Event Notification Report for July 03, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/02/2009 - 07/03/2009
EVENT NUMBERS
45183
Power Reactor
Event Number: 45183
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: DAVID BALFOUR
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: DAVID BALFOUR
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/03/2009
Notification Time: 14:32 [ET]
Event Date: 07/03/2009
Event Time: 13:05 [EDT]
Last Update Date: 07/03/2009
Notification Time: 14:32 [ET]
Event Date: 07/03/2009
Event Time: 13:05 [EDT]
Last Update Date: 07/03/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
JAMES TRAPP (R1DO)
JAMES TRAPP (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR TRIP RESULTING FROM TURBINE TRIP
A reactor trip occurred at 1305 EDT and a Connecticut "echo" event was declared at 1315 EDT. The load dispatcher reported a loss of a 115 kV line at the time of the trip which may have caused and/or contributed to the turbine trip. The turbine trip may have resulted from a loss of B12 MCC (motor control center) which carries stator cooling pumps or a momentary interruption to non-vital instrument panels VR11 and VR21.
The following events occurred:
"1) loss of non-vital power may have caused the turbine trip,
"2) RPS [Reactor Protective System] actuation from turbine trip,
"3) system operator reported brief loss of 115 kV line immediately prior to trip,
"4) Primary PORV [Pilot Operated Relief Valve on the pressurizer] lifted [at its setpoint of 2397psia],
"5) Steam generators reached a high level, and
"6) Main feed pump manually tripped due to high steam generator level and manually started AFW pumps [Auxiliary Feedwater Pumps].
"Note: The 'C' charging pump was inoperable at the time of the event."
All control rods fully inserted on the trip. The plant is in its normal shutdown electrical lineup. Decay heat is being dumped to the main condenser and steam generator level is being maintained with the AFW pumps. There was no effect on Unit-3.
The licensee notified the NRC Resident Inspector.
A reactor trip occurred at 1305 EDT and a Connecticut "echo" event was declared at 1315 EDT. The load dispatcher reported a loss of a 115 kV line at the time of the trip which may have caused and/or contributed to the turbine trip. The turbine trip may have resulted from a loss of B12 MCC (motor control center) which carries stator cooling pumps or a momentary interruption to non-vital instrument panels VR11 and VR21.
The following events occurred:
"1) loss of non-vital power may have caused the turbine trip,
"2) RPS [Reactor Protective System] actuation from turbine trip,
"3) system operator reported brief loss of 115 kV line immediately prior to trip,
"4) Primary PORV [Pilot Operated Relief Valve on the pressurizer] lifted [at its setpoint of 2397psia],
"5) Steam generators reached a high level, and
"6) Main feed pump manually tripped due to high steam generator level and manually started AFW pumps [Auxiliary Feedwater Pumps].
"Note: The 'C' charging pump was inoperable at the time of the event."
All control rods fully inserted on the trip. The plant is in its normal shutdown electrical lineup. Decay heat is being dumped to the main condenser and steam generator level is being maintained with the AFW pumps. There was no effect on Unit-3.
The licensee notified the NRC Resident Inspector.