRC-approved licensing methods in support of Unit 1 Cycle 7 operations.
The new curve presented in Figure 3.2.3-1 is more restrictive over the entire range where the recirculation flow controller failure event transient is limiting.
The staff finds this change to be acceptable.
The corrected Figure 3.2.3-1 will ensure reactor operation within its design basis and preserves the validity of the Unit 1 Cycle 7 reload safety analysis.
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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 official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION 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 (57 FR 24675).
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:
J. Raleigh Date:
July 14.
1992
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