Event Notification Report for October 20, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/19/2022 - 10/20/2022
Agreement State
Event Number: 56238
Rep Org: NJ Rad Prot And Rel Prevention Pgm
Licensee: Siemens Industry Inc.
Region: 1
City: State: NJ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Joesph Power
HQ OPS Officer: Kerby Scales
Licensee: Siemens Industry Inc.
Region: 1
City: State: NJ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Joesph Power
HQ OPS Officer: Kerby Scales
Notification Date: 11/23/2022
Notification Time: 14:46 [ET]
Event Date: 10/20/2022
Event Time: 00:00 [EST]
Last Update Date: 11/23/2022
Notification Time: 14:46 [ET]
Event Date: 10/20/2022
Event Time: 00:00 [EST]
Last Update Date: 11/23/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Carfang, Erin (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Carfang, Erin (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - CONTAMINATED WASTE STORAGE ROOM
The following was received from the state of New Jersey via email:
"Siemens has operated a take-back program for smoke detectors containing radiation sources since the 1990s. Most smoke detectors contained Am-241, but Ra-226 sources were also handled. This program has been discontinued and the licensee is now undergoing decommissioning. On October 20, 2022, as part of the license termination process, a consulting Health Physicist was contracted to perform characterization surveys of a waste storage room on site. The storage room was the only room where licensed materials were handled. Here, the licensee would disassemble smoke detectors for ultimate disposal via a licensed radioactive waste broker. The results of the survey indicated that fixed alpha contamination existed across the entire floor surface and on the walls in smaller concentrations. The highest reading observed on the floor was 4,387 cpm [counts per minute]. This equated to 13,282 dpm [disintegrations per minute]/100 centimeters squared with the health physicist's survey instrument. This was the first indication that contamination existed within this facility. This was an unplanned contamination event and possibly involved a quantity of material greater than five times the lowest annual limit on intake specified in Appendix B of 20.1001-20.2401 of 10 CFR Part 20, for Am-241.
"Licensee corrective actions: No more smoke detectors are being received by the licensee, so no changes to procedures will occur. Current decontamination work is underway by a licensed radiation contractor. The facility will need to be decontaminated to acceptable levels meeting New Jersey's 15 mrem/year release criteria.
"On November 17, 2022, the state performed independent surveys of the room to confirm areas of contamination. The presence of fixed contamination was confirmed and removable contamination was also discovered. The state instructed the licensee to cordon off contaminated areas to prevent entry of personnel. The state will also perform confirmatory surveys after decontamination work is completed."
The following was received from the state of New Jersey via email:
"Siemens has operated a take-back program for smoke detectors containing radiation sources since the 1990s. Most smoke detectors contained Am-241, but Ra-226 sources were also handled. This program has been discontinued and the licensee is now undergoing decommissioning. On October 20, 2022, as part of the license termination process, a consulting Health Physicist was contracted to perform characterization surveys of a waste storage room on site. The storage room was the only room where licensed materials were handled. Here, the licensee would disassemble smoke detectors for ultimate disposal via a licensed radioactive waste broker. The results of the survey indicated that fixed alpha contamination existed across the entire floor surface and on the walls in smaller concentrations. The highest reading observed on the floor was 4,387 cpm [counts per minute]. This equated to 13,282 dpm [disintegrations per minute]/100 centimeters squared with the health physicist's survey instrument. This was the first indication that contamination existed within this facility. This was an unplanned contamination event and possibly involved a quantity of material greater than five times the lowest annual limit on intake specified in Appendix B of 20.1001-20.2401 of 10 CFR Part 20, for Am-241.
"Licensee corrective actions: No more smoke detectors are being received by the licensee, so no changes to procedures will occur. Current decontamination work is underway by a licensed radiation contractor. The facility will need to be decontaminated to acceptable levels meeting New Jersey's 15 mrem/year release criteria.
"On November 17, 2022, the state performed independent surveys of the room to confirm areas of contamination. The presence of fixed contamination was confirmed and removable contamination was also discovered. The state instructed the licensee to cordon off contaminated areas to prevent entry of personnel. The state will also perform confirmatory surveys after decontamination work is completed."
