Event Notification Report for July 02, 2024

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 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

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."

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."

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)

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."

REMOVABLE CONTAMINATION LIMITS EXCEEDED

The following information was provided by the Veterans Health Administration (VHA) National Health Physics Program via phone and email:

"Per 10 CFR 20.1906(d), VHA National Health Physics Program is reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits.

"The package was received Wednesday, June 26, 2024, at about 0650 EDT, at the Carl Vinson VA Medical Center, 1826 Veterans Blvd, Dublin, Georgia. This facility operates under VHA permit number 10-09569-01 issued in accordance with master materials license number 03-23853-01VA.

"The package was checked in and surveyed upon receipt around 0650 EDT. A wipe performed on the external surface of the package indicated a removable contamination level that exceeded the regulatory limit of 240 dpm/cm^2 for beta-gamma emitters. The measured contamination was 26,679 dpm/100cm^2. After adjusting for a 10 percent wipe efficiency and converting units, this equals 2668 dpm/cm^2 or about 10 times the reporting limit. The contamination was isolated primarily to the package handle.

"The package contained four dosages of Tc-99m with a total activity of about 90 mCi (nominal). Analysis of the wipe test confirmed a gamma peak consistent with Tc-99m. Wipe tests of the interior of the delivery package resulted in levels below the exterior level of around 2800 dpm. The dosages themselves appeared to be unimpacted and able to be used. The container was isolated and is being stored in a designated, shielded area for decay.

"The facility Nuclear Medicine Technologist (NMT) notified the delivery carrier by phone about the contaminated package at around 0910 EDT. VHA National Health Physics Program, who manages the master materials license, was alerted to the incident around 0710 CT (0810 ET)."

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

HOO follow up calls with the licensee and the radiopharmaceutical delivery company confirmed no spread of contamination. The receipt area at the licensee indicated no spread of contamination. The delivery driver clothes and hands were surveyed clean. There is no indication of spread of contamination to the public.

AGREEMENT STATE REPORT - BROKEN BRACHYTHERAPY SEED

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

"The Agency was contacted on 6/25/24 by Bard Brachytherapy in Carol Stream, IL to advise that they received a package which contained an applicator device with a broken brachytherapy seed. The applicator device was found to be contaminated and was placed in the licensee's hood for decontamination, recovery, and proper disposal. The licensee indicated there was no staff or area contamination as a result. The South Carolina licensee, having shipped the seed, similarly reported no contamination or adverse impacts. Due to the condition of the damaged seed, the radionuclide (Pd-103 or I-125) as well as the model and lot number are still pending. The activity remaining is likely beneath 0.5 mCi. This matter is reportable under 32 Ill. Adm. Code 340.1220(c)(1) and was transmitted to the NRC. Updates will be provided as they become available.

"Bard Brachytherapy is a manufacturer and distributor of brachytherapy seeds (IL-02062-01). Their client, West Hospital in Charleston, SC, returned the damaged seed in proper packaging. There is no indication of a public health or contamination concern."

Illinois Report #: IL240015

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

INVALID PARTIAL CONTAINMENT ISOLATION

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

"At 1928 CDT on May 13, 2024, River Bend Station (RBS) was operating in Mode 1 at 100 percent power when an invalid isolation signal actuated multiple containment isolation valves in more than one system. The invalid isolation signal was caused by voltage perturbations on the offsite power distribution system due to multiple lightning strikes in the vicinity of RBS.

"The event caused one containment isolation valve to isolate in the floor and equipment drains system, and two containment isolation dampers to isolate in the auxiliary building ventilation system.

"This event was a partial system isolation for the affected systems and did not result in a full train actuation.

"This event meets the reportable criteria for 10 CFR 50.73(a)(2)(iv)(A) and is being reported as any event or condition that resulted in manual or automatic actuation of any systems listed in paragraph (a)(2)(iv)(B). This notification is being provided in lieu of a Licensee Event Report as indicated in 10 CFR 50.73(a)(1)."

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

The valve and dampers were immediately re-opened. The standby gas treatment system automatically initiated due to the closure of the containment isolation dampers in the auxiliary building ventilation system.