Event Notification Report for June 14, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/13/2003 - 06/14/2003
EVENT NUMBERS
39938
Power Reactor
Event Number: 39938
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: BAKER
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: BAKER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/14/2003
Notification Time: 14:32 [ET]
Event Date: 06/14/2003
Event Time: 10:53 [EDT]
Last Update Date: 06/14/2003
Notification Time: 14:32 [ET]
Event Date: 06/14/2003
Event Time: 10:53 [EDT]
Last Update Date: 06/14/2003
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):
MARK LESSER (R2)
MARK LESSER (R2)
| 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 |
REACTOR MANUALLY TRIPPED DUE TO MAIN FEEDWATER PUMP TRIP
At 1053 ,on 6/14/03, the reactor was manually tripped from 100% in response to a trip of the "B" main feedwater pump (MFP). Both motor-driven auxiliary feedwater pumps and the turbine driven auxiliary feedwater pump auto started due to the lo-lo steam generator level. Operations personnel responded to the event in accordance with applicable plant procedures and the plant was stabilized at normal operating no-load reactor coolant system (RCS) temperature and pressure following the reactor trip. The cause of the MFP trip is still under investigation. All rods fully inserted no ECCS actuation occurred and the PORV lifted and fully reseated.
The NRC Resident Inspector was notified.
At 1053 ,on 6/14/03, the reactor was manually tripped from 100% in response to a trip of the "B" main feedwater pump (MFP). Both motor-driven auxiliary feedwater pumps and the turbine driven auxiliary feedwater pump auto started due to the lo-lo steam generator level. Operations personnel responded to the event in accordance with applicable plant procedures and the plant was stabilized at normal operating no-load reactor coolant system (RCS) temperature and pressure following the reactor trip. The cause of the MFP trip is still under investigation. All rods fully inserted no ECCS actuation occurred and the PORV lifted and fully reseated.
The NRC Resident Inspector was notified.