Event Notification Report for April 02, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/01/2016 - 04/02/2016
Power Reactor
Event Number: 51845
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JUSTIN REYNOLDS
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: JUSTIN REYNOLDS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/02/2016
Notification Time: 18:27 [ET]
Event Date: 04/02/2016
Event Time: 12:57 [CDT]
Last Update Date: 04/02/2016
Notification Time: 18:27 [ET]
Event Date: 04/02/2016
Event Time: 12:57 [CDT]
Last Update Date: 04/02/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
PATTY PELKE (R3DO)
PATTY PELKE (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 99 | Power Operation | 99 | Power Operation |
INSULATOR FAILURE ON RESERVE AUXILIARY TRANSFORMER
"At approximately 1257 [CDT] on 4/02/16, the Main Control Room received numerous annunciators that indicated a trip of the Reserve Auxiliary Transformer (RAT) Static VAR Compensator (SVC) that was caused by an insulator failure of the 'A' phase 345kV Circuit Switcher. As a result of the voltage transient, the Division 1 Fuel Building Ventilation (VF) system isolation dampers closed causing a trip of VF supply and exhaust fans. With no running VF fans, secondary containment differential pressure rose to slightly greater than 0 inches water gauge which exceeded the Technical Specification requirement of greater than 0.25 inches vacuum water gauge. The Control Room entered EOP-8, Secondary Containment Control. This event is being reported as a 'Condition that Could Have Prevented Fulfillment of a Safety Function' under 10CFR50.72(b)(3)(v)(C). Secondary Containment differential pressure was restored within Technical Specification requirements at 1300 [CDT] by starting the Standby Gas Treatment HVAC (VG) system.
"The NRC Resident Inspector has been notified."
"At approximately 1257 [CDT] on 4/02/16, the Main Control Room received numerous annunciators that indicated a trip of the Reserve Auxiliary Transformer (RAT) Static VAR Compensator (SVC) that was caused by an insulator failure of the 'A' phase 345kV Circuit Switcher. As a result of the voltage transient, the Division 1 Fuel Building Ventilation (VF) system isolation dampers closed causing a trip of VF supply and exhaust fans. With no running VF fans, secondary containment differential pressure rose to slightly greater than 0 inches water gauge which exceeded the Technical Specification requirement of greater than 0.25 inches vacuum water gauge. The Control Room entered EOP-8, Secondary Containment Control. This event is being reported as a 'Condition that Could Have Prevented Fulfillment of a Safety Function' under 10CFR50.72(b)(3)(v)(C). Secondary Containment differential pressure was restored within Technical Specification requirements at 1300 [CDT] by starting the Standby Gas Treatment HVAC (VG) system.
"The NRC Resident Inspector has been notified."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 51846
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVID HURT
HQ OPS Officer: RICHARD SMITH
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVID HURT
HQ OPS Officer: RICHARD SMITH
Notification Date: 04/03/2016
Notification Time: 07:13 [ET]
Event Date: 04/02/2016
Event Time: 23:02 [CDT]
Last Update Date: 04/04/2016
Notification Time: 07:13 [ET]
Event Date: 04/02/2016
Event Time: 23:02 [CDT]
Last Update Date: 04/04/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
VINCENT GADDY (R4DO)
VINCENT GADDY (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
REACTOR PROTECTION SYSTEM ACTUATION WHILE REACTOR SHUTDOWN
"At 2302 [CDT] on April 2, 2016, with the plant shutdown, [with] all control rods inserted in the reactor and while attempting to reset the reactor trip breakers to support outage activities (reset of the main turbine), the reactor trip breakers reopened. This was identified to be due to having both trains of Solid State Protection System (SSPS) out of service while in Mode 5. With both trains of SSPS out of service, a condition was met that would cause a reactor trip signal due to having a general warning condition on both trains. Per procedure, the control rods were incapable of withdrawal and fully inserted. Reactor Coolant System boron was 2280 ppm. There were no actuations as a result of the reactor trip breakers opening due to SSPS being removed from service."
The licensee will be notifying the NRC Resident Inspector.
* * * RETRACTION AT 1635 EDT ON 4/4/16 FROM TIM HOLLAND TO JEFF HERRERA * * *
"At 0713 EDT on April 3, 2016, EN #51846 provided notification of a Reactor Protection System actuation as revealed by the reactor trip breakers opening. Upon further investigation, it has been determined that the system actuated during maintenance activities due to a reactor trip signal caused by both trains of the Solid State Protection System (SSPS) being in test. This signal was not in response to actual plant conditions or parameters satisfying the requirements for initiation of the system and was therefore invalid. As such, the notification made by EN #51846 for a valid actuation of a specified system is hereby retracted.
"In addition, an editorial change to the first sentence of the original notification description is hereby made. The first sentence is revised to read as follows:
"At 2303 EDT on April 2, 2016, with the plant shut down and all control rods inserted into the reactor, while attempting to reset the reactor trip breakers to support outage activities (reset of the main turbine), the reactor trip breakers reopened."
The NRC Resident Inspector will be notified.
Notified the R4DO (Kellar).
"At 2302 [CDT] on April 2, 2016, with the plant shutdown, [with] all control rods inserted in the reactor and while attempting to reset the reactor trip breakers to support outage activities (reset of the main turbine), the reactor trip breakers reopened. This was identified to be due to having both trains of Solid State Protection System (SSPS) out of service while in Mode 5. With both trains of SSPS out of service, a condition was met that would cause a reactor trip signal due to having a general warning condition on both trains. Per procedure, the control rods were incapable of withdrawal and fully inserted. Reactor Coolant System boron was 2280 ppm. There were no actuations as a result of the reactor trip breakers opening due to SSPS being removed from service."
The licensee will be notifying the NRC Resident Inspector.
* * * RETRACTION AT 1635 EDT ON 4/4/16 FROM TIM HOLLAND TO JEFF HERRERA * * *
"At 0713 EDT on April 3, 2016, EN #51846 provided notification of a Reactor Protection System actuation as revealed by the reactor trip breakers opening. Upon further investigation, it has been determined that the system actuated during maintenance activities due to a reactor trip signal caused by both trains of the Solid State Protection System (SSPS) being in test. This signal was not in response to actual plant conditions or parameters satisfying the requirements for initiation of the system and was therefore invalid. As such, the notification made by EN #51846 for a valid actuation of a specified system is hereby retracted.
"In addition, an editorial change to the first sentence of the original notification description is hereby made. The first sentence is revised to read as follows:
"At 2303 EDT on April 2, 2016, with the plant shut down and all control rods inserted into the reactor, while attempting to reset the reactor trip breakers to support outage activities (reset of the main turbine), the reactor trip breakers reopened."
The NRC Resident Inspector will be notified.
Notified the R4DO (Kellar).