Power Reactor
Event Number: 56171
Facility: Grand Gulf
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Ronald Walters
HQ OPS Officer: Bill Gott
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Ronald Walters
HQ OPS Officer: Bill Gott
Notification Date: 10/20/2022
Notification Time: 11:31 [ET]
Event Date: 10/20/2022
Event Time: 04:27 [CDT]
Last Update Date: 10/20/2022
Notification Time: 11:31 [ET]
Event Date: 10/20/2022
Event Time: 04:27 [CDT]
Last Update Date: 10/20/2022
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):
Groom, Jeremy (R4DO)
Groom, Jeremy (R4DO)
| 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: 10/21/2022
EN Revision Text: SECONDARY CONTAINMENT INOPERABLE DURING SURVEILLANCE
The following information was provided by the licensee via email:
"At 0427 CDT on October 20, 2022, Grand Gulf Nuclear Station (GGNS) was in Mode 1 at 100 percent power when a failure of a draw down surveillance resulted in the loss of secondary containment. During the performance of the surveillance GGNS was unable to maintain secondary containment pressure, as required by Technical Specification Surveillance Requirement 3.6.4.1.4, greater than or equal to 0.266 inches of water vacuum for 1 hour at a flow rate of less than or equal to 4000cfm.
"The test was secured. Secondary containment was declared inoperable and Technical Specification 3.6.4.1 A.1 was entered at 0427 CDT. Secondary containment was restored to operable status at 0520 CDT by restoring the configuration to a previously known operable condition.
"This event is being reported as an event or condition that could have prevented the fulfillment of a safety function.
"The NRC Resident Inspector was notified."
EN Revision Text: SECONDARY CONTAINMENT INOPERABLE DURING SURVEILLANCE
The following information was provided by the licensee via email:
"At 0427 CDT on October 20, 2022, Grand Gulf Nuclear Station (GGNS) was in Mode 1 at 100 percent power when a failure of a draw down surveillance resulted in the loss of secondary containment. During the performance of the surveillance GGNS was unable to maintain secondary containment pressure, as required by Technical Specification Surveillance Requirement 3.6.4.1.4, greater than or equal to 0.266 inches of water vacuum for 1 hour at a flow rate of less than or equal to 4000cfm.
"The test was secured. Secondary containment was declared inoperable and Technical Specification 3.6.4.1 A.1 was entered at 0427 CDT. Secondary containment was restored to operable status at 0520 CDT by restoring the configuration to a previously known operable condition.
"This event is being reported as an event or condition that could have prevented the fulfillment of a safety function.
"The NRC Resident Inspector was notified."
Power Reactor
Event Number: 56172
Facility: Catawba
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Stan Sinclair
HQ OPS Officer: Adam Koziol
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Stan Sinclair
HQ OPS Officer: Adam Koziol
Notification Date: 10/20/2022
Notification Time: 20:24 [ET]
Event Date: 10/20/2022
Event Time: 14:46 [EDT]
Last Update Date: 10/20/2022
Notification Time: 20:24 [ET]
Event Date: 10/20/2022
Event Time: 14:46 [EDT]
Last Update Date: 10/20/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(xii) - Offsite Medical
10 CFR Section:
50.72(b)(3)(xii) - Offsite Medical
Person (Organization):
Miller, Mark (R2DO)
Whited, Jeffrey (IR)
Felts, Russel (NRR EO)
Miller, Mark (R2DO)
Whited, Jeffrey (IR)
Felts, Russel (NRR EO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Hot Shutdown |
TRANSPORT OF A POTENTIALLY CONTAMINATED PERSON OFFSITE
The following information was provided by the licensee via email:
"At 1446 EDT on October 20, 2022, an individual was transported offsite for treatment at an offsite medical facility. Due to the nature of the medical condition, the individual was not thoroughly surveyed prior to being transported offsite. Follow-up surveys performed by radiation protection technicians identified no contamination of the worker or of the ambulance and response personnel.
"This is an eight-hour notification, non-emergency for the transportation of a contaminated person offsite. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xii).
"The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"At 1446 EDT on October 20, 2022, an individual was transported offsite for treatment at an offsite medical facility. Due to the nature of the medical condition, the individual was not thoroughly surveyed prior to being transported offsite. Follow-up surveys performed by radiation protection technicians identified no contamination of the worker or of the ambulance and response personnel.
"This is an eight-hour notification, non-emergency for the transportation of a contaminated person offsite. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xii).
"The NRC Resident Inspector has been notified."