Event Notification Report for July 03, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
07/02/2024 - 07/03/2024

EVENT NUMBERS
57192 57193 57202 57203 57206
Hospital
Event Number: 57192
Rep Org: Carl Vinson VA Medical Center
Licensee: Carl Vinson VA Medical Center
Region: 1
City: Dublin   State: GA
County:
License #: 03-23853-01VA
Agreement: N
Docket:
NRC Notified By: VA Nat'l HP Prog
HQ OPS Officer: Sam Colvard
Notification Date: 06/26/2024
Notification Time: 09:49 [ET]
Event Date: 06/26/2024
Event Time: 06:50 [EDT]
Last Update Date: 06/26/2024
Emergency Class: Non Emergency
10 CFR Section:
20.1906(d)(1) - Surface Contam Levels > Limits
Person (Organization):
Skokowski, Richard (R3DO)
NMSS_Events_Notification, (EMAIL)
Event Text
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
Event Number: 57193
Rep Org: Illinois Emergency Mgmt. Agency
Licensee: Bard Brachytherapy
Region: 3
City: Carol Stream   State: IL
County:
License #: IL-02062-01
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Sam Colvard
Notification Date: 06/26/2024
Notification Time: 12:52 [ET]
Event Date: 06/25/2024
Event Time: 00:00 [CDT]
Last Update Date: 06/26/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Skokowski, Richard (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
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


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."


Power Reactor
Event Number: 57206
Facility: River Bend
Region: 4     State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Darren Farthing
HQ OPS Officer: Robert A. Thompson
Notification Date: 07/02/2024
Notification Time: 10:08 [ET]
Event Date: 05/13/2024
Event Time: 19:28 [CDT]
Last Update Date: 07/02/2024
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
Agrawal, Ami (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
Event Text
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.