Event Notification Report for February 21, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/20/2015 - 02/21/2015
Power Reactor
Event Number: 50839
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN TUITE
HQ OPS Officer: JEFF ROTTON
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN TUITE
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/21/2015
Notification Time: 12:46 [ET]
Event Date: 02/21/2015
Event Time: 10:32 [EST]
Last Update Date: 02/21/2015
Notification Time: 12:46 [ET]
Event Date: 02/21/2015
Event Time: 10:32 [EST]
Last Update Date: 02/21/2015
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):
STEVE ROSE (R2DO)
STEVE ROSE (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP INSERTED DUE TO RAPID LOSS OF MAIN CONDENSER VACUUM
"On February 21, 2015 at 10:32 EST, Watts Bar Nuclear Plant Unit 1 reactor was manually tripped due to rapidly dropping main condenser vacuum. Concurrent with the reactor trip the Auxiliary Feedwater system actuated as designed.
"All Control and Shutdown rods fully inserted. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and S/G PORVs. Main Steam Isolation Valves are closed. The Station is in a normal shutdown electrical alignment.
"The cause is currently under investigation.
"This is being reported under 10CFR 50.72(b)(3)(iv)(A) and 10CFR 50.72 (b)(2)(iv)(B).
"The NRC Senior Resident has been notified."
This event had no affect on Unit 2 (Under Construction)
"On February 21, 2015 at 10:32 EST, Watts Bar Nuclear Plant Unit 1 reactor was manually tripped due to rapidly dropping main condenser vacuum. Concurrent with the reactor trip the Auxiliary Feedwater system actuated as designed.
"All Control and Shutdown rods fully inserted. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and S/G PORVs. Main Steam Isolation Valves are closed. The Station is in a normal shutdown electrical alignment.
"The cause is currently under investigation.
"This is being reported under 10CFR 50.72(b)(3)(iv)(A) and 10CFR 50.72 (b)(2)(iv)(B).
"The NRC Senior Resident has been notified."
This event had no affect on Unit 2 (Under Construction)
Power Reactor
Event Number: 50841
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE CICCONE
HQ OPS Officer: VINCE KLCO
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE CICCONE
HQ OPS Officer: VINCE KLCO
Notification Date: 02/21/2015
Notification Time: 21:35 [ET]
Event Date: 02/21/2015
Event Time: 19:50 [EST]
Last Update Date: 02/21/2015
Notification Time: 21:35 [ET]
Event Date: 02/21/2015
Event Time: 19:50 [EST]
Last Update Date: 02/21/2015
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):
RAY POWELL (R1DO)
RAY POWELL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SITE STACK RADIATION MONITOR FAILURE
The Millstone site stack radiation monitor, RM-8169, failed and was declared inoperable at 1950 EST on February 21, 2015. Repairs are in progress.
This event is reportable pursuant to 10 CFR 50.72(b)(3)(xiii) as any event that results in a major loss of emergency assessment capability, off-site response capability, or off-site communications capability.
The Instrument and Controls Department is conducting troubleshooting and repair. The cause of the radiation monitor failure was sample pump failure.
The licensee has notified the NRC Resident Inspector and applicable State and Local authorities.
The Millstone site stack radiation monitor, RM-8169, failed and was declared inoperable at 1950 EST on February 21, 2015. Repairs are in progress.
This event is reportable pursuant to 10 CFR 50.72(b)(3)(xiii) as any event that results in a major loss of emergency assessment capability, off-site response capability, or off-site communications capability.
The Instrument and Controls Department is conducting troubleshooting and repair. The cause of the radiation monitor failure was sample pump failure.
The licensee has notified the NRC Resident Inspector and applicable State and Local authorities.
Power Reactor
Event Number: 50842
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: CHARLIE ACUNA
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: CHARLIE ACUNA
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/22/2015
Notification Time: 02:36 [ET]
Event Date: 02/21/2015
Event Time: 21:22 [EST]
Last Update Date: 02/22/2015
Notification Time: 02:36 [ET]
Event Date: 02/21/2015
Event Time: 21:22 [EST]
Last Update Date: 02/22/2015
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):
RAY POWELL (R1DO)
RAY POWELL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
REACTOR VESSEL LEVEL MONITORING SYSTEM INOPERABLE
The licensee declared the reactor vessel level monitoring system (RVLMS) inoperable when an intermittent failure occurred in the 'B' train reactor vessel level monitoring system (RVLMS) concurrent with the loss of the 19% level sensor in the 'A' train. This caused entry into a 7-day LCO action statement under Technical Specification 3.3.6, Action E.
The 'B' train instrumentation was reset and indication returned to normal and the LCO action was exited after 36 minutes. A Condition Report was submitted to determine cause and repair, if needed.
The licensee has notified the NRC Resident Inspector as well as state and local authorities.
