Event Notification Report for January 03, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/02/2007 - 01/03/2007
EVENT NUMBERS
43072
Power Reactor
Event Number: 43072
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM KROSSMAN
HQ OPS Officer: MARK ABRAMOVITZ
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JIM KROSSMAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/03/2007
Notification Time: 19:32 [ET]
Event Date: 01/03/2007
Event Time: 18:03 [EST]
Last Update Date: 01/03/2007
Notification Time: 19:32 [ET]
Event Date: 01/03/2007
Event Time: 18:03 [EST]
Last Update Date: 01/03/2007
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):
CHARLIE PAYNE (R2)
CHARLIE PAYNE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO A CARD FAILURE
"A Unit-1 reactor trip was initiated by a Process Rock card failure that caused the 'B' main feed regulation valve to fail closed. The closure of the 'B' main feed regulation valve caused a reactor trip due to a steam flow - feed flow mismatch with a low steam generator water level. The auxiliary feed water system actuated as expected due to the reactor trip. The plant was stabilized with no other issues using the appropriate emergency procedures."
All control rods fully inserted on the trip and no relief or safety valves lifted in either the primary or secondary systems. Auxiliary feed water pumps automatically started and injected into the steam generators on a low water level signal. The operators restored normal feedwater flow to the steam generators. Decay heat is via the condenser steam dumps. The plant is aligned to the normal shut down electrical alignment. Card replacement is expected tonight and reactor startup is expected tomorrow.
The licensee notified the NRC Resident Inspector.
"A Unit-1 reactor trip was initiated by a Process Rock card failure that caused the 'B' main feed regulation valve to fail closed. The closure of the 'B' main feed regulation valve caused a reactor trip due to a steam flow - feed flow mismatch with a low steam generator water level. The auxiliary feed water system actuated as expected due to the reactor trip. The plant was stabilized with no other issues using the appropriate emergency procedures."
All control rods fully inserted on the trip and no relief or safety valves lifted in either the primary or secondary systems. Auxiliary feed water pumps automatically started and injected into the steam generators on a low water level signal. The operators restored normal feedwater flow to the steam generators. Decay heat is via the condenser steam dumps. The plant is aligned to the normal shut down electrical alignment. Card replacement is expected tonight and reactor startup is expected tomorrow.
The licensee notified the NRC Resident Inspector.