Event Notification Report for February 10, 2025
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/09/2025 - 02/10/2025
Agreement State
Event Number: 57523
Rep Org: New Mexico Rad Control Program
Licensee: Evolution Well Services
Region: 4
City: San Antonio State: TX
County:
License #: TX L06748
Agreement: Y
Docket:
NRC Notified By: Robert Bicknell
HQ OPS Officer: Karen Cotton-Gross
Licensee: Evolution Well Services
Region: 4
City: San Antonio State: TX
County:
License #: TX L06748
Agreement: Y
Docket:
NRC Notified By: Robert Bicknell
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 01/31/2025
Notification Time: 13:47 [ET]
Event Date: 01/31/2025
Event Time: 00:00 [CST]
Last Update Date: 01/31/2025
Notification Time: 13:47 [ET]
Event Date: 01/31/2025
Event Time: 00:00 [CST]
Last Update Date: 01/31/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Allen, Logan (NMSS)
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Allen, Logan (NMSS)
AGREEMENT STATE REPORT - OCCUPATIONAL EXPOSURE
The following is a summary of information provided by the New Mexico Rad Control Program via phone and email:
On January 31, 2025, at 0955 MST, RAP (Radiological Assistance Program) Team 4 of the Department of Energy reported that an individual from Evolution Well Services went to Baptist Hospital in San Antonio, TX stating radiation poisoning from transporting radioactive material (fracking density gauge; 20 mCi of cesium) from Texas to Jal, New Mexico. The RAP Team 4 was asked by New Mexico to investigate and are in route to survey the vehicle carrying the gauge. The RAP Team 4 will report back to New Mexico with their findings. Developments will be updated as new information is received.
The following is a summary of information provided by the New Mexico Rad Control Program via phone and email:
On January 31, 2025, at 0955 MST, RAP (Radiological Assistance Program) Team 4 of the Department of Energy reported that an individual from Evolution Well Services went to Baptist Hospital in San Antonio, TX stating radiation poisoning from transporting radioactive material (fracking density gauge; 20 mCi of cesium) from Texas to Jal, New Mexico. The RAP Team 4 was asked by New Mexico to investigate and are in route to survey the vehicle carrying the gauge. The RAP Team 4 will report back to New Mexico with their findings. Developments will be updated as new information is received.
Agreement State
Event Number: 57524
Rep Org: MA Radiation Control Program
Licensee: Republic Services
Region: 1
City: Devens State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Bob Locke
HQ OPS Officer: Karen Cotton-Gross
Licensee: Republic Services
Region: 1
City: Devens State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Bob Locke
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 01/31/2025
Notification Time: 15:19 [ET]
Event Date: 01/09/2025
Event Time: 00:00 [EST]
Last Update Date: 01/31/2025
Notification Time: 15:19 [ET]
Event Date: 01/09/2025
Event Time: 00:00 [EST]
Last Update Date: 01/31/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Warnek, Nicole (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Warnek, Nicole (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - ABANDONED SOURCES
The following information was provided by the Massachusetts Radiation Control Program via email:
"On 1/8/2024, area portal monitors at a dump site (Republic Services) alarmed. On 1/9/2025, a consultant was called and arrived at the scene. The consultant discovered an empty vial giving a dose rate of 4.1 mR/hr on contact. The vial had a marking which looked to have been removed before it was disposed.
"On 1/30/2025, three more vials were discovered in the same trash load. The vials were full of thin solid rods and maxed out the meter available at the dump site. The consultant was called back to the site and arrived on 1/31/2025. The consultant measured 40-50 mR/hr on contact for two of the vials, and 100 mR/hr on contact for the third vial. The dose rate with all of the vials in one bag measured 1.5 mR/hr at two feet from the bag. The consultant noted that the markings were removed from these vials, but a label reading 'radium' was still visible. The vials were placed in a secure location at the facility. A member of Massachusetts Division of Radiation Control staff was on-site on 1/31/2025, to ensure all material was handled appropriately.
