Event Notification Report for December 10, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/09/2024 - 12/10/2024
Agreement State
Event Number: 57467
Rep Org: Vermont Department of Health
Licensee: University of Vermont Medical Center
Region: 1
City: Burlington State: VT
County:
License #: 44-10187-03
Agreement: Y
Docket:
NRC Notified By: Fran O'Neill
HQ OPS Officer: Jordan Wingate
Licensee: University of Vermont Medical Center
Region: 1
City: Burlington State: VT
County:
License #: 44-10187-03
Agreement: Y
Docket:
NRC Notified By: Fran O'Neill
HQ OPS Officer: Jordan Wingate
Notification Date: 12/11/2024
Notification Time: 18:06 [ET]
Event Date: 12/10/2024
Event Time: 16:03 [EST]
Last Update Date: 12/11/2024
Notification Time: 18:06 [ET]
Event Date: 12/10/2024
Event Time: 16:03 [EST]
Last Update Date: 12/11/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Jackson, Don (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Jackson, Don (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - MEDICAL EVENT
The following is a summary of information provided by the Vermont Department of Health via email:
A patient was prescribed 49.2 mCi of Y-90 TheraSphere microspheres, but received 33.6 mCi. This is a 30 percent difference in the prescribed dose and is reportable in accordance with 10 CFR 35.3045.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
The following is a summary of information provided by the Vermont Department of Health via email:
A patient was prescribed 49.2 mCi of Y-90 TheraSphere microspheres, but received 33.6 mCi. This is a 30 percent difference in the prescribed dose and is reportable in accordance with 10 CFR 35.3045.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Power Reactor
Event Number: 57464
Facility: Arkansas Nuclear
Region: 4 State: AR
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: John Lindsey
HQ OPS Officer: Jordan Wingate
Region: 4 State: AR
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: John Lindsey
HQ OPS Officer: Jordan Wingate
Notification Date: 12/10/2024
Notification Time: 18:02 [ET]
Event Date: 12/10/2024
Event Time: 10:30 [CST]
Last Update Date: 12/10/2024
Notification Time: 18:02 [ET]
Event Date: 12/10/2024
Event Time: 10:30 [CST]
Last Update Date: 12/10/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition 50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel 50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition 50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel 50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Azua, Ray (R4DO)
Azua, Ray (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 67 | Power Operation | 100 | Power Operation |
SECONDARY CONTAINMENT INOPERABLE
The following information was provided by the licensee via phone and email:
"At 0930 CST on 12/10/2024, Arkansas Nuclear One, Unit 1, discovered both isolation valves open in a one-inch breathing air line containment (reactor building) penetration. This resulted in inoperable reactor building isolation valves in a required mode of applicability per Unit 1 Technical Specification 3.6.3 and an inoperable reactor building per Unit 1 Technical Specification 3.6.1. Unit 1 had recently entered the modes of applicability for both Technical Specifications at 0556 CST on 12/8/2024 following a planned maintenance outage.
"The outside isolation valve was locked closed at 0950 CST on 12/10/2024, restoring operability of the reactor building. The inside valve was locked closed at 1345 CST on 12/10/2024, restoring operability of both isolation valves.
"This condition is being reported under 10 CFR 50.72(b)(3)(ii)(B) as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. This condition is also being reported under 10 CFR 50.72(b)(3)(v)(C) and (D) as an event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function of structures or systems that are needed to: (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the out-of-position valves is under investigation. No evolutions were in progress besides a plant startup at the time of the event.
The following information was provided by the licensee via phone and email:
"At 0930 CST on 12/10/2024, Arkansas Nuclear One, Unit 1, discovered both isolation valves open in a one-inch breathing air line containment (reactor building) penetration. This resulted in inoperable reactor building isolation valves in a required mode of applicability per Unit 1 Technical Specification 3.6.3 and an inoperable reactor building per Unit 1 Technical Specification 3.6.1. Unit 1 had recently entered the modes of applicability for both Technical Specifications at 0556 CST on 12/8/2024 following a planned maintenance outage.
"The outside isolation valve was locked closed at 0950 CST on 12/10/2024, restoring operability of the reactor building. The inside valve was locked closed at 1345 CST on 12/10/2024, restoring operability of both isolation valves.
