ML20010E136

Application for Amend to Licenses DPR-24 & DPR-27 Submitted as Tech Spec Change Request 68 to Incorporate Addl Restrictions Re Use & Testing of Containment Purge Supply & Exhaust Sys Isolation Valves,Per NRC Request

ML20010E136
Person / Time
Site:	Point Beach
Issue date:	08/28/1981
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20010E137	List: ML20010E136 ML20010E141
References
TAC-44877, TAC-44878, NUDOCS 8109030132
Download: ML20010E136 (2)

Text

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1 l Wisconsin Electnc voun courm i 231 W. MICHICAN, P.o BOX 2046 MllWAUKEE, WI 53201 1

August 28, 1981

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J Mr. Harold R. Denton, Director hg "

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U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 - 3EP O 21981* ~

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Dear Mr. Denton:

f n g DOCKET NOS. 50-266 AND 50-301 ,

TECHNICAL SPECIFICATION CHANGE REQUEST NO. 68 CONTAINMENT PURGE VALVE OPERABILITY POINT BEACH NUCL2AR PLANT, UNITS 1 AND 2 In accordance with Section 50.59 of 10 CFR Part 50, Wisconsin Electric Power Company (Licensee) hereby applies for amendments to Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The purpose of these license amendments is to incorporate, as requested by the Nuclear Regulatory Commission Staff, additional restrictions into the Point Beach Nuclear Plant Technical Specifications regarding use and testing of the containment purge supply and exhaust system isolation valves.

In a letter dated November 28, 1978, the NRC requested licensees of operating reactors to respond to generic concerns about containment purging and venting during normal plant operation. Wisconsin Electric responded to this request by letter dated January 16, 1979. In that letter, we committed to obtain requested design and analytical data from the manufacturer of the Point Beach Nuclear Plant purge supply and exhaust isolation valves and to limit purging to the minimum necessarv during normal operation.

On April 11, 1979, we notifi'.J the NRC that data received from the purge valve manufacturer indic=t- chat the containment purge isolation valves may not be assured of closi' g fro. ne 1!11 open position if subjected to the postulated containment pr:. sure trz...si .c following a design basis loss of '

coolant accident. Accordingly, we committed at that time to maintaining the l containment purge supply and exhaust isolation valves shut during power operation I

and hot shutdown conditions. In our letter dated September 6, 1979, we confirmed i this commitment to limit purge valve operations to conditions of cold shutdown and noted that the plant procedures had been revised to reflect this commitment.

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Mr. H. R. Denton August 28, 1981 By letter dated November 19, 1979, the NRC requested licensees to commit to an interim position on containment purging and venting which included keeping the containr nt purge supply and exhaust isolation valves closed except for the cold shutdown and refueling modes pending analysis and modifica-tions addressing operability of these valves. We again confirmed our previous commitinents in a letter dated January 9,1980.

Most recently, in a letter dated July 21, 1981, the NRC has requested that we submit Technical Specification changes requiring closure of the contain-ment purge supply and exhaust valves in all but the cold shutdown and refueling conditions and requiring periodic surveillance testing of these valves. The first of these requests is addressed in a new Section C. to Specification 15.3.6. The periodic surveillance requirement has been proposed as an addition to Specification 15.4.4. The attached proposed Technical Specification pages contain the specific changes. The additions on each page have been identified by margin bars.

Ir accordance with the provisions of 10 CFR Section 170.22, Wisconsin Electric has determined that, as permitted by the second portion of footnote 2 to this section, these facility license amendments should be exempt from fees.

This license amendment application is the result of a written Commission request, namely Mr. R. A. Clark's letter dated July 21, 1981. The subject of the amendment has no safety significance since it imposes additional restrictions and conforms with tne guidance provided. That is, the proposed Technical Specification additions contained herewith are in agreement with the content of the wording suggested by the Commission in the attachment to the July 21, 1981 letter. Finally, the issuance of these license amendments ard the ,oroposed Technical Specifications is primarily for the convenience of the Commission s nce the licensee has, on several occasions, previously committed in writing i

to maintaining the containment purge supply and exhaust valves shut and has tested these valves for leak rate on at least cold shutdown intervals since the plant commenced operation in 1970. Accordingly, no fee for review and approval of this license amendment request is necessary.

We enclose herewith three signed originals and forty copies of the license amendment request and the attached proposed Technical Specification page changes. Please contact us if you have any questions regarding our response to your request for these changes.

Very truly yours, n

Sol Burstein Exe utive Vice President Copy to: NRC Resident Inspector Point Beach Nuclear Plant Subscribed and sworn to before me This pan day of Agu s t . 1981

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