ML20203P476

Notice of Violation from Insp on 860213-0312

ML20203P476
Person / Time
Site:	LaSalle
Issue date:	04/27/1986
From:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20203P473	List: IR 05000373/1986007 ML20203P472 ML20203P476
References
50-373-86-07, 50-373-86-7, 50-374-86-08, 50-374-86-8, NUDOCS 8605070314
Download: ML20203P476 (2)

Text

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NOTICE OF VIOLATION Commonwealth Edison Comapny Docket No. 50-373 Docket No. 50-374 As a result of the inspection conducted on February 13 through March 12, 1986, and in accordance with the General Policy and Procedure for NRC Enforcement Actions (10 CFR Part 2, Appendix C), the following violations were identified:

1. Technical Specification 6.2.A requires detailed written procedures including applicable checkoff lists covering various operations of the facility to be prepared, approved and adhered to:

a. Item 6.2.A.1 requires the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Section 4 of this guide requires procedures for startup, operation, and shutdown of safety related BWR systems including the Reactor Water Cleanup System.

b. Item 6.2.A.6 requires procedures for preventive and corrective maintenance operations which could have an effect on the operation of the facility.

10 CFR 50 Appendix B Criterion V states that activities affecting quality shall be prescribed by . . . procedures. . . of a type appropriate to the circumstances. . .

Contrary to the above, on March 2, 1986, the licensee failed to adhere to procedure, LOP-RT-05, for the Unit 2 Reactor Water Cleanup System which caused the system to isolate.

Contrary to the above, the licensee's corrective maintenance procedure for replacing the Unit 1 Standby Liquid Control System explosive valves was inappropriate in that it failed to assure the system piping was properly filled and vented which resulted in the unnecessary fast start of the "1B" Emergency Diesel Generator on February 26, 1986.

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

2. Technical Specification 4.4.4.C requires the reactor coolant conductivity to be determined at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the continuous conductivity monitor inoperable when not in Operational Conditions 1, 2, or 3.

Contrary to the above, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sample was missed for Unit 1 on February 18, 1986, when the continuous conductivity monitor was inoperable.

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

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Notice of Violation 2 .

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 item of violation: (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violation; and (3) the date when full compliance will be achieved.

Consideration may be given to extending your response time for good cause shown.

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Charles E. Norelius, Director Division of Reactor Projects 1

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