ML19242A874

LER 79-041/03L-0 on 790711:procedure for Drywell Equipment Drain Pump Functional Test & Calibr Was in Error.Caused by Implementation of Plant Mod During 1978 Refueling Outage in Which Equipment Pump Level Control Logic Was Revised

ML19242A874
Person / Time
Site:	FitzPatrick
Issue date:	08/02/1979
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19242A871	List: ML19242A870 ML19242A874
References
LER-79-041-03L, LER-79-41-3L, NUDOCS 7908060527
Download: ML19242A874 (2)

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POWER AUT110RITY OF TIIE STATE OF NEh' YORK JAMES A. FIT 2 PATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACIIMENT TO LER 79-041/03L-0 Page _1 of 1 While in a cold shutdown co'idition, during the conduct of Instrument Surveillance Procedure F-ISP-15 titled "Drywell Equipment Drain Sump Functional Test and Cali-bration", the Technicians performing the test noted that the procedure was in error.

The procedure was immediately corrected, however, investigation revealed that earlier surveillance was conducted on a monthly basis from December, 1978 through June, 1979 utilizing the procedure containing the error. The procedural error was a result of the implementation of plant modification during the 1978 Refueling Outage in which the equipment sump level control logic was revised. The pre-modification logic re-quired that during the conduct of F-ISP-IS that sump pump operating time be recorded in order to correct the daily total (integrated) flow from the sump since the inte-grator was under test. The modification changed the sump level control in that the pump operates continuously and level control is achieved by automatic operation of the discharge valve. The applicable section of the precedure should have been changed to reflect valve operation instead of pump operation.

A review of the surveillance conducted since December, 1978, revealed that no actual errors had been introduced into the integrated sump readings, therefore, the event did not represent any significant hazard to the public health and safety.

Technical Specifications Appendix A, Paragraph 6.8.A. requires implementation of procedures to control modifications, the update of procedures as the result of modi ficat ions , and certain other work. Contrary to these requirements, F-ISP-1S was not updated as part of the sump . level control nodification.

As noted above, the procedure was immediately corrected and the surveillance

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