Skip to main content

Event Notification Report for February 13, 2026

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/12/2026 - 02/13/2026

Power Reactor
Event Number: 58148
Facility: River Bend
Region: 4     State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Terry Blanchard
HQ OPS Officer: Josue Ramirez
Notification Date: 02/04/2026
Notification Time: 07:09 [ET]
Event Date: 02/03/2026
Event Time: 23:38 [CST]
Last Update Date: 02/12/2026
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation 50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
O'Keefe, Neil (R4DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
EN Revision Imported Date: 2/13/2026

EN Revision Text: EDG ACTUATION AND HPCS SYSTEM INOPERABLE

The following information was provided by the licensee via phone and email:

"On February 3, 2026, at 2338 CST, River Bend Station (RBS) was operating at 100 percent reactor power when the standby service water pump `C' (SWP-P2C) faulted, tripped, and locked out during the performance of a routine surveillance. The pump fault caused E22-ACB04, the normal division III 4.16 KV bus supply breaker, to trip and lock out. The division Ill emergency diesel generator (EDG) started as designed and powered the division III 4.16 KV bus. There are no signs of fire. The cause of the SWP-P2C fault is still under investigation.

"The trip of E22-ACB04 resulted in the inability to meet [surveillance requirement] SR 3.8.9.1 forcing entry into [limiting condition for operation] LCO 3.8.9 required action 'E.1' and declaring the [high pressure core spray] HPCS system inoperable.

"This event is being reported under 10 CFR 50.72(b)(3)(iv)(A) as an event or condition that results in valid actuation of emergency AC electrical power systems and 10 CFR 50.72(b)(3)(v)(D) as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function.

"The NRC Resident Inspector has been notified."

* * * PARTIAL RETRACTION ON 02/12/2026 AT 1946 EST FROM TERRY BLANCHARD TO ADAM KOZIOL * * *

"This event was initially reported under 10 CFR 50.72(b)(3)(iv)(A) as an event or condition that results in a valid actuation of emergency AC electrical power systems and 10 CFR 50.72(b)(3)(v) as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function. During subsequent investigation, it was determined that the trip of E22-ACB04 did not result in the inability to meet SR 3.8.9.1 which forced entry into LCO 3.8.9 required action 'E.1'. As a result, it has been determined that the HPCS system remained operable.

"Therefore, this condition is not reportable as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function. However, this event remains reportable as an event or condition that results in a valid actuation of emergency AC electrical power systems.

"The NRC Resident Inspector has been notified."

Notified R4DO (Dodson)


Agreement State
Event Number: 58153
Rep Org: Florida Bureau of Radiation Control
Licensee: All State Engineering & Testing Consultants, INC
Region: 1
City: Miami   State: FL
County:
License #: 1113-1
Agreement: Y
Docket:
NRC Notified By: John Williamson
HQ OPS Officer: Ernest West
Notification Date: 02/05/2026
Notification Time: 14:13 [ET]
Event Date: 02/04/2026
Event Time: 00:00 [EST]
Last Update Date: 02/06/2026
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Bickett, Brice (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - SURRENDER OF UNLICENSED DEVICE

The following information was provided by the Florida Bureau of Radiation Control (BRC) via email:

"Seizure/surrender of an unlicensed device [occurred] at the Port of Miami on 2/4/2026. The original FL license 1113-1 expired exactly 12 years ago. [The Florida] BRC Materials Administrator received a call [on 2/4/2026] that Customs and Border Protection (CBP) stopped an individual with an unlicensed soil moisture density device leaving the Port of Miami. CBP Officer [REDACTED] knew that they provided testing at a private business in the Port of Miami and currently has the person detained. The gauge was not in a case, which was another violation."

The gauge was picked up by BRC personnel on 2/4/2026 and is to be transported to a facility for safe storage.

Incident number: FL26-010

* * * UPDATE ON 02/06/2026 AT 1029 FROM JOHN WILLIAMSON TO KAREN COTTON * * *

The following is a summary of information provided by the Florida Bureau of Radiation Control (BRC) via email:

On 02/05/26 at 1700 EST, the gauge was retrieved and transported to the Orlando facility for safe storage.
Cs-137 presence and neutron counts were confirmed. Wipe tests did not detect any contamination.
Troxler last performed calibration and wipe tests in November of 2021.

Device: Soil Moisture Density
Manufacturer: Troxler
Model Number: 3411B
Serial Number: 7833

Source information:
Cs-137, Model number: 102112, Serial number: 40-5060
Am-241:Be, Model number: A-102451, 47-4153

Notified R1OD (Bickett) and NMSS Events Notifications (Email).


