Event Notification Report for December 06, 2021
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/05/2021 - 12/06/2021
Power Reactor
Event Number: 55626
Facility: Palo Verde
Region: 4 State: AZ
Unit: [3] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Joshua McDowell
HQ OPS Officer: Mike Stafford
Region: 4 State: AZ
Unit: [3] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Joshua McDowell
HQ OPS Officer: Mike Stafford
Notification Date: 12/06/2021
Notification Time: 17:17 [ET]
Event Date: 12/06/2021
Event Time: 12:03 [MST]
Last Update Date: 12/06/2021
Notification Time: 17:17 [ET]
Event Date: 12/06/2021
Event Time: 12:03 [MST]
Last Update Date: 12/06/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS Actuation - Critical
Person (Organization):
Young, Cale (R4)
Young, Cale (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 1/6/2022
EN Revision Text: UNIT 3 AUTOMATIC TRIP
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"At 1203 MST on December 6, 2021, the Unit 3 reactor automatically tripped on low departure from nucleate boiling ratio. A part-strength control element assembly was being moved at the time of the trip.
"Unit 3 is stable and in Mode 3. In response to the reactor trip, all control element assemblies inserted fully into the core. Safety-related electrical power remains energized from off-site power sources and reactor coolant pumps continue to provide forced circulation through the reactor. Decay heat is being removed by the steam bypass control system and main feedwater system. Required systems operated as expected.
"No emergency classification was required per the Emergency Plan.
"The NRC Senior Resident Inspector has been informed."
Units 1 and 2 were unaffected by this transient.
EN Revision Text: UNIT 3 AUTOMATIC TRIP
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"At 1203 MST on December 6, 2021, the Unit 3 reactor automatically tripped on low departure from nucleate boiling ratio. A part-strength control element assembly was being moved at the time of the trip.
"Unit 3 is stable and in Mode 3. In response to the reactor trip, all control element assemblies inserted fully into the core. Safety-related electrical power remains energized from off-site power sources and reactor coolant pumps continue to provide forced circulation through the reactor. Decay heat is being removed by the steam bypass control system and main feedwater system. Required systems operated as expected.
"No emergency classification was required per the Emergency Plan.
"The NRC Senior Resident Inspector has been informed."
Units 1 and 2 were unaffected by this transient.
Power Reactor
Event Number: 55627
Facility: Brunswick
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Joel Gordon
HQ OPS Officer: Thomas Kendzia
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: Joel Gordon
HQ OPS Officer: Thomas Kendzia
Notification Date: 12/06/2021
Notification Time: 18:14 [ET]
Event Date: 12/06/2021
Event Time: 11:25 [EST]
Last Update Date: 12/06/2021
Notification Time: 18:14 [ET]
Event Date: 12/06/2021
Event Time: 11:25 [EST]
Last Update Date: 12/06/2021
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):
Miller, Mark (R2)
Miller, Mark (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
EN Revision Imported Date: 1/6/2022
EN Revision Text: VALID SAFETY SYSTEM ACTUATION
"On December 6, 2021, at 1125 hours Eastern Standard Time (EST), during planned maintenance activities, electrical power was lost to the 4160V emergency bus E-3. The power loss to emergency bus E-3 affected both Unit 1 and 2. Emergency Diesel Generator #3 received an automatic start signal but was under clearance for planned maintenance. Emergency bus E-3 was re-energized at 1315 EST hours via offsite power.
"The loss of power to E3 resulted in Unit 2 Primary Containment Isolation System (PCIS) Group 2 (i.e., Drywell Equipment and Floor Drain, Residual Heat Removal (RHR) Discharge to Radwaste, and RHR Process Sample), Group 3 (i.e., Reactor Water Cleanup), Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling Systems), and Group 10 (i.e., air isolation to the drywell) isolations. The actuations of PCIVs were completed and the affected equipment responded as designed. Per design, no Unit 1 safety system group isolations or actuations occurred. Other Unit 2 actuations included the Reactor Building Ventilation System isolation (i.e., Secondary Containment isolation), and the automatic start signal to the Standby Gas Treatment (SGT) System trains A and B and the Control Room Emergency Ventilation System (CREV). Systems functioned as designed. Safety systems functioned as designed following the de-energization of bus E-3.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of PCIS on Unit 2 and an automatic start signal to Emergency Diesel Generator #3.
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Except for the Emergency Diesel Generator, which is out of service for planned maintenance, all equipment has been returned to its normal alignment.
