Event Notification Report for December 06, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/05/2001 - 12/06/2001
Power Reactor
Event Number: 38542
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: LEIGH TROCINE
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: LEIGH TROCINE
Notification Date: 12/06/2001
Notification Time: 04:55 [ET]
Event Date: 12/06/2001
Event Time: 03:50 [EST]
Last Update Date: 12/06/2001
Notification Time: 04:55 [ET]
Event Date: 12/06/2001
Event Time: 03:50 [EST]
Last Update Date: 12/06/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
PATRICK HILAND (R3)
PATRICK HILAND (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 Shutdown |
MANUAL REACTOR SCRAM DUE TO A LOSS OF STATOR WATER COOLING
The following text is a portion of a facsimile received from the licensee:
"At 0350 on 12/6/01 with the reactor at 100%, a manual reactor scram was inserted due to the loss of stator water cooling. All control rods fully inserted into the core. While taking a stator water sample, the heat exchanger vent line broke off the heat exchanger losing stator water from the system. A reactor scram was inserted prior to an [imminent] turbine generator trip."
"Following the reactor scram, water level dropped to approximately 120". Reactor water level is being maintained in the normal level band (197") with feedwater/condensate. The following 'Level 3' isolations occurred as expected:"
"Group 4 - RHR Shutdown Cooling and Head Spray"
"Group 13 - Drywell Sumps"
"Group 15 - Traversing Incore Probe Systems"
"All valves in [Groups] 4 and 15 were closed prior to the event. Group 13 valves closed as designed. No ECCS systems initiated, and no SRVs lifted. All Emergency Diesel Generators are operable."
The licensee stated that the main steam isolation valves remained open and that the main condenser is being used as the heat sink. Containment parameters are normal, and the grid is stable.
The licensee notified the NRC resident inspector.
The following text is a portion of a facsimile received from the licensee:
"At 0350 on 12/6/01 with the reactor at 100%, a manual reactor scram was inserted due to the loss of stator water cooling. All control rods fully inserted into the core. While taking a stator water sample, the heat exchanger vent line broke off the heat exchanger losing stator water from the system. A reactor scram was inserted prior to an [imminent] turbine generator trip."
"Following the reactor scram, water level dropped to approximately 120". Reactor water level is being maintained in the normal level band (197") with feedwater/condensate. The following 'Level 3' isolations occurred as expected:"
"Group 4 - RHR Shutdown Cooling and Head Spray"
"Group 13 - Drywell Sumps"
"Group 15 - Traversing Incore Probe Systems"
"All valves in [Groups] 4 and 15 were closed prior to the event. Group 13 valves closed as designed. No ECCS systems initiated, and no SRVs lifted. All Emergency Diesel Generators are operable."
The licensee stated that the main steam isolation valves remained open and that the main condenser is being used as the heat sink. Containment parameters are normal, and the grid is stable.
The licensee notified the NRC resident inspector.
Power Reactor
Event Number: 38544
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: WEEKLEY
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: WEEKLEY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 12/06/2001
Notification Time: 11:34 [ET]
Event Date: 12/06/2001
Event Time: 09:05 [CST]
Last Update Date: 12/06/2001
Notification Time: 11:34 [ET]
Event Date: 12/06/2001
Event Time: 09:05 [CST]
Last Update Date: 12/06/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ANTHONY GODY (R4)
ANTHONY GODY (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 12 | Power Operation | 1 | Startup |
THE LICENSEE MADE AN OFFSITE NOTIFICATION TO THE MISSOURI PUBLIC SERVICE COMMISSION
The following is a report to the Missouri Public Service Commission (MPSC) to notify them of a forced outage at the Callaway Nuclear Plant. This notification is reportable under 4CSR240-20.080(3)(B) because the outage is expected to last longer than 72 hours.
At 2248 CST, December 3, 2001, Callaway Plant shut down to effect repairs on the Main Generator. A leak had developed on a Main Generator cooling system requiring repairs which could only be made with the unit off-line. Initially, the Plant was expected to return to service within 72 hours, but due to the complexity of the repairs, the unit is now expected to return to service after the 72-hour deadline has expired. Expectations are to return to service by December 7, 2001.
The Licensee has informed the NRC Resident Inspector of the MPSC notification.
The following is a report to the Missouri Public Service Commission (MPSC) to notify them of a forced outage at the Callaway Nuclear Plant. This notification is reportable under 4CSR240-20.080(3)(B) because the outage is expected to last longer than 72 hours.
At 2248 CST, December 3, 2001, Callaway Plant shut down to effect repairs on the Main Generator. A leak had developed on a Main Generator cooling system requiring repairs which could only be made with the unit off-line. Initially, the Plant was expected to return to service within 72 hours, but due to the complexity of the repairs, the unit is now expected to return to service after the 72-hour deadline has expired. Expectations are to return to service by December 7, 2001.
The Licensee has informed the NRC Resident Inspector of the MPSC notification.
Power Reactor
Event Number: 38545
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: CHERI COLLINS
HQ OPS Officer: BOB STRANSKY
Region: 2 State: AL
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: CHERI COLLINS
HQ OPS Officer: BOB STRANSKY
Notification Date: 12/06/2001
Notification Time: 13:52 [ET]
Event Date: 12/06/2001
Event Time: 10:20 [CST]
Last Update Date: 12/06/2001
Notification Time: 13:52 [ET]
Event Date: 12/06/2001
Event Time: 10:20 [CST]
Last Update Date: 12/06/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
MARK LESSER (R2)
MARK LESSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY
A licensed operator (currently inactive) tested positive for illegal drug use under the licensee's fitness-for-duty (FFD) program. The individual was not on shift assignment, nor had the individual performed on-shift activities during the past year. The individual's site access has been terminated. The NRC resident inspector has been informed of this event by the licensee.
A licensed operator (currently inactive) tested positive for illegal drug use under the licensee's fitness-for-duty (FFD) program. The individual was not on shift assignment, nor had the individual performed on-shift activities during the past year. The individual's site access has been terminated. The NRC resident inspector has been informed of this event by the licensee.