Event Notification Report for January 02, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/01/2002 - 01/02/2002
EVENT NUMBERS
38604386053860638607
Power Reactor
Event Number: 38604
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: SCOTT SAUNDERS
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: SCOTT SAUNDERS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/02/2002
Notification Time: 04:56 [ET]
Event Date: 01/02/2002
Event Time: 03:05 [EST]
Last Update Date: 01/02/2002
Notification Time: 04:56 [ET]
Event Date: 01/02/2002
Event Time: 03:05 [EST]
Last Update Date: 01/02/2002
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):
ANNE BOLAND (R2)
ANNE BOLAND (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 7 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO DECREASING STEAM GENERATOR WATER LEVEL.
During a plant start-up at 7% reactor power, feedwater oscillations occurred on all three steam generators. At 0215 on 01/02/02 the main feedwater regulator bypass valves were placed in manual control to stabilize level. The bypass valves were then returned to automatic control at 0245 on 01/02/02, and the oscillations continued within the normal operating band of 52-62%. At 0300 0n 01/02/02. The Control Operator noted lowering level on the "C" steam generator at approximately 55% with indication that the "C" main feedwater regulator bypass valve was shut. The operator placed the "C" bypass valve in manual control and attempted to open the valve with no response noted in valve position indication. At 30% indicated level in the "C" steam generator and a lowering trend, the Unit Shift Control Operator ordered a manual reactor trip prior to receipt of a steam generator low water level trip signal at 25%. All safety systems functioned as expected. Both Motor Driven Auxiliary Feedwater Pumps automatically actuated on the subsequent 'C" steam generator low water level signal. All rods fully inserted into the core and the electrical grid is stable. An investigation into what caused this event is in progress.
The NRC resident inspector was notified of this event by the licensee.
During a plant start-up at 7% reactor power, feedwater oscillations occurred on all three steam generators. At 0215 on 01/02/02 the main feedwater regulator bypass valves were placed in manual control to stabilize level. The bypass valves were then returned to automatic control at 0245 on 01/02/02, and the oscillations continued within the normal operating band of 52-62%. At 0300 0n 01/02/02. The Control Operator noted lowering level on the "C" steam generator at approximately 55% with indication that the "C" main feedwater regulator bypass valve was shut. The operator placed the "C" bypass valve in manual control and attempted to open the valve with no response noted in valve position indication. At 30% indicated level in the "C" steam generator and a lowering trend, the Unit Shift Control Operator ordered a manual reactor trip prior to receipt of a steam generator low water level trip signal at 25%. All safety systems functioned as expected. Both Motor Driven Auxiliary Feedwater Pumps automatically actuated on the subsequent 'C" steam generator low water level signal. All rods fully inserted into the core and the electrical grid is stable. An investigation into what caused this event is in progress.
The NRC resident inspector was notified of this event by the licensee.
Power Reactor
Event Number: 38605
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: MYERS
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: MYERS
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/02/2002
Notification Time: 09:48 [ET]
Event Date: 01/02/2002
Event Time: 01:50 [EST]
Last Update Date: 01/02/2002
Notification Time: 09:48 [ET]
Event Date: 01/02/2002
Event Time: 01:50 [EST]
Last Update Date: 01/02/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GARY SHEAR (R3)
GARY SHEAR (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 |
SAFETY PARAMETER DISPLAY SYSTEM (SPDS) IS OUT OF SERVICE
The SPDS has not been functioning since 01:50. It has been operable for about one hour, but they are still monitoring it before they determine it to be completely operable.
The NRC Resident Inspector will be notified.
The SPDS has not been functioning since 01:50. It has been operable for about one hour, but they are still monitoring it before they determine it to be completely operable.
The NRC Resident Inspector will be notified.
Fuel Cycle Facility
Event Number: 38606
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: KEITH WILLIAMSON
HQ OPS Officer: STEVE SANDIN
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: KEITH WILLIAMSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/02/2002
Notification Time: 12:47 [ET]
Event Date: 01/02/2002
Event Time: 11:52 [EST]
Last Update Date: 01/02/2002
Notification Time: 12:47 [ET]
Event Date: 01/02/2002
Event Time: 11:52 [EST]
Last Update Date: 01/02/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GARY SHEAR (R3)
JOHN HICKEY (NMSS)
GARY SHEAR (R3)
JOHN HICKEY (NMSS)
4-HOUR REPORT DUE TO EPA NOTIFICATION REGARDING AN OPACITY VIOLATION
The #3 High Pressure Blower on Boiler #3 tripped due to a suspected equipment malfunction causing a pollutant discharge exceeding the 20% opacity limit in any one hour period specified by EPA to occur between 0915 and 0921EST. Operations notified the NRC Resident Inspector and the Ohio Environmental Protection Agency (OEPA) of the violation.
The #3 High Pressure Blower on Boiler #3 tripped due to a suspected equipment malfunction causing a pollutant discharge exceeding the 20% opacity limit in any one hour period specified by EPA to occur between 0915 and 0921EST. Operations notified the NRC Resident Inspector and the Ohio Environmental Protection Agency (OEPA) of the violation.
Power Reactor
Event Number: 38607
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JAMES GILMORE
HQ OPS Officer: STEVE SANDIN
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JAMES GILMORE
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/02/2002
Notification Time: 21:34 [ET]
Event Date: 01/02/2002
Event Time: 12:30 [CST]
Last Update Date: 01/04/2002
Notification Time: 21:34 [ET]
Event Date: 01/02/2002
Event Time: 12:30 [CST]
Last Update Date: 01/04/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
At 1230CST SPDS was lost for reasons unknown. Troubleshooting is currently in progress. The licensee informed the NRC Resident Inspector.
* * * Update on 01/04/02 at 1118EST by Rick Hubbard taken by S. SANDIN * * *
SPDS was restored to service at 2229CST on 01/03/02. R4DO (B. Spitzberg) notified. The licensee will inform the NRC Resident Inspector.
At 1230CST SPDS was lost for reasons unknown. Troubleshooting is currently in progress. The licensee informed the NRC Resident Inspector.
* * * Update on 01/04/02 at 1118EST by Rick Hubbard taken by S. SANDIN * * *
SPDS was restored to service at 2229CST on 01/03/02. R4DO (B. Spitzberg) notified. The licensee will inform the NRC Resident Inspector.