ML20237J779

Notice of Violation from Insp on 870621-0801.Violation Noted:Msiv 1B Inoperable for Maint & Open for Over 13 H While Reactor Remained in Mode 2 (Startup) & Licensee Exceeded 25% Extension of Some Surveillance Intervals

ML20237J779
Person / Time
Site:	Braidwood
Issue date:	08/25/1987
From:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20237J756	List: IR 05000456/1987023 ML20237J754 ML20237J779
References
50-456-87-23, NUDOCS 8709040071
Download: ML20237J779 (2)

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, , NOTICE OF VIOLATION l l

Commonwealth Edison Company Docket No. 50-456 l As a result of the inspection conducted on June 21 through August 1, 1987, and in accordance with the " General Po~1cy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C ( 985), the following violation was identified:

1. Technical Specification 3/4.7.1.5 requires each Main Steam Isolation l Valve (MSIV) to be operable in Modes 1, 2, and 3. In Mode 2, with one  !

MSIV inoperable, the valve must be maintained closed in order to continue '

operation. Otherwise, the reactor must be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Hot Shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Contrary to the above, on June 5 and 6, 1987, the 18 MSIV was inoperable for maintenance, and open for over 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> while the reactor remained in Mode 2 (startup).

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

2. Technical Specifications, Paragraph 4.0.2, requires that surveillance shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. l Contrary to the above the licensee exceeded the 25% extension of some surveillance intervals. Examples of these failures to perform the surveillance within the extended time interval are as follows:

a. On May 4,1987, while preparing to perform quarterly surveillance 18wVS 0.5-2.1, "ASME Surveillance Requirements for SX Valves," the licensee discovered that the critical date (normal frequency plus ,

25%) for the surveillance had been exceeded. l l

b. On May 27, 1987, the licensee discovered that surveillance 18w0S 3.3.6-1, " Accident Monitoring," had exceeded its critical date due to a scheduling error,

c. On June 17, 1987, the licensee discovered that 18w0S 3.2.1-808 had exceeded its critical date due to a scheduling error. The original computer data input had a frequency of 550 days. The actual i Technical Specification requirement is 92 days. On February 9, 1987, the schedule error was noted and the frequency was changed to 92 days. When the frequency was changed, the licensee failed to perft:m the surveillance and change the next due date which would have prevented exceeding the critical date.

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

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Notice of , Violation 2

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i 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; ano (3) the date when full compliance will be achieved.  ;

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

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AUG 2 51987 Oh04fw -

Dated Charles E. Norelius, Director  !

Director of Reactor Projects i 1

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