| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/23/2006 - 03/24/2006 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 42425 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOHN BRADY
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/17/2006
Notification Time: 01:30 [ET]
Event Date: 03/16/2006
Event Time: 22:50 [EST]
Last Update Date: 03/23/2006 | 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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF COMMUNICATION - ERDADS COMPUTER FAILED
"On 3/16/2006 at approximately 2010 [EST], the U2 ERDADS computer failed and stopped providing updated plant data to the Unit 2 and Technical Support Center operator consoles, leaving the displays essentially static. Investigation of the failure mode is ongoing and attempts to restore the ERDADS to normal are in progress.
"Loss of the ERDADS output for greater than one hour is reportable as a major loss of assessment and communication capability under 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM J. HESSLING TO W. GOTT AT 1603 ON 03/23/06 * * *
ERDADS system is restored.
The licensee notified the NRC Resident Inspector.
Notified R2DO (C. Evans) |
| Power Reactor | Event Number: 42429 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CALVIN WARD
HQ OPS Officer: JOHN MacKINNON | Notification Date: 03/19/2006
Notification Time: 17:44 [ET]
Event Date: 03/19/2006
Event Time: 12:40 [EST]
Last Update Date: 03/23/2006 | 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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNIT 2 ERDADS (EMERGENCY RESPONSE DATA ACQUISITION AND DISPLAY SYSTEM) COMPUTER DECLARED INOPERABLE.
"On 3/19/06 at approximately 1240, the U2 ERDADS computer failed and stopped providing updated plant data to the Unit 2 and Technical Support Center Operator Consoles, leaving the displays essentially static. Investigation of the failure mode is ongoing and attempts to restore the ERDADS to normal are in progress. A similar event occurred on 3/16/06, EN# 42425. Loss of the ERDADS output for greater than one hour is reportable as a major loss of assessment and communication capability under 10 CFR 50.72(b)(3)(xiii)."
The ERDADS computer has been restored but the licensee does not considered it fully operable. Vendor is coming in on 3/20/06 to try to correct the ERDADS computer problem.
The NRC Resident Inspector was notified of this by the licensee.
* * * UPDATE FROM J. HESSLING TO W. GOTT AT 1603 ON 03/23/06 * * *
ERDADS system is restored.
The licensee notified the NRC Resident Inspector.
Notified R2DO (C. Evans) |
| Power Reactor | Event Number: 42444 | Facility: SEQUOYAH
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAY WHITWORTH
HQ OPS Officer: PETE SNYDER | Notification Date: 03/22/2006
Notification Time: 19:49 [ET]
Event Date: 03/22/2006
Event Time: 16:24 [EST]
Last Update Date: 03/23/2006 | 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
| Person (Organization):
CAROLYN EVANS (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 | Event Text TURBINE TRIP / REACTOR TRIP CAUSED BY MAIN GENERATOR TRIP
"This notification fulfills the 4-hr. non-emergency reporting requirement for Reactor Protection System actuation and the 8-hr. non-emergency reporting requirement for an ESF actuation (specifically Auxiliary Feedwater System start).
"At 1624 EST, Unit 2 reactor tripped from full power due to main generator trip caused by actuation of the main generator neutral overvoltage relay (the 100% stator ground fault relay also actuated). Safety Injection did not actuate and was not required to actuate.
"All automatic actions occurred as designed (e.g., steam dump operation, feedwater system, etc.).
"The operating crew responded to the trip using emergency procedures. The unit is being maintained in Mode 3 (Hot Standby) using General Operating Instructions.
"No primary steam or steam generator safety valves opened due to this trip.
"An investigation has been initiated to determine the cause of this unit trip. A recovery plan will be developed."
All control rods fully inserted on the reactor trip. Decay heat is being removed by auxiliary feedwater feeding the steam generators and steaming through the steam dump valves to the main condenser. Offsite power is stable and all emergency busses are being powered via offsite power. All Emergency Diesel Generators are available if required.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 42445 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JOE HESSLING
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/23/2006
Notification Time: 10:25 [ET]
Event Date: 03/23/2006
Event Time: 10:30 [EST]
Last Update Date: 03/23/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
CAROLYN EVANS (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 | Event Text MAINTENANCE ON ENS PHONE LINE
"At approximately 1030 this morning, the ENS lines for unit 1, unit 2, and Technical Support Center will be unreliable and may be unavailable for maintenance on off-site telephone circuitry. The expected duration will be until 1600 on 3/23/06. Commercial telephones will still be available. The loss of the ENS communications is reportable under 10CFR 50.72 (b)(3)(xiii). St Lucie will perform a phone test following ENS restoration."
Commercial phone lines to the site are still available.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM J. HESSLING TO W. GOTT AT 1603 ON 03/23/06 * * *
ENS lines for unit 1, unit 2 and the Technical Support Center have been restored and tested.
The licensee notified the NRC Resident Inspector.
Notified R2DO (C. Evans) |
| Power Reactor | Event Number: 42446 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: FRED KIRK
HQ OPS Officer: STEVE SANDIN | Notification Date: 03/23/2006
Notification Time: 18:20 [ET]
Event Date: 03/23/2006
Event Time: 12:50 [EST]
Last Update Date: 03/23/2006 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
CAROLYN EVANS (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 99 | Power Operation | | 2 | N | Y | 100 | Power Operation | 99 | Power Operation | Event Text 24-HOUR CONDITION OF LICENSE REPORT DUE TO THERMAL POWER POTENTIALLY EXCEEDING LICENSED LIMIT
"McGuire Unit 1 and Unit 2 may have been operating greater than design thermal power limits of 3411 MW [Megawatt] by approximately 0.08% due to discovery of non-conservative thermal power calculations. Preliminary evaluation of Steam Generator Blow Down inputs into the thermal power calorimetric indicates a non-conservative error resulting in indicated total thermal power being approximately 0.08% lower than actual. Additional evaluations to confirm indicated power are ongoing. Power was reduced as soon as the on duty shift was made aware of the error and both Unit 1 and Unit 2 indicated thermal power is being limited to less than 99.85% to ensure actual reactor power remains less than 3411 MW.
"This notification is being made pursuant to the McGuire Facility Operating License Condition 2.C.(1) Maximum Power Level."
The licensee will inform the NRC Resident Inspector. | |