Event Notification Report for November 02, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/01/2025 - 11/02/2025
Agreement State
Event Number: 58022
Rep Org: Colorado Dept of Health
Licensee: Estes Park School District R-3
Region: 4
City: Estes Park State: CO
County:
License #: GL002169
Agreement: Y
Docket:
NRC Notified By: Kathryn Kirk
HQ OPS Officer: Ernest West
Licensee: Estes Park School District R-3
Region: 4
City: Estes Park State: CO
County:
License #: GL002169
Agreement: Y
Docket:
NRC Notified By: Kathryn Kirk
HQ OPS Officer: Ernest West
Notification Date: 11/04/2025
Notification Time: 16:19 [ET]
Event Date: 11/03/2025
Event Time: 00:00 [MST]
Last Update Date: 11/04/2025
Notification Time: 16:19 [ET]
Event Date: 11/03/2025
Event Time: 00:00 [MST]
Last Update Date: 11/04/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Vossmar, Patricia (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Vossmar, Patricia (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - LOST EXIT SIGNS
The following is a summary of information provided by the Colorado Department of Public Health and Environment via email:
The licensee reported that two exit signs, containing a total of 12.4 Ci of tritium, were lost in Estes Park, Colorado.
Manufacturer: Isolite Corporation
Model number: 2000
Event report ID number: CO250038
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 Colorado Department of Public Health and Environment via email:
The licensee reported that two exit signs, containing a total of 12.4 Ci of tritium, were lost in Estes Park, Colorado.
Manufacturer: Isolite Corporation
Model number: 2000
Event report ID number: CO250038
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: 58020
Facility: Surry
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Scott Satterfield
HQ OPS Officer: Adam Koziol
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: Scott Satterfield
HQ OPS Officer: Adam Koziol
Notification Date: 11/03/2025
Notification Time: 17:07 [ET]
Event Date: 11/03/2025
Event Time: 12:15 [EST]
Last Update Date: 11/03/2025
Notification Time: 17:07 [ET]
Event Date: 11/03/2025
Event Time: 12:15 [EST]
Last Update Date: 11/03/2025
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):
Mckown, Louis J (R2DO)
Mckown, Louis J (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EMERGENCY DIESEL GENERATOR (EDG) ACTUATION
The following information was provided by the licensee via phone and email:
"On November 3, 2025, at 1215 EST, the 'A' reserve station service transformer (RSST) pilot wire lockout actuated while restoring the 'A' RSST to service. This resulted in the electrical isolation of the 'A' RSST and the Unit 1 'J' emergency bus. The #3 EDG automatically started and loaded onto the Unit 1 'J' emergency bus, as designed. Operations entered the appropriate abnormal procedures and ensured stable conditions. All safety systems functioned as designed and all electrical parameters remained stable.
"No radiological consequences resulted from this event. This event is being reported pursuant to 10CFR50.72(b)(3)(iv)(A) due to actuation of the #3 EDG.
"The NRC Resident Inspector was notified."
The following information was provided by the licensee via phone and email:
"On November 3, 2025, at 1215 EST, the 'A' reserve station service transformer (RSST) pilot wire lockout actuated while restoring the 'A' RSST to service. This resulted in the electrical isolation of the 'A' RSST and the Unit 1 'J' emergency bus. The #3 EDG automatically started and loaded onto the Unit 1 'J' emergency bus, as designed. Operations entered the appropriate abnormal procedures and ensured stable conditions. All safety systems functioned as designed and all electrical parameters remained stable.
"No radiological consequences resulted from this event. This event is being reported pursuant to 10CFR50.72(b)(3)(iv)(A) due to actuation of the #3 EDG.
"The NRC Resident Inspector was notified."
Power Reactor
Event Number: 58018
Facility: LaSalle
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: Eric Pratt
HQ OPS Officer: Robert A. Thompson
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: Eric Pratt
HQ OPS Officer: Robert A. Thompson
Notification Date: 11/02/2025
Notification Time: 18:37 [ET]
Event Date: 11/02/2025
Event Time: 13:46 [CST]
Last Update Date: 11/02/2025
Notification Time: 18:37 [ET]
Event Date: 11/02/2025
Event Time: 13:46 [CST]
Last Update Date: 11/02/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Ziolkowski, Michael (R3DO)
Ziolkowski, Michael (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM
The following information was provided by the licensee via phone and email:
"At 1346 CST with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped on turbine control valve fast closure due to a generator lockout. The trip was not complex with all systems responding normally post-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).
"Operations responded using emergency operating procedures and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 2 is not affected.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"At 1346 CST with Unit 1 in mode 1 at 100 percent power, the reactor automatically tripped on turbine control valve fast closure due to a generator lockout. The trip was not complex with all systems responding normally post-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).
"Operations responded using emergency operating procedures and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 2 is not affected.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."