"Assuming all of the vials contain radium-226, with a dose rate of 1.5 mR/hr at 2 feet, a rough calculation estimates approximately 0.7 mCi of radium-226 exists in the vials.
"This quantity of found material is immediately reportable to NRC pursuant to 105 CMR 120.281."
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 information was provided by the Massachusetts Radiation Control Program via email:
"On 1/8/2024, area portal monitors at a dump site (Republic Services) alarmed. On 1/9/2025, a consultant was called and arrived at the scene. The consultant discovered an empty vial giving a dose rate of 4.1 mR/hr on contact. The vial had a marking which looked to have been removed before it was disposed.
"On 1/30/2025, three more vials were discovered in the same trash load. The vials were full of thin solid rods and maxed out the meter available at the dump site. The consultant was called back to the site and arrived on 1/31/2025. The consultant measured 40-50 mR/hr on contact for two of the vials, and 100 mR/hr on contact for the third vial. The dose rate with all of the vials in one bag measured 1.5 mR/hr at two feet from the bag. The consultant noted that the markings were removed from these vials, but a label reading 'radium' was still visible. The vials were placed in a secure location at the facility. A member of Massachusetts Division of Radiation Control staff was on-site on 1/31/2025, to ensure all material was handled appropriately.
"Assuming all of the vials contain radium-226, with a dose rate of 1.5 mR/hr at 2 feet, a rough calculation estimates approximately 0.7 mCi of radium-226 exists in the vials.
"This quantity of found material is immediately reportable to NRC pursuant to 105 CMR 120.281."
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
Agreement State
Event Number: 57529
Rep Org: Texas Dept of State Health Services
Licensee: Baylor Scott and White Health
Region: 4
City: College Station State: TX
County:
License #: L06557
Agreement: Y
Docket:
NRC Notified By: Bruce Hammond
HQ OPS Officer: Karen Cotton-Gross
Licensee: Baylor Scott and White Health
Region: 4
City: College Station State: TX
County:
License #: L06557
Agreement: Y
Docket:
NRC Notified By: Bruce Hammond
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 01/31/2025
Notification Time: 16:36 [ET]
Event Date: 01/31/2025
Event Time: 14:20 [CST]
Last Update Date: 01/31/2025
Notification Time: 16:36 [ET]
Event Date: 01/31/2025
Event Time: 14:20 [CST]
Last Update Date: 01/31/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - PACKAGE CONTAMINATION LIMITS EXCEEDED
The following information was provided by the Texas Department of State Health Services (the Agency) via email:
"On 1/31/2025, at approximately 1420 CST, the Agency was notified of a package received that exceeded limits from the radiation safety officer (RSO) at Baylor Scott and White Medical Center in College Station, Texas. The report was two cases from RLS Pharmacy in Temple were contaminated with Tc-99m. The initial results from wipe tests performed by the nuclear medicine technologist were 22.1k and 87.7k disintegrations per minute (dpm), respectively. No other contamination was present.
"There was no contamination found anywhere in the hospital or the courier vehicle. The courier vehicle and the courier were surveyed after returning to the pharmacy. Packages were surveyed prior to leaving the pharmacy and no contamination was present.
"Further Information will be provided in accordance with SA-300."
Texas Incident Number: 10164
Texas NMED Number: TX250008
The following information was provided by the Texas Department of State Health Services (the Agency) via email:
"On 1/31/2025, at approximately 1420 CST, the Agency was notified of a package received that exceeded limits from the radiation safety officer (RSO) at Baylor Scott and White Medical Center in College Station, Texas. The report was two cases from RLS Pharmacy in Temple were contaminated with Tc-99m. The initial results from wipe tests performed by the nuclear medicine technologist were 22.1k and 87.7k disintegrations per minute (dpm), respectively. No other contamination was present.
"There was no contamination found anywhere in the hospital or the courier vehicle. The courier vehicle and the courier were surveyed after returning to the pharmacy. Packages were surveyed prior to leaving the pharmacy and no contamination was present.
