Event Notification Report for January 25, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/24/2003 - 01/25/2003
Power Reactor
Event Number: 39535
Facility: SURRY
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ALISON MacKELLAR
HQ OPS Officer: STEVE SANDIN
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ALISON MacKELLAR
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/25/2003
Notification Time: 09:25 [ET]
Event Date: 01/25/2003
Event Time: 07:00 [EST]
Last Update Date: 01/25/2003
Notification Time: 09:25 [ET]
Event Date: 01/25/2003
Event Time: 07:00 [EST]
Last Update Date: 01/25/2003
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):
KEN BARR (R2)
KEN BARR (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 25 | Power Operation | 0 | Hot Shutdown |
UNIT 1 EXPERIENCED AN AUTOMATIC REACTOR TRIP ON LO-LO STEAM GENERATOR WATER LEVEL
"At 0700 hours, with Surry Power Station Unit 1 at 25% reactor power during power ascension, an automatic reactor trip was generated due to 2/3 channels on 'B' S/G Lo-Lo Level.
"All control rods fully inserted into the core as designed. Borated as necessary to ensure adequate shutdown margin. The shutdown margin for Unit 1 was determined to be satisfactory. 'A' and 'B' motor driven auxiliary feedwater pumps automatically initiated as designed on low low steam generator level following the trip. The turbine driven auxiliary feedwater pump tripped. All three Main Steam Trip Valves were manually closed due to the primary RCS cooldown. Primary RCS temperature decreased to approximately 526 degrees. Currently RCS temperature is stable at 547 degrees on the Secondary Power Operated Relief Valves.
"No primary safety or power operated relief valves were actuated during the event. No indication of primary to secondary leakage exists, therefore no adverse radiological consequences resulted from this event.
"All electrical busses remained energized following the trip and all emergency diesel generators are operable. There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. The cause of the event is being investigated.
"Unit 1 is currently at Hot Shutdown with RCS temperature being maintained at approximately 547 degrees.
'Unit 2 was not affected by this event and remains stable at 100% power operations.
"This event is being reported in accordance with 10CFR50.72(b)(2)(iv) and 10CFR50.72(b)(3)(iv)."
Operators were in the process of transitioning between manual and automatic S/G water level control when the automatic trip occurred. The licensee will investigate the cause of the automatic turbine driven auxiliary feedwater pump trip.
The licensee informed the NRC resident inspector.
"At 0700 hours, with Surry Power Station Unit 1 at 25% reactor power during power ascension, an automatic reactor trip was generated due to 2/3 channels on 'B' S/G Lo-Lo Level.
"All control rods fully inserted into the core as designed. Borated as necessary to ensure adequate shutdown margin. The shutdown margin for Unit 1 was determined to be satisfactory. 'A' and 'B' motor driven auxiliary feedwater pumps automatically initiated as designed on low low steam generator level following the trip. The turbine driven auxiliary feedwater pump tripped. All three Main Steam Trip Valves were manually closed due to the primary RCS cooldown. Primary RCS temperature decreased to approximately 526 degrees. Currently RCS temperature is stable at 547 degrees on the Secondary Power Operated Relief Valves.
"No primary safety or power operated relief valves were actuated during the event. No indication of primary to secondary leakage exists, therefore no adverse radiological consequences resulted from this event.
"All electrical busses remained energized following the trip and all emergency diesel generators are operable. There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. The cause of the event is being investigated.
"Unit 1 is currently at Hot Shutdown with RCS temperature being maintained at approximately 547 degrees.
'Unit 2 was not affected by this event and remains stable at 100% power operations.
"This event is being reported in accordance with 10CFR50.72(b)(2)(iv) and 10CFR50.72(b)(3)(iv)."
Operators were in the process of transitioning between manual and automatic S/G water level control when the automatic trip occurred. The licensee will investigate the cause of the automatic turbine driven auxiliary feedwater pump trip.
The licensee informed the NRC resident inspector.
