Event Notification Report for February 13, 2024

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/12/2024 - 02/13/2024

EVENT NUMBERS
56893 56912 56948 56949 56959
Power Reactor
Event Number: 56893
Facility: Saint Lucie
Region: 2     State: FL
Unit: [2] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Eric Laettner
HQ OPS Officer: Dan Livermore
Notification Date: 12/16/2023
Notification Time: 04:04 [ET]
Event Date: 12/15/2023
Event Time: 20:45 [EST]
Last Update Date: 02/12/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Miller, Mark (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Standby 0 Hot Shutdown
Event Text
EN Revision Imported Date: 2/13/2024

EN Revision Text: REACTOR COOLANT SYSTEM LEAK

"At 2045 EST on December 15, 2023, it was determined that the reactor coolant system barrier had a through wall flaw with leakage. The leakage is minor in nature and unquantifiable. The leakage is coming from the welded connection of a vent valve for safety injection tank 2A2 outlet valve rendering both trains of high-pressure safety injection inoperable. The unit is being cooled down to cold shutdown to comply with technical specifications.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(3)(v)(D).

"The NRC Resident Inspector has been notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The unit was heating up after a maintenance outage. The leak was discovered during mode 3 walkdown.

* * *UPDATE AT 1254 EST ON 02/12/24 FROM B. MURRELL TO T. HERRITY***

"The purpose of this notification update is to retract a portion of a previous report, made on 12/16/2023 at 0404 EST (EN 56893). Notification of the event to the NRC was initially made as a result of declaring both trains of unit 2 high pressure safety injection system inoperable due to reactor coolant barrier through wall leak on the vent line for the 2A2 safety injection tank.

"Subsequent to the initial report, Florida Power and Light has concluded that the through wall leak rate was insignificant, and therefore the safety injection system's safety-related function was maintained.

"Therefore, this portion of the event is not considered a safety system functional failure and is not reportable to the NRC pursuant 10 CFR 50.72(3)(v)(D).

"This update does not affect the original 10 CFR 50.72(b)(3)(ii)(A) report for the degraded condition related to the reactor coolant barrier through wall leak.

"The NRC Resident Inspector has been notified."

Notified R2DO (Miller).


Power Reactor
Event Number: 56912
Facility: Saint Lucie
Region: 2     State: FL
Unit: [2] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Eric Laettner
HQ OPS Officer: Brian Parks
Notification Date: 01/03/2024
Notification Time: 15:38 [ET]
Event Date: 01/03/2024
Event Time: 12:57 [EST]
Last Update Date: 02/12/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Miller, Mark (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Power Operation 0 Power Operation
Event Text
EN Revision Imported Date: 2/13/2024

EN Revision Text: PRESSURE BOUNDARY DEGRADED / BOTH TRAINS OF HIGH PRESSURE SAFETY INJECTION INOPERABLE

"At 1257 EST on January 3, 2024, it was determined that a class 1 system barrier had a through wall flaw with leakage. The leakage renders both trains of high pressure safety injection inoperable. The unit is being cooled down to cold shutdown to comply with technical specifications.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(A) and 10 CFR 50.72(b)(3)(v)(D).

"The NRC Resident Inspector has been notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officer Report Guidance:

At the time of the discovery, the unit was shutdown in mode 3. The unit was experiencing signs of reactor coolant system leakage and a shutdown was initiated in order to search for possible sources. The unit is currently cooling down and proceeding to mode 5, where the safety function is not required.

* * *UPDATE AT 1257 EST ON 02/12/24 FROM B. MURRELL TO T. HERRITY***

"The purpose of this notification update is to retract a portion of a previous report, made on 1/03/2024 at 1257 EST (EN 56912). Notification of the event to the NRC was initially made as a result of declaring both trains of unit 2 high pressure safety injection system inoperable due to reactor coolant barrier through wall leak on the vent line for the 2A2 safety injection tank.

"Subsequent to the initial report, Florida Power and Light has concluded that the through wall leak rate was insignificant, and therefore the safety injection system's safety-related function was maintained.

"Therefore, this portion of the event is not considered a safety system functional failure and is not reportable to the NRC pursuant 10 CFR 50.72(3)(v)(D).

"This update does not affect the original 10 CFR 50.72(b)(3)(ii)(A) report for the degraded condition related to the reactor coolant barrier through wall leak.

"The NRC Resident Inspector has been notified."

Notified R2DO (Miller).


