Event Notification Report for July 10, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/07/2023 - 07/10/2023
Agreement State
Event Number: 56599
Rep Org: Arizona Dept of Health Services
Licensee: Banner University Medical Center
Region: 4
City: Phoenix State: AZ
County:
License #: 07-478
Agreement: Y
Docket:
NRC Notified By: Brian D. Goretzki
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 06/30/2023
Notification Time: 00:33 [ET]
Event Date: 06/29/2023
Event Time: 00:00 [MST]
Last Update Date: 06/30/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION
The following information was provided by the Arizona Department of Health Services (The Department) via email:
"The Department received notification from the licensee about a medical event involving I-131. On June 29, 2023, two patients were scheduled to receive I-131 doses of 75 and 100 millicuries (mCi) each. When the certified nuclear medicine technologist (CNMT) was preparing the first dose for the patient (75 mCi), the CNMT assayed the wrong dose but with the correct paperwork.
"The authorized user was present for the administration and gave the patient a 100 mCi dose of I-131 when the prescribed dose was for 75 mCi. The licensee discovered the mistake prior to giving the second patient (prescribed 100 mCi) the incorrect dose of 75 mCi. The Department has requested additional information and continues to investigate the event."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Agreement State
Event Number: 56600
Rep Org: OK Deq Rad Management
Licensee: UHS of Oklahoma, LLC
Region: 4
City: Enid State: OK
County:
License #: OK-17087-01
Agreement: Y
Docket:
NRC Notified By: Julia McRoberts
HQ OPS Officer: Eric Simpson
Notification Date: 06/30/2023
Notification Time: 11:33 [ET]
Event Date: 06/26/2023
Event Time: 12:00 [CDT]
Last Update Date: 07/05/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - MEDICAL MISADMINISTRATION
The following information was provided by the Oklahoma Department of Environmental Quality (DEQ) via email:
"On June 26, 2023, a referring physician ordered 300 microcuries for an I-123 thyroid and uptake scan. Instead, outpatient scheduling ordered a 21.1 millicuries Tc-99m sestamibi parathyroid exam. Neither the registration nor the nuclear medicine department reviewed the physician's order, and the Tc-99m sestamibi was administered. Using the nuclear medicine dose tool, the radiation dose estimates provided by the licensee for the I-123 uptake and scan would have been an approximate effective dose equivalent of 0.24 rem with the thyroid being the critical organ receiving 5.20 rad. Using the nuclear medicine dose tool, the radiation dose estimates provided by the licensee for the Tc-99m sestamibi parathyroid exam was an approximate effective dose equivalent of 0.62 rem with the gallbladder being the critical organ receiving 3.83 rad.
"In his email, the radiation safety officer stated that their local steps after this incident will be: to have in-depth conversations with techs and outpatient scheduling manager; initiate an incident report (internal and misadministration form); make notifications to the patient and attending physician; and engage the risk management and internal sentinel event process. The incident will be documented and reviewed in the July radiation safety meeting. It will also be reviewed during the daily facility safety meeting with C-Suites and all facility directors/managers.
"Additional updates will be made as they are received according to SA-300."
DEQ Event #1278
* * * RETRACTION ON 07/05/23 AT 1022 EDT FROM JULIA ROBERTS TO KERBY SCALES * * *
The following is a summary of information provided by DEQ via email:
The event was not a reportable medical event due to not meeting the threshold for reporting under 10 CR 35.3045(a)(1)(ii)(A).
Notified R4DO (Drake) and NMSS Events Notification (email).
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Hospital
Event Number: 56601
Rep Org: Saint Louis University
Licensee: Saint Louis University
Region: 3
City: St. Louis State: MO
County:
License #: 24-00196-07
Agreement: N
Docket:
NRC Notified By: Kevin Ferguson
HQ OPS Officer: Eric Simpson
Notification Date: 06/30/2023
Notification Time: 12:15 [ET]
Event Date: 06/29/2023
Event Time: 12:01 [CDT]
Last Update Date: 06/30/2023
Emergency Class: Non Emergency
10 CFR Section:
35.3045(a)(1) - Dose <> Prescribed Dosage
Person (Organization):
Orlikowski, Robert (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
MEDICAL EVENT - PATIENT UNDERDOSE
The following information was provided by the licensee via phone and followed up with an email:
"Yesterday, June 29, 2023, from 1201 to 1314 CDT, a Therasphere procedure was performed on a patient. The prescribed dose was for 14.58 mCi of Yttrium-90 (Y-90) to the left lobe of the liver. The authorized user (AU) stated that everything seemed to go normally other than they remembered afterwards a little more resistance than usual while performing the injection. The patient was sent for imaging and it was discovered shortly after 1500 that there was no dose in the patient. This was investigated, and the dose was found to be in the tubing. It is believed that the radioactive particles got clogged within the catheter. The AU stated that the catheter used was a model Trinav 120 cm length catheter, which is a special catheter with anti-reflux basket to prevent reflux and specially designed for Y-90 delivery.
"The AU stated that they would inform the patient of the medical event on the morning of June 30, 2023 (today).
"Additional details will be provided in the 15-day written report."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Agreement State
Event Number: 56604
Rep Org: New Mexico Rad Control Program
Licensee: Acuren Inspection, Inc.
