ML20236Q162
| ML20236Q162 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/13/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8711190218 | |
| Download: ML20236Q162 (2) | |
Text
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l DUKE PowEn GOMPANY j
P.O. DOX 33180 CHARLOTTE N.C. 28242 II U.
R 37741 3 g,
November 13, 1987 U.S. Nuclear. Regulatory Commission
[' Washington,D.C. Document;ControlDeskl[
20555
Subject:
McGuire Nuclear Station Docket No. 50-369, Unit 1 Special Report Pursuant To Technical Specifications 3.5.3 and 6.9.2 Gentlemen:
Please find attached a special report concerning the safety inj ection which I
occurred on August 16, 1987, (reference Licensee Event Report 369/87-17).
This report is required to be submitted within ninety days in the event the Emergency Core Cooling system is actuated and injects water into the Reactor Coolant system.
The cumulative nozzle usage factor did not exceed 0.70.
If there are any questions concerning this matter, please contact Steve LeRoy of our Licensing staff at (704) 373-6233.
Very truly yours,
/
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Hal B. Tucker SEL/173/jgc Attachment xc:
Dr. J. Nelson Grace INPO Records Center Regional Administrator, Region II Suite 1500 U.S. Nuclear Regulatory Commission 1100 circle 75 Parkway 101 Marietta St., NW, Suite 2900 Atlanta, GA 30339 Atlanta, GA 30323 Mr. Darl Hood Mr. W.T. Orders U.S. Nuclear Regulatory Commission NRC. Resident Inspector Office of Nuclear Reactor Regulation McGuire Nuclear Station Washington, D.C.
20555 87i1190218 8 h69 PDR ADOCK O PDR
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Duke Power Company McGuire Nuclear Station Special Report Emergency Core Cooling System Actt.ation and Safety Injection On August 16, 1987, while Operations personnel were preparing to put the Unit 1 Turbine Generator on line af ter a short outage, a malfunction of the Main' Turbine controls caused a rapidly decreasing Main Steam line pressure which triggered a Safety Injection / Reactor Trip at 0105. An Unusual Event was declared by the Shift Supervisor.
Operations personnel determined that the Safety Injection could be terminated at 0113, (reference Licensee Event Report 369/87-17).
Reactor Coolant (NC) system conditions prior to the event were 559'F at 2250 psig.
NC system pressure stayed above 2190 psig throughout the event.
The injection fluid temperature was 86*F and the duration of the injection was 8 minutes.
This event was the fif th injection for the 1 1/2 inch cold leg Safety Injec-tion nozzles, and the accumulated nozzle usage factor has not exceeded 0.70.
At 1615 on the same day, the Unusual Event was terminated, but the unit remained shutdown for repairs.
All repairs had been completed and the unit was back on line at 1620 on August 21, 1987.
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