Event Notification Report for December 13, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/12/2023 - 12/13/2023
Agreement State
Event Number: 56879
Rep Org: WA Office of Radiation Protection
Licensee: WestRock Longview, LLC
Region: 4
City: Longview State: WA
County:
License #: WN-I090-1
Agreement: Y
Docket:
NRC Notified By: James Killingbeck
HQ OPS Officer: Ernest West
Licensee: WestRock Longview, LLC
Region: 4
City: Longview State: WA
County:
License #: WN-I090-1
Agreement: Y
Docket:
NRC Notified By: James Killingbeck
HQ OPS Officer: Ernest West
Notification Date: 12/05/2023
Notification Time: 20:37 [ET]
Event Date: 12/05/2023
Event Time: 00:00 [PST]
Last Update Date: 12/05/2023
Notification Time: 20:37 [ET]
Event Date: 12/05/2023
Event Time: 00:00 [PST]
Last Update Date: 12/05/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Dixon, John (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Dixon, John (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE - STUCK SHUTTER
The following information was provided by the The Washington State Department of Health via email:
"The shutter on a fixed nuclear gauge [a Vega Americas Corp. Model No. SH-F1 gauge containing 53 millicuries of Cs-137] was unable to be closed when licensee staff attempted to lock it out. Licensee staff consulted with the manufacturer and, per the manufacturer's recommendation, installed four inches of steel plates in front of the fixed nuclear gauge to shield it. After installation of the steel plates, radiation levels were 0.2 mR/hour. The licensee is planning to replace the entire fixed nuclear gauge, per the manufacturer's recommendation, as the manufacturer has previously replaced the shutter on this gauge. The steel plates will remain installed until the fixed nuclear gauge is replaced. The Washington State Department of Health will gather additional information about this event and will submit an updated event report. An investigation may be conducted."
WA Event Number: WA-23-031
The following information was provided by the The Washington State Department of Health via email:
"The shutter on a fixed nuclear gauge [a Vega Americas Corp. Model No. SH-F1 gauge containing 53 millicuries of Cs-137] was unable to be closed when licensee staff attempted to lock it out. Licensee staff consulted with the manufacturer and, per the manufacturer's recommendation, installed four inches of steel plates in front of the fixed nuclear gauge to shield it. After installation of the steel plates, radiation levels were 0.2 mR/hour. The licensee is planning to replace the entire fixed nuclear gauge, per the manufacturer's recommendation, as the manufacturer has previously replaced the shutter on this gauge. The steel plates will remain installed until the fixed nuclear gauge is replaced. The Washington State Department of Health will gather additional information about this event and will submit an updated event report. An investigation may be conducted."
WA Event Number: WA-23-031
Non-Agreement State
Event Number: 56886
Rep Org: Liveo Research Inc.
Licensee: Liveo Research Inc.
Region: 1
City: New Castle State: DE
County:
License #:
Agreement: N
Docket:
NRC Notified By: John Oikemus
HQ OPS Officer: Karen Cotton-Gross
Licensee: Liveo Research Inc.
Region: 1
City: New Castle State: DE
County:
License #:
Agreement: N
Docket:
NRC Notified By: John Oikemus
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 12/11/2023
Notification Time: 16:50 [ET]
Event Date: 08/21/2023
Event Time: 00:00 [EST]
Last Update Date: 12/11/2023
Notification Time: 16:50 [ET]
Event Date: 08/21/2023
Event Time: 00:00 [EST]
Last Update Date: 12/11/2023
Emergency Class: Non Emergency
10 CFR Section:
30.50(b)(2) - Safety Equipment Failure
10 CFR Section:
30.50(b)(2) - Safety Equipment Failure
Person (Organization):
Gray, Mel (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Gray, Mel (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
DAMAGED RADIOACTIVE SOURCE CONTAINMENT
The following is summary of information provided by the licensee via email and phone:
On December 11, 2023, the licensee reported that the point level sensor containment attached to a power feeder was damaged and the internal shutter would not close. The licensee noticed issues with the point level sensor on June 28, 2023. On July 6, 2023, a work order was submitted for servicing the point level sensor. On August 21, 2023, the level senor was serviced, and the technician informed the licensee that due to the damage of the containment the unit was non-repairable. The estimated dose to staff from June 28, 2023 to August 21, 2023 is 1.8 mrem. The device was removed from service on October 5, 2023.
