Event Notification Report for February 12, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/11/2003 - 02/12/2003
Power Reactor
Event Number: 39579
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Mc CONNELL
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Mc CONNELL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/12/2003
Notification Time: 13:46 [ET]
Event Date: 02/12/2003
Event Time: 09:45 [EST]
Last Update Date: 02/12/2003
Notification Time: 13:46 [ET]
Event Date: 02/12/2003
Event Time: 09:45 [EST]
Last Update Date: 02/12/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
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 |
LOSS OF SAFETY FUNCTION ON BOTH UNITS DUE TO TWO EMERGENCY D/G's BEING DECLARED INOPERABLE
Emergency Diesel Generator "2A" was removed from service for pre-planned maintenance. This condition renders the "2A" Nuclear service Water pump inoperable. They had a vital i/c inverter "2EID" to fail, rendering the "2B" Emergency Diesel Generator inoperable due to its fuel oil fill valve failing closed. By the "2B" Diesel Generator being inoperable it rendered the "2B" Nuclear Service Water pump inoperable. The Nuclear Service Water is shared between both units. A loss of safety function occurred on Unit 2 due to two Diesel Generators being inoperable and no Nuclear Service Water train being operable. Since the Nuclear Service Water system is a shared with Unit 1, it also experienced a loss of a safety function. The system was returned to service within 9 minutes after re-opening the fuel oil fill bypass valve which rendered Diesel Generator "2B" operable again.
The NRC Resident Inspector was notified. State and Local agencies will be notified.
Emergency Diesel Generator "2A" was removed from service for pre-planned maintenance. This condition renders the "2A" Nuclear service Water pump inoperable. They had a vital i/c inverter "2EID" to fail, rendering the "2B" Emergency Diesel Generator inoperable due to its fuel oil fill valve failing closed. By the "2B" Diesel Generator being inoperable it rendered the "2B" Nuclear Service Water pump inoperable. The Nuclear Service Water is shared between both units. A loss of safety function occurred on Unit 2 due to two Diesel Generators being inoperable and no Nuclear Service Water train being operable. Since the Nuclear Service Water system is a shared with Unit 1, it also experienced a loss of a safety function. The system was returned to service within 9 minutes after re-opening the fuel oil fill bypass valve which rendered Diesel Generator "2B" operable again.
The NRC Resident Inspector was notified. State and Local agencies will be notified.
Power Reactor
Event Number: 39582
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: NEVE
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: NEVE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/12/2003
Notification Time: 16:41 [ET]
Event Date: 02/12/2003
Event Time: 09:45 [CST]
Last Update Date: 02/12/2003
Notification Time: 16:41 [ET]
Event Date: 02/12/2003
Event Time: 09:45 [CST]
Last Update Date: 02/12/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
SONIA BURGESS (R3)
SONIA BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
SUPERVISOR TESTED POSITIVE FOR ALCOHOL IN RANDOM TEST
COMPENSATORY MEASURES PUT IN PLACE WHEN DISCOVERED.
NRC RESIDENT INSPECTOR WAS NOTIFIED
CONTACT HOO FOR ADDITIONAL INFORMATION
COMPENSATORY MEASURES PUT IN PLACE WHEN DISCOVERED.
NRC RESIDENT INSPECTOR WAS NOTIFIED
CONTACT HOO FOR ADDITIONAL INFORMATION
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 39583
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: LAUDENBACH
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: LAUDENBACH
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 02/12/2003
Notification Time: 21:21 [ET]
Event Date: 02/12/2003
Event Time: 17:04 [CST]
Last Update Date: 04/04/2003
Notification Time: 21:21 [ET]
Event Date: 02/12/2003
Event Time: 17:04 [CST]
Last Update Date: 04/04/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
SONIA BURGESS (R3)
SONIA BURGESS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE DURING TESTING
During a test of HPCI, the flow controller failed as the controller was being transferred from manual to balance. The system was manually tripped and remains inoperable. The system impacted is the High Pressure Coolant Injection and the cause is being investigated. The plant is also in a LCO action statement. Corrective action is being implemented to correct this single train system failure.
The NRC Resident Inspector was notified. State and local agencies will be notified.
*** EVENT RETRACTION BY TIM WITSCHEN TO ERIC THOMAS AT 1600 EST ON 4/4/03 ***
"Event report 39583 was determined not to be reportable. The HPCI system would have been able to perform its safety function of automatically delivering 2700 gpm to the reactor within 45 seconds of initiation signal in the event of a loss of coolant accident, and to mitigate the consequences of a high energy line break. [Therefore], this event is being retracted."
The licensee will notify the NRC Resident Inspector.
During a test of HPCI, the flow controller failed as the controller was being transferred from manual to balance. The system was manually tripped and remains inoperable. The system impacted is the High Pressure Coolant Injection and the cause is being investigated. The plant is also in a LCO action statement. Corrective action is being implemented to correct this single train system failure.
The NRC Resident Inspector was notified. State and local agencies will be notified.
*** EVENT RETRACTION BY TIM WITSCHEN TO ERIC THOMAS AT 1600 EST ON 4/4/03 ***
"Event report 39583 was determined not to be reportable. The HPCI system would have been able to perform its safety function of automatically delivering 2700 gpm to the reactor within 45 seconds of initiation signal in the event of a loss of coolant accident, and to mitigate the consequences of a high energy line break. [Therefore], this event is being retracted."
The licensee will notify the NRC Resident Inspector.