Region: 4
City: Carlsbad State: NM
County:
License #: IR-448
Agreement: Y
Docket:
NRC Notified By: Robert Bicknell
HQ OPS Officer: Eric Simpson
Notification Date: 06/30/2023
Notification Time: 19:27 [ET]
Event Date: 06/30/2023
Event Time: 15:50 [MDT]
Last Update Date: 07/07/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
O'Keefe, Neil (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Grant, Jeffery (IR)
MacDonald, Mark (ILTAB)
Event Text
EN Revision Imported Date: 7/10/2023
EN Revision Text: AGREEMENT STATE REPORT - MISSING RADIOGRAPHY CAMERA
The following information was provided by the New Mexico Environment Department via phone and email:
"Acuren Inspection, Inc., New Mexico Radioactive Materials License IR-448, reported a missing source of licensed material, a lost gamma camera for industrial radiography with an unknown total quantity of radioactivity. The device was lost between the cities of Carlsbad and Jal, New Mexico on Highway 128 around mile marker 38 on June 30, 2023, at approximately 1550 MDT. Crews are actively looking for the missing device.
"The licensee is licensed for gamma cameras with sources of iridium-192 not to exceed 150 curies and selenium-75 not to exceed 100 curies.
"A request for further information from the licensee as events develop has been made."
Notified external: DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS CISA Central, and EPA EOC and via E-mail: FDA EOC, Nuclear SSA, FEMA National Watch Center, and CWMD Watch Desk.
*** UPDATE ON 7/7/2023 at 1238 EDT FROM ROBERT BICKNELL TO SAMUEL COLVARD ***
The device was recovered in Kermit, Texas on July 3, 2023, and reported to the state of New Mexico at approximately 1220 [MDT].
Notified internal: R4DO (Drake), NMSS (email), NMSS (Williams), ILTAB (email), ILTAB (MacDonald), IRMOC (Crouch), INES (Smith), CNSNS (Mexico) (email).
Notified external: DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS CISA Central, and EPA EOC and via E-mail: FDA EOC, Nuclear SSA, FEMA National Watch Center, and CWMD Watch Desk.
THIS MATERIAL EVENT CONTAINS A 'Category 2' LEVEL OF RADIOACTIVE MATERIAL
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Power Reactor
Event Number: 56610
Facility: Millstone
Region: 1 State: CT
Unit: [2] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Jason Paris
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 07/06/2023
Notification Time: 16:48 [ET]
Event Date: 07/06/2023
Event Time: 12:32 [EDT]
Last Update Date: 07/06/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
Person (Organization):
Lilliendahl, Jon (R1DO)
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
UNANALYZED CONDITION
The following information was provided by the licensee via email:
"On July 6, 2023, at 1232 EDT, while operating in Mode 1 at 100 percent power, the supply check valve from the number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure.
"There was no radioactive release to the environment. The steam line from the steam generator to the turbine driven auxiliary feedwater pump was isolated by use of a motor operated valve in the discharge line of the number 2 steam generator. There was no impact to Unit 3 which remains at 100 percent power.
"The Senior Resident was notified.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety."
Power Reactor
Event Number: 56612
Facility: Summer
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: Hank Kirkland
HQ OPS Officer: Sam Colvard
Notification Date: 07/07/2023
Notification Time: 12:51 [ET]
Event Date: 05/11/2023
Event Time: 12:50 [EDT]
Last Update Date: 07/07/2023
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Miller, Mark (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
1 |
N |
N |
0 |
Hot Shutdown |
100 |
Power Operation |
Event Text
PART 21 - CAP SCREW IMPROPER LENGTH
The following information was provided by the licensee via email:
"This is a non-emergency notification required by 10 CFR 21.21(d)(3)(i). A written notification in accordance with 10 CFR 21.21(d)(3)(ii) will be provided within 30 days. Steam Generator Emergency Feedwater Header Discharge Isolation Check Valves (XVC01009A-EF, XVC01009B-EF, and XVC01009C-EF) were designed specifically for and supplied to VC Summer Nuclear Station (VCSNS) by Flowserve under PO 4500653391 to replace the previous valves in the Emergency Feedwater System during Refueling Outage 27. On May 11, 2023, after valve installation, but prior to initial service, the Socket Head Cap Screws were identified as being shorter than the required design length. Valve drawings indicate a design length of 1.25" while the Socket Head Cap Screws received were 0.875". The correct length Cap Screws were installed prior to initial service. VCSNS completed a Substantial Safety Hazard Evaluation and determined that the improper length of the Cap Screws constituted a substantial safety hazard. This deviation in Cap Screw length resulted in a partial engagement of the Cap Screw to the cylinder rod extension and could potentially affect valve operation.
"The NRC Senior Resident Inspector has been notified."
Power Reactor
Event Number: 56614
Facility: Vogtle 3/4
Region: 2 State: GA
Unit: [3] [] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: Taylor Joseph
HQ OPS Officer: Brian Lin
Notification Date: 07/09/2023
Notification Time: 16:57 [ET]
Event Date: 07/09/2023
Event Time: 13:28 [EDT]
Last Update Date: 07/09/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Miller, Mark (R2DO)
Power Reactor Unit Info
Unit |
SCRAM Code |
RX Crit |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
3 |
A/R |
Y |
45 |
Power Operation |
0 |
Hot Standby |
Event Text
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via email:
"At 1328 EDT on 07/09/2023, with Unit 3 in Mode 1 at 45 percent power, the reactor automatically tripped during power ascension testing due to low reactor coolant flow from decaying voltage to the reactor coolant pumps. The trip was not complex, with all safety-related systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by discharging steam via steam generator power operated relief valves to the atmosphere, and startup feedwater is supplying the steam generators. Units 1, 2, and 4 are 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). There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."