PNO-V-93-009B, provides Update on 930314 SG Tube Leak & Manual Reactor Trip at Facility.Licensee Will Use Modified Emergency Procedure to Further Cooldown SG-2 Using Condensate Pump.Nrc Inspector & Region 5 Responded to Event
| ML20034H756 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/14/1993 |
| From: | Sloan J, Wong H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| References | |
| PNO-V-93-009B, PNO-V-93-9B, NUDOCS 9303220025 | |
| Download: ML20034H756 (2) | |
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.3 i March 14, 1993 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-V-93-009B
-This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially rcceived without verification or evaluation, and is basically all that is known by the Region V staff on this date.
Facility Licensee Emeroency Classification Arizona Public Service Co.
Notification of Unusual Event Palo Verde 2 X Alert Wintersburg, Arizona Site Area Emergency Dockets: 50-529 General Emergency Not Applicable
Subject:
STEAM GENERATOR TUBE LEAK AND MANUAL REACTOR TRIP - SECOND UPDATE At 4:25 a.m. (all times MST) on March 14, 1993, operators at Palo Verde Unit 2 observed decreasing pressurizer level and pressure. At 4:48 a.m.,
operators manually tripped the reactor. A safety injection actuation signal (SIAS) and a containment isolation actuation signal (CIAS) initi-ated automatically at 4:58 a.m.
Radiation monitor alarms and auxiliary feedwater (AFW) flow rates to the two _ steam generators (SGs) indicated a leak in SG-2.
The licensee declared an ALERT at 5:02 a.m. and initiated actions as prescribed by emergency operating procedures (EOPs).
-Plant operators initiated cooldown and depressurization of the reactor coolant system (RCS) at 6:05 a.m., and isolated SG-2 at 7:30 a.m.
As of March 15,1993 at 1:15 a.m., RCS temperature and pressure were stable at 265 degrees F and 270 psig, respectively, using the shutdown cooling system. The licensee secured from the ALERT at 1:15 a.m.
The licensee will be using a modified emergency procedure to further cooldown SG-2 using a condensate pump to feed SG-2 and steam generator blowdown to remove inventory.
The NRC Headquarters and Region V incident response centers secured from the monitoring mode at 1:25 a.m.
This event did not involve a health hazard to offsite personnel. The release pathway, via the steam jet air ejectors, is filtered and monitored, and the activity released was a fraction of the Technical Specification limits. No activity attributed to the plant event was detected offsite by either the licensee or state monitoring teams.
The licensee made several press releases from the Joint Emergency News Center. The NRC responded to news inquiries.
Local press interest was moderate, with limited coverage by national media. The NRC resident inspector went to the site and coordinated with NRC Headquarters and Region V personnel in responding to the event.
This information is current as of 1:30 a.m. MST on March 15, 1993.
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9303220025 930314 PDR 18cE PNO-V-93-009B PDR Y3'
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