Event Notification Report for April 07, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/06/2001 - 04/07/2001
EVENT NUMBERS
37898
Power Reactor
Event Number: 37898
Facility: VOGTLE
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROB DORMAN
HQ OPS Officer: BOB STRANSKY
Region: 2 State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ROB DORMAN
HQ OPS Officer: BOB STRANSKY
Notification Date: 04/07/2001
Notification Time: 23:30 [ET]
Event Date: 04/07/2001
Event Time: 21:23 [EDT]
Last Update Date: 04/07/2001
Notification Time: 23:30 [ET]
Event Date: 04/07/2001
Event Time: 21:23 [EDT]
Last Update Date: 04/07/2001
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):
CAUDLE JULIAN (R2)
CAUDLE JULIAN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 46 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER FLOW
"While performing 14236-2, 'SGFPT A and B Trip TADOT [trip actuation device operational test]' on SGFPT A, the link disabling the trip signal to the running SGFPT B was not fully opened, resulting in a trip of SGFPT B. The reactor was manually tripped due to no SGFPT's running. Both trains of the Reactor Protection System functioned as expected. A Feed Water Isolation was received as expected from P4-Low Tavg. An Aux Feed Water Actuation Signal (AFWAS) was generated on the trip of both SGFPT's for both MDAFW pumps and on Lo-Lo Steam Generator level in two of four Steam Generators for the TDAFW pump. The Steam Generator Blow Down system also Isolated properly on the AFWAS signal. The plant is currently stable in Mode 3. A shut down was in progress at the time of this event for a planned refueling outage. The refueling outage will continue as planned."
The NRC resident inspector has been informed of this event by the licensee.
"While performing 14236-2, 'SGFPT A and B Trip TADOT [trip actuation device operational test]' on SGFPT A, the link disabling the trip signal to the running SGFPT B was not fully opened, resulting in a trip of SGFPT B. The reactor was manually tripped due to no SGFPT's running. Both trains of the Reactor Protection System functioned as expected. A Feed Water Isolation was received as expected from P4-Low Tavg. An Aux Feed Water Actuation Signal (AFWAS) was generated on the trip of both SGFPT's for both MDAFW pumps and on Lo-Lo Steam Generator level in two of four Steam Generators for the TDAFW pump. The Steam Generator Blow Down system also Isolated properly on the AFWAS signal. The plant is currently stable in Mode 3. A shut down was in progress at the time of this event for a planned refueling outage. The refueling outage will continue as planned."
The NRC resident inspector has been informed of this event by the licensee.