Event Notification Report for October 24, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/23/2019 - 10/24/2019
EVENT NUMBERS
5435154352543475434854349
Power Reactor
Event Number: 54351
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SCOTT SAYLORS
HQ OPS Officer: JEFF HERRERA
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SCOTT SAYLORS
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/25/2019
Notification Time: 03:24 [ET]
Event Date: 10/24/2019
Event Time: 20:51 [CDT]
Last Update Date: 10/25/2019
Notification Time: 03:24 [ET]
Event Date: 10/24/2019
Event Time: 20:51 [CDT]
Last Update Date: 10/25/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CALE YOUNG (R4DO)
CALE YOUNG (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
VALID UNDERVOLTAGE ACTUATION DURING EDG SEQUENCER MAINTENANCE
"On October 24, 2019, at 2051 Central Time, while performing Train C Sequencer maintenance, a valid undervoltage actuation signal was sent to Unit 2 Emergency Diesel Generator (EDG) 23. The ESF Train C bus loads were shed but EDG 23 did not automatically start because it had been placed in Pull-To-Stop to support the sequencer maintenance activities. EDG 23 was taken out of Pull-To-Stop by Control Room staff to allow it to auto start and load the bus. As a result of the bus strip signal, the in service Spent Fuel Pool Cooling Pump secured. Spent Fuel Pool Cooling was restored with no measurable increase in pool temperature.
"The reactor was not critical and reactor decay heat removal was not challenged throughout the event.
"This actuation is reportable per 10 CFR 50.72(b)(3)(iv)(A) due to the automatic actuation of a system listed in 10 CFR 50.72(b)(3)(iv)(B).
"The NRC Resident Inspector has been notified."
"On October 24, 2019, at 2051 Central Time, while performing Train C Sequencer maintenance, a valid undervoltage actuation signal was sent to Unit 2 Emergency Diesel Generator (EDG) 23. The ESF Train C bus loads were shed but EDG 23 did not automatically start because it had been placed in Pull-To-Stop to support the sequencer maintenance activities. EDG 23 was taken out of Pull-To-Stop by Control Room staff to allow it to auto start and load the bus. As a result of the bus strip signal, the in service Spent Fuel Pool Cooling Pump secured. Spent Fuel Pool Cooling was restored with no measurable increase in pool temperature.
"The reactor was not critical and reactor decay heat removal was not challenged throughout the event.
"This actuation is reportable per 10 CFR 50.72(b)(3)(iv)(A) due to the automatic actuation of a system listed in 10 CFR 50.72(b)(3)(iv)(B).
"The NRC Resident Inspector has been notified."
Agreement State
Event Number: 54352
Rep Org: ALABAMA RADIATION CONTROL
Licensee: ALABAMA RIVER CELLULOSE
Region: 1
City: PERDUE HILL State: AL
County:
License #: 634
Agreement: Y
Docket:
NRC Notified By: CASON COAN
HQ OPS Officer: JEFF HERRERA
Licensee: ALABAMA RIVER CELLULOSE
Region: 1
City: PERDUE HILL State: AL
County:
License #: 634
Agreement: Y
Docket:
NRC Notified By: CASON COAN
HQ OPS Officer: JEFF HERRERA
Notification Date: 10/25/2019
Notification Time: 10:19 [ET]
Event Date: 10/24/2019
Event Time: 00:00 [CDT]
Last Update Date: 10/25/2019
Notification Time: 10:19 [ET]
Event Date: 10/24/2019
Event Time: 00:00 [CDT]
Last Update Date: 10/25/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
10 CFR Section:
AGREEMENT STATE
Person (Organization):
BRICE BICKETT (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
BRICE BICKETT (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - FAILED SHUTTER ON A PROCESS GAUGE
The following report was received from the Alabama Department of Public Health via email:
"Representative reported that personnel found a gauge to have a failed shutter. Representative reported that the shutter is failed in the closed position. Representative reported that [the] gauge was discovered in the reported condition during some maintenance operations. Representative stated that the gauge was discovered in its reported condition on 10/24/2019. Representative reported this to [the] Agency [Alabama Department of Public Health] on 10/25/2019 at 0813 [CDT].
