| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/04/2004 - 08/05/2004 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 40920 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRIS SKINNER
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/04/2004
Notification Time: 04:14 [ET]
Event Date: 08/03/2004
Event Time: 10:46 [EDT]
Last Update Date: 08/04/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MOHAMED SHANBAKY (R1)
|
| 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 HIGH PRESSURE CORE SPRAY RENDERED INOPERABLE DUE TO FAULTY TEST EQUIPMENT
"Maintenance technicians were performing surveillance testing on the Division 3 Battery. The as-found bus voltage was approximately 139 VDC and the technicians adjusted the battery charger output voltage to 134 VDC.
"At 1046, the control room received an alarm with bus voltage at 125 VDC. The High Pressure Core Spray System was declared inoperable per Technical Specification 3.8.4 with Division 3 DC Bus voltage < 130 VDC.
"The maintenance technicians determined that the voltmeter used to measure the voltage was defective and actual bus voltage was adjusted to 125 VDC.
"At 1105, Division 3 bus voltage was restored above 130 VDC (136 VDC) and the High Pressure Core Spray System was declared operable. The High Pressure Core Spray System was inoperable for approximately 19 minutes from when the alarm was received until the maintenance technicians restored voltage to 136 VDC. The High Pressure Core Spray System is a single train system."
The licensee informed the NRC Resident Inspector. |
| Power Reactor | Event Number: 40921 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: ANTHONY STALLARD
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/04/2004
Notification Time: 11:14 [ET]
Event Date: 08/04/2004
Event Time: 10:24 [EDT]
Last Update Date: 08/04/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
CHRISTINE LIPA (R3)
TERRY REIS (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text UNEXPECTED REACTOR TRIP DURING MAINTENANCE ACTIVITIES
At 1024 EDT a reactor trip occurred during maintenance activities involving the control rod drive trip breakers. All control rods fully inserted. The unit is currently stable with decay heat removal via the main steam system through the turbine bypass valves to the main condenser. Post trip response was normal with the following exceptions noted:
1. #4 main turbine stop valve may not have fully closed.
2. A #2 Steam Generator Safety Valve may be lifting early (lifted at 1010 psi rather than the 1050 psi setpoint).
3. Turbine Bypass valve SP13A3 stuck slightly open - isolated.
All offsite power lines have been verified operable and both EDGs are available in standby, if needed. The licensee informed the local sheriff's department as required whenever a Steam Generator Safety valve lifts and the NRC Resident Inspector. |
| Power Reactor | Event Number: 40922 | Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LARRY BROOKS
HQ OPS Officer: ARLON COSTA | Notification Date: 08/04/2004
Notification Time: 15:18 [ET]
Event Date: 08/04/2004
Event Time: 07:15 [CDT]
Last Update Date: 08/04/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| 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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF EMERGENCY NOTIFICATION DUE TO INOPERABLE SIRENS
"At 0715 on August 4, 2004, Exelon was notified by Fulton Contracting that Braidwood Station had >[greater than] 25% of its emergency notification sirens inoperable. The cause of the inoperability [at 0626] for the sirens was due to a loss of power due to severe weather. As of 0708 on August 4, 2004, the number of inoperable sirens was less than 25%. Due to a major loss of emergency preparedness capabilities, this event is reportable per 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 40924 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: DOUGLAS NEVE
HQ OPS Officer: BILL GOTT | Notification Date: 08/04/2004
Notification Time: 16:57 [ET]
Event Date: 08/04/2004
Event Time: 08:38 [CDT]
Last Update Date: 08/04/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
| 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 FITNESS FOR DUTY
A licensed employee was determined to be under the influence of alcohol during a for cause test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee notified the NRC Resident Inspector. | |