ML20245K127
| ML20245K127 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/25/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245K123 | List: |
| References | |
| NUDOCS 8905040331 | |
| Download: ML20245K127 (2) | |
Text
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- UNITED STATES -
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NUCLEAR REGULATORY COMMISSION 5
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. WASHINGTON, D C. 20555 E
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k SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELAltD TO AMENDMENT N05.119 AND 122 TO FACILITY OPERATING LICENSE N05. DPR-24 AND DPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEXCH NUCLEAR PLANT. UNIT Nos. 1 AND 2 DOCKET N05. 50-266 AND 50-301
1.0 INTRODUCTION
by letter dated February 24, 1989 and supplemented on March 3, IS89, Wisconsin Electric Power Company (the licensee) submitted an application for. amendments to the Point-Beach Nuclear Plant, Units Nos. I and 2
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licenses. The proposed amendments will revise item 3.b. " Auxiliary Feedwater," of Technical Specification Table 15.3.5-3, " Emergency Cooling." This change is necessitated by the installation of the ATWS mitigating system. actuation circuitry (AMSAC) at Point Beach, which will r-bypass the " Trip of both snain.feedpumps starts motor driven pump" auxiliary feedwater actuation when reactor power is less than 40%.
2.0 EVALUATION The licensee requested the amendment to clarify the permissible bypass conditions of an extsting trip circuit for the motor driven auxiliary feedwater pumps. The proposed amendn,ents would add. a permissible bypass condition for the start of the auxiliary feedwater motor driven pumps upon trip of both main feedwater pumps.. This bypass would be an operational bypass, such that when reactor power is less than 40%, the automatic start of the auxiliary motor driven feedwater pumps would be bypassed upon trip of both main feedwater pumps. This change is based upon the design' arid installation of the AMSAC at Point Beach Nuclear Plant.
The licensee has provided to the NRC a description of the proposed AMSAC for installation at Point Beach Nuclear Plant. This information was j
provided in a letter dated April 23, 1987 and supplemented in letters dated J
December 30, 1987 and March 3, 1988.
In these submittals, it was demonstrated that the AMSAC equipment would have the quality and
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reliability necessary to perform its intended function while minimizing the potential for transients that may challenge the existing plant safety systems. This is accomplished by the use of instrumentation and logic hardware which are separate and diverse from that used in the reactor trip system. The power supplies for AMSAC are also independent and diverse from the reactor protection system power supplies.
Provisions are included in the AMSAC design for maintenance and testability using output bypass switching. The licensee has connitted to a complete end-to-end test of T.he system during each refueling outage and testing of P
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, those portions of AMSAC that can be tested at power, such as bistables, time delays, and logic relays, on a semi-annual basis. The testability provisions and periodic surveillance will provide assurance that the AMSAC is available to reliably perform its intended function.
The only safety related-interface of the AMSAC will be between the AMSAC and the auxiliary feedwater system.
Isolation at this interface will be achieved using electrical isolation devices that have been qualified and tested to class 1E electrical equipment requirements. The licensee has concluded that the provisions in the AMSAC design and installation do not involve an unreviewed safety question, as defined in 10 CFR 50.59.
The Point Beach Nuclear Plant AMSAC design was approved in a safety evaluation by the Office of Nuclear Reactor Regulation, " Compliance with ATWS Rule 10 CFR 50.62," dated August 4,1988. This design, as approved, provided for ali operational bypass at 40% reactor power.
Since this is an administrative change to clarify an AMSAC-related requirement which is required under 10 CFR 50.62, and to enhance the technical specifications, the staff finds the proposed change acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change an inspection or surveillance requirement. The 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 occupa-tional radiation exposure. The Comission has previously published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 651.22(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 these amendments.
4.0 CONCLUSION
l 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, and (2) such activities will be conducted in compliance with the Comission's regulations, and 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: Lawrence E. Kokajko l
Dated:
April 25,1989
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