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Event Notification Report for December 05, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
12/04/2024 - 12/05/2024

EVENT NUMBERS
57447 57448 57452 57453 57454
Agreement State
Event Number: 57447
Rep Org: Illinois Emergency Mgmt. Agency
Licensee: Princeton Technical Services
Region: 3
City: Chicago   State: IL
County:
License #: IL-02340-01
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 11/27/2024
Notification Time: 14:13 [ET]
Event Date: 11/26/2024
Event Time: 00:00 [CST]
Last Update Date: 11/27/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Skokowski, Richard (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED TROXLER GAUGE

The following information was provided by the Illinois Emergency Management Agency (The Agency) via email:

"The Agency was contacted the evening of 11/26/24 by the radiation safety officer for Princeton Technical Services to advise that a Troxler 3430 moisture density gauge had been hit by a vehicle while in use at the airport. Reportedly, the authorized user (AU) set the portable gauge next to his vehicle and forgot to properly secure it prior to moving. The vehicle struck the gauge and broke off the face plate and the electronic keypad. The AU stated that there was no damage to the source housings and the cesium source rod was fully retracted. These statements were confirmed by on scene Chicago Fire Department (CFD) personnel. The CFD used a Thermo RadEye device to measure the exposure rate at one meter which was compared to the shipping papers. The reading at one meter was 189 microR/hour and the listed transport index was 0.3 which supports the fact that the source rod was properly shielded. The gauge was then packaged in the undamaged case and transported back to the licensee's location.

"Agency inspectors conducted a reactive inspection the morning of 11/27/24 and corroborated the details above. The licensee's written report is pending and will be used to update this event with a root cause and corrective actions. The licensee attributes the cause of the event to human error and the failure to follow their procedure."

Illinois Item Number: IL240029
Source Number: 1
Source/Radioactive Material: Sealed Source Gauge
Manufacturer: AEA Technologies
Model Number: NR
Serial Number: 750-9439
Radionuclide: Cs-137
Activity: 0.008 Ci (8 mCi or 296 MBq)
Source Number: 2
Source/Radioactive Material: Sealed Source Gauge
Manufacturer: Isotope Products Lab
Model Number: NR
Serial Number: 47-6362
Radionuclide: Am-Be
Activity: 0.04 Ci (40 mCi or 1.48 GBq)


Agreement State
Event Number: 57448
Rep Org: New Mexico Rad Control Program
Licensee: NexTier Completion Solutions
Region: 4
City: Jal   State: NM
County:
License #: GA507-07
Agreement: Y
Docket:
NRC Notified By: Carl Sullivan
HQ OPS Officer: Brian P. Smith
Notification Date: 11/27/2024
Notification Time: 14:51 [ET]
Event Date: 11/27/2024
Event Time: 08:00 [MST]
Last Update Date: 11/27/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED DENSITOMETER

The following report was received by the New Mexico Radiation Control Program (the Program) via email and phone:

"The Program reported that a Berthold densitometer, model number 'LB8010', serial number '12133', Cesium-137 source with an activity of 20 mCi, had a shutter handle failure while on a fracking operation near Jal, New Mexico. The pad name is the Matador Firethorn. The device was not physically damaged, but the shutter handle became detached from the device. The failure is being considered a design failure on the Berthold device. The shutter is in the open position and cannot be closed. The vendor in Houston, Texas, has been requested to come to the location and change out the device for one that is operable. The vendor has been requested to transport the device back to Houston in preparation for disposal.

"There were no unnecessary exposures to any persons as a result of this incident."


Power Reactor
Event Number: 57452
Facility: South Texas
Region: 4     State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Jase Ashcraft
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/03/2024
Notification Time: 17:32 [ET]
Event Date: 12/03/2024
Event Time: 15:15 [CST]
Last Update Date: 12/03/2024
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Gepford, Heather (R4DO)
FFD Group, (EMAIL)
Power Reactor Unit Info
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 100 Power Operation 100 Power Operation
Event Text
FALSE NEGATIVE QUALITY ASSURANCE TEST

The following information was provided by the licensee via phone and email:

"Contrary to the requirements in 10 CFR 26.137(b), a Health and Human Services (HHS) certified laboratory returned a blind specimen result that was inconsistent with what was expected.

"On November 14, 2024, blind specimens from the same lot number were sent to the two contracted HHS laboratories. On November 27, 2024, one of the labs reported unexpected results while the other laboratory reported the expected results (positive for opiates). At approximately 1415 CST on December 3, 2024, the lab report was reviewed by the fitness-for-duty medical review officer (MRO) staff at the South Texas Project and the inaccurate result was identified. At approximately 1510 CST on December 3, 2024, MRO staff contacted the laboratory to discuss the testing discrepancy and directed the lab to retest the specimen. The MRO staff also requested that the laboratory initiate an investigation to determine the reason for the inaccurate result.

"10 CFR 26.719(c)(3), reporting requirements state, 'If a false negative error occurs on a quality assurance check of validity screening tests, as required in  26.137(b), the licensee or other entity shall notify the NRC within 24 hours after discovery of the error.'

"The licensee has notified the NRC Resident Inspector."


Power Reactor
Event Number: 57453
Facility: Turkey Point
Region: 2     State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Arturo Alvarez
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/04/2024
Notification Time: 13:24 [ET]
Event Date: 12/04/2024
Event Time: 10:33 [EST]
Last Update Date: 12/04/2024
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
3 A/R Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR TRIP

The following information was provided by the licensee via phone or email:

"At 1033 EST on December 4, 2024, with Unit 3 in mode 1 at 100% power, the reactor automatically tripped in response to a reactor protection system channel failure while planned maintenance was in progress on a redundant channel. The plant is currently in mode 3. Decay heat is being removed by steam dumps to atmosphere. Unit 4 is unaffected. An actuation of the auxiliary feedwater system occurred and started as designed. An actuation of the emergency core cooling system (ECCS) occurred and started as designed. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B), and 10 CFR 50.72(b)(3)(iv)(A).

"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 ECCS actuation included safety injection, residual heat removal, and emergency containment cooling. The cause of the trip and the ECCS actuation are under investigation. There are no indications of primary to secondary leakage.


Power Reactor
Event Number: 57454
Facility: Brunswick
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Chris Denton
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/04/2024
Notification Time: 19:01 [ET]
Event Date: 12/04/2024
Event Time: 16:40 [EST]
Last Update Date: 12/04/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
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 N Y 100 Power Operation 100 Power Operation
Event Text
SECONDARY CONTAINMENT INOPERABLE

The following information was provided by the licensee via phone and email:

"At 1640 EST, on December 4, 2024, secondary containment was declared inoperable. This condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(C), as an event or condition that could have prevented fulfillment of a safety function.

"Secondary containment was declared inoperable due to a small hole discovered in the service water piping within secondary containment. The effective safety function was restored at 1730 EST by installation of a temporary repair and secondary containment has been restored to operable.

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

Notified R2DO (Suber)