Event Notification Report for July 02, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/01/2024 - 07/02/2024
Agreement State
Event Number: 57189
Rep Org: NV Div of Rad Health
Licensee: Nevada Goldmines LLC-ELKO
Region: 4
City: Carlin State: NV
County:
License #: 05-11-13454-01
Agreement: Y
Docket:
NRC Notified By: Cory Creveling
HQ OPS Officer: Jordan Wingate
Notification Date: 06/24/2024
Notification Time: 11:48 [ET]
Event Date: 06/18/2024
Event Time: 00:00 [PDT]
Last Update Date: 06/24/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Josey, Jeffrey (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT- STUCK SHUTTER
The following information was provided by the Nevada Division of Radiation Health via email and phone:
"On June 18, 2024, Nevada Goldmines - Elko, discovered a failed shutter while conducting required 6-month shutter checks on a Berthold LB 7440 fixed gauge in the open position. In place radiation surveys were conducted to verify safety until a contractor would be available to remove the gauge and move it to storage. All readings were normal. The licensee coordinated with Radiation Technology Inc., (RTI) to remove the gauge and move it to the authorized storage area pending decision to repair or dispose of the gauge.
"RTI conducted onsite leak checks and results were less than 0.005 microcuries. A second set of leak check samples were taken to be returned to RTI lab for verification. A radiation survey following deinstallation confirmed them to be background.
"The gauge was removed from service, plates placed over the open window to provide shielding, and the device with plates covering the window was placed in storage. Surveys of the storage area show increase in radiation consistent with adding a new gauge to the job box, with the highest radiation level being 79 microR/hour at 12 inches."
Gauge Information:
Model: Berthold LB 7440
Serial number: 3015
Activity: Cs-137 (150 Ci)
Nevada Item Number: NV240004
Agreement State
Event Number: 57190
Rep Org: Utah Division of Radiation Control
Licensee: IHC Health Services DBA Mckay-Dee
Region: 4
City: Ogden State: UT
County:
License #: UT 2900147
Agreement: Y
Docket:
NRC Notified By: Spencer Wickham
HQ OPS Officer: Sam Colvard
Notification Date: 06/24/2024
Notification Time: 17:46 [ET]
Event Date: 06/04/2024
Event Time: 00:00 [MDT]
Last Update Date: 06/24/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Werner, Greg (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST I-125 SEED
The following information was received from the Utah Department of Environmental Quality, Division of Waste Management and Radiation Control (the Department) via email:
"On June 24, 2024, the Department was notified that on June 4, 2024, an I-125 seed for breast localization was not recovered during routine tissue processing of the tissue sample at the grossing bench or within the histology lab. The seed was verified in the tissue sample at the time of removal from the patient through both survey of the patient and a radiograph of the tissue sample. The seed was most likely disposed of either in the biohazard waste or in the non-biohazard waste.
"Upon discovery of the lost source, a survey of the lab with a low energy gamma detector was performed in an attempt to locate the source. The source was not found.
"Exposure to the public is expected to be very low or minimal. The low energy X-rays associated with I-125 decay are likely to be attenuated due to overlying waste, minimal time around the waste, and the given low exposure rate associated with the source. The material is encapsulated."
