ML20248E179

Notice of Violation from Insp on 890130-0313.Violations Noted:Licensee Failed to Review & Verify Completion of Field Change Request L85-87 & Licensee Had Not Reported ESF Actuations Via Emergency Notification Sys

ML20248E179
Person / Time
Site:	LaSalle
Issue date:	03/23/1989
From:	Mckenna E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20248E159	List: IR 05000373/1989003 ML20248E155 ML20248E179
References
50-373-89-03, 50-373-89-3, 50-374-89-03, 50-374-89-3, NUDOCS 8904120150
Download: ML20248E179 (2)

Text

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p NOTICE OF VIOLATION Commonwealth Edison Company Docket No. 50-373 Docket No. 50-374 As a result of the inspoction conducted on January 30 through March 13, 1989, and in accordance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the following violations were identified:

A. Technical Specification 6.2.A states, in part:

Detailed written procedures including applicable checkoff lists covering I items listed shall:be prepared, approved and adhered to: '

1. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 which includes administrative procedures.

Administrative procedure LAP-1300-5, Revision 10, Field Change Requests (FCR), steps F.22, F.23 and F.24 states, in part, the following:

F.22 Verifies that the work was completed by FCR and that the revised documents are updated acceptably.

F.23 Reviews and approves final disposition of FCR.

F.24 Verifies completion of FCR......

Contrary to the above, on July 13, 1987, which was the completion of modification M-1-2-84-136, Replacement of the Barton Differential Pressure (dp) Switches With Static-0-Ring (SOR) dp Switches, the licensee  ;

failed to review and verify completion of FCR L85-87 which required the installation of a pulsation dampener on SOR switch 2E31-N012 AA. The dampener was not installed but the drawing was changed and approved reflecting the installation of the dampener. This also made the drawing incorrect, not reflecting the actual plant configuration.

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1 This is a Severity Level IV violation (Supplement I).

B. Title 10, Code of Federal Regulations (CFR), Part 50.72, Immediate Notification, Section 2(ii) states, in part, "... . the licensee shall notify the NRC as soon as practical and in all cases within four hours

.. - of any event or condition that results in manual or automatic actuation of any Engineered Safety Feature (ESF). . . . . . . .

Contrary to the above, on February 4, 1989 and again on February 6, 1989, there had been an ESF actuation in that the Residual Heat Removal (RHR) shutdown cooling pump suction valve 2E12-F008 isolated on a high flow l signal and the licensee had not reported the actuations via the Emergency 1 Notification System (ENS). e.-.

O

' Notice of Violation 2 This is a Severity Level IV violation (Supplement I)..

C. Unit 1 Technical Specification Limiting Condition for Operation 3.8.3.1 requires that in Operational Condition 1, 2, or 3, that the AC circuits that supply power to all drywell lighting circuits inside primary containment be de-energized. I Contrary to the above, on November 28, 1988 at 5:00 p.m. (CST) with Unit 1 in Operational Condition 1, breakers in the Unit 1 Regular Lighting '

Cabinet 110 circuit, which supply power to the drywell lights, were found in the energized position. <

This is a Severity Level IV violation (Supplement I).

With respect to item C., the inspection showed that action had been taken to correct the identified violation and to prevent recurrence. Consequently, no reply to the violation is required and we have no further questions regarding this matter. With respect to items A. & B., pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.

MAR 2 31989 hyg k Dated Eileen McKenna, Acting Chief Reactor Projects Branch 1

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