Event Notification Report for May 01, 2005
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/30/2005 - 05/01/2005
Power Reactor
Event Number: 41654
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: MICHAEL SPELLMAN
HQ OPS Officer: JEFF ROTTON
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: MICHAEL SPELLMAN
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/01/2005
Notification Time: 04:08 [ET]
Event Date: 05/01/2005
Event Time: 00:21 [EDT]
Last Update Date: 05/01/2005
Notification Time: 04:08 [ET]
Event Date: 05/01/2005
Event Time: 00:21 [EDT]
Last Update Date: 05/01/2005
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):
JOEL MUNDAY (R2)
JOEL MUNDAY (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 |
MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSATE PUMP
"The plant was in Mode 1 at 100% power. At 0021 [EDT] the reactor was manually tripped following a loss of 1B Condensate pump per AOP-010, Feedwater Malfunctions. The cause of the 1B Condensate pump trip is not known at the present time. The plant is stable in Mode 3 at normal temperature and pressure. All safety systems functioned as expected; AFW automatically actuated due to low level in the steam generators to provide continued decay heat removal."
All control rods fully inserted on the manual reactor trip. Secondary PORVs opened on the trip and reclosed. Steam generators are discharging steam to the main condenser using the turbine steam dump valves. AFW has been secured and main feedwater is operating to maintain SG levels.
The licensee notified the NRC Resident Inspector.
"The plant was in Mode 1 at 100% power. At 0021 [EDT] the reactor was manually tripped following a loss of 1B Condensate pump per AOP-010, Feedwater Malfunctions. The cause of the 1B Condensate pump trip is not known at the present time. The plant is stable in Mode 3 at normal temperature and pressure. All safety systems functioned as expected; AFW automatically actuated due to low level in the steam generators to provide continued decay heat removal."
All control rods fully inserted on the manual reactor trip. Secondary PORVs opened on the trip and reclosed. Steam generators are discharging steam to the main condenser using the turbine steam dump valves. AFW has been secured and main feedwater is operating to maintain SG levels.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 41655
Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAMON RITTER
HQ OPS Officer: JOHN KNOKE
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAMON RITTER
HQ OPS Officer: JOHN KNOKE
Notification Date: 05/01/2005
Notification Time: 12:57 [ET]
Event Date: 05/01/2005
Event Time: 11:09 [EDT]
Last Update Date: 05/01/2005
Notification Time: 12:57 [ET]
Event Date: 05/01/2005
Event Time: 11:09 [EDT]
Last Update Date: 05/01/2005
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):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 17 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO MAIN TURBINE HIGH VIBRATION
" Seabrook Station initiated a Manual Reactor Trip during initial start of the main turbine following a refueling outage. Turbine vibrations elevated to the automatic trip set point during initial increase to normal operating speed. The reactor was manually tripped to allow breaking main condenser vacuum and reduce main turbine speed.
"The plant is currently stable in Mode 3. All control rods [fully] inserted and decay heat removal is via the main condenser steam dumps."
Emergency feedwater (EFW) pump actuation occurred because of lowering steam generator level due to the reactor trip. Steam generator level control was maintained using EFW. Condenser vacuum was broken until the turbine vibration alarms cleared and was then restored, allowing the condenser to be used for dumping steam.
The licensee notified the NRC Resident Inspector.
" Seabrook Station initiated a Manual Reactor Trip during initial start of the main turbine following a refueling outage. Turbine vibrations elevated to the automatic trip set point during initial increase to normal operating speed. The reactor was manually tripped to allow breaking main condenser vacuum and reduce main turbine speed.
"The plant is currently stable in Mode 3. All control rods [fully] inserted and decay heat removal is via the main condenser steam dumps."
Emergency feedwater (EFW) pump actuation occurred because of lowering steam generator level due to the reactor trip. Steam generator level control was maintained using EFW. Condenser vacuum was broken until the turbine vibration alarms cleared and was then restored, allowing the condenser to be used for dumping steam.
The licensee notified the NRC Resident Inspector.