Event Notification Report for October 01, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/30/2024 - 10/01/2024
Agreement State
Event Number: 57335
Rep Org: New Mexico Rad Control Program
Licensee: Acme Environmental, Inc.
Region: 4
City: Albuquerque State: NM
County: Bernalillo
License #: PA 526-02
Agreement: Y
Docket:
NRC Notified By: Victor Diaz
HQ OPS Officer: Jon Lilliendahl
Notification Date: 09/23/2024
Notification Time: 14:56 [ET]
Event Date: 09/23/2024
Event Time: 00:00 [CDT]
Last Update Date: 09/23/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Young, Cale (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
CNSNS (Mexico), - (EMAIL)
Event Text
AGREEMENT STATE REPORT - STOLEN SOURCE
The following is a summary of information that was provided by the New Mexico Radiation Control Program via phone and email:
During the weekend, Acme Environmental, Inc. (the licensee) was burglarized. An XRF lead paint analyzer, model Heuresis Pb200i, containing 5 mCi of Co-57 was stolen, along with numerous other items. The licensee notified the police, and the police are actively investigating.
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: 57337
Rep Org: Texas Dept of State Health Services
Licensee: East Texas Testing Laboratory, Inc
Region: 4
City: Winona State: TX
County:
License #: L 01423
Agreement: Y
Docket:
NRC Notified By: Arthur Tucker
HQ OPS Officer: Ian Howard
Notification Date: 09/24/2024
Notification Time: 13:07 [ET]
Event Date: 09/24/2024
Event Time: 00:00 [CDT]
Last Update Date: 09/24/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Young, Cale (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
CNSNS (Mexico), - (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST NUCLEAR GAUGE
The following information was provided by the Texas Department of State Health Services (the Department) via phone and email:
"On September 24, 2024, the Department was notified by the licensee that on September 21, 2024, one of its technicians lost a Troxler model 3440 moisture density gauge. The gauge contains a 40 millicurie Am-241/Be source and an 8 millicurie Cs-137 source. The technician had completed work at a temporary job site and placed the gauge on the back of the pickup truck they were using. The technician failed to place the gauge in the transport container. The technician failed to secure the gauge in the truck. The technician drove off the job site and after a short distance realized they had failed to secure the gauge. The technician stopped and found the gauge was no longer in the truck. The technician stated he looked for the gauge but did not find it. The licensee stated the technician brought the empty transport box back to the storage location and left it. The licensee stated that on September 24, 2024, they went to the storage location to use the gauge and found the box was empty. The licensee contacted the technician who stated they had lost the gauge on Saturday. The licensee stated the Cs-137 source rod was not locked in the shielded position. The license stated they will contact the local sheriff office and notify them of the lost gauge. Since the Cs-137 rod was not locked in the shielded position, they can not say with any certainty that the lost sources would not create an exposure risk to any individual."
Texas Incident #: 10131
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: 57351
Facility: Sequoyah
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Timothy Wood
HQ OPS Officer: Natalie Starfish
Notification Date: 09/29/2024
Notification Time: 08:40 [ET]
Event Date: 09/29/2024
Event Time: 05:56 [EDT]
Last Update Date: 09/29/2024
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):
Suber, Gregory (R2DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
1 |
A/R |
Y |
100 |
Power Operation |
0 |
Hot Standby |
Event Text
EN Revision Imported Date: 10/1/2024
EN Revision Text: AUTOMATIC REACTOR TRIP DUE TO TURBINE TRIP
The following information was provided by the licensee via phone and email:
"At 05:56 EDT on 09/29/2024, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The motor driven auxiliary feedwater (MDAFW) level control valves (LCV) for loop 1 failed to respond from the main control room. All others systems responded normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the auxiliary feedwater (AFW) and steam dump systems. Unit 2 is currently stable in Mode 6 for a maintenance outage and was not affected.
"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 AFW system. The AFW system started automatically and is operating as designed with the exception of the MDAFW LCVs for loop 1.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 57353
Facility: Prairie Island
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: Timothy Thomas
HQ OPS Officer: Brian P. Smith
Notification Date: 09/30/2024
Notification Time: 16:37 [ET]
Event Date: 09/30/2024
Event Time: 13:40 [CDT]
Last Update Date: 09/30/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Havertape, Joshua (R3DO)
Power Reactor Unit Info
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 |
Event Text
OFFSITE NOTIFICATION
The following information was provided by the licensee via phone and email:
"At 1340 CDT on 9/30/2024, Prairie Island Nuclear Generating Plant was informed that the Minnesota State Duty Officer and the Environmental National Response Center had been notified of a coolant leak from a diesel driven cooling pump expansion tank that had reached the waters of the state. The estimated quantity is 0.7 gallons of NALCO LCS-60. The leak has been isolated."
The NRC Resident Inspector has been notified.