ML20136G125

Application for Amend to License NPF-11,changing Tech Specs by Adding Excess Flow Check Valve to Instrument Line for Containment Floodup Measurement Sys During First Refueling Outage.Fee Paid

ML20136G125
Person / Time
Site:	LaSalle
Issue date:	11/13/1985
From:	Massin H COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20136G129	List: ML20136G125 ML20136G239
References
0880K, 880K, NUDOCS 8511220258
Download: ML20136G125 (3)

Text

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Commonwealth Edison

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) one First N1tional Plaza. Chicago. Illinois "7 Address Reply to: Post Office Box 767

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(/. Chicago. tilinois 60690.

November 13, 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 Specification for Facility Operating License NPF-ll Addition of an Excess Flow Check Valve NRC Docket Nos. 50-373 Reference (a): UFSAR Table 6.2-21

Dear Mr. Denton:

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

Attachment D is a single line diagram of the modification.

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.

The modification to add an excess flow check valve to the

. instrument line for the containment flood-up measurement system 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. Adding this valve, which already exists on Unit 2, makes Unit 1 look like Unit 2, which is a human factors concern. The instrument also provides a direct indication of containment flood-up level for use in the Emergency )

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H. .R. Denton November 13, 1985 y

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 of fice.

I i-Three (3) signed originals and thirty-seven (37) copies of  ;

this transmittal and its attachments are provided for your use.

Very truly-yours, Nuclear Licensing Administrator WH. L. Massin bs Attachments A: Background and Discussion B: Technical Specification Change to NPF-ll C: Evaluation of Significant Hazards Consideration D: Diagram of Modification cc: Region III Inspector - LSCS A. Bournia - NRR M. Parker - State of Ill to SUBSCIBED.ANDSWOgR befo me t)11s /$ s day af MIuhLljt , 1985 Y '- Olsh

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ATTACHMENT A TECHNICAL SPECIFICATION CHANGE REQUEST LASALLE COUNTY STATION UNIT 1 ADDITION OF AN EXCESS FLOW CHECK VALVE BACKGROUND Under certain post accident conditions, the primary containment must be flooded above the top of the active fuel to provide for long term recovery. I DISCUSSION To provide instrumentation to allow for potential conditions as described above a level indicator is being added to cover the level range in question. The level measurement system requires two inputs, a level signal (actually static water head plus over pressure), and a pressure signal (overpressure signal). The pressure transmitter which feeds this system must be connected to the primary containment atmosphere. The addition involved adding a three-quarter inch instrument line to a 2 inch vent line entering the primary containment at penetration M-21 inboard of the inboard isolation valve (Reference a).

This instrument line is designed to statisty the requireoants of General Design Criteria 56 . To perform its function, this instrument line has been designed to meet the requirements of Regulatory Guide 1.11 (Safety Guide 11). These lines are Seismic Category I and terminate in an instrument which is Seismic Category I. The line is provided with a manual isolation valve and an excess flow check valve. (Refer to Attachment D).

This excess flow check valve is a primary containment isolation

valve and therefore must be added to Technical Specification Table 3.6.3-1. The updated FSAR will be revised at the next update to include this change. This modification is scheduled to be performeo

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during first refueling outage.

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