Source and Containment Information:
Source: Cs-137
Containment Model Number: FQG60
Serial Number: J8003301141
Activity: 740 MBq/20 mCi
Manufacturing Date: 08/2014
The following is summary of information provided by the licensee via email and phone:
On December 11, 2023, the licensee reported that the point level sensor containment attached to a power feeder was damaged and the internal shutter would not close. The licensee noticed issues with the point level sensor on June 28, 2023. On July 6, 2023, a work order was submitted for servicing the point level sensor. On August 21, 2023, the level senor was serviced, and the technician informed the licensee that due to the damage of the containment the unit was non-repairable. The estimated dose to staff from June 28, 2023 to August 21, 2023 is 1.8 mrem. The device was removed from service on October 5, 2023.
Source and Containment Information:
Source: Cs-137
Containment Model Number: FQG60
Serial Number: J8003301141
Activity: 740 MBq/20 mCi
Manufacturing Date: 08/2014
Agreement State
Event Number: 56880
Rep Org: Texas Dept of State Health Services
Licensee: U of Texas MD Anderson Cancer Ctr
Region: 4
City: Houston State: TX
County:
License #: L00466
Agreement: Y
Docket:
NRC Notified By: Randall Redd
HQ OPS Officer: Ernest West
Licensee: U of Texas MD Anderson Cancer Ctr
Region: 4
City: Houston State: TX
County:
License #: L00466
Agreement: Y
Docket:
NRC Notified By: Randall Redd
HQ OPS Officer: Ernest West
Notification Date: 12/07/2023
Notification Time: 14:36 [ET]
Event Date: 12/07/2023
Event Time: 00:00 [CST]
Last Update Date: 12/09/2023
Notification Time: 14:36 [ET]
Event Date: 12/07/2023
Event Time: 00:00 [CST]
Last Update Date: 12/09/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Dixon, John (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Dixon, John (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE - SOURCE STUCK IN UNSHIELDED POSITION
The following information was provided by the Texas Department of State Health Services (the Department) via email:
"On December 7, 2023, the Department was notified by a Texas licensee's radiation safety officer (RSO) that while testing an MDS Nordion, Model Eldorado 8, teletherapy unit, the 1,817 curie cobalt-60 source became stuck in the unshielded position. The RSO stated that the room was isolated and dose rates taken outside the room did not create an exposure risk to any individual. The RSO stated that a service contractor would likely repair the unit on December 9, 2023. Access to the room was posted to prevent inadvertent entry into the room. An update will be provided when the source is returned to the shielded position and then further information will be provided per SA-300."
Texas Incident Number: I-10070
NMED Number: TX230056
* * * UPDATE ON 12/9/23 AT 1137 EST FROM RANDELL REDD TO KAREN COTTON * * *
"On December 9, 2023, the Department was notified that the cobalt-60 source had been returned to the shielded position by the licensed servicing company. The technician who returned the source received around 0.3 millirem. The source activity is likely around 1,000 curies and not 1,817 curies, as originally reported. The Department will wait for the licensee and service company reports for information regarding the cause of the incident and report this to NMED per SA-300."
Notified R4DO (Dixon) and NMSS Events Notification via email.
The following information was provided by the Texas Department of State Health Services (the Department) via email:
"On December 7, 2023, the Department was notified by a Texas licensee's radiation safety officer (RSO) that while testing an MDS Nordion, Model Eldorado 8, teletherapy unit, the 1,817 curie cobalt-60 source became stuck in the unshielded position. The RSO stated that the room was isolated and dose rates taken outside the room did not create an exposure risk to any individual. The RSO stated that a service contractor would likely repair the unit on December 9, 2023. Access to the room was posted to prevent inadvertent entry into the room. An update will be provided when the source is returned to the shielded position and then further information will be provided per SA-300."
Texas Incident Number: I-10070
NMED Number: TX230056
* * * UPDATE ON 12/9/23 AT 1137 EST FROM RANDELL REDD TO KAREN COTTON * * *
"On December 9, 2023, the Department was notified that the cobalt-60 source had been returned to the shielded position by the licensed servicing company. The technician who returned the source received around 0.3 millirem. The source activity is likely around 1,000 curies and not 1,817 curies, as originally reported. The Department will wait for the licensee and service company reports for information regarding the cause of the incident and report this to NMED per SA-300."
Notified R4DO (Dixon) and NMSS Events Notification via email.
Power Reactor
Event Number: 56887
Facility: River Bend
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Chris Dwyer
HQ OPS Officer: Ernest West
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Chris Dwyer
HQ OPS Officer: Ernest West
Notification Date: 12/13/2023
Notification Time: 05:50 [ET]
Event Date: 12/13/2023
Event Time: 01:02 [CST]
Last Update Date: 12/13/2023
Notification Time: 05:50 [ET]
Event Date: 12/13/2023
Event Time: 01:02 [CST]
Last Update Date: 12/13/2023
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):
Agrawal, Ami (R4DO)
Agrawal, Ami (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM
The following information was provided by the licensee via phone and email:
"At 0102 CST, while operating at 100 percent [reactor] power, River Bend Station experienced an automatic reactor scram caused by a turbine trip signal. The cause of the turbine trip signal is not known at this time and is being investigated. At 0108, reactor core isolation cooling (RCIC) was initiated due to a loss of reactor feed pumps following feedwater heater string isolation. At 0114, reactor water level control was transferred back to feedwater and RCIC was secured. Reactor water level is being maintained by feedwater pumps and reactor pressure is being maintained by turbine bypass valves. The scram was uncomplicated and all other plant systems responded as designed.
