ML20154R007

Application for Amend to License NPF-11,modifying Table of Primary Containment Isolation Valves to Identify New Excess Flow Check Valves Being Installed During Second Refuel Outage.Fee Paid

ML20154R007
Person / Time
Site:	LaSalle
Issue date:	05/23/1988
From:	Allen C COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20154R011	List: ML20154R007 ML20154R013
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 4677K, GL-84-23, NUDOCS 8806070189
Download: ML20154R007 (4)

Text

._____________

j ' ';

, , , 'N Commonwealth Edison

. [ '_ ) One First National Plaza. Chicago, Illinois

\ - Address Reply to: Post Offce Box 767

\ Chicago,luinois 60690 0767 May 23, 1988 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

LaSalle County Station Unit 1 Proposed Amendments to Primary Containment Isolation Valves Technical Specification for Facility Operating License NPF-ll NRC Docket No. 50-373 References (a): Federal Register Volume 51, No. 44 dated March 6, 1986.

Dear Sir:

Pursuant to 10 CFR 50.90, Commonwealth Edison proposes to amend Facility Operating License NPF-ll. This amendment is being submitted for your

-staff's review and approval with Reference (a).

This change modifies the table of primary containment isolation valves to identify new excess flow check valves being installed during the second refuel outage. These valves are being added as part of a modification to improve the reactor water level instrumentation system as required by NUREG-0737, Item II.F.2 and Generic Letter 84-23. Completion of this modification satisfies License condition 2.C.(30)(1) which should be deleted from the Facility Operating License. Also included in this request are corrections of typographical errors in Table 3.6.3-1.

This proposed amendment is administrative in nature and is similar to one approved for LaSalle Unit 1 Amendment 34. That amendment dated February 10, 1986 added an excess flow check valve (1CM 102) for containment flood up instrumentation. This amendment should become effective 45 days after approval.

Attachment A provides an introduction and discussion. Attachment B provides copies of the changes to be made to the Technical Specifications.

Commonwealth Edison has reviewed this document and finds that no significant hazards exists. This review is documented in Attachment C. l i )

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CCo6070189 880523 004I PDR ADOCK 05000373 P DCD g

US VRC May 25, 1988 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.

In accordance with 10 CFR 170, a fee remittance in the amount of

$150.00 is enclosed.

If you have any additional geestions regarding this matter, please contact this office.

Very truly yours, h -

C. M. Allen Nuclear Licensing Administrator 1m Attachments

Enclosure:

$150.00 Fee cc: P. Shemanski - NRR Regional Administrator - RIII NRC Resident Inspector - LSCS M.C. Parker - IDNS SUBSCRIBED AND y to before 'me this tr - day of a ljAb . , 1988 i ' L G. -

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' Notary Public

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ATTACHMENT A t<

TECHNICAL SPECIFICATION CHANGE REQUEST LASALLE COUNTY STATION UNIT 1 BACKGROUND AND DISCUSSION BACKGROUND Generic Letter 84-23 indicated a large error could occur in indicated reactor vessel water level under certain accident conditions. This potential error was required to be eliminated by improvements to existing instrumentation by NUREG-0737, II.F.2. This requirement was made part of the Unit 1 license in License Condition 2.C.(30)(i). j Commonwealth Edison (CECO) provided a response to Generic Letter 84-23 in a letter dated June 10, 1986 in which certain design changes were proposed to correct this problem. The NRC Staff accepted our proposed solution in a letter dated March 2, 1987.

Installation of the proposed modification has resulted in two additional instrument lines which pass through the primary containment in existing containment penetrations. General Design Criteria 55 requires the use of isolation devices for these lines. Excess flow check valves and manual isolation valves were installed outside the containment to perform this function. The excess flow check valves acting as automatic primary containment isolation valves must be added to Technical Specification Table 3.6.3-1.

DISCUSSION The proposed Technical Specification amendment adds the excess flow check valves installed as automatic isolation devices to Table 3.6.3-1. These valves are designated as 1B21-F570 and 1B21-F571. In addition, the following clerical changes are proposed.

(1) Correction of the following typographical errors in Table 3.6.3-1 on page 3/4 6-31:

Table Item Error as Listed Correction 3.6.3-1.c.62 ICM004 1CM004 3.6.3-1.c.63 ICM002 1CM002 3.6.3-1.c.64 ICM012 1cM012 3.6.3-1.c.65 ICM010 1CM010 3.6.3-1.c.66 IVQ061 1VQ061 (Change I to 1)

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(2)' Movement of Items 69 and 70 to to new page 3/4 6-31a for better margins -

These changes are administrative in nature and are similar to the one approved in Amendment 34 transmitted by letter from E.G. Adensam dated February 10, 1986 to add a containment isolation valve (ICM 102) for the containment flood up instrumentation.

4677K