"Further Information will be provided in accordance with SA-300."
Texas Incident Number: 10164
Texas NMED Number: TX250008
Agreement State
Event Number: 57531
Rep Org: NJ Rad Prot And Rel Prevention Pgm
Licensee: Nuclear Diagnostic Products
Region: 1
City: Rockway State: NJ
County:
License #: 457796
Agreement: Y
Docket:
NRC Notified By: Joe Power
HQ OPS Officer: Karen Cotton-Gross
Licensee: Nuclear Diagnostic Products
Region: 1
City: Rockway State: NJ
County:
License #: 457796
Agreement: Y
Docket:
NRC Notified By: Joe Power
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 02/03/2025
Notification Time: 14:45 [ET]
Event Date: 01/23/2025
Event Time: 00:00 [EST]
Last Update Date: 02/03/2025
Notification Time: 14:45 [ET]
Event Date: 01/23/2025
Event Time: 00:00 [EST]
Last Update Date: 02/03/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Young, Matt (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Young, Matt (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - LOST THEN FOUND SOURCE
The following information was provided by the New Jersey Radiation Protection And Release Prevention Program (NJDEP) via email:
"On 1/23/2025, the Bureau of Environmental Radiation was notified that a load of municipal solid waste was rejected at a landfill in Dunmore, PA for triggering radiation alarms. The waste was originally hauled by JP Mascaro in Mt. Olive, NJ. A maximum exposure rate on contact with the truck of 4.7 mrem/hr was observed. A Department of Transportation special permit was issued to permit the load to return to JP Mascaro.
"On 1/31/2025, NJDEP was notified via email by JP Mascaro that the load had been sorted, and a package containing a shipment of 1.54 Ci of I-131 was identified. This was a shipment from a radiopharmacy in Quebec, Canada bound for Nuclear Diagnostic Products (NDP). According to tracking information provided by the common carrier, the package arrived successfully at the facility in Budd Lake, NJ, and was marked as out for delivery before it went missing.
"On 2/3/2025, NJDEP contacted NDP to alert them of the missing package. NDP agreed that one of their private couriers would retrieve the package from JP Mascaro."
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 information was provided by the New Jersey Radiation Protection And Release Prevention Program (NJDEP) via email:
"On 1/23/2025, the Bureau of Environmental Radiation was notified that a load of municipal solid waste was rejected at a landfill in Dunmore, PA for triggering radiation alarms. The waste was originally hauled by JP Mascaro in Mt. Olive, NJ. A maximum exposure rate on contact with the truck of 4.7 mrem/hr was observed. A Department of Transportation special permit was issued to permit the load to return to JP Mascaro.
"On 1/31/2025, NJDEP was notified via email by JP Mascaro that the load had been sorted, and a package containing a shipment of 1.54 Ci of I-131 was identified. This was a shipment from a radiopharmacy in Quebec, Canada bound for Nuclear Diagnostic Products (NDP). According to tracking information provided by the common carrier, the package arrived successfully at the facility in Budd Lake, NJ, and was marked as out for delivery before it went missing.
"On 2/3/2025, NJDEP contacted NDP to alert them of the missing package. NDP agreed that one of their private couriers would retrieve the package from JP Mascaro."