* * * UPDATE FROM JJ STRNAD TO THOMAS KENDZIA AT 2028 EST ON DECEMBER 6, 2021 * * *
"The loss of power to E3 resulted in Unit 1 Primary Containment Isolation System (PCIS) Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling Systems). Other Unit 1 actuations included the Reactor Building Ventilation System isolation (i.e., Secondary Containment isolation), and the automatic start signal to the Standby Gas Treatment (SGT) System trains A and B and the Control Room Emergency Ventilation System (CREV). Systems functioned as designed. Safety systems functioned as designed following the de-energization of bus E-3.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of PCIS on Unit 1."
All Unit 1 equipment was returned to its normal alignment. The NRC Resident will be notified.
Notified R2DO (Miller).
EN Revision Text: VALID SAFETY SYSTEM ACTUATION
"On December 6, 2021, at 1125 hours Eastern Standard Time (EST), during planned maintenance activities, electrical power was lost to the 4160V emergency bus E-3. The power loss to emergency bus E-3 affected both Unit 1 and 2. Emergency Diesel Generator #3 received an automatic start signal but was under clearance for planned maintenance. Emergency bus E-3 was re-energized at 1315 EST hours via offsite power.
"The loss of power to E3 resulted in Unit 2 Primary Containment Isolation System (PCIS) Group 2 (i.e., Drywell Equipment and Floor Drain, Residual Heat Removal (RHR) Discharge to Radwaste, and RHR Process Sample), Group 3 (i.e., Reactor Water Cleanup), Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling Systems), and Group 10 (i.e., air isolation to the drywell) isolations. The actuations of PCIVs were completed and the affected equipment responded as designed. Per design, no Unit 1 safety system group isolations or actuations occurred. Other Unit 2 actuations included the Reactor Building Ventilation System isolation (i.e., Secondary Containment isolation), and the automatic start signal to the Standby Gas Treatment (SGT) System trains A and B and the Control Room Emergency Ventilation System (CREV). Systems functioned as designed. Safety systems functioned as designed following the de-energization of bus E-3.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of PCIS on Unit 2 and an automatic start signal to Emergency Diesel Generator #3.
There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
Except for the Emergency Diesel Generator, which is out of service for planned maintenance, all equipment has been returned to its normal alignment.
* * * UPDATE FROM JJ STRNAD TO THOMAS KENDZIA AT 2028 EST ON DECEMBER 6, 2021 * * *
"The loss of power to E3 resulted in Unit 1 Primary Containment Isolation System (PCIS) Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling Systems). Other Unit 1 actuations included the Reactor Building Ventilation System isolation (i.e., Secondary Containment isolation), and the automatic start signal to the Standby Gas Treatment (SGT) System trains A and B and the Control Room Emergency Ventilation System (CREV). Systems functioned as designed. Safety systems functioned as designed following the de-energization of bus E-3.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of PCIS on Unit 1."
All Unit 1 equipment was returned to its normal alignment. The NRC Resident will be notified.
Notified R2DO (Miller).
Agreement State
Event Number: 55628
Rep Org: MA Radiation Control Program
Licensee: Amherst College
Region: 1
City: Amherst State: MA
County:
License #: 03-5707
Agreement: Y
Docket:
NRC Notified By: Szymon Mudrewicz
HQ OPS Officer: Mike Stafford
Licensee: Amherst College
Region: 1
City: Amherst State: MA
County:
License #: 03-5707
Agreement: Y
Docket:
NRC Notified By: Szymon Mudrewicz
HQ OPS Officer: Mike Stafford
Notification Date: 12/06/2021
Notification Time: 18:30 [ET]
Event Date: 12/06/2021
Event Time: 14:35 [EST]
Last Update Date: 12/06/2021
Notification Time: 18:30 [ET]
Event Date: 12/06/2021
Event Time: 14:35 [EST]
Last Update Date: 12/06/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Dentel, Glenn (R1)
NMSS_Events_Notification, (EMAIL)
Dentel, Glenn (R1)
NMSS_Events_Notification, (EMAIL)
EN Revision Imported Date: 1/6/2022
EN Revision Text: AGREEMENT STATE - LEAKING SEALED SOURCE
The following was received from the Massachusetts Radiation Control Program (the Agency) via email:
"On December 6, 2021 at 1435 EST the Massachusetts Radiation Control Program received a call from the [Radiation Safety Officer] RSO at Amherst College reporting a leaking sealed source. The source is an open-window reference source (RM Corp, s/n R8023) containing 0.001 milliCi of Am-241 and the RSO believes he accidentally wiped the window while collecting the leak test sample of the source, the analysis of which showed 0.0908 microCi of removable activity which is in excess of regulatory limits. The RSO collected the leak test sample on November 29, 2021 at 0930 EST and sent it the same day to RSCS, Inc. for analysis. The leak test results were transmitted to the RSO by email on December 2, 2021 but the RSO was on vacation from December 2 through December 3 and was unable to review the email. The RSO was back at work on December 6, 2021 and reviewed the email at 1230 EST due to previous work commitments in the morning. The area where the source was handled was surveyed and no contamination was found. The RSO assumes the source window was damaged due to being wiped therefore the source will be secured and properly disposed of in accordance with the regulations.