"Gauge contains source s/n 8829GK, a 500 mCi Cs-137 source. Gauge is reported as an Ohmart model SH-2. No known device issues that could have caused a failed shutter.
"Licensee is in the process of ordering parts for repair. Representative stated that ABB will repair the gauge."
Alabama Incident number 19-29.
The following report was received from the Alabama Department of Public Health via email:
"Representative reported that personnel found a gauge to have a failed shutter. Representative reported that the shutter is failed in the closed position. Representative reported that [the] gauge was discovered in the reported condition during some maintenance operations. Representative stated that the gauge was discovered in its reported condition on 10/24/2019. Representative reported this to [the] Agency [Alabama Department of Public Health] on 10/25/2019 at 0813 [CDT].
"Gauge contains source s/n 8829GK, a 500 mCi Cs-137 source. Gauge is reported as an Ohmart model SH-2. No known device issues that could have caused a failed shutter.
"Licensee is in the process of ordering parts for repair. Representative stated that ABB will repair the gauge."
Alabama Incident number 19-29.
Power Reactor
Event Number: 54347
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JERONIMO JIMENEZ
HQ OPS Officer: CATY NOLAN
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JERONIMO JIMENEZ
HQ OPS Officer: CATY NOLAN
Notification Date: 10/24/2019
Notification Time: 16:24 [ET]
Event Date: 10/24/2019
Event Time: 15:24 [EDT]
Last Update Date: 10/24/2019
Notification Time: 16:24 [ET]
Event Date: 10/24/2019
Event Time: 15:24 [EDT]
Last Update Date: 10/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BRICE BICKETT (R1DO)
BRICE BICKETT (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Defueled | 0 | Defueled |
OFFSITE NOTIFICATION
"Holtec Decommissioning International has notified the State of New Jersey that during the conduct of Industrial Site Remediation Act (ISRA) non-radiological site investigation field sampling and analysis activities at the Oyster Creek site, soil and groundwater exceedances to New Jersey Default Impact to Groundwater Soil Levels, Residential Direct Contact Soil Remediation, Non-Residential Direct Contact Soil Remediation and Class IIA Groundwater Quality Standards were identified. These exceedances are reportable under New Jersey Administrative Code NJAC 7:26C. That notification was made at 1524 EDT."
The NRC Regional Inspector and the State of New Jersey were notified.
"Holtec Decommissioning International has notified the State of New Jersey that during the conduct of Industrial Site Remediation Act (ISRA) non-radiological site investigation field sampling and analysis activities at the Oyster Creek site, soil and groundwater exceedances to New Jersey Default Impact to Groundwater Soil Levels, Residential Direct Contact Soil Remediation, Non-Residential Direct Contact Soil Remediation and Class IIA Groundwater Quality Standards were identified. These exceedances are reportable under New Jersey Administrative Code NJAC 7:26C. That notification was made at 1524 EDT."
The NRC Regional Inspector and the State of New Jersey were notified.
Power Reactor
Event Number: 54348
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ALFONSO CROEZE
HQ OPS Officer: DONALD NORWOOD
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ALFONSO CROEZE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/24/2019
Notification Time: 16:25 [ET]
Event Date: 10/24/2019
Event Time: 10:35 [CDT]
Last Update Date: 10/24/2019
Notification Time: 16:25 [ET]
Event Date: 10/24/2019
Event Time: 10:35 [CDT]
Last Update Date: 10/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
CALE YOUNG (R4DO)
CALE YOUNG (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 |
AUTOMATIC DEPRESSURIZATION SYSTEM INOPERABLE
"At 1035 CDT the Automatic Depressurization System (ADS) was rendered inoperable due to the failure of the 'A' Safety Vent Valve (SVV) Compressor (SVV-C4A) to manually start with SVV-C4B tagged out. System pressure slowly dropped below 131 psig (normal pressure is 165 psig). This caused the ADS safety relief valves to be declared inoperable. The station entered Technical Specification 3.5.1 Condition G. The Required Action was to be in Mode 3 in 12 hours. As a result, the station was in a condition that could have prevented the fulfillment of a safety function.
