Event Notification Report for January 10, 2022

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
01/07/2022 - 01/10/2022

!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Fuel Cycle Facility
Event Number: 55564
Facility: Louisiana Energy Services
RX Type:
Comments: Uranium Enrichment Facility
Gas Centrifuge Facility
Region: 2
City: Eunice   State: NM
County: Lea
License #: SNM-2010
Docket: 70-3103
NRC Notified By: Blake Bixenman
HQ OPS Officer: Michael Bloodgood
Notification Date: 11/05/2021
Notification Time: 18:06 [ET]
Event Date: 11/05/2021
Event Time: 12:07 [MDT]
Last Update Date: 01/07/2022
Emergency Class: Non Emergency
10 CFR Section:
70.50(b)(2) - Safety Equipment Failure
Person (Organization):
NMSS_EVENTS_NOTIFICATION (EMAIL)
Miller, Mark (R2DO)
Event Text
EN Revision Imported Date: 1/10/2022

EN Revision Text: LOSS OF HIGH RADIATION AUDIBLE ALARM

"On November 5th, 2021, [1207 MDT] it was identified that a portable Area Radiation Monitor (ARM), which was performing the 10 CFR 70.24 safety function of the Criticality Accident Alarm System (CAAS) to energize clearly audible alarm signals if accidental criticality occurs, had been removed from the area in error.

"On July 20th, 2021, during routine CAAS maintenance, UUSA [Urenco USA] staff identified an area in which a CAAS alarm was not clearly audible. UUSA arranged the ARM as a compensatory measure which achieves an equivalent 10 CFR 70.24 safety function in the affected area. UUSA reported this event to the NRC under Event Notification 55480 in accordance with 10 CFR 70.50(b)(2) in which equipment is disabled or fails to function as designed when required by regulation.

"Removal of this ARM resulted in an inability for radiation detectors to energize clearly audible alarm signals if accidental criticality occurs in the affected area. UUSA hereby reports this event in accordance with 10 CFR 70.50(b)(2), in which equipment is disabled or fails to function as designed when required by regulation (10 CFR 70.24)."

The licensee will notify the NRC Region 2 office.

* * * RETRACTION ON 1/7/22 AT 1552 EST FROM BLAKE BIXENMAN TO THOMAS KENDZIA * * *

"On November 5th, 2021, Louisiana Energy Services, LLC, dba Urenco USA, submitted Event Notification (EN) 55564 to the NRC Emergency Operations Center. This event notified the NRC of a 24 hour reportable event where a portable Area Radiation Monitor (ARM) performing a 10 CFR 70.24 safety function of the Criticality Accident Alarm System (CAAS) was removed from service. UUSA reported this event in accordance with 10 CFR 70.50(b)(2), in which equipment is disabled or fails to function as designed when required by regulation (10 CFR 70.24).

"Following this event, UUSA staff revised the calculations defining the Immediate Evacuation Zone (IEZ). The location of the ARM was near the edge of the IEZ boundary and the original calculation was completed prior to construction of the facility. The calculation was reviewed to ensure the boundary was still adequate. UUSA determined the boundary remains adequate with the area in question no longer inside the IEZ. The affected location is now outside of the IEZ. The IEZ is an area where personnel could be subject to an excessive radiation dose in the event of a criticality, required by 10 CFR 70.24(b)(1). Therefore, CAAS equipment subject to the event described in EN 55564 was not required to prevent exposures to radiation and radioactive materials exceeding regulatory limits, or to mitigate the consequences of an accident and does not meet the criteria for a reportable event UUSA herby retracts EN 55564.

"Details related to the revised IEZ boundary determination can be found in UUSA document CALC-S-00150, Rev 1, Immediate Evacuation Zone Calculations at UUSA. "

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The licensee will notify the NRC Region 2 office.

