Event Notification Report for March 12, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/11/2013 - 03/12/2013
Power Reactor
Event Number: 48817
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: CHRIS TRENT
HQ OPS Officer: CHARLES TEAL
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: CHRIS TRENT
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/12/2013
Notification Time: 17:31 [ET]
Event Date: 03/12/2013
Event Time: 14:31 [EDT]
Last Update Date: 03/12/2013
Notification Time: 17:31 [ET]
Event Date: 03/12/2013
Event Time: 14:31 [EDT]
Last Update Date: 03/12/2013
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):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 3 | Startup | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO TURBINE INLET PRESSURE PERTURBATION
"Unit 3 experienced an automatic reactor trip from approximately 3% power. The turbine was off-line and undergoing testing following a control valve position indication repair. A turbine inlet pressure channel perturbation momentarily actuated the 'Reactor Trip by Turbine Trip' protection, causing the Unit 3 reactor to trip. Unit 3 is currently stable in Mode 3. No other complications were noted following the reactor trip. The cause of the turbine inlet pressure channel perturbation is currently under investigations."
All control rods fully inserted. Normal feedwater is supplying the steam generators and decay heat removal is to atmosphere via the atmospheric steam dumps. There is no primary to secondary leakage. Unit 3 is in a normal shutdown offsite electrical power alignment. There is no impact on Unit 4.
The NRC Resident Inspector has been notified.
"Unit 3 experienced an automatic reactor trip from approximately 3% power. The turbine was off-line and undergoing testing following a control valve position indication repair. A turbine inlet pressure channel perturbation momentarily actuated the 'Reactor Trip by Turbine Trip' protection, causing the Unit 3 reactor to trip. Unit 3 is currently stable in Mode 3. No other complications were noted following the reactor trip. The cause of the turbine inlet pressure channel perturbation is currently under investigations."
All control rods fully inserted. Normal feedwater is supplying the steam generators and decay heat removal is to atmosphere via the atmospheric steam dumps. There is no primary to secondary leakage. Unit 3 is in a normal shutdown offsite electrical power alignment. There is no impact on Unit 4.
The NRC Resident Inspector has been notified.
Power Reactor
Event Number: 48818
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: ANDREW TEREZAKIS
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: ANDREW TEREZAKIS
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 03/12/2013
Notification Time: 18:01 [ET]
Event Date: 03/12/2013
Event Time: 14:51 [EDT]
Last Update Date: 03/12/2013
Notification Time: 18:01 [ET]
Event Date: 03/12/2013
Event Time: 14:51 [EDT]
Last Update Date: 03/12/2013
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):
KATHLEEN O'DONOHUE (R2DO)
KATHLEEN O'DONOHUE (R2DO)
| 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 |
AUTOMATIC REACTOR TRIP ON THERMAL MARGIN/LOW PRESSURE
"On 3/12/13 at 1451 EDT, during normal full power operations, Unit 1 automatically tripped due to the Thermal Margin/ Low Pressure trip setpoint being exceeded. The trip was uncomplicated and all CEAs [control element assembly] fully inserted when the reactor was tripped. Main Steam Safety valves lifted momentarily post trip and reseated. No automatic safety system actuations were required and none occurred. The cause and details of the automatic trip are under investigation.
"The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Main Feedwater and Atmospheric Dump Valves in operation. The operation of the Steam Bypass Control System is under review by Engineering. The Offsite power grid is available and stable."
The licensee has notified the NRC Resident Inspector and there was no impact on Unit 2.
"On 3/12/13 at 1451 EDT, during normal full power operations, Unit 1 automatically tripped due to the Thermal Margin/ Low Pressure trip setpoint being exceeded. The trip was uncomplicated and all CEAs [control element assembly] fully inserted when the reactor was tripped. Main Steam Safety valves lifted momentarily post trip and reseated. No automatic safety system actuations were required and none occurred. The cause and details of the automatic trip are under investigation.
"The plant is stable in Mode 3 at normal operating temperature and pressure. RCS Heat Removal is being maintained with Main Feedwater and Atmospheric Dump Valves in operation. The operation of the Steam Bypass Control System is under review by Engineering. The Offsite power grid is available and stable."
