Event Notification Report for December 06, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/05/2024 - 12/06/2024
Power Reactor
Event Number: 57453
Facility: Turkey Point
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Arturo Alvarez
HQ OPS Officer: Jon Lilliendahl
Region: 2 State: FL
Unit: [3] [] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: Arturo Alvarez
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/04/2024
Notification Time: 13:24 [ET]
Event Date: 12/04/2024
Event Time: 10:33 [EST]
Last Update Date: 12/04/2024
Notification Time: 13:24 [ET]
Event Date: 12/04/2024
Event Time: 10:33 [EST]
Last Update Date: 12/04/2024
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical 50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Suber, Gregory (R2DO)
Suber, Gregory (R2DO)
Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
---|---|---|---|---|---|---|
3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP
The following information was provided by the licensee via phone or email:
"At 1033 EST on December 4, 2024, with Unit 3 in mode 1 at 100% power, the reactor automatically tripped in response to a reactor protection system channel failure while planned maintenance was in progress on a redundant channel. The plant is currently in mode 3. Decay heat is being removed by steam dumps to atmosphere. Unit 4 is unaffected. An actuation of the auxiliary feedwater system occurred and started as designed. An actuation of the emergency core cooling system (ECCS) occurred and started as designed. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B), and 10 CFR 50.72(b)(3)(iv)(A).
"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 ECCS actuation included safety injection, residual heat removal, and emergency containment cooling. The cause of the trip and the ECCS actuation are under investigation. There are no indications of primary to secondary leakage.
The following information was provided by the licensee via phone or email:
"At 1033 EST on December 4, 2024, with Unit 3 in mode 1 at 100% power, the reactor automatically tripped in response to a reactor protection system channel failure while planned maintenance was in progress on a redundant channel. The plant is currently in mode 3. Decay heat is being removed by steam dumps to atmosphere. Unit 4 is unaffected. An actuation of the auxiliary feedwater system occurred and started as designed. An actuation of the emergency core cooling system (ECCS) occurred and started as designed. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B), and 10 CFR 50.72(b)(3)(iv)(A).
"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 ECCS actuation included safety injection, residual heat removal, and emergency containment cooling. The cause of the trip and the ECCS actuation are under investigation. There are no indications of primary to secondary leakage.
Power Reactor
Event Number: 57454
Facility: Brunswick
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Chris Denton
HQ OPS Officer: Jon Lilliendahl
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Chris Denton
HQ OPS Officer: Jon Lilliendahl
Notification Date: 12/04/2024
Notification Time: 19:01 [ET]
Event Date: 12/04/2024
Event Time: 16:40 [EST]
Last Update Date: 12/04/2024
Notification Time: 19:01 [ET]
Event Date: 12/04/2024
Event Time: 16:40 [EST]
Last Update Date: 12/04/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
10 CFR Section:
50.72(b)(3)(v)(C) - Pot Uncntrl Rad Rel
Person (Organization):
Suber, Gregory (R2DO)
Suber, Gregory (R2DO)
Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
---|---|---|---|---|---|---|
1 | N | Y | 100 | Power Operation | 100 | Power Operation |
SECONDARY CONTAINMENT INOPERABLE
The following information was provided by the licensee via phone and email:
"At 1640 EST, on December 4, 2024, secondary containment was declared inoperable. This condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(C), as an event or condition that could have prevented fulfillment of a safety function.
"Secondary containment was declared inoperable due to a small hole discovered in the service water piping within secondary containment. The effective safety function was restored at 1730 EST by installation of a temporary repair and secondary containment has been restored to operable.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
Notified R2DO (Suber)
The following information was provided by the licensee via phone and email:
"At 1640 EST, on December 4, 2024, secondary containment was declared inoperable. This condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(C), as an event or condition that could have prevented fulfillment of a safety function.
"Secondary containment was declared inoperable due to a small hole discovered in the service water piping within secondary containment. The effective safety function was restored at 1730 EST by installation of a temporary repair and secondary containment has been restored to operable.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
Notified R2DO (Suber)
Agreement State
Event Number: 57450
Rep Org: Illinois Emergency Mgmt. Agency
Licensee: Advocate Christ Hospital
Region: 3
City: Oak Lawn State: IL
County:
License #: IL-01720-01
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Tenisha Meadows
Licensee: Advocate Christ Hospital
Region: 3
City: Oak Lawn State: IL
County:
License #: IL-01720-01
Agreement: Y
Docket:
NRC Notified By: Gary Forsee
HQ OPS Officer: Tenisha Meadows
Notification Date: 12/02/2024
Notification Time: 16:26 [ET]
Event Date: 12/02/2024
Event Time: 00:00 [CST]
Last Update Date: 12/02/2024
Notification Time: 16:26 [ET]
Event Date: 12/02/2024
Event Time: 00:00 [CST]
Last Update Date: 12/02/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Learn, Matthew (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Learn, Matthew (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE - SOURCE FAILED TO RETRACT
The following information was provided by the Illinois Emergency Management Agency (the Agency) via email and phone:
"The Agency was contacted on 12/2/24 by radiation oncology staff at Advocate Christ Hospital to advise a 4.3 Ci Ir-192 source for a high dose rate afterloader (HDR) was stuck in the exposed position. The source was extended for daily quality assurance checks and is within a shielded vault. There were no staff or patient exposures. The manufacturer has been contacted to dispatch a service technician to the site and is expected 12/3/24. Agency staff conducted a reactive inspection on 12/2/24 to verify public exposure rates were within limits, verify adequate room security could be maintained, and determine the resources made available by the licensee to prevent any radiation exposures. After investigation, inspectors found the licensee had effectively restricted access by installing a secondary key-pad controlled door outside the vault door. Appropriate signage had been installed and survey readings in all areas were confirmed to be below public exposure limits (max 40 microrem per hour). The fault appears to be electrical and updates will be provided once obtained from Varian staff."
