ML20247R642

Application for Amends to Licenses NPF-11 & NPF-18,adding Statements to Allow Periodic Cycling of Pneumatically Operated Vq Valves Per Mfg Recommendation

ML20247R642
Person / Time
Site:	LaSalle
Issue date:	06/01/1989
From:	Morgan W COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
Shared Package
ML20247R646	List: ML20247R642 ML20247R649
References
0148T, 148T, NUDOCS 8906070283
Download: ML20247R642 (3)

Text

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., . Commonwealth Edison -  !

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• ',43 "k *4 -. 72 West AddressAdams Reply to: Post Street Office Chicago, Box 767 Illinois '!

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,I l1 Dr. Thomas E. Murley, Director .

ii Office of Nuclear Reactor Regulation 4 U.S.' Nuclear-Regulatory Commission- 1 1

. Washington, DC- 20555 l'  ;

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Subjects, LaSalle County Station Units 1.and 2 '

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2 Application for Amendment to Facility l Operating Licenses NPF-ll'and NPF-18' i Periodic Cycling of the Pneumatically Operated VQ Valves l NRC Docket Nos. 50-373 and 50-374 Dr. Murley:;

Pursuant to 10 CFR 50, Commonwealth Edison is'hereby applying for an amendment to Facility Operating Licenses NPF-ll and NPF-18, Appendix A - -1 LTechnical Specifications. The. purpose of this amendment is to add the necessary statements to allow the periodic cycling of pneumatically operated

'VQ valves per the n. manufacturer'u' recommendation. 'j i

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1 Attachment A contains, background information.and justification for j the proposed change. Attachment B contains the proposed change to.the .' j Technical' Specifications. The proposed change has been zeviewed'and approved 'j by both On-Site and Off-Site Review in accordance with Commonwealth Edison 'l  !

Company procedures. This amendment request has.been evaluated in accordance with 10 CFR 50.92(c) and it was determined that no significant hazards:

consideration exists. That evaluation is documented in Attachment C.

Attachment D provides additional support material (selected UFSAR references) :J which will aide in the review of the proposed amendment request.

Commonwealth Edison is notifying the State of Illinois of our application for amendment by transmitting'a copy of this letter and .1ts  ;

attachments to the designated State Official.

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$ 8906070283 89060'1

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Dr..T.E. Murley" June 1,.1989 h

Please. direct any questions you may have regarding this matter to this office.

r very truly yours, M

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W.E@ organ Nuclear Licensing Administrator

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Attachments As. Background and Information B Proposed Technical Specification Change C Evaluation of Significant Hazards Consideration D Additional Support Material: Selected UFSAR References cc:- Senior Resident Inspector, LaSalle

P. Shemanski - Project Manager, NRR Office of Nuclear Facility Safety - IDNS Regional Administrator - Reg.lon III

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SUBSQRIBED AND SWORN to ;l "0FFICIAL SEAL"  ? i

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. , A IACilM MI_A TECHNICAL SPECIFICATION CHANGE REOUEST LMALLE_ COUNTY STATION UNITS 1 AND 2 DMTSRQUND:

During the first refuel outage for both Units 1 and 2, ten motor operated valves in the primary vent and purge system were replaced with pneumatically actuated valves. Bettis Corporation, the manufacturer of the valve actuators, recommends that these valves be cycled monthly to exercise the dynamic seals in the actuators. The intent of this cycling is to extend the life of the seals, which will reduce the required maintenance on the valves. The valves are presently cycled quarterly in Conditions 4 or 5.

During the review of Technical Specifications 3.6.1.8 and the Bases for Technical Specifications 3/4.6.1.8, to allow for this periodic cycling when in Conditions 1, 2 or 3, it was determined that the present Limiting Condition for Operation requires entry into the action statement even if only one valve in a line is open and is not consistent with Specification 3.6.3, " Primary Containment Isolation Valves".

The following valves that are being discussed:

1/2VQO26 Suppression Pool Vent and Purge Outboard Inlet Valvo 1/2VQO27 Suppression Pool Vent and Purge Inboard Inlet Valve 1/2VQO31 Suppression Pool Vent and Purge Inboard Outlet Valve 1/2VQ040 Suppression Pool Vent and Purge Outboard Outlet Valve 1/2VQ043 Suppression Pool Vent and Purge Nitrogen Supply Valve 1/2VQO29 Drywell Vent and Purge Outboard Inlet valve 1/2VQO30 Drywell Vent and Purge Inboard Inlet Valve 1/2VQO34 Drywell Vent and Purge Inboard Outlet Valve 1/2VQO36 Drywell Vent and Purge Outboard Outlet Valve 1/2VQ042 Drywell Vent and Purge Nitrogen Supply Valve DISCUSSION:

Presently, this rpecifict.tica would require a shttdwon if either of the valves in series is open, even though the penetration is isolated by another valve. This is not the intent of this specification in that the intent is not to have these penetrations open when not needed for inerting, deinerting or pressure control.

These changes are being proposed to make Technical Specification 3.6.1.8 consistent with Technical Specification 3.6.3, since there is a minimum of two contianment isolation valves in series in each primary containi..ent penett ation. Therefore, primary containment would be maintained during the condition where one va}ve was closed in each containment penetration.

Based on this, Commonwealth Edison Company's LaSalle County Nuclear Power Station is proposing to amend the Unit 1 License, NTF-11 and the Unit 2 License, NPF-18, as shown in the Attachment, Proposed Page Changes to the Technical Specification for Operating Licenses NPF-11 and NPF-18, to allow f r4r the individual cycling of the above stated valves in Conditions 1, 2 and 3.

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