Event Notification Report for November 15, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
11/14/2024 - 11/15/2024

EVENT NUMBERS
57416 57417 57422 57423 57424
Agreement State
Event Number: 57416
Rep Org: Louisiana Radiation Protection Div
Licensee: Mistras Group Inc.
Region: 4
City: Geismar   State: LA
County:
License #: LA-10986-L01, Amendment 92
Agreement: Y
Docket:
NRC Notified By: James Pate
HQ OPS Officer: Kerby Scales
Notification Date: 11/08/2024
Notification Time: 14:27 [ET]
Event Date: 11/07/2024
Event Time: 19:30 [CST]
Last Update Date: 11/08/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Dixon, John (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - CRIMPED SOURCE GUIDE TUBE

The following is a summary of information received from the Louisiana Department of Environmental Quality (LDEQ) via email:

On November 7, 2024 at 1930 CST, a source guide tube became crimped which prevented source retraction to the shielded condition. The industrial radiography camera being used was a QSA 880 Delta (serial number D12667) containing a 106 Curie Ir-192 source (serial number 10791P).

The licensee was able to retrieve the source. One authorized user received 500 mR radiation exposure.

Louisiana Event Report ID Number: LA20240011


Agreement State
Event Number: 57417
Rep Org: Colorado Dept of Health
Licensee: Sonnenalp Vail
Region: 4
City: Vail   State: CO
County:
License #: GL002227
Agreement: Y
Docket:
NRC Notified By: Kathryn Kirk
HQ OPS Officer: Adam Koziol
Notification Date: 11/08/2024
Notification Time: 18:12 [ET]
Event Date: 07/02/2024
Event Time: 00:00 [MST]
Last Update Date: 11/12/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Dixon, John (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Event Text
AGREEMENT STATE REPORT - LOST EXIT SIGNS

The following is a summary of information received from the Colorado Department of Public Health and Environment via email:

Two tritium exit signs were determined to be lost by the licensee.

Manufacturer: Isolite Corporation
Model Number: 880
Activity: 12 Ci H-3

Manufacturer: Shield Source Inc.
Model Number: 101
Activity: 13 Ci H-3

* * * UPDATE ON 11/12/2024 AT 1720 EST FROM KATHRYN KIRK TO TENISHA MEADOWS * * *

The following information was provided by the Colorado Department of Public Health and Environment via email:

The event date is 10/1/2023, which occurred during a renovation period of October 2023 through November 2023.

Notified R4DO (Young), NMSS Events Notification (email), and ILTAB (email).

Colorado event number: CO0026

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: 57422
Facility: Millstone
Region: 1     State: CT
Unit: [3] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Robert Mello
HQ OPS Officer: Tenisha Meadows
Notification Date: 11/13/2024
Notification Time: 13:38 [ET]
Event Date: 10/10/2024
Event Time: 09:02 [EST]
Last Update Date: 11/13/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Lilliendahl, Jon (R1DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation
Event Text
SECONDARY CONTAINMENT BOUNDARY INOPERABLE

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

"At 0902 EST, on 10/10/2024, with Millstone Unit 3 in mode 1 at 100 percent power, it was discovered that the secondary containment boundary was inoperable when the latch that secured a hatch that was part of the secondary containment boundary was not functional. The latch was repaired by 1115, on 10/10/2024, and the secondary containment boundary was declared operable at 1200, on 10/10/2024. The initial assessment of reportability concluded that an immediate report was not required. However, upon additional review, it has been determined that because the secondary containment boundary is a single-train system that performs a safety function, an 8-hour report was required in accordance with 10 CFR 50. 72 (b)(3)(v)(C) and (D).

"This report should have been made on 10/10/2024 and is late.

"There has been no impact to Unit 2, and Unit 3 continues to operate in mode 1 at 100 percent power.

"There is no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."