"This event is being reported under 10 CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical and 10 CFR 50.72(b)(3)(iv)(A) specified system actuation as result of expected post scram [reactor water] level 3 isolations and manual initiation of RCIC.
"No radiological releases have occurred due to this event from the unit.
"The NRC Senior Resident Inspector has been notified of this event."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the turbine trip, while still under investigation, was likely due to an electrical transient involving the main generator. Walkdowns in the switchyard post-scram identified damage to one of the output breaker disconnects.
The following information was provided by the licensee via phone and email:
"At 0102 CST, while operating at 100 percent [reactor] power, River Bend Station experienced an automatic reactor scram caused by a turbine trip signal. The cause of the turbine trip signal is not known at this time and is being investigated. At 0108, reactor core isolation cooling (RCIC) was initiated due to a loss of reactor feed pumps following feedwater heater string isolation. At 0114, reactor water level control was transferred back to feedwater and RCIC was secured. Reactor water level is being maintained by feedwater pumps and reactor pressure is being maintained by turbine bypass valves. The scram was uncomplicated and all other plant systems responded as designed.
"This event is being reported under 10 CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical and 10 CFR 50.72(b)(3)(iv)(A) specified system actuation as result of expected post scram [reactor water] level 3 isolations and manual initiation of RCIC.
"No radiological releases have occurred due to this event from the unit.
"The NRC Senior Resident Inspector has been notified of this event."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The cause of the turbine trip, while still under investigation, was likely due to an electrical transient involving the main generator. Walkdowns in the switchyard post-scram identified damage to one of the output breaker disconnects.
Part 21
Event Number: 56888
Rep Org: Sequoyah Nuclear Plant
Licensee: Sequoyah Nuclear Plant
Region: 2
City: Soddy-Daisy State: TN
County: Hamilton
License #:
Agreement: Y
Docket:
NRC Notified By: Jeff Sowa
HQ OPS Officer: Ernest West
Licensee: Sequoyah Nuclear Plant
Region: 2
City: Soddy-Daisy State: TN
County: Hamilton
License #:
Agreement: Y
Docket:
NRC Notified By: Jeff Sowa
HQ OPS Officer: Ernest West
Notification Date: 12/13/2023
Notification Time: 09:45 [ET]
Event Date: 12/11/2023
Event Time: 13:32 [EST]
Last Update Date: 12/13/2023
Notification Time: 09:45 [ET]
Event Date: 12/11/2023
Event Time: 13:32 [EST]
Last Update Date: 12/13/2023
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Miller, Mark (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
Miller, Mark (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
PART 21 - CIRCUIT BREAKER DEFECTS
The following information is a synopsis of information provided by the licensee via phone and email:
On December 11, 2023, Tennessee Valley Authority Sequoyah Nuclear Plant completed an internal 10 CFR Part 21 evaluation concerning Siemens 6.9kV, 1200A vacuum circuit breakers, Model No. 7-HKR-50-1200-130. Three separate breakers were found with issues including loose wires terminated incorrectly and the mechanism-operated control switch clevis pin missing a cotter key. Additionally, the mastic insulating pads were found defective on all three lower primaries by way of separation. The affected breakers were never installed in a safety related application.
The NRC Resident Inspector will be notified.
A written notification will be provided within 30 days.
The manufacturer, Siemens, was notified of the defects.
The only plant known to be affected at the time of the report is the Sequoyah Nuclear Plant.
The following information is a synopsis of information provided by the licensee via phone and email:
On December 11, 2023, Tennessee Valley Authority Sequoyah Nuclear Plant completed an internal 10 CFR Part 21 evaluation concerning Siemens 6.9kV, 1200A vacuum circuit breakers, Model No. 7-HKR-50-1200-130. Three separate breakers were found with issues including loose wires terminated incorrectly and the mechanism-operated control switch clevis pin missing a cotter key. Additionally, the mastic insulating pads were found defective on all three lower primaries by way of separation. The affected breakers were never installed in a safety related application.
The NRC Resident Inspector will be notified.
A written notification will be provided within 30 days.
The manufacturer, Siemens, was notified of the defects.
The only plant known to be affected at the time of the report is the Sequoyah Nuclear Plant.