Event Notification Report for March 03, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/02/2024 - 03/03/2024
Agreement State
Event Number: 57005
Rep Org: Louisiana Radiation Protection Div
Licensee:
Region: 4
City: Baton Rouge State: LA
County:
License #: Unknown
Agreement: Y
Docket:
NRC Notified By: James Pate
HQ OPS Officer: Bill Gott
Licensee:
Region: 4
City: Baton Rouge State: LA
County:
License #: Unknown
Agreement: Y
Docket:
NRC Notified By: James Pate
HQ OPS Officer: Bill Gott
Notification Date: 03/04/2024
Notification Time: 10:25 [ET]
Event Date: 03/03/2024
Event Time: 21:52 [CST]
Last Update Date: 03/04/2024
Notification Time: 10:25 [ET]
Event Date: 03/03/2024
Event Time: 21:52 [CST]
Last Update Date: 03/04/2024
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
Gaddy, Vincent (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB, (EMAIL) (EMAIL)
AGREEMENT STATE REPORT - LOST SOURCE FOUND
The following is a summary of the information provided by the Louisiana Department of Environmental Quality (LDEQ) via email:
At 2152 CST on March 3, 2024, a lost source was found along Corporate Blvd., Baton Rouge, LA. The device is a Model IC-51 Calibrator with 1000 mCi of Cs-137 as of August 25, 1980. The label on the device indicates the manufacturer was Gulf Nuclear, Inc., of Webster, Texas. LDEQ took possession of the device on March 4, 2024, and has it at the time of this report.
Event Report ID No.: LA20240003
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: 57003
Facility: Prairie Island
Region: 3 State: MN
Unit: [2] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: David Malek
HQ OPS Officer: Howie Crouch
Region: 3 State: MN
Unit: [2] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: David Malek
HQ OPS Officer: Howie Crouch
Notification Date: 03/03/2024
Notification Time: 15:51 [ET]
Event Date: 03/03/2024
Event Time: 11:42 [CST]
Last Update Date: 03/03/2024
Notification Time: 15:51 [ET]
Event Date: 03/03/2024
Event Time: 11:42 [CST]
Last Update Date: 03/03/2024
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):
Ruiz, Robert (R3DO)
Ruiz, Robert (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 29 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO LOSS OF MAIN FEEDWATER PUMP SUCTION
The following information was provided by the licensee via email:
"At 1142 CST on 3/3/2024, with Unit 2 in Mode 1 at 29 percent power, the reactor automatically tripped due to a turbine trip caused by a loss of suction to the 22 main feedwater pump. All systems responded normally post trip. Decay heat is being removed via the auxiliary feedwater water system. Secondary steam control mechanism is the steam generator PORVs [power operated relief valves]. Unit 1 remains at 100 percent power and is unaffected.
"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 resident NRC inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The trip occurred while the licensee was returning to power operations after a refueling outage. During the trip, all rods inserted into the core. The plant is in a normal shutdown electrical lineup with offsite power available. The plant will be maintained at normal operating temperature and pressure. There is no known primary to secondary leakage. The cause of the loss of 22 main feedwater pump suction is under investigation.
The following information was provided by the licensee via email:
"At 1142 CST on 3/3/2024, with Unit 2 in Mode 1 at 29 percent power, the reactor automatically tripped due to a turbine trip caused by a loss of suction to the 22 main feedwater pump. All systems responded normally post trip. Decay heat is being removed via the auxiliary feedwater water system. Secondary steam control mechanism is the steam generator PORVs [power operated relief valves]. Unit 1 remains at 100 percent power and is unaffected.
"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 resident NRC inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The trip occurred while the licensee was returning to power operations after a refueling outage. During the trip, all rods inserted into the core. The plant is in a normal shutdown electrical lineup with offsite power available. The plant will be maintained at normal operating temperature and pressure. There is no known primary to secondary leakage. The cause of the loss of 22 main feedwater pump suction is under investigation.
Power Reactor
Event Number: 57004
Facility: Nine Mile Point
Region: 1 State: NY
Unit: [2] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: Patrick Walsh
HQ OPS Officer: Howie Crouch
Region: 1 State: NY
Unit: [2] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: Patrick Walsh
HQ OPS Officer: Howie Crouch
Notification Date: 03/03/2024
Notification Time: 22:15 [ET]
Event Date: 03/03/2024
Event Time: 19:42 [EST]
Last Update Date: 03/03/2024
Notification Time: 22:15 [ET]
Event Date: 03/03/2024
Event Time: 19:42 [EST]
Last Update Date: 03/03/2024
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):
Bickett, Brice (R1DO)
Bickett, Brice (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 55 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO MAIN TURBINE TRIP ON LOW CONDENSER VACUUM
The following information was provided by the licensee via email:
"On 3/3/24 at 1942 EST, while performing a plant shutdown in preparation for a refuel outage, Nine Mile Point Unit 2 experienced a reactor scram due to a main turbine trip on low condenser vacuum. The plant was at approximately 55 percent power at the time of the reactor scram.
"Additionally, following the scram a low RPV [reactor pressure vessel] level scram and containment isolation signal on level 3 was received, as expected. The containment isolation signal impacted RHR [residual heat removal] shutdown cooling, RHR letdown to radwaste, and RHR sampling. All impacted valves were closed at the time the isolation occurred.
"All control rods were fully inserted. Plant response was as expected. Post scram, the main turbine bypass valves are being used to control decay heat, and normal post scram level control is via the feed / condensate system.
"This is being report under 10 CFR 50.72(b)(2)(iv)(B), 'RPS Actuation', and 10 CFR 50.72(b)(3)(iv)(A), 'Specified System Actuation'.
"Unit 1 is not affected. 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 cause of the low condenser vacuum was a momentary loss of sealing steam. The condenser remained viable for decay heat removal. All safety equipment is available. The grid is stable with the plant in its normal shutdown electrical configuration.
The following information was provided by the licensee via email:
"On 3/3/24 at 1942 EST, while performing a plant shutdown in preparation for a refuel outage, Nine Mile Point Unit 2 experienced a reactor scram due to a main turbine trip on low condenser vacuum. The plant was at approximately 55 percent power at the time of the reactor scram.
"Additionally, following the scram a low RPV [reactor pressure vessel] level scram and containment isolation signal on level 3 was received, as expected. The containment isolation signal impacted RHR [residual heat removal] shutdown cooling, RHR letdown to radwaste, and RHR sampling. All impacted valves were closed at the time the isolation occurred.
"All control rods were fully inserted. Plant response was as expected. Post scram, the main turbine bypass valves are being used to control decay heat, and normal post scram level control is via the feed / condensate system.
"This is being report under 10 CFR 50.72(b)(2)(iv)(B), 'RPS Actuation', and 10 CFR 50.72(b)(3)(iv)(A), 'Specified System Actuation'.
"Unit 1 is not affected. 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 cause of the low condenser vacuum was a momentary loss of sealing steam. The condenser remained viable for decay heat removal. All safety equipment is available. The grid is stable with the plant in its normal shutdown electrical configuration.