Event Notification Report for July 10, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/09/2003 - 07/10/2003
EVENT NUMBERS
39988
Power Reactor
Event Number: 39988
Facility: POINT BEACH
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ROB HARRSCH
HQ OPS Officer: BILL GOTT
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: ROB HARRSCH
HQ OPS Officer: BILL GOTT
Notification Date: 07/10/2003
Notification Time: 15:55 [ET]
Event Date: 07/10/2003
Event Time: 13:44 [CDT]
Last Update Date: 07/10/2003
Notification Time: 15:55 [ET]
Event Date: 07/10/2003
Event Time: 13:44 [CDT]
Last Update Date: 07/10/2003
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CHRIS MILLER (R3)
TERRY REIS (NRR)
CHRIS MILLER (R3)
TERRY REIS (NRR)
| 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 |
AUTOMATIC REACTOR TRIP DUE TO MAIN FEEDWATER PUMP TRIP
"At 1342, The Unit 2 'B' Main Feedwater Pump tripped, this was followed by an automatic reactor trip at 1344. All Reactor Protection and Safety Systems responded as required. The Unit 2 'B' Heater Drain Tank Pump also tripped during the transient. The 'B' Main Feedwater Pump trip was due to an electrical fault, the cause is unknown at this time. Unit 2 is stable in Mode 3 at this time."
Additionally, due to the initial low levels in the Unit 2 Steam Generators due to the Main Feedwater Pump trip, Auxiliary Feed Water initiated as expected.
The licensee reported that all rods fully inserted, decay heat is being removed by dumping steam to the main condenser, and no primary or secondary relief valves lifted..
The licensee notified the NRC Resident Inspector.
"At 1342, The Unit 2 'B' Main Feedwater Pump tripped, this was followed by an automatic reactor trip at 1344. All Reactor Protection and Safety Systems responded as required. The Unit 2 'B' Heater Drain Tank Pump also tripped during the transient. The 'B' Main Feedwater Pump trip was due to an electrical fault, the cause is unknown at this time. Unit 2 is stable in Mode 3 at this time."
Additionally, due to the initial low levels in the Unit 2 Steam Generators due to the Main Feedwater Pump trip, Auxiliary Feed Water initiated as expected.
The licensee reported that all rods fully inserted, decay heat is being removed by dumping steam to the main condenser, and no primary or secondary relief valves lifted..
The licensee notified the NRC Resident Inspector.