| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/24/2005 - 10/25/2005 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 42069 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: ALAN T. HALL
HQ OPS Officer: JOE O'HARA | Notification Date: 10/24/2005
Notification Time: 00:26 [ET]
Event Date: 10/23/2005
Event Time: 23:00 [EDT]
Last Update Date: 10/24/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MIKE ERNSTES (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | | 2 | N | Y | 25 | Power Operation | 25 | Power Operation | Event Text NON-EMERGENCY EVENT DECLARED FOR LOSS OF ERDADS SYSTEM AFFECTING BOTH UNITS
"On 10/23/05 at 2300, the Unit 1 and Unit 2 emergency response data acquisition and display system's emergency response data system (ERDS) link to the NRC failed. Troubleshooting and restoration work is in progress."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 42072 | Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: ARLON COSTA | Notification Date: 10/24/2005
Notification Time: 12:41 [ET]
Event Date: 10/21/2005
Event Time: 09:00 [EDT]
Last Update Date: 10/24/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
CHRISTINE LIPA (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 | Event Text UNANALYZED CONDITION DUE TO RELOCATION OF A FIRE DOOR BOUNDARY
"This event is being reported as 10CFR50.72(b)(3)(ii)(B), an unanalyzed condition that significantly degrades plant safety. A postulated fire water system line break did not take into consideration the movement of a fire door boundary. Consequently, the break may affect safe shutdown of the plant. The door boundary was moved in May 1999.
"While assessing a calculation to update fire pump curves (CR 04-00422-04) it was found that the calculation does not appear to have been updated for the tornado depressurization event modifications (DCP 99-05014). Specifically, door DG-112 was moved to the control complex wall from the diesel generator wall. This door movement isolates the rattle space that was previously credited as a relief path for this internal flood.
"A full break is postulated for this line as the result of a safe shutdown earthquake. As the result of the postulated pipe break, both fire protection pumps are expected to auto start resulting in a break flow rate into the hallway of approximately 6,000 gpm. Standard Perry design practice is to assume a 30 minute duration for the pipe break flow isolation unless justified otherwise.
"The line in question was isolated at 2027 on 10/21/05. The valves are being maintained closed under administrative controls."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42073 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: POUL CHRISTIANSEN
HQ OPS Officer: MIKE RIPLEY | Notification Date: 10/24/2005
Notification Time: 16:47 [ET]
Event Date: 10/24/2005
Event Time: 13:14 [EDT]
Last Update Date: 10/24/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MIKE ERNSTES (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | | 2 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text LOSS OF EMERGENCY RESPONSE DATA ACQUISITION AND DISPLAY SYSTEM
"On 10/24/2005 at 12:14 hours, Saint Lucie Units 1 & 2 lost both of the computer trains associated with Emergency Response Data Acquisition and Display System (ERDADS). This is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as a major loss of emergency assessment capability. Other means to monitor critical data exist in each unit. Troubleshooting and restoration work is in progress."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42074 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: MICHAEL MURPHY
HQ OPS Officer: JOE O'HARA | Notification Date: 10/25/2005
Notification Time: 02:16 [ET]
Event Date: 10/24/2005
Event Time: 23:00 [EDT]
Last Update Date: 10/25/2005 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
MIKE ERNSTES (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Standby | 0 | Hot Standby | | 4 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text INOPERABLE START-UP TRANSFORMERS; HIGH SWITCHYARD VOLTAGE DUE TO HURRICANE WILMA
"At 2300 on October 24, 2005, both unit 3 and unit 4 start up transformers were declared inoperable and Tech Spec 3.8.1.1.e action statements were entered. With both units being energized from their respective start-up transformers, the high voltage limit is 241.5kV in accordance with 0-ONOP-004.6, Degraded Switchyard Voltage. System Operations reported switchyard voltage at 243.5 kV and 242.5 kV for unit 3 and unit 4 respectfully. System Operations was requested to lower switchyard voltage to within limits. At 0015 on October 25, 2005, switchyard voltage being lowered to within the switchyard limits and both start-up transformers were declared operable. The high switchyard voltage is due to hurricane Wilma's impact on the Florida service area that has [led] to low system load with cooler weather conditions."
The NRC Resident Inspector has been notified. | |