Event Notification Report for May 24, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/23/2019 - 05/24/2019
EVENT NUMBERS
54087540885408954085
Power Reactor
Event Number: 54087
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: CATY NOLAN
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEFF ISCH
HQ OPS Officer: CATY NOLAN
Notification Date: 05/24/2019
Notification Time: 17:12 [ET]
Event Date: 05/24/2019
Event Time: 13:10 [CDT]
Last Update Date: 05/24/2019
Notification Time: 17:12 [ET]
Event Date: 05/24/2019
Event Time: 13:10 [CDT]
Last Update Date: 05/24/2019
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):
HEATHER GEPFORD (R4DO)
HEATHER GEPFORD (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 97 | Power Operation |
LOSS OF OFFSITE POWER DUE TO FIRE ON STARTUP TRANSFORMER
"At 1310 CDT on 5/24/2019, Wolf Creek experienced a loss of offsite power to the safety-related NB02 bus, due to an external fire on a bushing on the startup transformer. The NB02 bus was reenergized when the 'B' Emergency Diesel Generator started and the output breaker automatically closed. The shutdown sequencer automatically started equipment as expected.
"Due to the undervoltage condition on the NB02 bus, an AFAS-T [Auxiliary Feedwater Actuation Signal] signal was generated which started the turbine driven auxiliary feedwater pump. Turbine load was reduced to maintain reactor power less than 100% in response to the start of turbine driven and 'B' motor driven auxiliary feedwater pumps.
"The fire was extinguished using a fire extinguisher at 1320 CDT.
"The unit is stable at 97% power."
The NB02 bus remains on the 'B' Emergency Diesel Generator (EDG). The other EDG is operable in standby.
The NRC Resident Inspector was notified.
"At 1310 CDT on 5/24/2019, Wolf Creek experienced a loss of offsite power to the safety-related NB02 bus, due to an external fire on a bushing on the startup transformer. The NB02 bus was reenergized when the 'B' Emergency Diesel Generator started and the output breaker automatically closed. The shutdown sequencer automatically started equipment as expected.
"Due to the undervoltage condition on the NB02 bus, an AFAS-T [Auxiliary Feedwater Actuation Signal] signal was generated which started the turbine driven auxiliary feedwater pump. Turbine load was reduced to maintain reactor power less than 100% in response to the start of turbine driven and 'B' motor driven auxiliary feedwater pumps.
"The fire was extinguished using a fire extinguisher at 1320 CDT.
"The unit is stable at 97% power."
The NB02 bus remains on the 'B' Emergency Diesel Generator (EDG). The other EDG is operable in standby.
The NRC Resident Inspector was notified.
Agreement State
Event Number: 54088
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: FROEHLING & ROBERTSON, INC.
Region: 1
City: CHESAPEAKE State: VA
County:
License #: 087-096-2
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: HOWIE CROUCH
Licensee: FROEHLING & ROBERTSON, INC.
Region: 1
City: CHESAPEAKE State: VA
County:
License #: 087-096-2
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/24/2019
Notification Time: 17:43 [ET]
Event Date: 05/24/2019
Event Time: 00:00 [EDT]
Last Update Date: 05/24/2019
Notification Time: 17:43 [ET]
Event Date: 05/24/2019
Event Time: 00:00 [EDT]
Last Update Date: 05/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
10 CFR Section:
AGREEMENT STATE
Person (Organization):
FRANK ARNER (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
FRANK ARNER (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - UNABLE TO RETRACT SOURCE ON MOISTURE DENSITY GAUGE
The following information was obtained from the Commonwealth of Virginia via email:
"On May 24, 2019, the Radiation Safety Office for the licensee made a preliminary report of an incident which occurred earlier on that day. The technician extended the source rod while using a portable moisture density gauge but was unable to retract it. The technician placed the gauge, with source rod extended, in the bed of his truck and drove back to his office, approximately 15 miles.
"When he arrived at his office, the other technicians were able to retract the source. A radiation survey confirmed the source was secured in its shield.
The Virginia Office of Radiological Health will perform a reactive inspection to investigate this incident. This notification will be updated with additional information determined during the inspection."
Virginia Event Report ID: VA 19-001
The following information was obtained from the Commonwealth of Virginia via email:
"On May 24, 2019, the Radiation Safety Office for the licensee made a preliminary report of an incident which occurred earlier on that day. The technician extended the source rod while using a portable moisture density gauge but was unable to retract it. The technician placed the gauge, with source rod extended, in the bed of his truck and drove back to his office, approximately 15 miles.
"When he arrived at his office, the other technicians were able to retract the source. A radiation survey confirmed the source was secured in its shield.
The Virginia Office of Radiological Health will perform a reactive inspection to investigate this incident. This notification will be updated with additional information determined during the inspection."
Virginia Event Report ID: VA 19-001
Power Reactor
Event Number: 54089
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: KENNETH NOEL
HQ OPS Officer: DAN LIVERMORE
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: KENNETH NOEL
HQ OPS Officer: DAN LIVERMORE
Notification Date: 05/25/2019
Notification Time: 00:30 [ET]
Event Date: 05/24/2019
Event Time: 20:19 [EDT]
Last Update Date: 05/25/2019
Notification Time: 00:30 [ET]
Event Date: 05/24/2019
Event Time: 20:19 [EDT]
Last Update Date: 05/25/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
FRANK ARNER (R1DO)
FFD GROUP (EMAIL)
FRANK ARNER (R1DO)
FFD GROUP (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
LICENSED EMPLOYEE FAILED A RANDOM FITNESS -FOR-DUTY TEST
"A licensed employee was determined to be under the influence of alcohol during a random [fitness-for-duty] test. The employee's access to the plant has been canceled."
The licensee notified the NRC Resident Inspector.
"A licensed employee was determined to be under the influence of alcohol during a random [fitness-for-duty] test. The employee's access to the plant has been canceled."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 54085
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID DUESING
HQ OPS Officer: CATY NOLAN
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID DUESING
HQ OPS Officer: CATY NOLAN
Notification Date: 05/24/2019
Notification Time: 13:09 [ET]
Event Date: 05/24/2019
Event Time: 07:30 [EDT]
Last Update Date: 05/24/2019
Notification Time: 13:09 [ET]
Event Date: 05/24/2019
Event Time: 07:30 [EDT]
Last Update Date: 05/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JAMNES CAMERON (R3DO)
JAMNES CAMERON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOW PRESSURE CORE SPRAY INOPERABLE
"At 0730 [EDT] on May 24, 2019, it was discovered that the Low-Pressure Core Spray System was inoperable. At Perry, the Low-Pressure Core Spray system is considered a single train system in Modes 1, 2, and 3; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). Inoperability of the Low-Pressure Core Spray system was caused by Emergency Service Water Pump A inoperability.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
"At 0730 [EDT] on May 24, 2019, it was discovered that the Low-Pressure Core Spray System was inoperable. At Perry, the Low-Pressure Core Spray system is considered a single train system in Modes 1, 2, and 3; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). Inoperability of the Low-Pressure Core Spray system was caused by Emergency Service Water Pump A inoperability.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."