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Event Notification Report for September 06, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
09/05/2024 - 09/06/2024

EVENT NUMBERS
57297 57302 57304 57305
Non-Agreement State
Event Number: 57297
Rep Org: IRISNDT Services
Licensee: IRISNDT Services
Region: 3
City: Detroit   State: MI
County: Wayne
License #: 13-32791-01
Agreement: N
Docket:
NRC Notified By: Kyle Ledbetter
HQ OPS Officer: Josue Ramirez
Notification Date: 08/29/2024
Notification Time: 10:42 [ET]
Event Date: 08/28/2024
Event Time: 15:30 [EDT]
Last Update Date: 09/04/2024
Emergency Class: Non Emergency
10 CFR Section:
20.2202(b)(1) - Pers Overexposure/TEDE >= 5 Rem
Person (Organization):
Hills, David (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
UNABLE TO RETRACT RADIOGRAPHY CAMERA SOURCE

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

While performing industrial radiography at a refinery, equipment did not function properly and personnel were unable to return the source to the shielded position. Personnel contacted the radiation safety officer (RSO) and upon instruction were able to retrieve the source into the shielded position. Personnel red tagged the equipment and took it out of service. There was no overexposures to personnel.
Source is a Ir-192 (90 Ci) source.
NRC Region 3 and the National Response Center were notified.

National Response Center Incident report #: 1409302


Power Reactor
Event Number: 57302
Facility: Hope Creek
Region: 1     State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Brian Padworny
HQ OPS Officer: Nestor Makris
Notification Date: 09/04/2024
Notification Time: 14:31 [ET]
Event Date: 07/10/2024
Event Time: 09:02 [EDT]
Last Update Date: 09/04/2024
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
Ferdas, Marc (R1DO)
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
60-DAY OPTIONAL TELEPHONIC NOTIFICATION OF INVALID RESIDUAL HEAT REMOVAL ACTIVATION

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

"A 10 CFR 50.73(a)(1) invalid specified system actuation reported under 10 CFR 50.73(a)(2)(iv)(a) invalid actuation of residual heat removal (RHR).

"This 60-day telephone notification is being made per 10 CFR 50.73 (a)(2)(iv)(a) under the provision of 10 CFR 50.73 (a)(1) as an invalid actuation of the RHR. On July 10, 2024, while at 100 percent power, a partial train actuation of RHR was initiated by an invalid actuation signal while performing RHR valve logic testing.

"The cause for the RHR system logic actuation was due to improper configuration of an emergency core cooling system (ECCS) logic tester. The RHR system started and functioned as designed for the actuation signals it received from the ECCS logic tester.

"There was no impact on the health and safety of the public or plant personnel.

"The NRC resident inspector was notified."


Part 21
Event Number: 57304
Rep Org: Westinghouse Electric Company
Licensee:
Region: 1
City: Cranberry Township   State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Camille Zozula
HQ OPS Officer: Natalie Starfish
Notification Date: 09/04/2024
Notification Time: 18:51 [ET]
Event Date: 09/04/2024
Event Time: 19:09 [EDT]
Last Update Date: 09/04/2024
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Ferdas, Marc (R1DO)
Masters, Anthony (R2DO)
Hills, David (R3DO)
Part 21/50.55 Reactors, - (EMAIL)
Event Text
EN Revision Imported Date: 9/6/2024

EN Revision Text: PART 21 - STRESS CORROSION CRACKING IN CONTROL ROD BLADES

The following information was provided by Westinghouse Electric Company via phone and email:

This issue concerns the Westinghouse designed and manufactured CR99 and Trident X boiling water reactor (BWR) control rod blades (CRBs). The CR99 CRBs were designed with dimensional and material choices for mechanical stability such that the mechanical function is maintained throughout the life of the control rod. However, observed cracking at United States licensees, resulting from irradiation assisted stress corrosion cracking (IASCC), occurred before the nuclear end of life. Therefore, the current depletion limits that define nuclear end of life are not sufficient to prevent cracking, and the continued use of uninspected CRBs can lead to further cracking. With severe cracking of the CRBs, boron loss can occur and negatively impact the shutdown margin.

Westinghouse is aware that plants which experienced CRB cracking have been able to scram their cracked CRBs, safely shut down the reactor, and maintain it in a safe shutdown condition. Trident X CRBs are susceptible to IASCC and within the scope of this notification. However, the first Trident X CRBs were installed in a US operating plant earlier in 2024 and have operated for less than one cycle.

Westinghouse continues to communicate with impacted licensees and will issue plant-specific operating recommendations.

Operating Plants with Generation 2 and 3 CR99 CRBs
Brunswick Units 1 and 2, Dresden Unit 3, Hatch Units 1 and 2, Hope Creek, La Salle Unit 1, Nine Mile Point Unit 2, Quad Cities Unit 1, Susquehanna Units 1 and 2

Permanently Shutdown/Decommissioned Plants with Generation 2 and 3 CR99 CRBs
Duane Arnold

Operating Plants with Trident x CRBs
Brunswick Unit 1

Point of Contract:
Camille Zozula
Manager, Global Nuclear Regulatory Affairs
Westinghouse Electric Company LLC
412-374-2577
zozulact@westinghouse.com


Independent Spent Fuel Storage Installation
Event Number: 57305
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: Guadalupe Robles
HQ OPS Officer: Robert A. Thompson
Notification Date: 09/05/2024
Notification Time: 11:06 [ET]
Event Date: 09/05/2024
Event Time: 08:00 [PDT]
Last Update Date: 09/05/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Drake, James (R4DO)
Event Text
OFFSITE AGENCY NOTIFICATION OF LOW-LEVEL TRITIUM DETECTED IN GROUNDWATER

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

"On September 5, 2024, Southern California Edison reported, as a proactive measure, detectable levels of tritium in onsite groundwater wells to offsite government agencies. The tritium levels do not exceed reporting thresholds in the [Nuclear Energy Institute's] NEI 07-07 communication protocol, the offsite dose calculation manual (ODCM), nor the NRC regulations in 10 CFR Part 20. Offsite ocean water samples have not identified the presence of tritium above detectable levels. An investigation is currently ongoing to determine the source of tritium and determine mitigative actions, if any.

"This notification is being made solely as a four-hour, non-emergency notification for a notification of another government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi).

"There was no impact on the health and safety of the public or plant personnel."

The NRC regional inspector will be notified.