Agreement State
Event Number: 56948
Rep Org: Tennessee Div of Rad Health
Licensee: Diversified Scientific Services Inc
Region: 1
City: Nashville   State: TN
County:
License #: R-73014
Agreement: Y
Docket:
NRC Notified By: Andrew Holcomb
HQ OPS Officer: Kerby Scales
Notification Date: 02/05/2024
Notification Time: 20:26 [ET]
Event Date: 02/05/2024
Event Time: 15:36 [EST]
Last Update Date: 02/05/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Lilliendahl, Jon (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Miller, Mark (R2DO)
Crouch, Howard (IR)
Clark, Theresa (MSST DD)
Event Text
AGREEMENT STATE REPORT - FIRE DAMAGED MATERIAL

The following is a summary of information received from the Tennessee Division of Radiological Health via email:

A fire on a truck involving a super sack containing low level waste consisting mostly of personal protective equipment and other small items occurred on Interstate 40 in Nashville. The licensee believes there may have been batteries in the sack that could have caused the fire. With the fire out there were no airborne or exposure hazards associated with the material involved. The exposure rates at the trailer were approximately 15 microR/hr. The licensee has dispatched health physicists and a truck with overpack materials to re-pack the load for transport back to their facility in Oak Ridge. No personnel exposures were reported.

Tennessee Event Report Identification Number: TN-24-015
National Response Center Incident Report Number: 1390886


Agreement State
Event Number: 56949
Rep Org: Virginia Rad Materials Program
Licensee: Global Geotechnical Consultants, LLC.
Region: 1
City: Spotsylvania   State: VA
County:
License #: 153-619-1
Agreement: Y
Docket:
NRC Notified By: Sheila Nelson
HQ OPS Officer: Natalie Starfish
Notification Date: 02/06/2024
Notification Time: 18:23 [ET]
Event Date: 02/06/2024
Event Time: 00:00 [EST]
Last Update Date: 02/06/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Lilliendahl, Jon (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Event Text
AGREEMENT STATE REPORT - DAMAGED GAUGE

The following information was provided by the Virginia Office of Radiological Health via email:

"At approximately 0730 EST on 2/06/24, VA Office of Radiological Health was notified by phone of a traffic incident involving a portable nuclear gauge. This was reported by the Assistant Chief of the Spotsylvania County Hazmat, the on-scene incident command, who had secured the scene and gauge. Earlier this morning (exact time unknown at this point), a Troxler gauge Model 3440 Plus, in its transportation box, containing an 8 mCi Cs-137 source, reportedly fell from a truck, presumably unknown to the driver, and was struck by a tractor trailer truck and possibly other vehicles. This occurred at or near the intersection of Plank Road and Eley Ford Road in Spotsylvania, VA. There was damage to the transport box and plastic housing of the gauge. VA Department of Emergency Management Division 7 arrived on scene and conducted radiation surveys. Per the Assistant Chief of the Spotsylvania County Hazmat, there were no readings above background indicating the source was most likely still in its shielded position; so, no radiation exposures occurred. He also reported there had been no injuries to any individuals during the incident, only vehicle damage. The licensee/owner of the gauge was contacted, and they retrieved the gauge.

"The licensee contacted the VA Office of Radiological Health at 0830 EST indicating they were en route to acquire the gauge. The licensee later confirmed the damaged gauge was secure at the storage location, the source was in the shielded position, and all survey readings were at background. The licensee indicated that the gauge electronics were damaged, and it will be sent to the manufacture for evaluation.

"The Radioactive Materials Program will follow up with an investigation."

Virginia Event Report ID: VA240001


Power Reactor
Event Number: 56959
Facility: Hatch
Region: 2     State: GA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Kenneth Hunter
HQ OPS Officer: Natalie Starfish
Notification Date: 02/11/2024
Notification Time: 11:38 [ET]
Event Date: 02/11/2024
Event Time: 10:11 [EST]
Last Update Date: 02/11/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition
Person (Organization):
Miller, Mark (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
Event Text
PRIMARY CONTAINMENT DEGRADED

The following information was provided by the licensee via email:

"At 1011 EST on 02/11/2024, during a refueling outage at 0 percent power, while performing local leakage rate testing (LLRT) of the feedwater check valves [part of the containment boundary], it was determined that the Unit 1 primary containment leakage rate did not meet 10 CFR 50 Appendix J requirements specified in Technical Specification 5.5.12. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).

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

"The NRC Resident Inspector has been notified. "