ML20045G667

RO:930702,unusual Event Declared When RCS Calculated Unidentified Leak Rate Exceeded 1 Gpm.Caused by Leakage from Reactor Coolant Pump Seal Injection Filter Drain Valve. Valves Corrected to Eliminate Leak

ML20045G667
Person / Time
Site:	Comanche Peak
Issue date:	07/02/1993
From:	William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-93256, NUDOCS 9307150026
Download: ML20045G667 (2)

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. $ Log # TXX-93256 r r File # 10013 7UELECTRlC Ref. # 1 50.72(a)(i)

July 2, 1993 Wmlam J. Cahill, Jr.

Group Vice President

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U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 i

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-446 TRANSMITTAL OF REPORT FOLLOWING A NOTIFICATION OF UNUSUAL EVENT Gentlemen:

As specified in the CPSES Emergency Plan, TU Electric hereby transmits the enclosed report which summarizes the event which occurred on July 2, 1993.

Sincerely, Y h- .) h, I

William J. Cahill, Jr. i l

BY: Y Roger D. Walker Manager of Regulatory Affairs For Nuclear Production OB:bm cc: Mr. R. D. Martin, Region IV '

Resident Inspectors, CPSES (2)

Mr. Robert Lansford, Division of Emergency Management Mr. B. E. Holian, NRR Mr. T. A. Bergman, NRR l-9307150026 930703 "

PDR ADOCK 05000446  ;;;

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h00 N. Olive Street LB. 81 Dallas. Texas 75201

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$nclosuretoTXX-93256 Page 1 of 1 TU ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 2 DOCKET NO. 50-446 Notification of Unusual Event As a Result of Reactor Coolant System Leakage Reportina Reauirement This report is being submitted as recommended by NUREG-0654, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" and in accordance with Comanche Peak Steam Electric Station (CPSES) Emergency Plan Procedures. The CPSES Emergency Plan procedures re: quire that a written summary be submitted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the closecut of the Notification of Unusual Event (NOUE).

Event Description At approximately 5:15 a.m. (CDT), with the Unit in MODE 3, a Notification of Unusual Event was declared, because Reactor Coolant System (RCS) calculated unidentified leak rate exceeded one (1) gallon per minute (GPM). The Nuclear Regulatory Commission and appropriate offsite agencies were notified in accordance with the applicable regulatory and procedural requirements.

At approximately 1:05 p.m. (CDT) the Notice of Unusual Event was terminated after personnel took measures to reduce the unidentified leak rate to less than one GPM.

Correstive Action Immediate actions were taken to detect the leak. The majority of the leakage was from the Reactor Coolant Pump Seal Injection filter drain valve.

The subject valves were corrected to eliminate the leak.

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