PNO-II-89-019, on 890307,Unit 1 Manually Tripped Due to Drop in Pressurizer Level,Increase in Main Steam Line Radiation & Increased Charging Flow Revealed Primary to Secondary Leak. Alert Declared & Onsite Emergency Response Activated

PNO-II-89-019:on 890307,Unit 1 Manually Tripped Due to Drop in Pressurizer Level,Increase in Main Steam Line Radiation & Increased Charging Flow Revealed Primary to Secondary Leak. Alert Declared & Onsite Emergency Response Activated

ML20246L464
Person / Time
Site:	McGuire
Issue date:	03/08/1989
From:	Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
References
PNO-II-89-019, PNO-II-89-19, NUDOCS 8903240185
Download: ML20246L464 (2)

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03/08/89 PRELIMINARYNdTIFICATIONOFEVENTORUNUSUALOCCURRENCEPNO-II-89-19 j

.This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or 1 public interest significance. The information is as initially received without verifi- l cation or evaluation, and is basically all that is known by the Region II staff on this j date ,

l FACILITY: Duke Power Company Licensee Emergency Classification. 4 McGuire, Unit 1 Notification of Unusual Event '

Docket No. 50-369 X Alert Charlotte, North Carolina Site Area Emergency General Emergency Not Applicable

SUBJECT:

REACTOR TRIP At 11:45 p.m. (EST) on 3/7/89, McGuire Unit I was manually tripped from 100 percent power when a drop in the pressurizer level, increase in main steam line radiation, and increased charging flow revealed a primary to secondary leak of 100 to 150 gpm from the "B" steam  ;

generator. An alert was declared by the licensee at 11:45 p.m. The licensee activated t their onsite emergency response facilities and the NRC partially manned the Region II and Headquarters Incident Response Centers. Radioactivity was released to the atmosphere from the steam jet air ejector and from three main steam power operated relief valves which opened for about three minutes. The licensee isolated the "B" steam generator and began cooldown and depressurization of the reactor coolant system. The maximum accumulated dose at the site boundary, calculated by the licensee, was less than 0.001 mrem.

As of 5:00 a.m. (EST), 3/8/89, the licensee is cooling down the plant by utilizing auxiliary feedwater and steaming to condenser through the unaffected steam generators. The contents of the "B" steam generator are being blown down to the condenser hotwell through condensate demineralizers. All safety systems are functioning normally. Unit 2 is operating at 100 percent power.

The licensee has issued a press release and there has been local news media interest.

The Resident Inspectors are on site. The States of North and South Carolina, EPA, DOE, and FEMA have been notified.

This PN is is based on information current as of 7:00 a.m. on March 8,1989.

CONTACT: M. Sinkule - 242-5506 03/08/89 0 0711 TO REGIONS AND HQ 1

8903240185 890308 PDR 18eE PNO-II-89-019 PNU 0l

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