ML20133E978

Application for Amend to License NPF-11,changing Tech Specs Re Vent & Purge Isolation Valve Mod.Fee Paid

ML20133E978
Person / Time
Site:	LaSalle
Issue date:	10/02/1985
From:	Massin H COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20133E980	List: ML20133E978 ML20133F094
References
0701K, 701K, NUDOCS 8510100082
Download: ML20133E978 (3)

Text

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. f'~N Commonwealth Edison

[ ) one First Nationit Plaza. Chic'go. Ilhnois '

[ i O "7 Address Reply 13: Post Offica Box 767

( / Chicago. tilinois 60690 October 2, 1985

.Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Unit 1 Proposed Amendment to Technical Sprification for Facility Operating License W F-ll Vent and Purge Isolation Valve Modification NRC-Docket Nos. 50-373 l

References (a): NPF-18 License Condition 2.C.(8)

Containment Isolation System (b): C. W. Schroeder letter to H. R. Denton dated November 7, 1983.

(c): Technical Specification and Basis 3/4.6.1.8.

(d): NUREG-0123, Standard Technical Specification for GE BWR/5s.

(e): Qualification Report of Clow 8-inch and 26-inch Wafer Valve Assmeblies, Clow Job

1. 84-2842(N),PEI-TR-852202-3, dated June 18, 1985.

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Dear Mr. Denton:

. Pursuant to 10 CFR 50.59, Commonwealth Edison proposes to amend Appendix A, Technical Specification, to Facility Operating License WF-11.

These changes are being submitted for your staff's review and approval.

-Attachment A provides background and discussion. The proposed change is enclosed in Attachment B. The_ attached change has received both Oa-Site and Off-Site review and approval. We have reviewed this amendment request and find that no significant hazards consideration exists. Our review ls documented in Attachment C.

Commonwealth Edison is notifying the State of Illinois of our request for this amendment by transmitting a copy of this letter and its attacnments to the designated State Official.

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ADOCK 05000373 PDR # /OU.<0 s

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n, H. R. Denton October 2, 1985 This modification will be performed during the first refueling outage and the amendment must be approved before startup for Cycle 2. This

.is currently scheduled for March, 1985.

In accordance with the requirements of 10 CFR 50.170, a fee remittance in the amount of $150.00 is enclosed.

Please direct any questions you may have concerning this matter to

.this office.

Three (3) signed originals and thirty-seven (37) copies of this transmittal and its attachments are provided for your use.

r Very truly yours, 1

l Md H. L. Massin Nuclear Licensing Administrator l 1m I

Attachments A: Background and Discussion B: Technical Specification Change to NPF-11 L

C: Evaluation of Significant Hazards Consideration I J: Qualification Report dated June 18, 1985 t-I.

cc: Region III Inspector - LSCS A. Bournia - MIR M. Parker - State of Ill to SUBSCRIBE befogm is e3 0'AND., SWOP day of. / /r & ua , 1985 jibcA.nk

' Notary Puolic

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ATTACHMENT A TECHNICAL SPECIFICATION CHANGE REQLEST LASALLE COUNTY-STATION UNIT 1

SUBJECT:

VENT AND PURGE ISOLATION VALVES MODIFICATION BACKGROUND: During the review of the draft Unit 2 Technical Specifications in 1983 the NRR Staff determined that the 40 second closure time for the 26 inch vent and purge butterfly valves was unacceptable.

A meeting was held at the NRC offices on September 19, 1983 to discuss the problem. Subsequently Commonwealth Edison committed to replace eight 26-inch and two 8-inch vent and purge isolation valves in each unit witn valves which will close in less than or equal to 10 seconds. This must be completed prior to startup following the refueling outage. (References (a) and (b)).

DISCUSSION In response to these requirements, Commonwealth Edison has ordered the aforementioned valves from Clow Corporation. These valves are high performance air operated butterfly valves which meet all requirements for containment vent and purge isolation valves. Since the new valves are qualified to close from an position including the full open (90o) position (Reference (y)),

e Technical Specifications 3.6.1.8, 4.6.1.8 and associated basis 3/4.6.1.8 must be revised to remove the 50 limit on valve opening. This limit was required "until these valves have been demonstrated capable of closing during a LOCA or steam line break accident" (Reference (c)).

In addition the new valves do not contain resilient seals.

Reference (d) requires accelerated leakage rate testing (every 92 days) of vent and purge valves with resilient seals to

" provide early indication of resilient material seal degradation." Since these new valves do not have such material, the once per 92 days leakage surveillance is no longer required and only the requirements of 10CFR50 Appendix J and Technical Specification 4.6.1.2.d apply.

Since these valves are air operated, no thermal overload bypass functions are required. Therefore Technical Specification 3.8.3.3 is revised to delete these valves from table 3.8.3.3-1.

Since these modications will not be performed until the first refueling outage on each respective unit this amendment must not be made effective until startup after the first refueling outage.

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