Agreement State
Event Number: 57423
Rep Org: WA Office of Radiation Protection
Licensee: Acuren
Region: 4
City: Anacortes   State: WA
County:
License #: IR067
Agreement: Y
Docket:
NRC Notified By: John Martell
HQ OPS Officer: Tenisha Meadows
Notification Date: 11/13/2024
Notification Time: 21:09 [ET]
Event Date: 11/12/2024
Event Time: 13:00 [PST]
Last Update Date: 11/15/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Young, Cale (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Silberfeld, Dafna (NMSS)
Event Text
EN Revision Imported Date: 11/15/2024

EN Revision Text: AGREEMENT STATE REPORT - OVEREXPOSURE FROM RADIOGRAPHY SOURCE

The following information was provided by the Washington State Office of Radiation Protection (the Department) via email:

"Radiography was being performed in a tank at the refinery. [A radiation protection boundary was set up around a tank], and the source was secured in the exposure device. One radiographer was outside the boundary and the other radiographer was inside the boundary with another individual (contractor) outside of the tank. The contractor was in a lift moving upwards next to the tank. Unfortunately, due to a miscommunication between the radiographers and the contractor, the two individuals outside the tank and within the radiation boundaries were exposed to the source for 2 minutes.

"The licensee radiation safety officer (RSO) estimates 1.8 R radiation exposure for the 2 minutes duration right outside the tank as a worst-case scenario. The RSO is currently performing a dose investigation of the affected contract personnel and radiographer. The RSO recommended the contactor to receive medical monitoring (blood draw) as a precaution. The Department set expectations for the licensee to send a full detailed report on findings for this incident. More information to follow for this incident report."

Device information:
Isotope: 87 Ci of Ir-192
Manufacturer: QSA Global
Device Model: 880D

Incident number: WA-24-022

* * * UPDATE ON 11/14/2024 AT 1958 EDT FROM JOHN MARTELL TO TENISHA MEADOWS * * *

The following information was provided by the Washington State Office of Radiation Protection (the Department) via email:

"On 11/14/2024, inspectors from the Department will be conducting a reactive onsite visit of the overexposure event which occurred on 11/12/2024. The inspectors will be meeting at the refinery site where the overexposure occurred with the licensee representatives including the RSO to gather information on the event related to what and how the event occurred and to review related records.

"The Department staff will continue to gather information on the event to determine the extent of the exposures, the potential root cause of this incident, any correlation to previous incidents with this licensee, and appropriate corrective actions. This may include potential enforcement actions in addition to the corrective actions. Updates will be provided as additional information is received."

Notified R4DO (Young), NMSS MSST Deputy Division Director (Silberfeld), and NMSS (email)


Power Reactor
Event Number: 57424
Facility: Seabrook
Region: 1     State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Shaun Matthews
HQ OPS Officer: Bill Nytko
Notification Date: 11/14/2024
Notification Time: 10:58 [ET]
Event Date: 10/01/2024
Event Time: 07:38 [EST]
Last Update Date: 11/15/2024
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Lilliendahl, Jon (R1DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 99 Power Operation 100 Power Operation
Event Text
PART 21 - CONTROL RELAY DEFECT
The following information was provided by the licensee via phone and email:

"NextEra Energy Seabrook LLC. makes the following notification under 10 CFR 21.21(d)(3)(i) of a defect found in a GE - Hitachi Relay, CR120B (Model #DD945E118P0060) during pre-installation bench testing. During bench testing, the relay failed to energize and transfer all associated contacts. The relay was purchased from GE - Hitachi (GEH) as safety-related, GE CR-120B relays. All GE CR-120B relays that were purchased in the same batch as the failed relay were located and quarantined in order to be returned to GEH for forensic testing. NextEra Energy Seabrook, LLC has concluded that this defect constitutes a substantial safety hazard (SSH). A SSH exists because the nature of the defect was such that, if installed in certain safety-related applications and failed, it would have prevented the fulfillment of a safety function. On November 12, 2024, the Seabrook site Vice President was notified of the requirement to report this event under 10 CFR 21.21. This is a non-emergency notification required by 10 CFR 21.21(d)(3)(i). A written notification will be provided in accordance with 10 CFR 21.21(d)(3)(ii).

"Because the defect was discovered prior to installation, there was no impact to safety-related equipment.

"The NRC Senior Resident Inspector has been informed."