Agreement State
Event Number: 58154
Rep Org: Arizona Dept of Health Services
Licensee: Epsilon Engineering & Material, LLC
Region: 4
City: Goodyear   State: AZ
County:
License #: 07-534
Agreement: Y
Docket:
NRC Notified By: Brian D. Goretzki
HQ OPS Officer: Ernest West
Notification Date: 02/05/2026
Notification Time: 17:15 [ET]
Event Date: 02/05/2026
Event Time: 00:00 [MST]
Last Update Date: 02/05/2026
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - STUCK SHUTTER

The following information was provided by the Arizona Department of Health Services (the Department) via email:

"During a routine inspection [on 2/5/2026], the Department identified a shutter on a portable gauge that was stuck open and could not be retracted. The gauge was a Troxler model 3430, serial number 36475, containing 8 millicuries of cesium-137 and 40 millicuries of americium-241/beryllium. The gauge was taken out of service, and a service provider was scheduled to come onsite to troubleshoot the issue.

"The Department has requested additional information and continues to investigate the event."

Arizona Incident Number: 26-005


Non-Power Reactor
Event Number: 58155
Rep Org: Penn State University (PENN)
Licensee: Penn State University
Region: 0
City: University Park   State: PA
County: Centre
License #: R-2
Agreement: N
Docket: 05000005
NRC Notified By: Aaron Wilmot
HQ OPS Officer: Ernest West
Notification Date: 02/05/2026
Notification Time: 21:15 [ET]
Event Date: 02/05/2026
Event Time: 00:00 [EST]
Last Update Date: 02/05/2026
Emergency Class: Non Emergency
10 CFR Section:
20.1906(d)(1) - Surface Contam Levels > Limits
Person (Organization):
NMSS_EVENTS_NOTIFICATION (EMAIL)
Bickett, Brice (R1DO)
Torres, Paulette (NPR - PM)
Balazik, Michael (NPR - PM)
Waugh, Andrew (NPR )
Event Text
SHIPMENT EXCEEDS SURFACE CONTAMINATION LIMITS

The following is a summary of information provided by the licensee via phone:

The radiation safety officer reported that a package was received with removable gamma and beta contamination that measured at the limit of 240 disintegrations per minute per centimeter squared.

The package was a container that was being shipped back to Penn State University. The container originally contained Na-24 and was sent to a facility for disposal. The facility that returned the container has been notified and it is currently under investigation regarding how the container was returned with contamination. The container is locked in a secure facility.

Penn State personnel conducted surveys and verified no spread of contamination at the facility. The carrier was contacted and no contamination was found in the delivery vehicle. Wider contamination surveys are planned as well. No personnel were contaminated.


Agreement State
Event Number: 58156
Rep Org: Texas Dept of State Health Services
Licensee: Acuren Inspection Inc
Region: 4
City: Tarzan   State: TX
County:
License #: 01774
Agreement: Y
Docket:
NRC Notified By: Bruce Hammond
HQ OPS Officer: Ian Howard
Notification Date: 02/06/2026
Notification Time: 16:21 [ET]
Event Date: 02/05/2026
Event Time: 00:00 [CST]
Last Update Date: 02/06/2026
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED RADIOGRAPHY CAMERA

The following information was provided by the Texas Department of State Health Services (the Department) via phone and email:

"On February 5, 2026, the Department was notified by the licensee that a guide tube was crimped after being impacted by a falling object. The QSA Delta 880 camera was loaded with a QSA model 424-9 iridium source of 23 curies. The radiation safety officer (RSO) went to the scene and uncrimped the tube enough to retract the source. The camera was put back into use with a new guide tube. No overexposures were reported to the operators or the RSO. The radiographer's exposure was less than 20 mrem and the RSO's exposure was 90 mrem.

"Additional information will be provided in accordance with SA300 requirements."

Texas NMED: 260002


Power Reactor
Event Number: 58163
Facility: Columbia Generating Station
Region: 4     State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: Zachary Dunham
HQ OPS Officer: Jon Lilliendahl
Notification Date: 02/12/2026
Notification Time: 09:25 [ET]
Event Date: 02/12/2026
Event Time: 02:49 [PST]
Last Update Date: 02/12/2026
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By TS 50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Dodson, Doug (R4DO)
Grant, Jeffery (IR MOC)
Feliz-Adorno, Nestor (NRR EO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 100 Power Operation 0 Hot Shutdown
Event Text
MANUAL REACTOR TRIP DUE TO A LOSS OF BOTH REACTOR RECIRCULATION PUMPS

The following information was provided by the licensee via phone and email:

"At 0249 PST, on February 12, 2026, with the unit in Mode 1 at 100 percent power, the reactor was manually tripped due to a loss of both reactor recirculation pumps because of abnormal pump drive parameters. Following reset of the reactor trip signal, operators observed erratic automatic operation of the reactor feed pumps with an associated reactor water level transient to less than plus 13 inches resulting in an additional reactor trip signal. Operators took manual control of the reactor feed pumps and recovered reactor water level, stabilizing water level at above plus 13 inches. The reactor trip signal was reset, and reactor water level was raised to support natural circulation flow of the reactor.

"Decay heat is being removed via natural circulation in the reactor with steam to the main condenser.

"Due to the valid reactor protection system actuations, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i), four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B), and eight-hour, non-emergency notification, per 10 CFR 50.72(b)(3)(iv)(A).

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."