Event Notification Report for August 26, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
08/23/2024 - 08/26/2024

EVENT NUMBERS
57243 57272 57273 57284 57285
Part 21
Event Number: 57243
Rep Org: RSSC dba Marmon
Licensee:
Region: 1
City: East Granby   State: CT
County:
License #:
Agreement: N
Docket:
NRC Notified By: Phillip Sargenski
HQ OPS Officer: Adam Koziol
Notification Date: 07/25/2024
Notification Time: 11:05 [ET]
Event Date: 07/23/2024
Event Time: 00:00 [EDT]
Last Update Date: 08/23/2024
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Lilliendahl, Jon (R1DO)
Feliz-Adorno, Nestor (R3DO)
Azua, Ray (R4DO)
Event Text
EN Revision Imported Date: 8/26/2024

EN Revision Text: PART 21 REPORT - NON-COMPLIANT INSULATED CONDUCTOR

The following is a synopsis of information received via fax:

A reel of insulated conductor was found non-compliant due to failure of insulation tensile and elongation at break test following air oven aging. Wire from the non-compliant reel was delivered to nine plants.

Affected plants: Wolf Creek, Dresden, LaSalle, Limerick, Peach Bottom, Arkansas Nuclear One, Waterford, Susquehanna, and Davis Besse.

Reporting company point of contact:
RSSC Wire and Cable LLC
dba Marmon Industrial Energy and Infrastructure
20 Bradley Park Road
East Granby, CT 06026

Phillip Sargenski - Quality Assurance Manager
Phone: 860-653-8376
Fax: 860-653-8301
Phillip.sargenski@marmoniei.com


* * * UPDATE ON 08/23/24 AT 1315 EDT FROM PHILLIP SARGENSKI TO JOSUE RAMIREZ * * *

The vendor provided the final report for this event listing corrective actions and the estimated completion dates.

Notified R1DO (Lilliendahl), R3DO (Skokowski), R4DO (Vossmar), and Part 21 group (Email).


Agreement State
Event Number: 57272
Rep Org: PA Bureau of Radiation Protection
Licensee: Nondestructive & Visual Inspection
Region: 1
City: Eighty-Four   State: PA
County:
License #: PA-1413
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Natalie Starfish
Notification Date: 08/16/2024
Notification Time: 07:15 [ET]
Event Date: 07/31/2024
Event Time: 00:00 [EDT]
Last Update Date: 08/16/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Ford, Monica (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED RADIOGRAPHY CAMERA

The following was received from the Pennsylvania Bureau of Radiation Protection (the Department) via email:

"On August 15, 2024, the licensee notified the Department of a disabled device. It is reportable per 10 CFR 34.101(a)(2) and 30.50(b)(2).

"On July 31, 2024, the licensee reported damage to a QSA 880D (serial number D14778, source serial number FC2203), camera containing 38 curies of Ir-192. The licensee was on site performing weld inspections for a client. After the second exposure, the source did not return to the shielded position. The technicians on site called the radiation safety officer (RSO) and established a restricted area around the source. They also notified the client to keep their personnel away from the area. The RSO arrived on site and was able to retrieve the source. The licensee staff determined that the technicians on site did not receive any overexposure. The RSO received 451 mR during the source retrieval. The badges have been sent to Landauer for verification. The equipment was taken out of service for repair."

PA Event Report Identification Number: PA240017


Agreement State
Event Number: 57273
Rep Org: Virginia Rad Materials Program
Licensee: ECS Mid Atlantic LLC
Region: 1
City: Fairfax   State: VA
County: Fairfax
License #: 107-314-1
Agreement: Y
Docket:
NRC Notified By: Sheila Nelson
HQ OPS Officer: Sam Colvard
Notification Date: 08/16/2024
Notification Time: 16:37 [ET]
Event Date: 08/16/2024
Event Time: 09:00 [EDT]
Last Update Date: 08/23/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Ford, Monica (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
EN Revision Imported Date: 8/26/2024

EN Revision Text: AGREEMENT STATE REPORT - POSSIBLE DAMAGED PORTABLE GAUGE

The following information was provided by the Virginia Department of Health, Office of Radiologic Health (RMP) via email:

"At approximately 1100 EDT on 8/16/2024, RMP was notified of an incident involving a portable nuclear gauge. At approximately 0900, at a deep trench construction site in Fairfax, a CPN International gauge model MC-1, containing 10 mCi Cs-137 and 50 mCi Am-241, was dropped approximately 15 feet when a rope pulley system slipped. The authorized user notified the radiation safety officer (RSO) who arrived on site and then they notified the RMP.

"Per the RSO, the gauge fell onto dirt at the bottom of a trench. The device landed flat onto the base of the gauge. The gauge functions and is operational. The rod handle was retracted and locked at the time, and the source remained retracted in the shielded position. The RSO obtained survey readings of 0.4 mR/h at 1 meter from the gauge. The gauge was placed in its transportation box, secured in the back of a pickup truck, and transported back to the licensee's office for secure storage. A leak test was obtained and analysis indicates there is no leakage. The gauge will be sent for assessment by an authorized dealer.

"RMP will follow up with an investigation."

Event Report ID No.: VA240004

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: 57284
Facility: Wolf Creek
Region: 4     State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Alex Meyer
HQ OPS Officer: Sam Colvard
Notification Date: 08/23/2024
Notification Time: 09:02 [ET]
Event Date: 08/23/2024
Event Time: 08:00 [CDT]
Last Update Date: 08/23/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By TS
Person (Organization):
Vossmar, Patricia (R4DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 98 Power Operation 98 Power Operation
Event Text
SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS

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

"At 0500 CDT on 8/23/24, Wolf Creek entered technical specification limiting condition for operation (LCO) 3.7.5 required action D.1 which requires shutdown to mode 3 within 6 hours. The turbine driven auxiliary feedwater pump discharge valve to the 'B' steam generator was not successfully restored to operable prior to expiration of the 72 hour completion time. At 0800 CDT, the shutdown to mode 3 was initiated, which is being reported in accordance with 10CFR50.72(b)(2)(i)."

The NRC Resident Inspector has been notified.


Power Reactor
Event Number: 57285
Facility: Sequoyah
Region: 2     State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Timothy Wood
HQ OPS Officer: Josue Ramirez
Notification Date: 08/23/2024
Notification Time: 13:44 [ET]
Event Date: 08/23/2024
Event Time: 12:19 [EDT]
Last Update Date: 08/23/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Masters, Anthony (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR TRIP

The following information was provided by the licensee via email:

"At 1219 EDT, with unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex, with all systems responding normally post-trip.
"Operations responded and stabilized the plant. Decay heat is being removed by the auxiliary feedwater (AFW) and steam dump systems. Unit 2 is currently in a refueling outage (U2R26) and was 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) and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system. The AFW system started automatically and is operating as designed.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."