Equipment information:
Device name: Remote afterloader HDR
Model number: GammaMed Plus iX
Serial number: H641313
Manufacturer: Varian
Illinois item number: IL240030
The following information was provided by the Illinois Emergency Management Agency (the Agency) via email and phone:
"The Agency was contacted on 12/2/24 by radiation oncology staff at Advocate Christ Hospital to advise a 4.3 Ci Ir-192 source for a high dose rate afterloader (HDR) was stuck in the exposed position. The source was extended for daily quality assurance checks and is within a shielded vault. There were no staff or patient exposures. The manufacturer has been contacted to dispatch a service technician to the site and is expected 12/3/24. Agency staff conducted a reactive inspection on 12/2/24 to verify public exposure rates were within limits, verify adequate room security could be maintained, and determine the resources made available by the licensee to prevent any radiation exposures. After investigation, inspectors found the licensee had effectively restricted access by installing a secondary key-pad controlled door outside the vault door. Appropriate signage had been installed and survey readings in all areas were confirmed to be below public exposure limits (max 40 microrem per hour). The fault appears to be electrical and updates will be provided once obtained from Varian staff."
Equipment information:
Device name: Remote afterloader HDR
Model number: GammaMed Plus iX
Serial number: H641313
Manufacturer: Varian
Illinois item number: IL240030
Power Reactor
Event Number: 57459
Facility: Brunswick
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Jason Wiley
HQ OPS Officer: Karen Cotton-Gross
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Jason Wiley
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 12/06/2024
Notification Time: 17:00 [ET]
Event Date: 12/05/2024
Event Time: 23:58 [EST]
Last Update Date: 12/06/2024
Notification Time: 17:00 [ET]
Event Date: 12/05/2024
Event Time: 23:58 [EST]
Last Update Date: 12/06/2024
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Suber, Gregory (R2DO)
Suber, Gregory (R2DO)
Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
---|---|---|---|---|---|---|
1 | N | Y | 100 | Power Operation | 100 | Power Operation |
2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE
The following information was provided by the licensee via phone and email:
"At 2358 Eastern Standard Time (EST) on December 5, 2024, emergency diesel generator (EDG) '1' was declared inoperable due to a failure in the standby lube oil temperature control circuit. At this time, EDG '2' was already inoperable due to failure of a relay in the starting air circuity. As a result, both EDGs were simultaneously inoperable; therefore, this condition is being reported as a non-emergency notification per 10 CFR 50.72(b)(3)(v)(D), as an event or condition that could have prevented fulfillment of a safety function.
"Offsite power, EDG '3', and EDG '4' were operable during the entire time period that EDGs '1' and '2' were inoperable. The effective safety function was restored at time 0148 on December 6, 2024, when lube oil temperature was restored and EDG '1' was declared operable. EDG '1' was inoperable concurrently with EDG '2' for approximately 1 hour and 50 minutes.
"There was no impact on the health and safety of the public or plant personnel.
"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 inoperability of two EDGs placed the plant in LCO 3.8.1.
The following information was provided by the licensee via phone and email:
"At 2358 Eastern Standard Time (EST) on December 5, 2024, emergency diesel generator (EDG) '1' was declared inoperable due to a failure in the standby lube oil temperature control circuit. At this time, EDG '2' was already inoperable due to failure of a relay in the starting air circuity. As a result, both EDGs were simultaneously inoperable; therefore, this condition is being reported as a non-emergency notification per 10 CFR 50.72(b)(3)(v)(D), as an event or condition that could have prevented fulfillment of a safety function.
"Offsite power, EDG '3', and EDG '4' were operable during the entire time period that EDGs '1' and '2' were inoperable. The effective safety function was restored at time 0148 on December 6, 2024, when lube oil temperature was restored and EDG '1' was declared operable. EDG '1' was inoperable concurrently with EDG '2' for approximately 1 hour and 50 minutes.
"There was no impact on the health and safety of the public or plant personnel.
"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 inoperability of two EDGs placed the plant in LCO 3.8.1.