"The breaker for SVV-C4B was reset and the clearance for SVV-V4B was released. System pressure was restored to greater than 131 psig at 1116 CDT which allowed exit of the action statement to be in Mode 3 in 12 hours. System parameters are currently stable in the normal pressure range. Investigation for the cause of the system failure is ongoing.
"No radiological releases have occurred due to this event from the unit."
The licensee notified the NRC Resident Inspector.
"At 1035 CDT the Automatic Depressurization System (ADS) was rendered inoperable due to the failure of the 'A' Safety Vent Valve (SVV) Compressor (SVV-C4A) to manually start with SVV-C4B tagged out. System pressure slowly dropped below 131 psig (normal pressure is 165 psig). This caused the ADS safety relief valves to be declared inoperable. The station entered Technical Specification 3.5.1 Condition G. The Required Action was to be in Mode 3 in 12 hours. As a result, the station was in a condition that could have prevented the fulfillment of a safety function.
"The breaker for SVV-C4B was reset and the clearance for SVV-V4B was released. System pressure was restored to greater than 131 psig at 1116 CDT which allowed exit of the action statement to be in Mode 3 in 12 hours. System parameters are currently stable in the normal pressure range. Investigation for the cause of the system failure is ongoing.
"No radiological releases have occurred due to this event from the unit."
The licensee notified the NRC Resident Inspector.
Non-Power Reactor
Event Number: 54349
Rep Org: ARMED FORCES RADIOBIOLOGY RSCH INST
Licensee: ARMED FORCES RADIOBIOLOGY RSCH INST
Region: 0
City: BETHESDA State: MD
County: MONTGOMERY
License #: R-84
Agreement: Y
Docket: 05000170
NRC Notified By: DALE TOMLINSON
HQ OPS Officer: DONALD NORWOOD
Licensee: ARMED FORCES RADIOBIOLOGY RSCH INST
Region: 0
City: BETHESDA State: MD
County: MONTGOMERY
License #: R-84
Agreement: Y
Docket: 05000170
NRC Notified By: DALE TOMLINSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 10/24/2019
Notification Time: 16:30 [ET]
Event Date: 10/24/2019
Event Time: 00:00 [EDT]
Last Update Date: 10/24/2019
Notification Time: 16:30 [ET]
Event Date: 10/24/2019
Event Time: 00:00 [EDT]
Last Update Date: 10/24/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
BRICE BICKETT (R1DO)
CINDY MONTGOMERY (DLP)
NMSS_EVENTS_NOTIFICATION (EMAIL)
LEAH SMITH (ILTAB)
BRICE BICKETT (R1DO)
CINDY MONTGOMERY (DLP)
NMSS_EVENTS_NOTIFICATION (EMAIL)
LEAH SMITH (ILTAB)
UNACCOUNTED FOR FISSION CHAMBER
On October 24, 2019, during performance of an annual inventory, one fission chamber could not be accounted for. After a thorough search, the fission chamber was declared missing. The fission chamber was manufactured by Reuter-Stokes with a part number of: RS-P6-0805-134 and a serial number of: 14K024C5. The fission chamber contains 0.12988 grams of Uranium-235.
The last known accounting of this fission chamber was during the previous annual inventory. The licensee is continuing to search for the fission chamber.
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
On October 24, 2019, during performance of an annual inventory, one fission chamber could not be accounted for. After a thorough search, the fission chamber was declared missing. The fission chamber was manufactured by Reuter-Stokes with a part number of: RS-P6-0805-134 and a serial number of: 14K024C5. The fission chamber contains 0.12988 grams of Uranium-235.
The last known accounting of this fission chamber was during the previous annual inventory. The licensee is continuing to search for the fission chamber.
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