Event Notification Report for November 07, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/06/2023 - 11/07/2023
Power Reactor
Event Number: 56838
Facility: Seabrook
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Ed Kotkowski
HQ OPS Officer: Karen Cotton-Gross
Region: 1 State: NH
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Ed Kotkowski
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 11/07/2023
Notification Time: 18:18 [ET]
Event Date: 11/07/2023
Event Time: 12:00 [EST]
Last Update Date: 11/08/2023
Notification Time: 18:18 [ET]
Event Date: 11/07/2023
Event Time: 12:00 [EST]
Last Update Date: 11/08/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(B) - Pot RHR Inop
10 CFR Section:
50.72(b)(3)(v)(B) - Pot RHR Inop
Person (Organization):
Eve, Elise (R1DO)
Eve, Elise (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 11/9/2023
EN Revision Text: AUXILIARY FEEDWATER SYSTEM INOPERABLE
The following information was provided by the licensee via email:
"On November 07, 2023 at 1200 EST, it was discovered that all pumps in the Auxiliary Feedwater system were inoperable due to the loss of control power to the 'B' train Emergency Feedwater (EFW) flow control valve which supplies the 'D' steam generator. The redundant 'A' train EFW control valve for the 'D' steam generator remains functional, as well as the capability of the Auxiliary Feedwater system to supply all steam generators.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(B).
"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 'A' and 'B' EFW Flow Control Valves are arranged in a series configuration for each Steam Generator. Failure of any of the 8 EFW Flow Control Valves to meet its Surveillance Requirements will render all EFW
Pumps inoperable per tech specs."
EN Revision Text: AUXILIARY FEEDWATER SYSTEM INOPERABLE
The following information was provided by the licensee via email:
"On November 07, 2023 at 1200 EST, it was discovered that all pumps in the Auxiliary Feedwater system were inoperable due to the loss of control power to the 'B' train Emergency Feedwater (EFW) flow control valve which supplies the 'D' steam generator. The redundant 'A' train EFW control valve for the 'D' steam generator remains functional, as well as the capability of the Auxiliary Feedwater system to supply all steam generators.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(B).
"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 'A' and 'B' EFW Flow Control Valves are arranged in a series configuration for each Steam Generator. Failure of any of the 8 EFW Flow Control Valves to meet its Surveillance Requirements will render all EFW
Pumps inoperable per tech specs."
Power Reactor
Event Number: 56839
Facility: Calvert Cliffs
Region: 1 State: MD
Unit: [2] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Ervin Lyson
HQ OPS Officer: Sam Colvard
Region: 1 State: MD
Unit: [2] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Ervin Lyson
HQ OPS Officer: Sam Colvard
Notification Date: 11/07/2023
Notification Time: 18:42 [ET]
Event Date: 11/07/2023
Event Time: 16:17 [EST]
Last Update Date: 11/07/2023
Notification Time: 18:42 [ET]
Event Date: 11/07/2023
Event Time: 16:17 [EST]
Last Update Date: 11/07/2023
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):
Eve, Elise (R1DO)
Eve, Elise (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR TRIP DUE TO NON-SAFETY RELATED BUS UNDER VOLTAGE
The following information was provided by the licensee via email:
"At 1617 on 11/7/2023, Calvert Cliffs Unit 2 experienced an automatic trip from a Reactor Protection System (RPS) based on reactor trip bus under voltage (UV). At that time a loss of U-4000-22 caused a loss of 22, 23, and 24 4kV busses. This resulted in a loss of both motor generator (MG) sets causing the reactor trip bus UV condition. The loss of 22 and 23 4kV non-safety related busses resulted in a loss of main feedwater. Auxiliary feedwater (AFW) was manually initiated and is feeding both steam generators. The 2B diesel generator (DG) started and restored the 24 4kV safety related bus. Heat removal is via the normal turbine bypass valves to the main condenser.
"RPS actuation is reportable under 10 CFR 50.72(b)(2)(iv)(B) - 4-hour report.
"ESFAS actuation (2B DG start on UV) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"ESFAS actuation (AFW manual initiation) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"Site Senior NRC resident inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Unit 1 was unaffected. Estimation of duration of shutdown is 24 hours.
The following information was provided by the licensee via email:
"At 1617 on 11/7/2023, Calvert Cliffs Unit 2 experienced an automatic trip from a Reactor Protection System (RPS) based on reactor trip bus under voltage (UV). At that time a loss of U-4000-22 caused a loss of 22, 23, and 24 4kV busses. This resulted in a loss of both motor generator (MG) sets causing the reactor trip bus UV condition. The loss of 22 and 23 4kV non-safety related busses resulted in a loss of main feedwater. Auxiliary feedwater (AFW) was manually initiated and is feeding both steam generators. The 2B diesel generator (DG) started and restored the 24 4kV safety related bus. Heat removal is via the normal turbine bypass valves to the main condenser.
"RPS actuation is reportable under 10 CFR 50.72(b)(2)(iv)(B) - 4-hour report.
"ESFAS actuation (2B DG start on UV) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"ESFAS actuation (AFW manual initiation) is reportable under 10CFR50.72(b)(3)(iv)(A) - 8-hour report.
"Site Senior NRC resident inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Unit 1 was unaffected. Estimation of duration of shutdown is 24 hours.
Agreement State
Event Number: 56837
Rep Org: Florida Bureau of Radiation Control
Licensee: Environmental Safety Consultant Florida, LLC
Region: 1
City: Fort Myers State: FL
County:
License #: 3440-6
Agreement: Y
Docket:
NRC Notified By: Mark Seidensticker
HQ OPS Officer: Karen Cotton-Gross
Licensee: Environmental Safety Consultant Florida, LLC
Region: 1
City: Fort Myers State: FL
County:
License #: 3440-6
Agreement: Y
Docket:
NRC Notified By: Mark Seidensticker
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 11/07/2023
Notification Time: 12:46 [ET]
Event Date: 11/07/2023
Event Time: 11:30 [EST]
Last Update Date: 11/07/2023
Notification Time: 12:46 [ET]
Event Date: 11/07/2023
Event Time: 11:30 [EST]
Last Update Date: 11/07/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Eve, Elise (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Eve, Elise (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following information was provided by the Florida Bureau of Radiation Control (BRC) via email:
A Radiation Safety Officer (RSO) with Environmental Safety Consultant (ESC) Florida, LLC called BRC in Orlando on November 7, 2023, at 1150 EST to report a soil moisture density gauge (Model: Instro Tek Xplorer 3500, 8 mCi Cs-137, 40 mCi Am-241:Be) was run over on a job site around 1130 this morning. The RSO indicated that the source rod was retracted when the incident occurred. An inspector was sent to investigate.
Florida Event Number: FL23-161
The following information was provided by the Florida Bureau of Radiation Control (BRC) via email:
A Radiation Safety Officer (RSO) with Environmental Safety Consultant (ESC) Florida, LLC called BRC in Orlando on November 7, 2023, at 1150 EST to report a soil moisture density gauge (Model: Instro Tek Xplorer 3500, 8 mCi Cs-137, 40 mCi Am-241:Be) was run over on a job site around 1130 this morning. The RSO indicated that the source rod was retracted when the incident occurred. An inspector was sent to investigate.
Florida Event Number: FL23-161