Event Notification Report for October 06, 2022

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
10/05/2022 - 10/06/2022

EVENT NUMBERS
56131 56138 56140
Agreement State
Event Number: 56131
Rep Org: California Radiation Control Prgm
Licensee: Twining, Inc.
Region: 4
City: Mira Loma   State: CA
County:
License #: 7899-56
Agreement: Y
Docket:
NRC Notified By: Andrew Taylor
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 09/29/2022
Notification Time: 15:24 [ET]
Event Date: 09/06/2022
Event Time: 22:30 [PDT]
Last Update Date: 09/29/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Kellar, Ray (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE - STOLEN AND RECOVERED TROXLER GAUGE

The following information was provided by the California Department of Public Health (CDPH) via email:

"Twining Inc. reported the theft of a Troxler model 3430 # 30952 portable soils gauge to the Sacramento CDPH office via California OES (Office of Emergency Services) on 9/8/22. The gauge contains two sealed sources: Cs-137, 0.30 GBq (8mCi) and Am-241/Be, 1.48 GBq (40mCi). The theft occurred around 2230 PDT on 9/6/2022, from the gauge operator's home. A police report was made to a deputy with the Riverside County Sheriff's office on the morning of 9/7/2022. The gauge had an airtag attached to it for tracking purposes.

"On 9/22/2022, Maurer Technical Services, who calibrates these types of soils gauges was contacted by a person who indicated he had this gauge. The caller's name, phone number and address in Riverside were obtained. Maurer Technical verified the gauge's serial number belonged to Twining, Inc. and their office was notified. Staff from Twining's Riverside office went to pick-up the gauge and it was transferred back to the Ventura office, where it was evaluated and leak tested on 9/25/2022 (found to be not leaking). The Riverside County Sheriff's office was informed that the gauge was recovered. Additionally, the Radiologic Health Branch was also notified that the stolen gauge had been recovered.

"On 9/29/2022, it was discovered that a supervisor at ICE RHB had received the initial notification from the CDPH duty officer, but due to competing demands, failed to forward the report to the RHB South office for follow-up action and reporting to the NRC."

CA Event Number: 092222

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: 56138
Facility: Brunswick
Region: 2     State: NC
Unit: [2] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Jacob Cottle
HQ OPS Officer: Howie Crouch
Notification Date: 10/04/2022
Notification Time: 10:27 [ET]
Event Date: 08/06/2022
Event Time: 06:28 [EDT]
Last Update Date: 10/04/2022
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
Miller, Mark (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
Event Text
60-DAY OPTIONAL TELEPHONIC NOTIFICATION OF INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES

The following information was provided by the licensee via email:

"This 60-day optional telephone notification is being made in lieu of an LER submittal as allowed by 10 CFR 50.73(a)(1). This notification is made pursuant to the reporting requirements specified in 10 CFR 50.73(a)(2)(iv)(A) for invalid actuations of one of the systems listed in 10 CFR 50.73(a)(2)(iv)(B).

"At approximately 0628 Eastern Daylight Time (EDT) on August 6, 2022, an invalid actuation of group 6 Primary Containment Isolation Valves (PCIVs) (i.e., containment atmospheric control/monitoring and post accident sampling isolation valves) occurred. The group 6 isolation signal resulted from the reactor building ventilation radiation monitor `A' channel exceeding the setpoint value. This condition recurred at approximately 1305 EDT on August 12, 2022. In both instances, the `B' channel, located in the same plenum, remained steady and below the setpoint value through the entire event. This, along with readings made by radiation protection technicians, confirmed that there were no actual high radiation conditions in the reactor building exhaust in either instance. Following each invalid actuation, upon returning unit 2 reactor building ventilation to service, the `A' channel readings returned to be consistent with the `B' channel. It was determined that these invalid actuations likely resulted from degradation of circuit components associated with the radiation monitor. The `A' channel radiation monitor was replaced on September 22, 2022.

"During these two events, the PCIVs functioned successfully and the actuations were complete. The actuations were not initiated in response to actual plant conditions, they were not an intentional manual initiation, and there were no parameters satisfying the requirements for initiation of the system. Therefore, these events have been determined to be invalid actuations.

"These events did not result in any adverse impact to the health and safety of the public."


Power Reactor
Event Number: 56140
Facility: Arkansas Nuclear
Region: 4     State: AR
Unit: [1] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: Matt Isely
HQ OPS Officer: Thomas Herrity
Notification Date: 10/04/2022
Notification Time: 15:54 [ET]
Event Date: 10/04/2022
Event Time: 07:40 [CDT]
Last Update Date: 10/04/2022
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Dixon, John (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 -1 Power Operation 71 Power Operation
2 N Y 100 Power Operation 100 Power Operation
Event Text
FITNESS FOR DUTY REPORT

A non-licensed supervisor had a confirmed positive during a random fitness-for-duty test. The employee's access to the plant has been terminated.

The NRC Resident Inspector has been notified.

Page Last Reviewed/Updated Thursday, October 06, 2022