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Event Notification Report for April 17, 2006

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
04/16/2006 - 04/17/2006

EVENT NUMBERS
42506

Power Reactor
Event Number: 42506
Facility: VOGTLE
Region: 2     State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE PHILLIPS
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/17/2006
Notification Time: 01:20 [ET]
Event Date: 04/17/2006
Event Time: 00:26 [EDT]
Last Update Date: 04/17/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ROBERT HAAG (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 33 Power Operation 0 Hot Standby
Event Text
UNIT 1 MANUALLY TRIPPED DUE TO FAILURE OF A MAIN FEED REGULATING VALVE TO CONTROL STEAM GENERATOR LEVEL

"Unit 1 reactor was manually tripped from 33% RTP due to the Loop 3 Main Feed Regulating Valve (MFRV) 1LV-0530 not controlling steam generator level in manual or AUTO.

"A unit shutdown was in progress at the time of the trip due to concerns with the Loop 3 MFRV. The unit shutdown had commenced from 100% power on 04/16/2006 at 1603 hrs.

"All systems functioned as required on the reactor trip including a feedwater isolation and the Loop 3 MFRV closing as expected. The unit is presently in Mode 3 at normal operating temperature and pressure. An investigation team is being assembled concerning the Loop 3 MFRV."

All control rods fully inserted. No primary or secondary reliefs/safeties lifted during the transient. Unit 1 is currently in Mode 3 Hot Standby controlling Steam Generator Water Level using Auxiliary Feedwater supplied by both Motor Driven and the Steam Driven pumps. Decay Heat is being removed via the Bypass Valves to the Main Condenser. Offsite power is stable and all EDGs are available, if necessary.

The licensee informed the NRC Resident Inspector.