Event Notification Report for December 10, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/09/2020 - 12/10/2020
Power Reactor
Event Number: 55028
Facility: Arkansas Nuclear
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: Danny Watts
HQ OPS Officer: Kerby Scales
Region: 4 State: AR
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: Danny Watts
HQ OPS Officer: Kerby Scales
Notification Date: 12/10/2020
Notification Time: 20:43 [ET]
Event Date: 12/10/2020
Event Time: 16:08 [CST]
Last Update Date: 12/11/2020
Notification Time: 20:43 [ET]
Event Date: 12/10/2020
Event Time: 16:08 [CST]
Last Update Date: 12/11/2020
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):
RAY KELLAR (R4DO)
RAY KELLAR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 12/14/2020
EN Revision Text: AUTOMATIC REACTOR SCRAM DUE TO LOW STEAM GENERATOR WATER LEVEL
"On December 10, 2020 at 1608 CST, Arkansas Nuclear One, Unit 2 (ANO-2) experienced an automatic reactor scram from 100 percent power due to Low Steam Generator Water Level in 2E-24A Steam Generator. Emergency Feedwater actuated automatically due to low water level in the A Steam Generator. Due to inadequate control of the B Main Feedwater Control System, water level in the B Steam generator rose to a level requiring manual trip of the B Main Feedwater pump. Emergency Feedwater responded as designed to feed both steam generators automatically.
"All other systems responded as designed. All electrical power is being supplied from offsite power and maintaining unit electrical loads as designed.
"Unit 2 is currently stable in Mode 3 (Hot Standby) maintaining pressure and temperature via Emergency Feedwater and secondary system steaming.
"There are no indications of a radiological release on either unit as a result of this event.
"This report satisfies the reporting criteria of both 10 CFR 50.72(b)(2)(iv)(6) for the Reactor Protection System actuation and 10 CFR 50.72(b)(3)(iv)(A) for the actuation of the Emergency Feedwater System.
"The Arkansas Nuclear One NRC Senior Resident Inspector has been notified."
* * * UPDATE FROM JOHN LINDSEY TO DONALD NORWOOD AT 1605 EST ON 12/11/2020 * * *
"The purpose of this [report] is to provide an update to NRC Event Number 55028.
"The cause of the inadequate control of the B Main Feedwater Control System to control B Steam Generator Level was verified to be associated with the failure that led to the A Steam Generator low level condition.
"After taking action to trip the B Main Feedwater Pump, Emergency Feedwater was manually actuated for the B Steam Generator and the Emergency Feedwater System was verified to maintain proper automatic control of both Steam Generator levels.
"At the time of the initial event notification, plant temperature and pressure control had been transferred from Emergency Feedwater to Auxiliary Feedwater along with secondary system steaming."
The licensee notified the NRC Resident Inspector.
Notified R4DO (Kellar).
EN Revision Text: AUTOMATIC REACTOR SCRAM DUE TO LOW STEAM GENERATOR WATER LEVEL
"On December 10, 2020 at 1608 CST, Arkansas Nuclear One, Unit 2 (ANO-2) experienced an automatic reactor scram from 100 percent power due to Low Steam Generator Water Level in 2E-24A Steam Generator. Emergency Feedwater actuated automatically due to low water level in the A Steam Generator. Due to inadequate control of the B Main Feedwater Control System, water level in the B Steam generator rose to a level requiring manual trip of the B Main Feedwater pump. Emergency Feedwater responded as designed to feed both steam generators automatically.
"All other systems responded as designed. All electrical power is being supplied from offsite power and maintaining unit electrical loads as designed.
"Unit 2 is currently stable in Mode 3 (Hot Standby) maintaining pressure and temperature via Emergency Feedwater and secondary system steaming.
"There are no indications of a radiological release on either unit as a result of this event.
"This report satisfies the reporting criteria of both 10 CFR 50.72(b)(2)(iv)(6) for the Reactor Protection System actuation and 10 CFR 50.72(b)(3)(iv)(A) for the actuation of the Emergency Feedwater System.
"The Arkansas Nuclear One NRC Senior Resident Inspector has been notified."
* * * UPDATE FROM JOHN LINDSEY TO DONALD NORWOOD AT 1605 EST ON 12/11/2020 * * *
"The purpose of this [report] is to provide an update to NRC Event Number 55028.
"The cause of the inadequate control of the B Main Feedwater Control System to control B Steam Generator Level was verified to be associated with the failure that led to the A Steam Generator low level condition.
"After taking action to trip the B Main Feedwater Pump, Emergency Feedwater was manually actuated for the B Steam Generator and the Emergency Feedwater System was verified to maintain proper automatic control of both Steam Generator levels.
"At the time of the initial event notification, plant temperature and pressure control had been transferred from Emergency Feedwater to Auxiliary Feedwater along with secondary system steaming."
The licensee notified the NRC Resident Inspector.
Notified R4DO (Kellar).
Agreement State
Event Number: 55043
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: RSL (USA) Inc.
Region: 1
City: Wilkes-Barre State: PA
County:
License #: PA-0892
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Andrew Waugh
Licensee: RSL (USA) Inc.
Region: 1
City: Wilkes-Barre State: PA
County:
License #: PA-0892
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Andrew Waugh
Notification Date: 12/23/2020
Notification Time: 11:30 [ET]
Event Date: 12/10/2020
Event Time: 11:50 [EST]
Last Update Date: 12/23/2020
Notification Time: 11:30 [ET]
Event Date: 12/10/2020
Event Time: 11:50 [EST]
Last Update Date: 12/23/2020
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
ELISE BURKET (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ELISE BURKET (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - LOST AND RECOVERED RADIOACTIVE MATERIAL
The following information was received via email:
"On December 10, 2020, the licensee discovered a lost iodine-131 shipment. The shipper of the 475 mCi of iodine-131 Liquid (Yellow II label) delivered the package to the wrong address, a neighboring business. The package was delivered to the licensee by the recipient before the package was known to be 'lost', later on the scheduled delivery date. The surface reading of 12 mR/hr was obtained upon the licensee receiving the package. The package was estimated to be in the possession of the recipient for approximately 1 hour. The estimated dose was approximately 12 mrem if an individual had been in contact with the package for the entire time it was in the possession of the recipient. Since the material was delivered by the recipient within the time frame the shipper would normally deliver, and the facility had no reason to suspect the material was incorrectly delivered, the licensee will inform the shipper of the incident to handle training of their staff on proper delivery of radioactive packages."
PA Event Report ID No.: PA200024
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
The following information was received via email:
"On December 10, 2020, the licensee discovered a lost iodine-131 shipment. The shipper of the 475 mCi of iodine-131 Liquid (Yellow II label) delivered the package to the wrong address, a neighboring business. The package was delivered to the licensee by the recipient before the package was known to be 'lost', later on the scheduled delivery date. The surface reading of 12 mR/hr was obtained upon the licensee receiving the package. The package was estimated to be in the possession of the recipient for approximately 1 hour. The estimated dose was approximately 12 mrem if an individual had been in contact with the package for the entire time it was in the possession of the recipient. Since the material was delivered by the recipient within the time frame the shipper would normally deliver, and the facility had no reason to suspect the material was incorrectly delivered, the licensee will inform the shipper of the incident to handle training of their staff on proper delivery of radioactive packages."
PA Event Report ID No.: PA200024
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