The licensee declared the reactor vessel level monitoring system (RVLMS) inoperable when an intermittent failure occurred in the 'B' train reactor vessel level monitoring system (RVLMS) concurrent with the loss of the 19% level sensor in the 'A' train. This caused entry into a 7-day LCO action statement under Technical Specification 3.3.6, Action E.
The 'B' train instrumentation was reset and indication returned to normal and the LCO action was exited after 36 minutes. A Condition Report was submitted to determine cause and repair, if needed.
The licensee has notified the NRC Resident Inspector as well as state and local authorities.
Power Reactor
Event Number: 51756
Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: JOHN SHOEMAKER
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: DEREK ETUE
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/25/2016
Notification Time: 16:35 [ET]
Event Date: 02/21/2015
Event Time: 00:30 [EST]
Last Update Date: 03/02/2016
Notification Time: 16:35 [ET]
Event Date: 02/21/2015
Event Time: 00:30 [EST]
Last Update Date: 03/02/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 91 | Power Operation |
POWER REDUCTION DUE TO AUTOMATIC OPENING OF A TURBINE BYPASS VALVE
"On February 21, 2015, at approximately 0030 EST, with Fermi 2 in Mode 1 operating at 100 percent reactor thermal power, the West Turbine Bypass Valve (TBV) automatically opened in response to the number two High Pressure Turbine Stop Valve (TSV) cycling from full open to closed and then to 22 percent open. Reactor power was subsequently lowered to 91.5 percent reactor thermal power and the bypass valve closed.
"Per Technical Specification Bases 3.3.1.1, TBVs must remain shut while reactor thermal power is at or above 29.5 percent to consider the TSV closure and Turbine Control Valve (TCV) fast closure Reactor Protection System (RPS) functions operable. The condition was recognized at the time of the event and the RPS functions were declared inoperable. The Limiting Condition for Operation was exited at 0031 EST following TBV closure.
"Since the RPS functions were verified to remain enabled, Fermi 2 did not report this event within 8 hours of occurrence. However, this event was subsequently determined to meet the reporting criterion and is being reported pursuant to 10 CFR 50.72(b)(3)(v)(A).
"The licensee informed the NRC Resident Inspector."
The cause of the High Pressure Turbine Stop Valve cycling was due to a communication card failure that has since been corrected.
This event was determined to be reportable at 1200 EST on 02/24/16. See EN #51755 for a similar event that occurred on 01/06/16.
* * * UPDATE FROM JEFF GROFF TO STEVEN VITTO ON 03/02/2016 AT 1530 EST * * *
"Upon further review, it was determined that this event also meets the reporting criterion of 10CFR50.72(b)(3)(v)(D) for a condition that could have prevented the fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident.
"Although this event was determined to be reportable at 1200 EST on 02/24/16, it met the reporting requirement on the date of the event (02/21/2015).
"The licensee informed the NRC Resident Inspector."
Notified R3DO (Valos).
"On February 21, 2015, at approximately 0030 EST, with Fermi 2 in Mode 1 operating at 100 percent reactor thermal power, the West Turbine Bypass Valve (TBV) automatically opened in response to the number two High Pressure Turbine Stop Valve (TSV) cycling from full open to closed and then to 22 percent open. Reactor power was subsequently lowered to 91.5 percent reactor thermal power and the bypass valve closed.
"Per Technical Specification Bases 3.3.1.1, TBVs must remain shut while reactor thermal power is at or above 29.5 percent to consider the TSV closure and Turbine Control Valve (TCV) fast closure Reactor Protection System (RPS) functions operable. The condition was recognized at the time of the event and the RPS functions were declared inoperable. The Limiting Condition for Operation was exited at 0031 EST following TBV closure.
"Since the RPS functions were verified to remain enabled, Fermi 2 did not report this event within 8 hours of occurrence. However, this event was subsequently determined to meet the reporting criterion and is being reported pursuant to 10 CFR 50.72(b)(3)(v)(A).
"The licensee informed the NRC Resident Inspector."
The cause of the High Pressure Turbine Stop Valve cycling was due to a communication card failure that has since been corrected.
This event was determined to be reportable at 1200 EST on 02/24/16. See EN #51755 for a similar event that occurred on 01/06/16.
* * * UPDATE FROM JEFF GROFF TO STEVEN VITTO ON 03/02/2016 AT 1530 EST * * *
"Upon further review, it was determined that this event also meets the reporting criterion of 10CFR50.72(b)(3)(v)(D) for a condition that could have prevented the fulfillment of a safety function of structures or systems that are needed to mitigate the consequences of an accident.
"Although this event was determined to be reportable at 1200 EST on 02/24/16, it met the reporting requirement on the date of the event (02/21/2015).
"The licensee informed the NRC Resident Inspector."
Notified R3DO (Valos).