ML20205T755

Application to Amend License NPF-18,modifying Tech Specs Re Purge & Vent Isolation Valves.Fee Paid

ML20205T755
Person / Time
Site:	LaSalle
Issue date:	06/11/1986
From:	Allen C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20205T756	List: ML20205T755 ML20205T759
References
1762K, NUDOCS 8606160191
Download: ML20205T755 (3)

Text

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Commonwealth Edison

} 72 West Adams Street, Chic"go, Illinois

'" Address Reply to: Post Offica Box 767 Chicago, Ithnois 60690 -0767 June 11, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Unit 2 Proposed Amendment to Technical Specification for Facility Operating License NPF-18 Vent and Purge Isolation Valve Modification NRC Docket Nos. 50-374 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.

(f): H. L. Massin letter to H. R. Denton dated October 25, 1985.

(g): C. M. Allen letter to H. R. Denton dated December 17, 1985.

(h): Issuance of Amendment NO. 37 to Facility Operating License NPF-ll, LaSalle County Station Unit 1 - E. G. Andensam letter to D. L. Farrar dated April 2, 1986.

^

Dear Mr. Denton:

e .

Pursuant to 10 CFR 50e59, Commonwealth Edison proposes to amend Appendix A, Technical Specification, to Facility Operating License NPF-18.

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

8606160191 860611 PDR ADOCK 05000374

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r H. R. Denton June 11, 1986 Attachment A provides background and discussion. The proposed change is enclosed in Attachment B. The attached change had received both on-Site and off-Site review and approval. We have reviewed this amendment request and find that no significant hazards consideration exists. Our review is documented in Attachment C. References (b) through (h) identify correspondence between Ceco and the NRC that resulted in Amendment 37 to NPP-11 which approved this modification for Unit 1.

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

This modification will be performed during the first refueling outage and the amendment must be approved before startup for Cycle 2.

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.

Very truly yours, i

V C. M. Allen Nuclear Licensing Administrator 1m Attachments A: Background and Discussion B: Technical Specification Change to NPF-18 C: Evaluation of Significant Hazards Consideration cc: Region III Inspector - LSCS A. Bournia - NRR M. Parker - State of Ill SUBSCRIBED AND S N to befoOemethis., -- day of U/ 'f)LL, , 1986

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e ATTAC N NT A TECHNICAL SPECIFICATION CHANGE RBOUEST LASALLE COUNTY STATION UNIT 2

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 with valves which will close in less than or equal to 10 seconds. This must be completed prior to startup following the first refueling outage. (References (a) and (b)).

DISCUSSION In response to these requirements, Commonwealth Edison has ordered the aforementioned valves from Clow corporatior . 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 any position including the full open (90') position (Reference (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 10 CFR 50 Appendix J and Technical Specification 4.6.1.2.d apply.

No thermal overload bypass functions are required since these valves are air operated. 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 Unit 2 this amendment must not be made effective until startup after the first refueling outage. This Technical Specification change is the same as the one approved for Unit 1 in reference (h).

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