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: 57537
Facility: Browns Ferry
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: Eric Steel
HQ OPS Officer: Ernest West
Region: 2 State: AL
Unit: [1] [2] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: Eric Steel
HQ OPS Officer: Ernest West
Notification Date: 02/09/2025
Notification Time: 00:28 [ET]
Event Date: 02/08/2025
Event Time: 22:48 [CST]
Last Update Date: 02/09/2025
Notification Time: 00:28 [ET]
Event Date: 02/08/2025
Event Time: 22:48 [CST]
Last Update Date: 02/09/2025
Emergency Class: Unusual Event
10 CFR Section:
50.72(a) (1) (i) - Emergency Declared 50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation 50.72(b)(2)(xi) - Offsite Notification
10 CFR Section:
50.72(a) (1) (i) - Emergency Declared 50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation 50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Suggs, LaDonna (R2DO)
Franovich, Michael (NRR)
Miller, Mark (R2 RA)
Erlanger, Craig (NSIR)
Crouch, Howard (IR)
Suggs, LaDonna (R2DO)
Franovich, Michael (NRR)
Miller, Mark (R2 RA)
Erlanger, Craig (NSIR)
Crouch, Howard (IR)
| 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 | 89 | Power Operation | 89 | Power Operation |
| 3 | A/R | Y | 67 | Power Operation | 0 | Hot Shutdown |
NOTIFICATION OF UNUSUAL EVENT DUE TO SMOKE IN UNIT 3 TURBINE BUILDING
The following information was provided by the licensee via phone and email:
"On 2/8/2025, at 2248 CST, Browns Ferry Unit 3 experienced a main generator fault causing Unit 3 to experience an automatic reactor scram. Smoke was observed in multiple areas that required greater than 15 minutes to verify that no fire occurred. Browns Ferry declared a Notification of Unusual Event (NOUE), Emergency Action Level HU4, [at 2310] and completed the applicable notifications. The fault causing the main generator trip is still under investigation.
"A loss of power to the 3EA and 3EB 4KV shutdown boards resulted in a valid actuation of the 3A and 3B emergency diesel generators (EDGs) which successfully re-energized the boards as designed. During the scram response, there was a valid actuation of the primary containment isolation system (PCIS) groups 2, 3, 6, and 8. Upon receipt of these signals, all components actuated as required. Local offsite fire assistance was requested based on the initial indications but was not required. Operators responded and stabilized the plant. Units 1 and 2 were not affected.
"This event requires a 4 hour non-emergency report per 10 CFR 50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.
"This event requires a 4 hour non-emergency report per 10 CFR 50.72(b)(2)(xi), any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.
"This event requires an 8-hour non-emergency report per 10 CFR 50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B): 1) reactor protection system (RPS) including: reactor scram or reactor trip. 2) general containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). 8) emergency AC electrical power systems, including: EDGs.
"All safety systems operated as expected. At no time was public health and safety at risk. The NRC Resident Inspector has been notified"
Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC, CWMD Watch Desk (email), DHS NRCC THD Desk (email), and DHS Nuclear SSA (email).
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Browns Ferry Unit 3 intentions are to proceed to mode 4. Offsite power has been restored, and both the 3A and 3B EDGs have been secured. The NOUE was terminated on 2/9/2025, at 0110 CST.
The following information was provided by the licensee via phone and email:
"On 2/8/2025, at 2248 CST, Browns Ferry Unit 3 experienced a main generator fault causing Unit 3 to experience an automatic reactor scram. Smoke was observed in multiple areas that required greater than 15 minutes to verify that no fire occurred. Browns Ferry declared a Notification of Unusual Event (NOUE), Emergency Action Level HU4, [at 2310] and completed the applicable notifications. The fault causing the main generator trip is still under investigation.
"A loss of power to the 3EA and 3EB 4KV shutdown boards resulted in a valid actuation of the 3A and 3B emergency diesel generators (EDGs) which successfully re-energized the boards as designed. During the scram response, there was a valid actuation of the primary containment isolation system (PCIS) groups 2, 3, 6, and 8. Upon receipt of these signals, all components actuated as required. Local offsite fire assistance was requested based on the initial indications but was not required. Operators responded and stabilized the plant. Units 1 and 2 were not affected.
"This event requires a 4 hour non-emergency report per 10 CFR 50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.
"This event requires a 4 hour non-emergency report per 10 CFR 50.72(b)(2)(xi), any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.
"This event requires an 8-hour non-emergency report per 10 CFR 50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B): 1) reactor protection system (RPS) including: reactor scram or reactor trip. 2) general containment isolation signals affecting containment isolation valves in more than one system or multiple main steam isolation valves (MSIVs). 8) emergency AC electrical power systems, including: EDGs.
