ML20113E357

Application for Amends to Licenses DPR-24 & DPR-27, Consisting of Tech Spec Change Request 103,re Power Operation Limitations Based on Number of Operating Reactor Coolant Pumps.Fee Paid

ML20113E357
Person / Time
Site:	Point Beach
Issue date:	04/10/1985
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20113E359	List: ML20113E357 ML20113E364
References
TAC-57555, TAC-57556, NUDOCS 8504160260
Download: ML20113E357 (3)

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Wisconsin Electnc eona couranr 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 April 10, 1985 CERTIFIED MAIL Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKETS 50-266 AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 103 REACTOR COOLANT PUMP OPERATION POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with 10 CFR 50.59 (c) , Wisconsin Electric Power Company (Licensee) hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27 for Point Beach Nuclear Plant, Units 1 and 2, respectively, to incorporate changes into the plant Technical Specifications. The proposed changes, which are discussed in greater detail below, involve power operation limitations based on the number of operating reactor coolant pumps at Point Beach Nuclear Plant. These changes are necessitated by the findings of a review begun after the completion of Licensee Event Report 84-005-00. These changes are also necessitated by the basis of the new reload transition safety report performed to address the reanalysis of various accidents described in the Final Safety Analysis Report (FSAR) for the use of optimized fuel assemblies in core fuel reloads.

Details of the major changes requested in this license amendments application are discussed below. These changes are identified with margin bars in the attached proposed Technical Specification pages.

1. Specification 15.3.1.A.l.a This proposed specification is an addition to the Technical Specifications and would require that, except for testing, at least one reactor coolant pump shall be in operation when the reactor is critical.

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Mr. H. R. Denton April 10, 1985

2. Specification 15. 3.1. A. l. a (1)

Existing Specification 15.3.1. A.l.b (1) has been renumbered.

3. Specification 15.3.1.A.l.a(2)

Existing Specification 15.3.1.A.1.b(2) has been renumbered.

4. Specification 15.3.1.A.1.a(3)

This proposed specification change requires that, except for testing,_the reactor be shut down and the reactor trip breakers opened within one hour if both reactor coolant pumps cease operating.

5. Specification 15.3.1.A.1.b This is another addition to the Technical Specifications which proposes additional limitation on plant operation.

The specification requires that, except for testing, one reactor coolant pump shall'be in operation when the average reactor coolant temperature is above 350 F.

The specification also permits both reactor coolant pumps to be deenergized provided no operations occur which would result in dilution of system boron concentration, core outlet temperature is maintained at least 10*F below saturation, and the reactor trip-breakers are.open.

6. Specification 15.3.1.A.l.c Existing Specification 15.3.1.A.l.a has been renumbered.

Please note that the second paragraph of the basis for Specification 15.3.1, " Reactor Coolant System", has been revised to reflect the new analysis for optimized fuel assemblies and the specifications mentioned above.

As required by 10 CFR 50.91(a), we have evaluated these changes in accordance with the standards specified in 10 CFR 50.92 to determine whether or not these proposed changes constitute a significant hazards consideration. The changes proposed with l this license amendments application consist of additional limitations, restrictions, or controls not presently contained in the Point Beach Technical Specications. Changes of this nature l are consistent with example (ii) of the NRC guidance provided at 48 Federal Register 14864 as examples of amendments that are

t Mr. H. R. Denton April 10, 1985 considered not likely to involve significant hazards considerations.

Therefore, we conclude that the proposed specifications discussed herein do not involve a significant hazards consideration.

Also enclosed herewith is a check payable to the Nuclear Regulatory Commission in the amount of $150. This check is submitted in accordance with 10 CFR 170.21 as the application fee for this license amendments application.

As required by Commission regulation, we are providing three signed originals and, under separate cover, forty copies of this license snendments application. Please contact us if you have any questions regarding this submittal.

Very truly yours,

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Vice President-Nuclear Power C. W. Fay Enclosures (Check No. 840892 )

Copies to NRC Resident Inspector R. S. Cullen, PSCW Subscribed and sworn to before me this t s.tL day of April 1985.

b31m C. Nmoeu Notary Publid/, State of Wisconsin My Commission expires Qtw //. /9ff .

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