"This condition is being reported under 10 CFR 50.72(b)(3)(ii)(B) as an event or condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. This condition is also being reported under 10 CFR 50.72(b)(3)(v)(C) and (D) as an event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function of structures or systems that are needed to: (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.
"There was no impact to the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the out-of-position valves is under investigation. No evolutions were in progress besides a plant startup at the time of the event.
Agreement State
Event Number: 57462
Rep Org: MA Radiation Control Program
Licensee: Lantheus Medical Imaging Inc
Region: 1
City: Billerica State: MA
County:
License #: 60-0088
Agreement: Y
Docket:
NRC Notified By: Bob Locke
HQ OPS Officer: Jordan Wingate
Licensee: Lantheus Medical Imaging Inc
Region: 1
City: Billerica State: MA
County:
License #: 60-0088
Agreement: Y
Docket:
NRC Notified By: Bob Locke
HQ OPS Officer: Jordan Wingate
Notification Date: 12/10/2024
Notification Time: 16:14 [ET]
Event Date: 12/10/2024
Event Time: 15:00 [EST]
Last Update Date: 12/11/2024
Notification Time: 16:14 [ET]
Event Date: 12/10/2024
Event Time: 15:00 [EST]
Last Update Date: 12/11/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Jackson, Don (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Jackson, Don (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
AGREEMENT STATE REPORT - MISSING TC-99M GENERATOR PACKAGE
The following report was received from the Massachusetts Radiation Control Program (the Agency) via email:
"On 12/10/2024, at around 1500 EST, Lantheus Medical Imaging, Inc. (license number 60-0088) was notified that a package containing a 1 Ci Mo-99/Tc-99m generator in a type B package was missing in transit and notified the Agency at 1545 on the same day.
"The reporting requirement is immediate per 105 Code of Massachusetts Regulations (CMR) 120.281(A)(1), missing licensed radioactive materials in aggregate quantity equal to or greater than 1,000 times quantity specified in 105 CMR 120.297, Appendix C.
"The Agency considers this event to be open."
Generator Model: Technelite-LEU 37.0 GBq Domestic
Generator Serial Number: B338411A04
Shipped to Southwest Health Systems in Cortez, Colorado.
Deemed lost by common carrier on 12/10/2024. The most recent reported location was Memphis, TN.
Activity: 37 Gbq, Mo-99/Tc-99m
Calibration date: 12/03/2024
Shipped as Yellow III, TI of 1.3
* * * UPDATE ON 12/11/2024 AT 1335 EST FROM ROBERT LOCKE TO JORDAN WINGATE * * *
"At 1318 EST on 12/11/2024, the licensee reported that the missing package had been delivered to its intended destination. The Agency considers this event closed."
Notified R1DO (Jackson), NMSS Events Notification (email), and ILTAB (email).
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 report was received from the Massachusetts Radiation Control Program (the Agency) via email:
"On 12/10/2024, at around 1500 EST, Lantheus Medical Imaging, Inc. (license number 60-0088) was notified that a package containing a 1 Ci Mo-99/Tc-99m generator in a type B package was missing in transit and notified the Agency at 1545 on the same day.
"The reporting requirement is immediate per 105 Code of Massachusetts Regulations (CMR) 120.281(A)(1), missing licensed radioactive materials in aggregate quantity equal to or greater than 1,000 times quantity specified in 105 CMR 120.297, Appendix C.
"The Agency considers this event to be open."
Generator Model: Technelite-LEU 37.0 GBq Domestic
Generator Serial Number: B338411A04
Shipped to Southwest Health Systems in Cortez, Colorado.
Deemed lost by common carrier on 12/10/2024. The most recent reported location was Memphis, TN.
Activity: 37 Gbq, Mo-99/Tc-99m
Calibration date: 12/03/2024
Shipped as Yellow III, TI of 1.3
* * * UPDATE ON 12/11/2024 AT 1335 EST FROM ROBERT LOCKE TO JORDAN WINGATE * * *
"At 1318 EST on 12/11/2024, the licensee reported that the missing package had been delivered to its intended destination. The Agency considers this event closed."
Notified R1DO (Jackson), NMSS Events Notification (email), and ILTAB (email).
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