Event Notification Report for March 26, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/25/2019 - 03/26/2019
Power Reactor
Event Number: 53959
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATTHEW SLOUKA
HQ OPS Officer: JEFFREY WHITED
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: MATTHEW SLOUKA
HQ OPS Officer: JEFFREY WHITED
Notification Date: 03/26/2019
Notification Time: 16:08 [ET]
Event Date: 03/26/2019
Event Time: 10:30 [CDT]
Last Update Date: 03/26/2019
Notification Time: 16:08 [ET]
Event Date: 03/26/2019
Event Time: 10:30 [CDT]
Last Update Date: 03/26/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
REPORT OF DEGRADED CONDITION DUE TO LEAKING VALVE
"On 3/26/2019 at 1030 CDT Engineering evaluation determined that Traversing lncore Probe (TIP) System test results related to Leak Rate Testing of 2-CKV-76-653, TIP Purge Header Check Valve, during the Unit 2 Refueling Outage resulted in a reportable condition. On 3/24/2019 at 1558 CDT, Leak Rate Testing identified a [local leak rate test] LLRT failure of 2-CKV-76-653. The gross leakage Leak Rate value exceeded the Technical Specification allowable value for Type C valves of less than 0.6 [allowable leakage] La.
"This constitutes an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(ii)(A) - Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The short-term corrective actions include repairing the valve such that it passes the test. The valve needs to be repaired before the unit can change modes.
"On 3/26/2019 at 1030 CDT Engineering evaluation determined that Traversing lncore Probe (TIP) System test results related to Leak Rate Testing of 2-CKV-76-653, TIP Purge Header Check Valve, during the Unit 2 Refueling Outage resulted in a reportable condition. On 3/24/2019 at 1558 CDT, Leak Rate Testing identified a [local leak rate test] LLRT failure of 2-CKV-76-653. The gross leakage Leak Rate value exceeded the Technical Specification allowable value for Type C valves of less than 0.6 [allowable leakage] La.
"This constitutes an 8-hour NRC notification in accordance with 10 CFR 50.72(b)(3)(ii)(A) - Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The short-term corrective actions include repairing the valve such that it passes the test. The valve needs to be repaired before the unit can change modes.
Agreement State
Event Number: 55535
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: Infiana USA, Inc.
Region: 1
City: Malvern State: PA
County:
License #: PA-G0087
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Thomas Herrity
Licensee: Infiana USA, Inc.
Region: 1
City: Malvern State: PA
County:
License #: PA-G0087
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Thomas Herrity
Notification Date: 10/21/2021
Notification Time: 11:04 [ET]
Event Date: 03/26/2019
Event Time: 00:00 [EDT]
Last Update Date: 10/21/2021
Notification Time: 11:04 [ET]
Event Date: 03/26/2019
Event Time: 00:00 [EDT]
Last Update Date: 10/21/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
BICKETT, BRICE (R1)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
BICKETT, BRICE (R1)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
EN Revision Imported Date: 11/19/2021
EN Revision Text: AGREEMENT STATE REPORT - STUCK SHUTTER
The following was received from Pennsylvania, Bureau of Radiation Protection (the Department) via email:
"On October 20, 2021, the licensee informed the Department of a failure of a shutter. It is reportable per 10 CFR 31.5(b)(5).
"On March 26, 2019, the licensee identified a defective linear actuator assembly on one of its Beta Control Mk 1.0 (serial number 559 / KP983) devices. The device contains 267 mCi (9.9 GBq) of Kr-85. The defect prevented the source from returning fully to its home shielded position. After initial discovery, a service provider manually moved the device to fully align with the shutter assembly. At a later date, it was discovered the unit had drifted out of alignment again. At this time a service provider installed a plate directly on the device effectively sealing the unit, regardless of alignment with shutter assembly. No exposures resulted from this event.
"The Department will perform a reactive inspection. A service provider has already corrected the problem."
Event Report ID No: PA210016
EN Revision Text: AGREEMENT STATE REPORT - STUCK SHUTTER
The following was received from Pennsylvania, Bureau of Radiation Protection (the Department) via email:
"On October 20, 2021, the licensee informed the Department of a failure of a shutter. It is reportable per 10 CFR 31.5(b)(5).
"On March 26, 2019, the licensee identified a defective linear actuator assembly on one of its Beta Control Mk 1.0 (serial number 559 / KP983) devices. The device contains 267 mCi (9.9 GBq) of Kr-85. The defect prevented the source from returning fully to its home shielded position. After initial discovery, a service provider manually moved the device to fully align with the shutter assembly. At a later date, it was discovered the unit had drifted out of alignment again. At this time a service provider installed a plate directly on the device effectively sealing the unit, regardless of alignment with shutter assembly. No exposures resulted from this event.
"The Department will perform a reactive inspection. A service provider has already corrected the problem."
Event Report ID No: PA210016