Event Notification Report for April 14, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/13/2022 - 04/14/2022
Agreement State
Event Number: 55845
Rep Org: Virginia Rad Materials Program
Licensee: Newport News Shipbuilding
Region: 1
City: Newport News State: VA
County:
License #: 700-383-1
Agreement: Y
Docket:
NRC Notified By: Rose Yankoski
HQ OPS Officer: Brian Parks
Licensee: Newport News Shipbuilding
Region: 1
City: Newport News State: VA
County:
License #: 700-383-1
Agreement: Y
Docket:
NRC Notified By: Rose Yankoski
HQ OPS Officer: Brian Parks
Notification Date: 04/15/2022
Notification Time: 14:50 [ET]
Event Date: 04/14/2022
Event Time: 11:03 [EDT]
Last Update Date: 04/15/2022
Notification Time: 14:50 [ET]
Event Date: 04/14/2022
Event Time: 11:03 [EDT]
Last Update Date: 04/15/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Cahill, Christopher (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Cahill, Christopher (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - SOURCE UNABLE TO RETRACT TO SAFE POSITION
The following was received from the Commonwealth of Virginia via email:
"On April 14, 2022 at 2249 hours EDT, the Office of Radiological Health Radioactive Materials Program (ORH) received an incident report from the licensee, Huntington Ingalls Incorporated Newport News Shipbuilding. The source, 79 curies of Ir-192, could not be retracted to its shielded position during radiographic work. The incident occurred on April 14, 2022 at about 1103, while a radiographic work was being performed in a permanent radiography booth to inspect a pipe for use upon a naval vessel at Newport News Shipbuilding. The incident occurred because the metal pipe fell off of the metal sawhorse, crushing the source tube and preventing full retraction back into the shielded position. The root cause of the pipe falling off of the sawhorse has yet to be determined. The radiography crew immediately closed the permanent radiography booth, took radiation surveys to ensure that with the door closed the radiation levels were below 2 mR/hr, and notified the Radiation Safety Officer (RSO). The site was supervised by the radiography crew constantly between the time of the incident until the source was retracted at approximately 1310 on April 15, 2022. The highest exposure of the crew from the pocket dosimeters was 5.5 mrem. In addition, the whole body dosimeters were sent to the licensee's internal dosimetry program for analysis. The results are not yet available. The RMP Southeast regional inspector responded to the incident and performed radiation safety assessment at the event site."
Virginia Event Report ID Number: VA220001
The following was received from the Commonwealth of Virginia via email:
"On April 14, 2022 at 2249 hours EDT, the Office of Radiological Health Radioactive Materials Program (ORH) received an incident report from the licensee, Huntington Ingalls Incorporated Newport News Shipbuilding. The source, 79 curies of Ir-192, could not be retracted to its shielded position during radiographic work. The incident occurred on April 14, 2022 at about 1103, while a radiographic work was being performed in a permanent radiography booth to inspect a pipe for use upon a naval vessel at Newport News Shipbuilding. The incident occurred because the metal pipe fell off of the metal sawhorse, crushing the source tube and preventing full retraction back into the shielded position. The root cause of the pipe falling off of the sawhorse has yet to be determined. The radiography crew immediately closed the permanent radiography booth, took radiation surveys to ensure that with the door closed the radiation levels were below 2 mR/hr, and notified the Radiation Safety Officer (RSO). The site was supervised by the radiography crew constantly between the time of the incident until the source was retracted at approximately 1310 on April 15, 2022. The highest exposure of the crew from the pocket dosimeters was 5.5 mrem. In addition, the whole body dosimeters were sent to the licensee's internal dosimetry program for analysis. The results are not yet available. The RMP Southeast regional inspector responded to the incident and performed radiation safety assessment at the event site."
Virginia Event Report ID Number: VA220001
Power Reactor
Event Number: 55843
Facility: North Anna
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Bob Page
HQ OPS Officer: Kerby Scales
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Bob Page
HQ OPS Officer: Kerby Scales
Notification Date: 04/14/2022
Notification Time: 11:18 [ET]
Event Date: 04/14/2022
Event Time: 09:28 [EDT]
Last Update Date: 04/14/2022
Notification Time: 11:18 [ET]
Event Date: 04/14/2022
Event Time: 09:28 [EDT]
Last Update Date: 04/14/2022
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):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DURING CONTROL ROD TESTING
The following information was provided by the licensee via email:
"On April 14, 2022, at 0928 [EDT] hours, Unit 1 automatically tripped from 100 percent power during the control rod operability periodic test. The reactor trip occurred during the manipulation of the rod control mode selector switch as part of the rod operability testing. The Operations crew entered the reactor trip procedure and stabilized Unit 1 in Mode 3 at normal operating temperature and pressure. The reactor trip was uncomplicated, and all control rods fully inserted into the core. This reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater pumps actuated as designed because of the reactor trip and provide makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater system is reportable per 10 CFR 50.72(b)(3)(iv) (A) for a valid actuation of an ESF [Engineered Safety Features] system. The Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 1 is in a normal shutdown electrical lineup. An investigation into the cause of the reactor trip is underway."
The NRC Resident Inspector has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
There was no affect to Unit 2. Unit 2 is operating at 100 percent power.
The following information was provided by the licensee via email:
"On April 14, 2022, at 0928 [EDT] hours, Unit 1 automatically tripped from 100 percent power during the control rod operability periodic test. The reactor trip occurred during the manipulation of the rod control mode selector switch as part of the rod operability testing. The Operations crew entered the reactor trip procedure and stabilized Unit 1 in Mode 3 at normal operating temperature and pressure. The reactor trip was uncomplicated, and all control rods fully inserted into the core. This reactor protection system actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). The Auxiliary Feedwater pumps actuated as designed because of the reactor trip and provide makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater system is reportable per 10 CFR 50.72(b)(3)(iv) (A) for a valid actuation of an ESF [Engineered Safety Features] system. The Auxiliary Feedwater pumps were subsequently secured and returned to automatic. Decay heat is being removed by the condenser steam dump system. Unit 1 is in a normal shutdown electrical lineup. An investigation into the cause of the reactor trip is underway."
The NRC Resident Inspector has been notified.
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
There was no affect to Unit 2. Unit 2 is operating at 100 percent power.