Event Notification Report for December 15, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/14/2023 - 12/15/2023
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Non-Agreement State
Event Number: 56892
Rep Org: JAN X-Ray Services, Inc.
Licensee: JAN X-Ray Services, Inc.
Region: 3
City: Parma State: MI
County:
License #: 21-16560-01
Agreement: N
Docket:
NRC Notified By: James Maramba
HQ OPS Officer: Thomas Herrity
Licensee: JAN X-Ray Services, Inc.
Region: 3
City: Parma State: MI
County:
License #: 21-16560-01
Agreement: N
Docket:
NRC Notified By: James Maramba
HQ OPS Officer: Thomas Herrity
Notification Date: 12/15/2023
Notification Time: 16:16 [ET]
Event Date: 12/15/2023
Event Time: 06:52 [EST]
Last Update Date: 01/12/2024
Notification Time: 16:16 [ET]
Event Date: 12/15/2023
Event Time: 06:52 [EST]
Last Update Date: 01/12/2024
Emergency Class: Non Emergency
10 CFR Section:
20.2202(b)(1) - Pers Overexposure/TEDE >= 5 Rem
10 CFR Section:
20.2202(b)(1) - Pers Overexposure/TEDE >= 5 Rem
Person (Organization):
McCraw, Aaron (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
McCraw, Aaron (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
EN Revision Imported Date: 1/16/2024
EN Revision Text: NON-AGREEMENT STATE - POSSIBLE EXPOSURE ABOVE LIMIT (TEDE > 5 rem)
The following is a synopsis of information provided by the licensee via phone call:
On December 15, 2023, at 0652 EST, JAN X-ray Services received notification from the laboratory performing regularly scheduled analysis of their employee's thermoluminescent dosimeters (TLDs) that one of the units is indicating an employee received a dose of 5.729 rem. The limit is 5.0 rem. The worker is not normally involved in radiography. The licensee is investigating how the employee received the indicated dose.
* * * RETRACTION ON 01/12/24 AT 0934 EST FROM JAMES MARAMBA TO KERBY SCALES * * *
The following retraction is a summary of information provided by the licensee via email:
JAN X-Ray Services requested the event be retracted based on findings that indicated that the exposure was to whole-body monitoring badge and not the individual.
Notified R3DO (Szwarc) and NMSS Event Notifications via email.
EN Revision Text: NON-AGREEMENT STATE - POSSIBLE EXPOSURE ABOVE LIMIT (TEDE > 5 rem)
The following is a synopsis of information provided by the licensee via phone call:
On December 15, 2023, at 0652 EST, JAN X-ray Services received notification from the laboratory performing regularly scheduled analysis of their employee's thermoluminescent dosimeters (TLDs) that one of the units is indicating an employee received a dose of 5.729 rem. The limit is 5.0 rem. The worker is not normally involved in radiography. The licensee is investigating how the employee received the indicated dose.
* * * RETRACTION ON 01/12/24 AT 0934 EST FROM JAMES MARAMBA TO KERBY SCALES * * *
The following retraction is a summary of information provided by the licensee via email:
JAN X-Ray Services requested the event be retracted based on findings that indicated that the exposure was to whole-body monitoring badge and not the individual.
Notified R3DO (Szwarc) and NMSS Event Notifications via email.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Non-Power Reactor
Event Number: 56898
Rep Org: Texas A&M University (TAMN)
Licensee: Texas A&M University
Region: 0
City: College Station State: TX
County: Brazos
License #: R-83
Agreement: Y
Docket: 05000128
NRC Notified By: Jere Jenkins
HQ OPS Officer: Natalie Starfish
Licensee: Texas A&M University
Region: 0
City: College Station State: TX
County: Brazos
License #: R-83
Agreement: Y
Docket: 05000128
NRC Notified By: Jere Jenkins
HQ OPS Officer: Natalie Starfish
Notification Date: 12/19/2023
Notification Time: 16:15 [ET]
Event Date: 12/15/2023
Event Time: 11:00 [CST]
Last Update Date: 12/15/2024
Notification Time: 16:15 [ET]
Event Date: 12/15/2023
Event Time: 11:00 [CST]
Last Update Date: 12/15/2024
Emergency Class: Non Emergency
10 CFR Section:
10 CFR Section:
Person (Organization):
Holly Cruz (NRR)
Andrew Waugh (NRR)
Holly Cruz (NRR)
Andrew Waugh (NRR)
EN Revision Imported Date: 12/16/2024
EN Revision Text: TECHNICAL SPECIFICATIONS VIOLATION
The following information was provided by the licensee via phone and email:
"At approximately 1100 CST on December 15, 2023, the facility was discovered to be in violation of a Limiting Condition of Operation (LCO) according to Technical Specification 3.3.2.2, which requires that the static pressure measurement in the confinement exhaust system measure -0.1 inches of water or less during operation. It was discovered that this plant variable was not tied to the PANALARM trip for 'Building Pressure', nor was the sensor output value available in the control room to be checked by operators. The PANALARM trip for 'Building Pressure' was set to a different variable not related to the LCO required value. This condition has existed since 2006.
"The reactor was not in operation at the time of the discovery, and the situation creating this LCO violation is being corrected prior to the next reactor startup."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The issue was discovered by the vendor when a controller board was being replaced after damage from a power outage.
* * * RETRACTION ON 12/15/2024 AT 2233 EST FROM JERE JENKINS TO IAN HOWARD * * *
The following information was provided by the licensee via email:
"This event report is hereby withdrawn. The reactor was not operated in contravention with the LCO. The confinement pressure was maintained."
Notified NRR (Boyle) and NRR (Waugh)
EN Revision Text: TECHNICAL SPECIFICATIONS VIOLATION
The following information was provided by the licensee via phone and email:
"At approximately 1100 CST on December 15, 2023, the facility was discovered to be in violation of a Limiting Condition of Operation (LCO) according to Technical Specification 3.3.2.2, which requires that the static pressure measurement in the confinement exhaust system measure -0.1 inches of water or less during operation. It was discovered that this plant variable was not tied to the PANALARM trip for 'Building Pressure', nor was the sensor output value available in the control room to be checked by operators. The PANALARM trip for 'Building Pressure' was set to a different variable not related to the LCO required value. This condition has existed since 2006.
"The reactor was not in operation at the time of the discovery, and the situation creating this LCO violation is being corrected prior to the next reactor startup."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The issue was discovered by the vendor when a controller board was being replaced after damage from a power outage.
* * * RETRACTION ON 12/15/2024 AT 2233 EST FROM JERE JENKINS TO IAN HOWARD * * *
The following information was provided by the licensee via email:
"This event report is hereby withdrawn. The reactor was not operated in contravention with the LCO. The confinement pressure was maintained."
Notified NRR (Boyle) and NRR (Waugh)
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
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
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
10 CFR Section:
50.72(b)(3)(ii)(A) - Degraded Condition 50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Standby | 0 | Hot Shutdown |
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).
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).