Event Notification Report for June 26, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/25/2001 - 06/26/2001
Power Reactor
Event Number: 38097
Facility: LIMERICK
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PETE GARDNER
HQ OPS Officer: DOUG WEAVER
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: PETE GARDNER
HQ OPS Officer: DOUG WEAVER
Notification Date: 06/26/2001
Notification Time: 16:59 [ET]
Event Date: 06/26/2001
Event Time: 13:38 [EDT]
Last Update Date: 06/26/2001
Notification Time: 16:59 [ET]
Event Date: 06/26/2001
Event Time: 13:38 [EDT]
Last Update Date: 06/26/2001
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):
RICHARD BARKLEY (R1)
RICHARD BARKLEY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
TURBINE TRIP - REACTOR SCRAM
Unit 2 reactor scram occurred at 1338 on June 26, 2001. The reactor scram occurred as a result of a main turbine trip caused by actuation of unit protection relaying. All systems actuated as designed. The unit is being maintained in hot shutdown at normal reactor vessel water level. The cause of the turbine trip/generator lockout is under investigation. No SRVs lifted and all control rods fully inserted. One reactor recirculation pump has been restarted and the scram has been reset.
The licensee notified the State, the surrounding counties and the NRC resident inspector.
Unit 2 reactor scram occurred at 1338 on June 26, 2001. The reactor scram occurred as a result of a main turbine trip caused by actuation of unit protection relaying. All systems actuated as designed. The unit is being maintained in hot shutdown at normal reactor vessel water level. The cause of the turbine trip/generator lockout is under investigation. No SRVs lifted and all control rods fully inserted. One reactor recirculation pump has been restarted and the scram has been reset.
The licensee notified the State, the surrounding counties and the NRC resident inspector.
Power Reactor
Event Number: 38094
Facility: BYRON
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WINTER
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WINTER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/26/2001
Notification Time: 07:52 [ET]
Event Date: 06/26/2001
Event Time: 06:09 [CDT]
Last Update Date: 06/26/2001
Notification Time: 07:52 [ET]
Event Date: 06/26/2001
Event Time: 06:09 [CDT]
Last Update Date: 06/26/2001
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):
GEOFFREY WRIGHT (R3)
GEOFFREY WRIGHT (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP FROM 100% POWER DUE TO FEEDWATER REGULATOR VALVE FAILURE
Unit 2 was manually tripped from 100% power after the "2D" feedwater regulating valve (2FW540) was found failed closed. The "2A" and "2B" auxiliary feedwater pumps auto started as expected on low 2-steam generator level. All rods fully inserted no ECCS actuation or relief valves lifted. The plant is stable and heat sink is to the condenser through the steam dumps. The cause of the feed reg valve failure is being investigated.
The NRC Resident Inspector will be notified.
* * * UPDATE on 6/26/01 @ 0839 BY WINTER TO GOULD * * *
The plant had a second automatic start (0733CDT) of the "2B" auxiliary feedwater pump on low-2 S/G level.
The NRC Resident Inspector was informed.
REG 3 RDO (Wright) was notified
Unit 2 was manually tripped from 100% power after the "2D" feedwater regulating valve (2FW540) was found failed closed. The "2A" and "2B" auxiliary feedwater pumps auto started as expected on low 2-steam generator level. All rods fully inserted no ECCS actuation or relief valves lifted. The plant is stable and heat sink is to the condenser through the steam dumps. The cause of the feed reg valve failure is being investigated.
The NRC Resident Inspector will be notified.
* * * UPDATE on 6/26/01 @ 0839 BY WINTER TO GOULD * * *
The plant had a second automatic start (0733CDT) of the "2B" auxiliary feedwater pump on low-2 S/G level.
The NRC Resident Inspector was informed.
REG 3 RDO (Wright) was notified
Power Reactor
Event Number: 38095
Facility: FARLEY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: YOUNGBLOOD
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: YOUNGBLOOD
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/26/2001
Notification Time: 08:10 [ET]
Event Date: 06/26/2001
Event Time: 06:46 [CDT]
Last Update Date: 06/26/2001
Notification Time: 08:10 [ET]
Event Date: 06/26/2001
Event Time: 06:46 [CDT]
Last Update Date: 06/26/2001
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):
STEPHEN CAHILL (R2)
STEPHEN CAHILL (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR AUTOMATIC TRIP FROM 100% POWER DUE TO TURBINE TRIP
The plant had a reactor trip from 100% power due to a turbine trip. All rods fully inserted, no ECCS actuated or relief valves lifted. The cause of the turbine trip may be due to a problem with the DEH system but they are continuing the investigation.
The NRC Resident Inspector was notified.
The plant had a reactor trip from 100% power due to a turbine trip. All rods fully inserted, no ECCS actuated or relief valves lifted. The cause of the turbine trip may be due to a problem with the DEH system but they are continuing the investigation.
The NRC Resident Inspector was notified.