Event Notification Report for November 20, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/19/2016 - 11/20/2016
Power Reactor
Event Number: 52381
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JOSH MCGUIRE
HQ OPS Officer: JEFF ROTTON
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JOSH MCGUIRE
HQ OPS Officer: JEFF ROTTON
Notification Date: 11/20/2016
Notification Time: 06:01 [ET]
Event Date: 11/20/2016
Event Time: 03:42 [EST]
Last Update Date: 11/20/2016
Notification Time: 06:01 [ET]
Event Date: 11/20/2016
Event Time: 03:42 [EST]
Last Update Date: 11/20/2016
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):
BRICE BICKETT (R1DO)
BRICE BICKETT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 90 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DURING MAIN TURBINE TESTING
"At 0342 EST, an automatic reactor scram was processed during turbine valve testing. All rods inserted into the core as expected and all systems functioned as expected during the scram.
"The event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical except when the actuation results from and is part of a preplanned sequence during testing or reactor operation."
The plant response to the reactor scram was uncomplicated. The main feedwater system is maintaining reactor water level and decay heat is being removed by the main turbine bypass valves to the main condenser. The unit is in a normal shutdown electrical lineup. No SRVs lifted during the scram. The licensee was testing the main turbine trip function just prior to the scram. The cause is under investigation.
The licensee notified the NRC Resident Inspector.
"At 0342 EST, an automatic reactor scram was processed during turbine valve testing. All rods inserted into the core as expected and all systems functioned as expected during the scram.
"The event is reportable within 4 hours per 10 CFR 50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical except when the actuation results from and is part of a preplanned sequence during testing or reactor operation."
The plant response to the reactor scram was uncomplicated. The main feedwater system is maintaining reactor water level and decay heat is being removed by the main turbine bypass valves to the main condenser. The unit is in a normal shutdown electrical lineup. No SRVs lifted during the scram. The licensee was testing the main turbine trip function just prior to the scram. The cause is under investigation.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 52382
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: ZACHARY DUNHAM
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: ZACHARY DUNHAM
HQ OPS Officer: DONALD NORWOOD
Notification Date: 11/20/2016
Notification Time: 18:53 [ET]
Event Date: 11/20/2016
Event Time: 14:02 [PST]
Last Update Date: 11/20/2016
Notification Time: 18:53 [ET]
Event Date: 11/20/2016
Event Time: 14:02 [PST]
Last Update Date: 11/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RAY AZUA (R4DO)
RAY AZUA (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 97 | Power Operation | 97 | Power Operation |
SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE LESS THAN TECHNICAL SPECIFICATION REQUIREMENT
"On November 20, 2016 at 1402 PST, Reactor Building Exhaust Air Fan 1B, REA-FN-1B, failed to start in manual which caused the Technical Specification (TS) for secondary containment pressure boundary to not be met. The duration of the time that the secondary containment TS was not met was approximately less than one minute. REA-FN-1B was being started in manual during a shift of Reactor Building Ventilation to support a post-maintenance support task on REA-FN-1B.
"Secondary containment differential pressure was restored within the TS requirement of greater than or equal to 0.25 inch of vacuum water gauge by restarting Reactor Building HVAC Train A.
"The cause of REA-FN-1B failing to start is currently under investigation.
"This condition is being reported under 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D) for an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material and accident mitigation.
"The licensee has notified the NRC Resident Inspector."
"On November 20, 2016 at 1402 PST, Reactor Building Exhaust Air Fan 1B, REA-FN-1B, failed to start in manual which caused the Technical Specification (TS) for secondary containment pressure boundary to not be met. The duration of the time that the secondary containment TS was not met was approximately less than one minute. REA-FN-1B was being started in manual during a shift of Reactor Building Ventilation to support a post-maintenance support task on REA-FN-1B.
"Secondary containment differential pressure was restored within the TS requirement of greater than or equal to 0.25 inch of vacuum water gauge by restarting Reactor Building HVAC Train A.
"The cause of REA-FN-1B failing to start is currently under investigation.
"This condition is being reported under 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D) for an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material and accident mitigation.
"The licensee has notified the NRC Resident Inspector."