"All safety systems operated as expected. At no time was public health and safety at risk. The NRC Resident Inspector has been notified"
Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC, CWMD Watch Desk (email), DHS NRCC THD Desk (email), and DHS Nuclear SSA (email).
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Browns Ferry Unit 3 intentions are to proceed to mode 4. Offsite power has been restored, and both the 3A and 3B EDGs have been secured. The NOUE was terminated on 2/9/2025, at 0110 CST.
Agreement State
Event Number: 57532
Rep Org: Arizona Dept of Health Services
Licensee: Strytek Engineering
Region: 4
City: Lake Havasu State: AZ
County:
License #: 08-049
Agreement: Y
Docket:
NRC Notified By: Brian Goretzki
HQ OPS Officer: Adam Koziol
Licensee: Strytek Engineering
Region: 4
City: Lake Havasu State: AZ
County:
License #: 08-049
Agreement: Y
Docket:
NRC Notified By: Brian Goretzki
HQ OPS Officer: Adam Koziol
Notification Date: 02/04/2025
Notification Time: 12:23 [ET]
Event Date: 02/03/2025
Event Time: 14:00 [MST]
Last Update Date: 02/04/2025
Notification Time: 12:23 [ET]
Event Date: 02/03/2025
Event Time: 14:00 [MST]
Last Update Date: 02/04/2025
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 AND RECOVERED GAUGE
The following information was provided by the Arizona Department of Health Services (The Department) via email:
"The Department received notification that an Instrotek 3500 Xplorer nuclear moisture/density gauge fell off the back of a truck in front of Lake Havasu High School. The technician returned to retrieve the gauge approximately 30-45 minutes later. The gauge contains 10 millicuries of Cs-137 and 40 millicuries of Am-241. The Department has requested additional information and continues to investigate the event.
"Additional information will be provided as it is received in accordance with SA-300."
Arizona Incident Number: 25-003
The following information was provided by the Arizona Department of Health Services (The Department) via email:
"The Department received notification that an Instrotek 3500 Xplorer nuclear moisture/density gauge fell off the back of a truck in front of Lake Havasu High School. The technician returned to retrieve the gauge approximately 30-45 minutes later. The gauge contains 10 millicuries of Cs-137 and 40 millicuries of Am-241. The Department has requested additional information and continues to investigate the event.
"Additional information will be provided as it is received in accordance with SA-300."
Arizona Incident Number: 25-003
Agreement State
Event Number: 57533
Rep Org: Arizona Dept of Health Services
Licensee: Sonoran Heart, PLC
Region: 4
City: Avondale State: AZ
County:
License #: 07-603
Agreement: Y
Docket:
NRC Notified By: Brian Goretzki
HQ OPS Officer: Ian Howard
Licensee: Sonoran Heart, PLC
Region: 4
City: Avondale State: AZ
County:
License #: 07-603
Agreement: Y
Docket:
NRC Notified By: Brian Goretzki
HQ OPS Officer: Ian Howard
Notification Date: 02/04/2025
Notification Time: 11:02 [ET]
Event Date: 12/31/2024
Event Time: 00:00 [MST]
Last Update Date: 02/05/2025
Notification Time: 11:02 [ET]
Event Date: 12/31/2024
Event Time: 00:00 [MST]
Last Update Date: 02/05/2025
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 - UNQUALIFIED PERSONNEL
The following information was provided by the Arizona Department of Health Services (the Department) via phone and email:
"Seven (7) patients were injected with Tc-99m by a non-certified nuclear medicine technologist who knew he was not qualified to be injecting patients. The Department has requested additional information and continues to investigate the event."
Arizona Incident Number: 25-002
The following information was provided by the Arizona Department of Health Services (the Department) via phone and email:
"Seven (7) patients were injected with Tc-99m by a non-certified nuclear medicine technologist who knew he was not qualified to be injecting patients. The Department has requested additional information and continues to investigate the event."