The licensee has notified the NRC Resident Inspector and there was no impact on Unit 2.
Power Reactor
Event Number: 48819
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL QUITTER
HQ OPS Officer: STEVE SANDIN
Region: 4 State: CA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL QUITTER
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/13/2013
Notification Time: 00:58 [ET]
Event Date: 03/12/2013
Event Time: 17:06 [PDT]
Last Update Date: 03/13/2013
Notification Time: 00:58 [ET]
Event Date: 03/12/2013
Event Time: 17:06 [PDT]
Last Update Date: 03/13/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
DALE POWERS (R4DO)
DALE POWERS (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
UNIT 2 LOSS OF SHUTDOWN MONITORING INSTRUMENTATION SYSTEM
"On March 12, 2013, at 1706 PDT, with the reactor coolant system not intact, plant operators identified [an] unexpected increase in nuclear reactivity count rate as indicated by source range instrumentation channel N-32. This increase was NOT indicated on redundant wide range instrumentation channels N-51 and N-52. Operators identified that technicians working in the area of the N-32 cable routing had bumped the cabling, resulting in the false increase in the count rate. The source range channel N-32 was subsequently declared inoperable. Prior to this event the other source range channel N-31 had been declared inoperable.
"The above event resulted in loss of control room audible indication required by DCPP [Diablo Canyon Power Plant] technical specification to monitor the core reactivity condition and consequently caused loss of the monitoring system. Operators retained capability of monitoring core reactivity conditions through use of the two wide range nuclear instrumentation channels N-51 and N-52.
"In response to this concern, plant operators verified all core alterations were suspended, verified boron concentration was within acceptable limits for current conditions, suspended operations that could dilute the boron concentration, verified reactor trip breakers were open and control rods incapable of withdrawal, and initiated actions to restore to service one of the source range instrumentation channels with its associated control room audible count rate indication.
"NRC Resident Inspectors have been notified."
* * * UPDATE AT 0848 EDT ON 3/13/13 FROM MICHAEL QUITTER TO DONG PARK * * *
"This is an update to EN #48819 reported on March 12, 2013 at 2158 PDT.
"This update informs the NRC that PG&E, in accordance with provisions of TS 3.0.4b, will be restoring the source range instrumentation channel N-32 to service in Mode 5, maintaining the availability and monitoring of the wide range instrumentation channels while in Mode 5 until the source range channel is returned to service."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Powers).
"On March 12, 2013, at 1706 PDT, with the reactor coolant system not intact, plant operators identified [an] unexpected increase in nuclear reactivity count rate as indicated by source range instrumentation channel N-32. This increase was NOT indicated on redundant wide range instrumentation channels N-51 and N-52. Operators identified that technicians working in the area of the N-32 cable routing had bumped the cabling, resulting in the false increase in the count rate. The source range channel N-32 was subsequently declared inoperable. Prior to this event the other source range channel N-31 had been declared inoperable.
"The above event resulted in loss of control room audible indication required by DCPP [Diablo Canyon Power Plant] technical specification to monitor the core reactivity condition and consequently caused loss of the monitoring system. Operators retained capability of monitoring core reactivity conditions through use of the two wide range nuclear instrumentation channels N-51 and N-52.
"In response to this concern, plant operators verified all core alterations were suspended, verified boron concentration was within acceptable limits for current conditions, suspended operations that could dilute the boron concentration, verified reactor trip breakers were open and control rods incapable of withdrawal, and initiated actions to restore to service one of the source range instrumentation channels with its associated control room audible count rate indication.
"NRC Resident Inspectors have been notified."
* * * UPDATE AT 0848 EDT ON 3/13/13 FROM MICHAEL QUITTER TO DONG PARK * * *
"This is an update to EN #48819 reported on March 12, 2013 at 2158 PDT.
"This update informs the NRC that PG&E, in accordance with provisions of TS 3.0.4b, will be restoring the source range instrumentation channel N-32 to service in Mode 5, maintaining the availability and monitoring of the wide range instrumentation channels while in Mode 5 until the source range channel is returned to service."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Powers).