Utah Event Report ID: 240004
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: 57199
Facility: Monticello
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: Brian Olson
HQ OPS Officer: Robert A. Thompson
Notification Date: 06/28/2024
Notification Time: 16:28 [ET]
Event Date: 06/28/2024
Event Time: 01:10 [CDT]
Last Update Date: 07/01/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(B) - Pot RHR Inop
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Skokowski, Richard (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 |
Event Text
BOTH DIVISIONS OF LPCI INOPERABLE
The following information was provided by the licensee via email:
"This condition is being reported in accordance with 10 CFR50.72(b)(3)(v) as a condition that could have prevented fulfillment of a safety function. On 6/27/2024 at 2158 CDT, [technical specification] TS 3.5.1 condition 'D' (both divisions of [low pressure coolant injection] LPCI inoperable) was entered for surveillance testing. On 6/28/2024 at 0110 CDT, MO-2012 [residual heat removal] RHR Division 1 LPCI injection outboard valve was attempted to be cycled. It was discovered to be inoperable resulting in an inability to exit TS 3.5.1 'D'. Initial review of this condition for immediate reportability under 50.72(b)(3)(v) event or a condition that could have prevented fulfillment of a safety function, concluded the condition was not reportable based on the operability of other emergency core cooling systems (ECCS). Specifically, core spray and high pressure coolant injection were both operable to perform the function of emergency core cooling. Subsequent reviews determined that the reportability decision under 50.72(b)(3)(v) as an event or condition that could have prevented fulfillment of a safety function should be based on the safety function at the LPCI system level, rather than at the ECCS system level. The decision to report the inoperability of LPCI under 50.72(b)(3)(v) was made at 1030 CDT on 6/28/2024. The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 57201
Facility: South Texas
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Randall Maus
HQ OPS Officer: Ernest West
Notification Date: 06/30/2024
Notification Time: 16:13 [ET]
Event Date: 06/30/2024
Event Time: 12:22 [CDT]
Last Update Date: 06/30/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Werner, Greg (R4DO)
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
OFFSITE NOTIFICATION
The following information was provided by the licensee via phone and email:
"At 1222 CDT on 06/30/24, South Texas Project notified the Texas Commission on Environmental Quality (TCEQ) and the National Response Center regarding an oil spill of 280 gallons to the ground inside the protected area. This event was recorded as TECQ Event number: 20242394 and Incident Response Center incident number: 1403420.
"The spill occurred due to the overflow of an oily waste sump. The influent to the sump was stopped. The spill was confined to a 15 feet by 15 feet area on the ground and did not enter any waterway.
"This notification is being made solely as a four-hour, non-emergency notification for a notification to another government agency. This was determined to be reportable as required by 10CFR50.72(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."
Independent Spent Fuel Storage Installation
Event Number: 57202
Rep Org: San Onofre
Licensee: Southern California Edison Company
Region: 4
City: San Clemente State: CA
County: San Diego
License #: GL
Agreement: Y
Docket: 72-41
NRC Notified By: Kevin Bryan
HQ OPS Officer: Robert A. Thompson
Notification Date: 07/01/2024
Notification Time: 14:13 [ET]
Event Date: 07/01/2024
Event Time: 07:34 [PDT]
Last Update Date: 07/01/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Agrawal, Ami (R4DO)
Event Text
OFFSITE NOTIFICATION FOR REPORTED LEAK
The following information was provided by San Onofre Nuclear Generating Station (SONGS) via email:
"At 2200 PDT on June 30, 2024, the California Office of Emergency Services (CAL OES) received a hazardous material spill report from BNSF Railway. BNSF reported a leak from a rail car that was transporting 'radioactive material surface contaminated objects'. BNSF contacted the local fire department to investigate the leaking material. This rail car was transporting the decommissioned Unit 2 pressurizer.
"Informational surveys conducted by a third party have determined that the leaked material did not involve contamination above background levels. Currently, there are SONGS radiation protection personnel en-route to investigate the reported leak.
"At 0734 PDT on July 1, 2024, SONGS personnel identified through the CAL OES website that BNSF had reported a hazardous spill to CAL OES. This is a 4-hour report due to a notification made to a government agency.
"Notification has been made to Region IV due to SONGS not having a NRC resident."
* * * UPDATE ON 07/01/2024 AT 2046 EDT FROM KEVIN BRYAN TO NATALIE STARFISH * * *
The following information was provided by the licensee via phone and email:
"Additional radiological surveys performed by SONGS radiation protection personnel have confirmed that there is no detectable contamination in the leaked material."
Notified R4DO (Agrawal)
Power Reactor
Event Number: 57203
Facility: Oconee
Region: 2 State: SC
Unit: [1] [2] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: Chris Judd
HQ OPS Officer: Natalie Starfish
Notification Date: 07/01/2024
Notification Time: 15:11 [ET]
Event Date: 07/01/2024
Event Time: 09:42 [EDT]
Last Update Date: 07/01/2024
Emergency Class: Non Emergency
10 CFR Section:
26.719 - Fitness For Duty
Person (Organization):
Suggs, LaDonna (R2DO)
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 |
3 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
POSITIVE FITNESS FOR DUTY TEST
The following information was provided by the licensee via phone and email:
"At 0942 EDT on July 1, 2024, it was determined that an individual had a confirmed positive test as specified by the fitness-for-duty testing program. The individual's authorization for site access has been terminated.
"The NRC Resident Inspector has been notified."