Event Notification Report for July 09, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
07/08/2024 - 07/09/2024

EVENT NUMBERS
57204 57205 57211 57213 57214
Agreement State
Event Number: 57204
Rep Org: Colorado Dept of Health
Licensee: Five Rivers Cattle Feeding, LLC
Region: 4
City: Kersey   State: CO
County:
License #: GL002212
Agreement: Y
Docket:
NRC Notified By: Matthew Gift
HQ OPS Officer: Natalie Starfish
Notification Date: 07/01/2024
Notification Time: 18:51 [ET]
Event Date: 07/01/2024
Event Time: 15:30 [MDT]
Last Update Date: 07/01/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Agrawal, Ami (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST EXIT SIGNS

The following information was provided by the Colorado Department of Public Health and Environment (the Department) via email:

"Five Rivers Cattle Feeding, LLC reported eight missing tritium (H-3) exit signs. The initial registration received on June 26, 2012, indicated that each tritium exit sign contained 6.2 Ci (49.6 Ci total)."

Colorado State Event Report Number: CO240016

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


Non-Agreement State
Event Number: 57205
Rep Org: Agilent Technologies
Licensee: Agilent Technologies
Region: 1
City: Wilmington   State: DE
County: New Castle
License #: 07-28762-01
Agreement: N
Docket:
NRC Notified By: David Bennett
HQ OPS Officer: Robert A. Thompson
Notification Date: 07/02/2024
Notification Time: 07:45 [ET]
Event Date: 06/05/2024
Event Time: 07:00 [EDT]
Last Update Date: 07/02/2024
Emergency Class: Non Emergency
10 CFR Section:
20.2201(a)(1)(ii) - Lost/Stolen LNM>10x
Person (Organization):
Carfang, Erin (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
LOST SOURCE

The following information was provided by Agilent Technologies (the licensee) via phone:

A single electron capture device (ECD) containing 15 mCi of Ni-63 was reported to be lost. The ECD was one of ten in a package being transferred by a customer on June 5, 2024. The licensee believes that the ECD was erroneously discarded by a licensee operator. The licensee attempted to recover the ECD without success.

The licensee's root cause analysis determined the event occurred due to the employee not following the established procedure. In addition, employee training was inadequate due to failure to update the training program. Corrective action to update the training program has been undertaken by the licensee.

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The licensee believes that the ECD was discarded in the facility's normal waste stream.


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: 57211
Facility: Byron
Region: 3     State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Peter Leonhardt
HQ OPS Officer: Ian Howard
Notification Date: 07/07/2024
Notification Time: 23:12 [ET]
Event Date: 07/07/2024
Event Time: 14:40 [CDT]
Last Update Date: 07/07/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Hartman, Tom (R3DO)
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
BOTH TRAINS OF CONTROL ROOM VENTILATION TEMPERATURE CONTROL SYSTEM INOPERABLE

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

"At 1440 CDT on 7/7/2024, it was discovered that both trains of the control room ventilation temperature control system were simultaneously inoperable. Due to this 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).

"There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified.

"One train of control room ventilation temperature control was restored to operable status at 1634 CDT on 7/7/2024."


Power Reactor
Event Number: 57213
Facility: Harris
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: Trent Plummer
HQ OPS Officer: Ernest West
Notification Date: 07/08/2024
Notification Time: 11:04 [ET]
Event Date: 07/08/2024
Event Time: 07:48 [EDT]
Last Update Date: 07/08/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Suggs, LaDonna (R2DO)
Grant, Jeffery (IR)
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
INADVERTENT SIREN ACTIVATION

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

"On July 8, 2024, at 0748 EDT, six emergency response sirens were inadvertently actuated. Four sirens are located in Chatham County and two sirens are in Wake County. The first notification was made to Wake County at 0754. Investigation is ongoing to determine the cause of the actuation. Duke Energy notified the state and all counties within the emergency planning zone (EPZ). A press release was issued by Wake and Chatham Counties.

"This is a four-hour notification, non-emergency for the notification of another government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi).

"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: 57214
Facility: Watts Bar
Region: 2     State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Paul Blakely
HQ OPS Officer: Sam Colvard
Notification Date: 07/08/2024
Notification Time: 18:24 [ET]
Event Date: 07/08/2024
Event Time: 15:21 [EDT]
Last Update Date: 07/08/2024
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):
Suggs, LaDonna (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
AUTOMATIC REACTOR TRIP

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

"At 1521 EDT on July 8, 2024, with Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a main turbine trip. The [reactor] trip was not complex with all systems responding normally post trip.

"Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the main condenser using the steam dump system and the auxiliary feedwater (AFW) system. Unit 2 is 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). The expected actuation of the AFW system (an engineered safety feature) is being reported as an eight-hour report under 10 CFR 50.72(b)(3)(iv)(A).

"There was no impact on 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 specific cause of the turbine trip is under investigation by the licensee.