Event Notification Report for August 24, 2006
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/23/2006 - 08/24/2006
EVENT NUMBERS
42800
Power Reactor
Event Number: 42800
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: STEVE PRUSSMAN
HQ OPS Officer: PETE SNYDER
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: STEVE PRUSSMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 08/24/2006
Notification Time: 15:08 [ET]
Event Date: 08/24/2006
Event Time: 11:35 [EDT]
Last Update Date: 08/24/2006
Notification Time: 15:08 [ET]
Event Date: 08/24/2006
Event Time: 11:35 [EDT]
Last Update Date: 08/24/2006
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RICHARD CONTE (R1)
RICHARD CONTE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 1 | Startup | 1 | Startup |
MAIN FEEDWATER PUMP TRIP DURING STARTUP
"On August 24, 2006, at approximately 1135 hours, during startup from a reactor trip on August 23, 2006, a trip of Main Boiler Feedwater Pump (MBFP) 21 sent an actuation signal to automatically start both motor driven Auxiliary Feedwater Pumps (AFPs) as well as isolate steam generator blowdown, and close MBFP discharge valve BFD-2-21. At the time, the plant was at about 1% power and both motor driven AFPs were in operation. All plant responses were as expected. The cause of the MBFP trip is under evaluation.
"Offsite power is normal and emergency diesel generators are operable." The plant is currently at 8% power.
The licensee notified the NRC Resident Inspector.
"On August 24, 2006, at approximately 1135 hours, during startup from a reactor trip on August 23, 2006, a trip of Main Boiler Feedwater Pump (MBFP) 21 sent an actuation signal to automatically start both motor driven Auxiliary Feedwater Pumps (AFPs) as well as isolate steam generator blowdown, and close MBFP discharge valve BFD-2-21. At the time, the plant was at about 1% power and both motor driven AFPs were in operation. All plant responses were as expected. The cause of the MBFP trip is under evaluation.
"Offsite power is normal and emergency diesel generators are operable." The plant is currently at 8% power.
The licensee notified the NRC Resident Inspector.