Event Notification Report for December 25, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/24/2004 - 12/25/2004
Power Reactor
Event Number: 41292
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: BRIAN STAMP
HQ OPS Officer: JOHN KNOKE
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: BRIAN STAMP
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/25/2004
Notification Time: 08:50 [ET]
Event Date: 12/25/2004
Event Time: 07:36 [EST]
Last Update Date: 12/25/2004
Notification Time: 08:50 [ET]
Event Date: 12/25/2004
Event Time: 07:36 [EST]
Last Update Date: 12/25/2004
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):
CAUDLE JULIAN (R2)
CAUDLE JULIAN (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNIT 4 MANUALLY TRIPPED DUE TO LOWERING CONDENSER VACUUM
"Manual reactor trip at 21.5" Hg and lowering. AFW initiated and operated as designed."
On 12/25/04 Unit 4 at Turkey Point experienced a declining vacuum in the main condenser. When the condenser vacuum reached 21.5 Hg, manual trip criteria was reached and the plant was manually shut down. Decay heat is being removed via the Atmospheric Steam Dumps. There is no known primary to secondary tube leakage. The AFW system started as expected. All rods inserted correctly and all systems functioned as designed.
The licensee will notify the NRC Resident Inspector.
"Manual reactor trip at 21.5" Hg and lowering. AFW initiated and operated as designed."
On 12/25/04 Unit 4 at Turkey Point experienced a declining vacuum in the main condenser. When the condenser vacuum reached 21.5 Hg, manual trip criteria was reached and the plant was manually shut down. Decay heat is being removed via the Atmospheric Steam Dumps. There is no known primary to secondary tube leakage. The AFW system started as expected. All rods inserted correctly and all systems functioned as designed.
The licensee will notify the NRC Resident Inspector.
Power Reactor
Event Number: 41293
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: PATRICK KINNE
HQ OPS Officer: JOHN KNOKE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: PATRICK KINNE
HQ OPS Officer: JOHN KNOKE
Notification Date: 12/25/2004
Notification Time: 08:55 [ET]
Event Date: 12/25/2004
Event Time: 06:52 [EST]
Last Update Date: 12/27/2004
Notification Time: 08:55 [ET]
Event Date: 12/25/2004
Event Time: 06:52 [EST]
Last Update Date: 12/27/2004
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 | 100 | Power Operation | 0 | Hot Standby |
UNIT 2 MANUALLY TRIPPED TO REMOVE FAILING CONDENSATE PUMP FROM SERVICE
"Manual reactor trip due to condensate pump failure. All systems functioned as required post trip. The plant is currently stable in Mode 3."
On 12/25/04 Unit 2 at St. Lucie experienced a high amperage reading on a condensate pump. Visual observation of the pump indicated blistering paint at the electrical connections. The condensate pump was taken out of service and Unit 2 was manually shut down. Decay heat is being removed via normal means to the condenser. The AFW system started as expected. All rods inserted correctly and all systems functioned as designed.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM ST. LUCIE (BASHWINER) TO NRC (HUFFMAN) AT 1239 EST ON 12/27/04 * * *
The licensee called to provide some additional information concerning this event:
1) The manual trip of Unit 2 was due to the failure of the 2B condensate pump.
2) The condensate pump failure was a result of a failed termination of the "A" phase motor lead to the field cable.
3) The failure of the motor lead is considered a random event and does not have an generic implications.
The licensee also noted that the reactor power had actually been reduced to 95% immediately prior to the manual trip.
The NRC Resident Inspector and R2DO (Julian) have been notified.
* * * UPDATE AND CLARIFICATION FROM BASHWINER TO CROUCH @1346 EST ON 12/27/04 * * *
The following information was obtained from the licensee via facsimile:
"This notification is an amended notification to the original notification of unit trip and RPS actuation due to failure of 2B condensate pump.
"The amended notification includes an 8-hour notification non-emergency 10 CFR 50.72 (b)(3)(iv)(A) to identify Aux Feedwater Actuation automatically actuated post manual reactor trip on 12/25/04.
"Specified System Actuation per 50.72 (b)(3)(iv)(B)(6) AFAS [Auxiliary Feedwater Actuation System]."
The licensee notified the NRC Resident inspector. R2DO (Julian) notified of this update.
"Manual reactor trip due to condensate pump failure. All systems functioned as required post trip. The plant is currently stable in Mode 3."
On 12/25/04 Unit 2 at St. Lucie experienced a high amperage reading on a condensate pump. Visual observation of the pump indicated blistering paint at the electrical connections. The condensate pump was taken out of service and Unit 2 was manually shut down. Decay heat is being removed via normal means to the condenser. The AFW system started as expected. All rods inserted correctly and all systems functioned as designed.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM ST. LUCIE (BASHWINER) TO NRC (HUFFMAN) AT 1239 EST ON 12/27/04 * * *
The licensee called to provide some additional information concerning this event:
1) The manual trip of Unit 2 was due to the failure of the 2B condensate pump.
2) The condensate pump failure was a result of a failed termination of the "A" phase motor lead to the field cable.
3) The failure of the motor lead is considered a random event and does not have an generic implications.
The licensee also noted that the reactor power had actually been reduced to 95% immediately prior to the manual trip.
The NRC Resident Inspector and R2DO (Julian) have been notified.
* * * UPDATE AND CLARIFICATION FROM BASHWINER TO CROUCH @1346 EST ON 12/27/04 * * *
The following information was obtained from the licensee via facsimile:
"This notification is an amended notification to the original notification of unit trip and RPS actuation due to failure of 2B condensate pump.
"The amended notification includes an 8-hour notification non-emergency 10 CFR 50.72 (b)(3)(iv)(A) to identify Aux Feedwater Actuation automatically actuated post manual reactor trip on 12/25/04.
"Specified System Actuation per 50.72 (b)(3)(iv)(B)(6) AFAS [Auxiliary Feedwater Actuation System]."
The licensee notified the NRC Resident inspector. R2DO (Julian) notified of this update.