ML20141E516

Revised Application for Amends to Licenses DPR-24 & DPR-27, Changing Tech Specs to Allow Single Reactor Coolant Pump Operation W/Power Above 3.5%

ML20141E516
Person / Time
Site:	Point Beach
Issue date:	02/14/1986
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, Lear G Office of Nuclear Reactor Regulation
Shared Package
ML20141E521	List: ML20141E516 ML20141E548
References
CON-NRC-86-14 TAC-57555, TAC-57556, VPNPD-86-61, NUDOCS 8602250273
Download: ML20141E516 (2)

Text

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l il POnER COMPANY 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 VPNPD-86-61 l NRC-86-14 l February 14, 1986 I

l Mr. H. R. Denton, Director

, Office of Nuclear Reactor Regulation l U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. G. Lear, Project Director PWR Project Directorate No. 1 Genticmon DOCKETS 50-266 AND 50-301 MODIFICATION TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 103 REACTOR COOLANT PUMP OPERATION POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Our letter dated April 10, 1985 requestod licanso amendmonts  ;

for Point Loach Nuclear Plant, Units 1 and 2. Those amendments I l

would change the limiting conditions for operation of the reactor coolant pumps. Subsequently, your letter dated September 6,

, . 1985 requested additional information. We provided that informa-l tion to you in a submittal dated November 1, 1985.

l l Following our last submittal, another question was raised by l your staff regarding proposed Technical Specification 15.3.1.A.l.a.

Tho question was whether or not the Point Beach Nuclear Plant can operato at 10% rated thermal power with natural circulation.

Based on our review of past analyscu and tests of natural l circulation operation, we are submitting a revision to our proposed Technical Specification 15.3.1.A.l.a. The specification

now states that 3.5%, in place of 10%, is the power above which single reactor coolant pump operation is not allowed. Tho ,

specification has also boon revised regarding action taken in l f

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Mr. H. R. Denton February 14, 1986 Page 2 +

the event of the loss of both reactor coolant pumps stating that if both pumps are lost while power is greater than 3.5%,

reactor shutdown shall commence immediately and reactor trip breakers opened within one hour. We feel that this revision provides a specification which is justifiable in reference to the existing analysis in Section 14.1.11 of the FSAR. The proposed technical specifications are attached with specific changes identified by margin bars. .

We have reviewed the 10 CFR 50.91 significant hazards consideration  ;

determination provided with our April 10 application. The modifi-cations to our change request provided with this letter do not change the basis or conclusion of that determination.

We have enclosed three signed originals and 40 copies of this t modification to Technical Specification Change Request 103; }

the revised Technical Specification pages supersede those pages  ;

i provided with our April 10 letter.

i Please contact us if you have any questions.

5 i

Very truly yours,  ;

h'c/  ;

C. W. Fay'  !

Vice President Nuclear Power Enclosurc Copies to R. S. Cullen, PSCW NRC Resident Inspector Subscribe and sworn to before me this ,/ day of February, 1986.

YA$NAJ AL Notary Publfe,

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a$b o,. Wisconsin My Commission expires /Eadf /fff. -

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