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Event Notification Report for June 19, 2025

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
06/18/2025 - 06/19/2025

EVENT NUMBERS
577725776957768
Power Reactor
Event Number: 57772
Facility: Byron
Region: 3     State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Dan Szutenbach
HQ OPS Officer: Karen Cotton
Notification Date: 06/20/2025
Notification Time: 17:21 [ET]
Event Date: 06/20/2025
Event Time: 13:53 [CDT]
Last Update Date: 06/20/2025
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Zurawski, Paul (R3DO)
FFD Group, (EMAIL)
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
2 N Y 100 Power Operation 100 Power Operation
Event Text
FAILED FITNESS FOR DUTY TEST

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

"At 1353 CDT on 6/20/2025, it was determined that a supervisor tested positive in accordance with the fitness-for-duty (FFD) testing program. The individual's authorization for site access has been terminated.

"The NRC Resident inspector has been notified."


Power Reactor
Event Number: 57769
Facility: Farley
Region: 2     State: AL
Unit: [2] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Blake Mitchell
HQ OPS Officer: Josue Ramirez
Notification Date: 06/19/2025
Notification Time: 23:56 [ET]
Event Date: 06/19/2025
Event Time: 20:27 [CDT]
Last Update Date: 06/20/2025
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
Person (Organization):
Blamey, Alan (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR TRIP AND AUTOMATIC ACTUATION OF AUXILIARY FEEDWATER SYSTEM

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

"On June 19, 2025, at 2027 CDT, with Unit 2 in mode 1 at 100 percent power, the reactor automatically tripped due to an `A' steam generator (SG) water level low signal. The low level in the SG was caused by a feedwater control system malfunction. All safety related systems responded normally post-trip. Operations responded and stabilized the plant.
"Decay heat is being removed by steam dumps to the main condenser. Farley Unit 1 is not affected.
"An automatic actuation of auxiliary feedwater system also occurred, which is an expected response from the reactor trip.
"Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the auxiliary feedwater system.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."


Non-Agreement State
Event Number: 57768
Rep Org: Ascent Consulting and Engineering
Licensee: Ascent Consulting and Engineering
Region: 1
City: Fairmont   State: WV
County:
License #: 47-35519-01
Agreement: N
Docket:
NRC Notified By: Andrew Kincell
HQ OPS Officer: Ernest West
Notification Date: 06/19/2025
Notification Time: 17:14 [ET]
Event Date: 06/19/2025
Event Time: 16:45 [EDT]
Last Update Date: 06/19/2025
Emergency Class: Non Emergency
10 CFR Section:
20.2201(a)(1)(ii) - Lost/Stolen LNM>10x
Person (Organization):
Warnek, Nicole (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
STOLEN MOISTURE DENSITY GAUGE

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

On 6/19/2025, at approximately 1645 EDT, a CPN International MC3 Elite moisture density gauge containing approximately 10 mCi of Cs-137 and 50 mCi of Am-241:Be was stolen from the back of a worker's truck while they were in a store. The moisture density gauge was in its case and the case was locked to the truck; both the case and gauge were missing when the worker discovered the gauge was stolen. The worker notified the police and licensee management of the stolen gauge.

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