ML20235Q795

Application for Amends to Licenses DPR-24 & DPR-27, Consisting of Tech Spec Change Request 128,revising Item 3.b, Auxiliary Feedwater of Tech Spec Table 15.3.5-3, Emergency Cooling

ML20235Q795
Person / Time
Site:	Point Beach
Issue date:	02/24/1989
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20235Q797	List: ML20235Q795 ML20235Q952
References
CON-NRC-89-024, CON-NRC-89-24 VPNPD-89-109, NUDOCS 8903030037
Download: ML20235Q795 (2)

Text

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[/ ' ' 231' W. Michigart Ro. Box 2046, Mdwoukee, WI 53201 (414)221-2345 )

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' February 24, 1989  !

T ~ Document Control' Desk- .

10 CFR 50.90 )

U.S. NUCLEARLREGULATORY COMMISSION Mail' Station PI-137 LWashington, .D.C. :20555 Gentlemen:

DOCKETS'NOS. 50-266'AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST 128 CLARIFICATION OF MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP START FOLLOWING INSTALLATION OF AMSAC f POINT BEACH NUCLEAR PLANT In accordance with the requirements of 10 CFR 50.59 and 50.90,

Wisconsin Electric Power Company (Licensee) hereby submits an application for amendments to Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2.

LThese proposed amendments will revise Item'3.b, " Auxiliary Feed-water," of Technical Specification Table 15.3.5-3, " Emergency Cooling."- We have enclosed herewith revised Technical Speci-fication;pages containing the proposed clarification and have identified'those changes with margin bars.

In a letter dated August 4, 1988, the NRC forwarded the Safety

?r s Evaluation by the Office of Nuclear Reactor Regulation for s . licensee's compliance with the ATWS Rule, 10 CFR 50.62. In that report, the'NRC staff concluded that the-AMSAC (ATWS mitigating system actuation circuitry) design proposed by the licensee for the Point' Beach' Nuclear Plant' Units'l and'2,'is acceptable and is in compliance with the ATWS Rule.

The topic of whether and to what' extent Technical Specifications are required for the AMSAC was deferred in the August 4, 1988, letter pending the staff's further review of ATWS requirements to the criteria in the Commission's Policy Statement on Technical Specification Improvements.

Although the resolution of Technical Specifications for the AMSAC, also referred to at Point Beach as the Loss of Feedwater Turbine Trip, is still pending, we believe a clarification of an existing specification is necessary following the AMSAC installation.

Specifically, Item 3b of Table 15.3.5-3 lists the number of channels and minimum degree of redundancy for the " Trip of Both Main Feedpumps Starts Motor Driven Pumps" auxiliary feedwater ,

actuation. Following the AMSAC implementation at Point Beach, this actuation will not occur when reactor power, as sensed by h035 8903030037 890224 ^

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February 24, 1989-Page;2-A.T ifirst1 stage. turbine pressure,is less than.44%. We therefore 4 . propose in.this. license amendments application that this' item

-. include a-clarification under'" Permissible Bypass Conditions" to

read, " Reactor Power is'less'than 44%."

In our.-letter. dated October 10, 1986, we had committed to instal-ling,the'AMSAC equipment during the first refueling outages after

a' twelve month' period following the NRC approval of our installa-tion. We are presently planning on improving that schedule and completing.the AMSAC installation in Point Beach Unit 1 during the spring 1989 refueling outage and in Unit 2 during the fall 1989 refu.eling outage. Accordingly, we request you issue these amend-ments effective upon startup from these outages. Scheduled outage completion dates are presently May 12, 1989, for Unit 1 and

-November 17, 1989,-for Unit,2.

As. required by.10 CFR 50.91(a), we have evaluated this proposed clarification in'accordance with the standards specified in

10 CFR'50.92 to determine if the proposed changes constitute a ,

significant hazards consideration. The change clarifies the  !

permissible bypass conditions of an existing trip circuit for the I motor driven auxiliary feedwater pumps. The design and installa-tion of the AMSAC, which results in the need for the clarification identified.by this change, has previously been reviewed and approved by the Commission in its August-4, 1988, safety evalu-ation report (SER). Since this conditional actuation of the auxiliary feedwater pump start following main feedwater pumps trip )

was' evaluated in that SER, we conclude that this change does not

/ involve a significant-hazards consideration.

We have' enclosed a signed original and three copies of this license amendments application. Recent. revisions to 10 CFR 170.12

now preclude. submission of an application fee. Please contact us if you'have any questions concerning this-application.

Very-truly yours, uy C.'W. Fe y Vice President Nuclear Power Copies to NRC Resident Inspector NRC Regional Administrator, Region III R. S. Cullen, PSCW and sworn to before me

.SubscribegdayofFebruary, this 2.81 1989 l

40 Notary Public, State'of Wisconsin

! 'My. Commission expires- I-27-70

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