Arizona Incident Number: 25-002
Agreement State
Event Number: 57534
Rep Org: Florida Bureau of Radiation Control
Licensee: Universal Engineering Sciences
Region: 1
City: Medley State: FL
County:
License #: 4896-9
Agreement: Y
Docket:
NRC Notified By: Monroe Cooper
HQ OPS Officer: Ian Howard
Licensee: Universal Engineering Sciences
Region: 1
City: Medley State: FL
County:
License #: 4896-9
Agreement: Y
Docket:
NRC Notified By: Monroe Cooper
HQ OPS Officer: Ian Howard
Notification Date: 02/04/2025
Notification Time: 14:20 [ET]
Event Date: 02/04/2025
Event Time: 12:30 [EST]
Last Update Date: 02/04/2025
Notification Time: 14:20 [ET]
Event Date: 02/04/2025
Event Time: 12:30 [EST]
Last Update Date: 02/04/2025
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Young, Matt (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Young, Matt (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE
The following is a summary of information provided by the State of Florida, Bureau of Radiation Control (the BRC) via email:
On 2/4/2025, at 1334 EST, the BRC received notification of a damaged Troxler gauge. At around 1230, an employee accidently backed over the gauge. The gauge was not in use at the time of the incident. The backup radiation safety officer states the sources are contained and secured, only the housing was damaged. Prior to notifying the BRC, the licensee returned the gauge to its storage location.
Moisture Density Gauge Information
Manufacturer: Troxler
Model Number: 3430
Serial Number: 37867
Cs-137 Activity: 8 mCi
Am-241 Activity: 40 mCi
Florida Incident Number: FL25-012
The following is a summary of information provided by the State of Florida, Bureau of Radiation Control (the BRC) via email:
On 2/4/2025, at 1334 EST, the BRC received notification of a damaged Troxler gauge. At around 1230, an employee accidently backed over the gauge. The gauge was not in use at the time of the incident. The backup radiation safety officer states the sources are contained and secured, only the housing was damaged. Prior to notifying the BRC, the licensee returned the gauge to its storage location.
Moisture Density Gauge Information
Manufacturer: Troxler
Model Number: 3430
Serial Number: 37867
Cs-137 Activity: 8 mCi
Am-241 Activity: 40 mCi
Florida Incident Number: FL25-012
Power Reactor
Event Number: 57540
Facility: Summer
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Elvis Zimmerman
HQ OPS Officer: Brian P. Smith
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Elvis Zimmerman
HQ OPS Officer: Brian P. Smith
Notification Date: 02/10/2025
Notification Time: 15:21 [ET]
Event Date: 02/10/2025
Event Time: 12:16 [EST]
Last Update Date: 02/10/2025
Notification Time: 15:21 [ET]
Event Date: 02/10/2025
Event Time: 12:16 [EST]
Last Update Date: 02/10/2025
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):
Suggs, LaDonna (R2DO)
Suggs, LaDonna (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 67 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DUE TO ELECTROHYDRAULIC CONTROL SYSTEM LEAK
?
The following information was provided by the licensee via phone and email:
"At 1216 EST, on 2/10/2025 with Unit 1 in mode 1 at 66.5 percent power, the reactor was manually tripped due to an electro-hydraulic control power system leak. The trip was not complex with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system.
"Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR50.72(b)(2)(iv)(B) and an eight-hour, non-emergency notification per 10CFR 50.72(b)(3)(iv)(A) resulting from a valid actuation of the reactor protection and emergency feedwater systems.
"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 1216 EST, on 2/10/2025 with Unit 1 in mode 1 at 66.5 percent power, the reactor was manually tripped due to an electro-hydraulic control power system leak. The trip was not complex with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the emergency feedwater system.
"Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR50.72(b)(2)(iv)(B) and an eight-hour, non-emergency notification per 10CFR 50.72(b)(3)(iv)(A) resulting from a valid actuation of the reactor protection and emergency feedwater systems.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."