Event Notification Report for September 13, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/12/2009 - 09/13/2009
Power Reactor
Event Number: 45347
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: BILL POIRIER
HQ OPS Officer: PETE SNYDER
Region: 4 State: CA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: BILL POIRIER
HQ OPS Officer: PETE SNYDER
Notification Date: 09/13/2009
Notification Time: 16:12 [ET]
Event Date: 09/13/2009
Event Time: 12:43 [PDT]
Last Update Date: 09/13/2009
Notification Time: 16:12 [ET]
Event Date: 09/13/2009
Event Time: 12:43 [PDT]
Last Update Date: 09/13/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
DAVID PROULX (R4DO)
DAVID PROULX (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 94 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP FOLLOWING TURBINE TRIP FOR LOSS OF CONDENSER VACUUM
"The SONGS Unit 2 reactor automatically tripped from approximately 94% power at 1243 PDT due to loss of turbine load caused by lowering main condenser vacuum. Prior to the reactor trip, personnel were attempting to conduct a heat treat on Unit 2. During this evolution, Gate 5 in the main circulating water system was being repositioned when it stopped moving at 45 percent. This resulted in a recirculation and subsequent increase in circulating water temperature, a lowering main condenser vacuum, a loss of load on the main turbine, and an associated automatic reactor trip.
"All rods inserted on the automatic reactor trip and the electric grid is stable.
"This event report is being made under 10CFR50.72(b)(2)(iv)(B) as a valid Reactor Protection System actuation."
Decay heat is being removed via normal feedwater to steam generators steaming through the condenser bypass valves to the main condenser.
"At the time of this event, SONGS Unit 3 was operating at approximately 99% power."
The licensee notified the NRC Resident Inspector.
"The SONGS Unit 2 reactor automatically tripped from approximately 94% power at 1243 PDT due to loss of turbine load caused by lowering main condenser vacuum. Prior to the reactor trip, personnel were attempting to conduct a heat treat on Unit 2. During this evolution, Gate 5 in the main circulating water system was being repositioned when it stopped moving at 45 percent. This resulted in a recirculation and subsequent increase in circulating water temperature, a lowering main condenser vacuum, a loss of load on the main turbine, and an associated automatic reactor trip.
"All rods inserted on the automatic reactor trip and the electric grid is stable.
"This event report is being made under 10CFR50.72(b)(2)(iv)(B) as a valid Reactor Protection System actuation."
Decay heat is being removed via normal feedwater to steam generators steaming through the condenser bypass valves to the main condenser.
"At the time of this event, SONGS Unit 3 was operating at approximately 99% power."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 45348
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CAMERON CAMPBELL
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: PA
Unit: [] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CAMERON CAMPBELL
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 09/14/2009
Notification Time: 01:49 [ET]
Event Date: 09/13/2009
Event Time: 22:44 [EDT]
Last Update Date: 09/14/2009
Notification Time: 01:49 [ET]
Event Date: 09/13/2009
Event Time: 22:44 [EDT]
Last Update Date: 09/14/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RAY POWELL (R1DO)
RAY POWELL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | M/R | Y | 0 | Startup | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM DUE TO SHORT PERIOD DURING PLANT SHUTDOWN
"During the scheduled shutdown to commence the Peach Bottom Unit 3 refueling outage, Unit 3 was manually shutdown using the mode switch in accordance with GP-3, 'Normal Plant Shutdown,' when reactor period lowered below 50 seconds as indicated on the WRNM [Wide Range Nuclear Monitoring] system. The Feedwater Startup Level Controller was in automatic set at 23" when a small addition of cold water added enough positive reactivity to cause reactor period to be less than 50 seconds. The shortest period observed was 44 seconds. The WRNM system RPS [Reactor Protective System] automatic SCRAM setpoint is 19 seconds."
All control rods inserted into the core. Decay heat is being removed by shutdown cooling. The plant is continuing into its scheduled refueling outage.
The licensee notified the NRC Resident Inspector.
"During the scheduled shutdown to commence the Peach Bottom Unit 3 refueling outage, Unit 3 was manually shutdown using the mode switch in accordance with GP-3, 'Normal Plant Shutdown,' when reactor period lowered below 50 seconds as indicated on the WRNM [Wide Range Nuclear Monitoring] system. The Feedwater Startup Level Controller was in automatic set at 23" when a small addition of cold water added enough positive reactivity to cause reactor period to be less than 50 seconds. The shortest period observed was 44 seconds. The WRNM system RPS [Reactor Protective System] automatic SCRAM setpoint is 19 seconds."
All control rods inserted into the core. Decay heat is being removed by shutdown cooling. The plant is continuing into its scheduled refueling outage.
The licensee notified the NRC Resident Inspector.