ML19350D334

Safety Evaluation Supporting Amends 47 & 52 to Licenses DPR-24 & DPR-27,respectively

ML19350D334
Person / Time
Site:	Point Beach
Issue date:	03/31/1981
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19350D333	List: ML19350D332 ML19350D334 ML19350D336
References
TAC-12955, TAC-12956, TAC-47404, TAC-47405, NUDOCS 8104150270
Download: ML19350D334 (2)

Text

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e SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTCR REGULATION RELATED TO AMENDMENT NO. 47 TO FACILITY OPERATING LICENSE 40. DPR-24 AND AMEN 0 MENT NO. r2 TO FACILITY OPERATING LICENSE NO. OPR-27 WIST.ONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-266 AND 50-301 Introduction The criteria and staff positions pertaining to degraded grid voltage protection were transmitted to Wisconsin Electric Power Company (WEPCO) by NRC generic letter dated June 2,1977. In response to this, by letters dated July 28, 1977, August 24, 1979, January 17, 1980, April 17, 1980 and September 22, 1980, the licensee proposed certain design modifications and changes to the Technical Specifications.

r Discussion and Evaluation The modifications ccnsist of installing three undervoltage relays on each of the two Class 1E 4160-volt buses for each unit. These relays are arranged in a two-out-of-three coincident logic. These relays will monitor the voltage and initiate disconnection of the buses from offsite source if the voltage drops below 88% of nominal bus voltage for more than 13.6 seconds.

Load shedding is being maintained once the diesel generators are supplying power to their respective buses. The licensee's basis for this is that the setpoint initiating the load shed (256 volts + 3%) is low enough (53% of nominal voltage) to eliminate the need to bloa the load-shed feature.

The licensee has also requested changes in the Technical Specification surveillance testing requirements that will " simulate loss of offsite power in conjunction with a safety-injection actuation signal and will simulate interruption and subsequent reconnection of onsite power sources".

We have reviewed the licensee's proposed Technical Specification changes and find that:

The proposed Technical Specification changes to document relay setpoints, surveillance requirements and limiting conditions for operation are acceptable.

The proposed modifications will protect the Class 1E equipment and systems from a sustained degraded voltage of the offsite power source, and the proposed changes to the Technical Specifications meet the staff's require-

ents. Therefore, we conclude that WEPCO's proposed design modification and changes to the Technical Specifications are acceptable.

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. Invironmental Consideration We have determined that the amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental inpact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4), that an environmental inpact statement or negative declaration and environ-

= ental impact appraisal need not be prepared in connection with the issuance of these amendments.

Conclusion We have concluded, based on the considerations discussed above, that:

(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendmnts do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in conpliance with the Comission's regulations and the issuance of these amendments will not be inimical to the cocinon defense and security or to the health and safety of the public.

Cate: March 31, 1981

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