Event Notification Report for September 14, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/13/2025 - 09/14/2025
Agreement State
Event Number: 57933
Rep Org: Florida Department of Health
Licensee: Troxler Corp
Region: 1
City: Jacksonville State: FL
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: Mark Seidensticker
HQ OPS Officer: Robert A. Thompson
Licensee: Troxler Corp
Region: 1
City: Jacksonville State: FL
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: Mark Seidensticker
HQ OPS Officer: Robert A. Thompson
Notification Date: 09/16/2025
Notification Time: 16:30 [ET]
Event Date: 09/15/2025
Event Time: 00:00 [EDT]
Last Update Date: 09/16/2025
Notification Time: 16:30 [ET]
Event Date: 09/15/2025
Event Time: 00:00 [EDT]
Last Update Date: 09/16/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Schussler, Jason (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Schussler, Jason (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - NON-LICENSEE IN POSSESSION OF LICENSED MATERIAL
The following is a summary of information provided by the Florida Department of Health (the Department) via phone and email:
On September 15, 2025, US Customs and Border Protection (CBP) identified a Troxler model 3430 moisture density gauge (S/N 20331, 8 mCi Cs-137, 40 mCi Am-241/Be) in a vehicle leaving the Port of Jacksonville. CBP held the vehicle and determined that the company, RQ Construction Co., was not licensed to possess a gauge with this level of radioactivity. CBP notified the Department of the incident and contacted Troxler and arranged for transport of the gauge to Troxler's facility in North Carolina. The Department has learned that the model 3430 gauge was sent for calibration and leak testing at Troxler by a Florida-licensed company in Tampa, FL.
The Department has learned that RQ Construction Co. recently purchased a Troxler 4950 soil density gauge. This model of gauge does not require a radioactive materials license for possession and use. Troxler is investigating how the model 3430 gauge was returned to an unlicensed company in Jacksonville, FL.
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following is a summary of information provided by the Florida Department of Health (the Department) via phone and email:
On September 15, 2025, US Customs and Border Protection (CBP) identified a Troxler model 3430 moisture density gauge (S/N 20331, 8 mCi Cs-137, 40 mCi Am-241/Be) in a vehicle leaving the Port of Jacksonville. CBP held the vehicle and determined that the company, RQ Construction Co., was not licensed to possess a gauge with this level of radioactivity. CBP notified the Department of the incident and contacted Troxler and arranged for transport of the gauge to Troxler's facility in North Carolina. The Department has learned that the model 3430 gauge was sent for calibration and leak testing at Troxler by a Florida-licensed company in Tampa, FL.
The Department has learned that RQ Construction Co. recently purchased a Troxler 4950 soil density gauge. This model of gauge does not require a radioactive materials license for possession and use. Troxler is investigating how the model 3430 gauge was returned to an unlicensed company in Jacksonville, FL.
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Power Reactor
Event Number: 57944
Facility: South Texas
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Marc Hill
HQ OPS Officer: Ernest West
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Marc Hill
HQ OPS Officer: Ernest West
Notification Date: 09/23/2025
Notification Time: 16:16 [ET]
Event Date: 09/15/2025
Event Time: 13:00 [CDT]
Last Update Date: 09/23/2025
Notification Time: 16:16 [ET]
Event Date: 09/15/2025
Event Time: 13:00 [CDT]
Last Update Date: 09/23/2025
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Drake, James (R4DO)
FFD Group, (EMAIL)
Drake, James (R4DO)
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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY EVENT
The following information was provided by the licensee via phone and email:
"At 1300 CDT on September 15, 2025, it was determined that a non-licensed supervisor had tested positive for a controlled substance, in violation of South Texas Project's fitness for duty policy. Prior to this, the individual's unescorted access had been administratively withdrawn pending retesting. This is reportable under 10 CFR 26.719 and is a late 24-hour notification.
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"At 1300 CDT on September 15, 2025, it was determined that a non-licensed supervisor had tested positive for a controlled substance, in violation of South Texas Project's fitness for duty policy. Prior to this, the individual's unescorted access had been administratively withdrawn pending retesting. This is reportable under 10 CFR 26.719 and is a late 24-hour notification.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 57929
Facility: Comanche Peak
Region: 4 State: TX
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Victor Alanis
HQ OPS Officer: Ernest West
Region: 4 State: TX
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Victor Alanis
HQ OPS Officer: Ernest West
Notification Date: 09/15/2025
Notification Time: 00:16 [ET]
Event Date: 09/14/2025
Event Time: 20:20 [CDT]
Last Update Date: 09/15/2025
Notification Time: 00:16 [ET]
Event Date: 09/14/2025
Event Time: 20:20 [CDT]
Last Update Date: 09/15/2025
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):
Agrawal, Ami (R4DO)
Agrawal, Ami (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP
The following information was provided by the licensee via phone and email:
"At 2020 CDT [on 9/14/2025], [Comanche Peak] Unit 2 reactor was manually tripped due to a malfunction of the electro-hydraulic control (EHC) system on the main turbine. All auxiliary feedwater pumps started due to steam generator `Lo-Lo' levels post trip. This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a reactor trip and 10 CFR 50.72(b)(3)(iv)(A) for an actuation of auxiliary feedwater. Unit 2 is being maintained in hot standby (mode 3) in accordance with integrated plant operating procedures. Decay heat is being rejected to the main condenser via the steam dump valves."
The NRC Resident Inspector was notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Unit 1 was not affected. The cause of the malfunction of EHC is unknown and under investigation. All rods fully inserted upon the reactor being tripped.
The following information was provided by the licensee via phone and email:
"At 2020 CDT [on 9/14/2025], [Comanche Peak] Unit 2 reactor was manually tripped due to a malfunction of the electro-hydraulic control (EHC) system on the main turbine. All auxiliary feedwater pumps started due to steam generator `Lo-Lo' levels post trip. This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a reactor trip and 10 CFR 50.72(b)(3)(iv)(A) for an actuation of auxiliary feedwater. Unit 2 is being maintained in hot standby (mode 3) in accordance with integrated plant operating procedures. Decay heat is being rejected to the main condenser via the steam dump valves."
The NRC Resident Inspector was notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Unit 1 was not affected. The cause of the malfunction of EHC is unknown and under investigation. All rods fully inserted upon the reactor being tripped.