Power Reactor
Event Number: 39536
Facility: SURRY
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN DUFF
HQ OPS Officer: MIKE RIPLEY
Region: 2 State: VA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN DUFF
HQ OPS Officer: MIKE RIPLEY
Notification Date: 01/25/2003
Notification Time: 17:35 [ET]
Event Date: 01/25/2003
Event Time: 14:14 [EST]
Last Update Date: 01/25/2003
Notification Time: 17:35 [ET]
Event Date: 01/25/2003
Event Time: 14:14 [EST]
Last Update Date: 01/25/2003
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):
KEN BARR (R2)
HERB BERKOW (NRR)
KEN BARR (R2)
HERB BERKOW (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP DUE TO A MAIN GENERATOR TRIP
"At 1414 hours, with Surry Power Station Unit 2 at 100% reactor power an automatic reactor trip was generated due to a main generator trip. The main generator tripped due to a differential lockout.
"Individual rod position indications (IRPI) for three control rods indicated between 11 and 20 steps following the trip. An emergency boration was initiated followed by a normal boration in accordance with station procedures to ensure adequate shutdown margin. The shutdown margin for Unit 2 was determined to be satisfactory. All other control rod indications fully inserted into the core as designed. The three IRPIs that initially did not indicate fully inserted slowly drifted to less that 10 steps.
"All three auxiliary feedwater pumps automatically initiated as designed on low low steam generator level following the trip. Currently RCS temperature is stable at 547 degrees and being controlled by condenser steam dump valves. No primary or secondary safety or power operated relief valves were actuated during the event. No indications of primary to secondary leakage exist.
"All electrical busses transferred properly following the trip and all emergency diesel generators are operable. At the time of the Unit 2 reactor trip, Surry Unit 1 was off-line due to a previous trip. Load shed occurred on the station service busses as designed. As a result of the load shed signal, the Surry Unit 1 "B" Main Feed Pump tripped. The Unit 1 "A" Main Feed Pump had previously been shut down. This resulted in a loss of both Main Feed Pumps on Unit 1 and restarted the Unit 1 Motor Driven Auxiliary Feedwater Pumps.
"There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. The cause of the Unit 2 trip is being investigated.
"Unit 2 is currently at Hot Shutdown with RCS temperature being maintained at approximately 547 degrees. Unit 1 is also at Hot Shutdown with RCS temperature being maintained at approximately 547 degrees.
"This event is being reported in accordance with 10CFR50.72(b)(2)(iv) and 10CFR50.72(b)(3)(iv)."
The licensee is investigating the cause of the main generator trip. The licensee notified the NRC resident inspector.
"At 1414 hours, with Surry Power Station Unit 2 at 100% reactor power an automatic reactor trip was generated due to a main generator trip. The main generator tripped due to a differential lockout.
"Individual rod position indications (IRPI) for three control rods indicated between 11 and 20 steps following the trip. An emergency boration was initiated followed by a normal boration in accordance with station procedures to ensure adequate shutdown margin. The shutdown margin for Unit 2 was determined to be satisfactory. All other control rod indications fully inserted into the core as designed. The three IRPIs that initially did not indicate fully inserted slowly drifted to less that 10 steps.
"All three auxiliary feedwater pumps automatically initiated as designed on low low steam generator level following the trip. Currently RCS temperature is stable at 547 degrees and being controlled by condenser steam dump valves. No primary or secondary safety or power operated relief valves were actuated during the event. No indications of primary to secondary leakage exist.
"All electrical busses transferred properly following the trip and all emergency diesel generators are operable. At the time of the Unit 2 reactor trip, Surry Unit 1 was off-line due to a previous trip. Load shed occurred on the station service busses as designed. As a result of the load shed signal, the Surry Unit 1 "B" Main Feed Pump tripped. The Unit 1 "A" Main Feed Pump had previously been shut down. This resulted in a loss of both Main Feed Pumps on Unit 1 and restarted the Unit 1 Motor Driven Auxiliary Feedwater Pumps.
"There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. The cause of the Unit 2 trip is being investigated.
"Unit 2 is currently at Hot Shutdown with RCS temperature being maintained at approximately 547 degrees. Unit 1 is also at Hot Shutdown with RCS temperature being maintained at approximately 547 degrees.
"This event is being reported in accordance with 10CFR50.72(b)(2)(iv) and 10CFR50.72(b)(3)(iv)."
The licensee is investigating the cause of the main generator trip. The licensee notified the NRC resident inspector.