Event Notification Report for April 14, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/13/2012 - 04/14/2012
EVENT NUMBERS
47836
Power Reactor
Event Number: 47836
Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF TODD
HQ OPS Officer: JOHN KNOKE
Region: 2 State: GA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEFF TODD
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/14/2012
Notification Time: 16:12 [ET]
Event Date: 04/14/2012
Event Time: 13:46 [EDT]
Last Update Date: 04/14/2012
Notification Time: 16:12 [ET]
Event Date: 04/14/2012
Event Time: 13:46 [EDT]
Last Update Date: 04/14/2012
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):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOW MAIN FEEDWATER FLOW
"At 1346 EDT, Vogtle Unit 1 reactor was manually tripped from 100% power due to Main Feedwater Pump 'B' discharge flow lowering unexpectedly. All control rods fully inserted. AFW system automatically actuated as expected. System responses allowed for an uncomplicated reactor trip response. Plant is stable in Mode 3 during cause investigation."
The electrical lineup remained normal. No safety valves lifted due to the trip. Decay heat is being removed via the steam dumps to the main condenser.
The licensee has notified the NRC Resident Inspectors.
"At 1346 EDT, Vogtle Unit 1 reactor was manually tripped from 100% power due to Main Feedwater Pump 'B' discharge flow lowering unexpectedly. All control rods fully inserted. AFW system automatically actuated as expected. System responses allowed for an uncomplicated reactor trip response. Plant is stable in Mode 3 during cause investigation."
The electrical lineup remained normal. No safety valves lifted due to the trip. Decay heat is being removed via the steam dumps to the main condenser.
The licensee has notified the NRC Resident Inspectors.