Event Notification Report for March 03, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/02/2025 - 03/03/2025
Agreement State
Event Number: 57585
Rep Org: Florida Bureau of Radiation Control
Licensee: Central Florida Testing Laboratories
Region: 1
City: Clearwater State: FL
County:
License #: 1062-1
Agreement: Y
Docket:
NRC Notified By: Monroe A. Cooper
HQ OPS Officer: Robert A. Thompson
Licensee: Central Florida Testing Laboratories
Region: 1
City: Clearwater State: FL
County:
License #: 1062-1
Agreement: Y
Docket:
NRC Notified By: Monroe A. Cooper
HQ OPS Officer: Robert A. Thompson
Notification Date: 03/04/2025
Notification Time: 16:00 [ET]
Event Date: 03/04/2025
Event Time: 10:30 [EST]
Last Update Date: 03/04/2025
Notification Time: 16:00 [ET]
Event Date: 03/04/2025
Event Time: 10:30 [EST]
Last Update Date: 03/04/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Ford, Monica (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Ford, Monica (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
EN Revision Imported Date: 3/12/2025
EN Revision Text: AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE
The following information was provided by the Florida Bureau of Radiation Control (BRC) via email:
"The BRC received notification from Central Florida Testing Laboratories at 1500 EST 03/04/2025 of a missing Troxler soil moisture density gauge (8 mCi Cs-137, 40 mCi Am-241/Be). The transporter was returning to the storage location from a worksite when they were notified by another driver at a stoplight that something fell out of the vehicle. When [the transporter] turned around to see what had fallen, they noticed the gauge was no longer in the back of the vehicle. [The transporter] retraced their steps, returning to the worksite, and could not locate the gauge. The last confirmed possession of the gauge was at approximately 1030 EST on 03/04/2025."
Florida incident number: FL25-021
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
EN Revision Text: AGREEMENT STATE REPORT - LOST MOISTURE DENSITY GAUGE
The following information was provided by the Florida Bureau of Radiation Control (BRC) via email:
"The BRC received notification from Central Florida Testing Laboratories at 1500 EST 03/04/2025 of a missing Troxler soil moisture density gauge (8 mCi Cs-137, 40 mCi Am-241/Be). The transporter was returning to the storage location from a worksite when they were notified by another driver at a stoplight that something fell out of the vehicle. When [the transporter] turned around to see what had fallen, they noticed the gauge was no longer in the back of the vehicle. [The transporter] retraced their steps, returning to the worksite, and could not locate the gauge. The last confirmed possession of the gauge was at approximately 1030 EST on 03/04/2025."
Florida incident number: FL25-021
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: 57586
Facility: Monticello
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: Aaron Mann
HQ OPS Officer: Robert A. Thompson
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: Aaron Mann
HQ OPS Officer: Robert A. Thompson
Notification Date: 03/04/2025
Notification Time: 21:46 [ET]
Event Date: 03/04/2025
Event Time: 10:30 [CST]
Last Update Date: 03/04/2025
Notification Time: 21:46 [ET]
Event Date: 03/04/2025
Event Time: 10:30 [CST]
Last Update Date: 03/04/2025
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Edwards, Rhex (R3DO)
FFD Group, (EMAIL)
Edwards, Rhex (R3DO)
FFD Group, (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 97 | Power Operation | 97 | Power Operation |
FITNESS FOR DUTY - PROGRAMMATIC FAILURE
The following information was provided by the licensee via phone and email:
"On March 4, 2025, fitness-for-duty (FFD) program administrators identified a site employee who was required to be part of the FFD program random testing pool, had been inadvertently removed from it on August 5, 2024. The employee's protected area access has been placed on hold in accordance with the station process. The issue has been placed into the site corrective action program for further review and evaluation to determine the cause. This event notification is being made in accordance with 10 CFR 26.719(b)(4)."
The NRC resident inspector has been notified.
The following information was provided by the licensee via phone and email:
"On March 4, 2025, fitness-for-duty (FFD) program administrators identified a site employee who was required to be part of the FFD program random testing pool, had been inadvertently removed from it on August 5, 2024. The employee's protected area access has been placed on hold in accordance with the station process. The issue has been placed into the site corrective action program for further review and evaluation to determine the cause. This event notification is being made in accordance with 10 CFR 26.719(b)(4)."
The NRC resident inspector has been notified.
Power Reactor
Event Number: 57582
Facility: Limerick
Region: 1 State: PA
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: David Holcomb
HQ OPS Officer: Ernest West
Region: 1 State: PA
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: David Holcomb
HQ OPS Officer: Ernest West
Notification Date: 03/03/2025
Notification Time: 18:09 [ET]
Event Date: 03/03/2025
Event Time: 10:44 [EST]
Last Update Date: 03/03/2025
Notification Time: 18:09 [ET]
Event Date: 03/03/2025
Event Time: 10:44 [EST]
Last Update Date: 03/03/2025
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Ford, Monica (R1DO)
Ford, Monica (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
HPCI DECLARED INOPERABLE
The following information was provided by the licensee via phone and email:
"At 1044 EST, Unit 2 high pressure coolant injection (HPCI) system was declared inoperable per technical specification 3.5.1.C.1 during planned surveillance testing due to test equipment failure and subsequent inadvertent isolation of the outboard HPCI turbine exhaust line vacuum breaker primary containment isolation valve. The test equipment was removed, and the vacuum breaker isolation valve was re-opened. HPCI was restored to operable status at 1351.
"Due to inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72.(b)(3)(v)(D).
"There was no impact to 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 1044 EST, Unit 2 high pressure coolant injection (HPCI) system was declared inoperable per technical specification 3.5.1.C.1 during planned surveillance testing due to test equipment failure and subsequent inadvertent isolation of the outboard HPCI turbine exhaust line vacuum breaker primary containment isolation valve. The test equipment was removed, and the vacuum breaker isolation valve was re-opened. HPCI was restored to operable status at 1351.
"Due to inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72.(b)(3)(v)(D).
"There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 57583
Facility: Turkey Point
Region: 2 State: FL
Unit: [4] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Arturo Alvarez
HQ OPS Officer: Ernest West
Region: 2 State: FL
Unit: [4] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Arturo Alvarez
HQ OPS Officer: Ernest West
Notification Date: 03/03/2025
Notification Time: 22:32 [ET]
Event Date: 03/03/2025
Event Time: 18:03 [EST]
Last Update Date: 03/03/2025
Notification Time: 22:32 [ET]
Event Date: 03/03/2025
Event Time: 18:03 [EST]
Last Update Date: 03/03/2025
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):
Penmetsa, Ravi (R2DO)
Penmetsa, Ravi (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | N | N | 0 | Cold Shutdown | 0 | Refueling |
DEGRADED CONDITION
The following information was provided by the licensee via phone and email:
"At 1803 EST on 03/03/25, it was determined that the reactor coolant system pressure boundary does not meet American Society of Mechanical Engineers (ASME) section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak where the thimble tube connects to penetration number 6. The cause of this event is currently being investigated. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"At 1803 EST on 03/03/25, it was determined that the reactor coolant system pressure boundary does not meet American Society of Mechanical Engineers (ASME) section XI, Table IWB-341 0-1, 'Acceptable Standards' due to a through wall leak where the thimble tube connects to penetration number 6. The cause of this event is currently being investigated. This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been notified."