"The Agency considers this event open."
Massachusetts Event Number: TBD
EN Revision Text: AGREEMENT STATE - LEAKING SEALED SOURCE
The following was received from the Massachusetts Radiation Control Program (the Agency) via email:
"On December 6, 2021 at 1435 EST the Massachusetts Radiation Control Program received a call from the [Radiation Safety Officer] RSO at Amherst College reporting a leaking sealed source. The source is an open-window reference source (RM Corp, s/n R8023) containing 0.001 milliCi of Am-241 and the RSO believes he accidentally wiped the window while collecting the leak test sample of the source, the analysis of which showed 0.0908 microCi of removable activity which is in excess of regulatory limits. The RSO collected the leak test sample on November 29, 2021 at 0930 EST and sent it the same day to RSCS, Inc. for analysis. The leak test results were transmitted to the RSO by email on December 2, 2021 but the RSO was on vacation from December 2 through December 3 and was unable to review the email. The RSO was back at work on December 6, 2021 and reviewed the email at 1230 EST due to previous work commitments in the morning. The area where the source was handled was surveyed and no contamination was found. The RSO assumes the source window was damaged due to being wiped therefore the source will be secured and properly disposed of in accordance with the regulations.
"The Agency considers this event open."
Massachusetts Event Number: TBD
Agreement State
Event Number: 55630
Rep Org: PA Bureau of Radiation Protection
Licensee: Thomas Jefferson Univ. Hospitals
Region: 1
City: Philadelphia State: PA
County:
License #: PA-0130
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Bethany Cecere
Licensee: Thomas Jefferson Univ. Hospitals
Region: 1
City: Philadelphia State: PA
County:
License #: PA-0130
Agreement: Y
Docket:
NRC Notified By: John Chippo
HQ OPS Officer: Bethany Cecere
Notification Date: 12/08/2021
Notification Time: 09:01 [ET]
Event Date: 12/06/2021
Event Time: 00:00 [EST]
Last Update Date: 12/08/2021
Notification Time: 09:01 [ET]
Event Date: 12/06/2021
Event Time: 00:00 [EST]
Last Update Date: 12/08/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Dentel, Glenn (R1)
NMSS_Events_Notification, (EMAIL)
Dentel, Glenn (R1)
NMSS_Events_Notification, (EMAIL)
EN Revision Imported Date: 1/7/2022
EN Revision Text: AGREEMENT STATE REPORT - UNDERDOSE OF Y-90
The following was received from the Commonwealth of Pennsylvania by email:
"On December 6, 2021, a patient underwent a Y-90 TheraSphere treatment. There were no apparent issues during the treatment, but the four-sided equipment readings before and after treatment indicated that only 63% of the prescribed dosage got into the patient. The prescribed dose was 4.08 GBq and the calculated received dose was 2.57 GBq. Preliminarily the licensee believes there was a flow issue and the micro catheter caused some of the material to precipitate out. The licensee is currently investigating to determine if that is the cause. The patient and physician have been informed. No adverse effects to the patient are anticipated."
PA Event Report ID No: PA210019
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
EN Revision Text: AGREEMENT STATE REPORT - UNDERDOSE OF Y-90
The following was received from the Commonwealth of Pennsylvania by email:
"On December 6, 2021, a patient underwent a Y-90 TheraSphere treatment. There were no apparent issues during the treatment, but the four-sided equipment readings before and after treatment indicated that only 63% of the prescribed dosage got into the patient. The prescribed dose was 4.08 GBq and the calculated received dose was 2.57 GBq. Preliminarily the licensee believes there was a flow issue and the micro catheter caused some of the material to precipitate out. The licensee is currently investigating to determine if that is the cause. The patient and physician have been informed. No adverse effects to the patient are anticipated."
PA Event Report ID No: PA210019
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.