Notified the R2DO (Miller) and NMSS Events Notification (email)


Agreement State
Event Number: 55683
Rep Org: Colorado Dept of Health
Licensee: Element Hotel
Region: 4
City: Superior   State: CO
County:
License #: GL002594
Agreement: Y
Docket:
NRC Notified By: Phillip Peterson
HQ OPS Officer: Lloyd Desotell
Notification Date: 01/03/2022
Notification Time: 12:46 [ET]
Event Date: 12/30/2021
Event Time: 00:00 [MST]
Last Update Date: 01/03/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
Person (Organization):
Werner, Greg (R4)
NMSS_Events_Notification, (EMAIL)
ILTAB, (EMAIL)
Roldan-Otero, Lizette (R4)
Event Text
EN Revision Imported Date: 1/10/2022

EN Revision Text: AGREEMENT STATE REPORT - DESTROYED TRITIUM EXIT SIGNS

The following was sent by the state of Colorado by email:

"On 12/30/2021 - 12/31/2021, the Marshall wildfire damaged or destroyed nearly 1000 buildings in the towns of Superior and Louisville, Colorado. On 01/01/2022, Boulder County released a preliminary address list of affected properties. The Element Hotel is listed on the property list as destroyed. The Element Hotel has registered with Colorado 33 tritium exit signs. Based on photos of the Element Hotel, it is assumed that all 33 tritium exit signs were consumed and destroyed in the fire.

"Isotope: Hydrogen-3
"Manufacturer: Isolite Corporation
"Model: 2000
"Serial numbers: H118210, H118212 - H118241, H118243 - H118244
"Activity: 7.62 Ci per sign (251.46 Ci total)"

Event Report ID No.: CO220001

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


Power Reactor
Event Number: 55691
Facility: Cook
Region: 3     State: MI
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Brent Snyder
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 01/06/2022
Notification Time: 11:06 [ET]
Event Date: 01/06/2022
Event Time: 10:44 [EST]
Last Update Date: 01/06/2022
Emergency Class: Unusual Event
10 CFR Section:
50.72(a) (1) (i) - Emergency Declared
Person (Organization):
Skokowski, Richard (R3)
Veil, Andrea (NRR)
Shuaibi, Mohammed (R3 DRA)
Kennedy, Silas (IR)
Felts, Russell (EO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
EN Revision Imported Date: 1/10/2022

EN Revision Text: UNUSUAL EVENT DECLARED DUE TO A FIRE IN THE AUX CABLE VAULT

The following information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

On 01/06/22 at 1044 (EST), an Unusual Event was declared due to a Fire Detection Actuation in the Unit 1, auxiliary cable vault (EAL H.U 4.1). No fire was detected. Unit 1 and Unit 2 remain at 100 percent power.

The Llcensee notified the NRC Resident Inspector, the state, and local authorities.

Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), and DHS Nuclear SSA (email).

* * * UPDATE FROM DAN WALTER TO TOM KENDZIA AT 1452 (EST) ON 01/06/2022 * * *

At 1441 (EST), DC Cook Unit 1 terminated their notification of unusual event. The basis for termination was that the inspection identified no damage to cables or cable trays. The fire protection system is out of service for the auxiliary cable vault with compensatory measures in effect.

The licensee has notified the state and local authorities and will notify the NRC Resident Inspector.

Notified R3DO (Skokowski), IRD MOC (Grant), NRR EO (Felts), IR (Kennedy)(email), NRR (Veil)(email), R3 DRA (Shuaibi)(email), DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).


Power Reactor
Event Number: 55692
Facility: South Texas
Region: 4     State: TX
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Long Han
HQ OPS Officer: Kerby Scales
Notification Date: 01/06/2022
Notification Time: 12:29 [ET]
Event Date: 01/06/2022
Event Time: 06:03 [CST]
Last Update Date: 01/06/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
Roldan-Otero, Lizette (R4)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
Event Text
EN Revision Imported Date: 1/10/2022

EN Revision Text: SPECIFIED SYSTEM ACTUATION - AUTO START EMERGENCY DIESEL GENERATOR

"At 0603 CST on 1/6/2022, with Unit 2 in Mode 1 at 100 percent power, the South Texas Project (STP) south switchyard electrical bus was de-energized momentarily and re-energized approximately 40 seconds later. Emergency Diesel Generators (EDG) 22 automatically started in response to loss of offsite power on Train B Engineered Safety Feature (ESF) Bus.

"This event is reportable under 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in the valid actuation of an emergency AC electrical power system (50.72(b)(3)(iv)(B)(8)).

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

Unit 2 is in a 72 hour LCO per TS 3.8.1.1.A for the loss of one offsite power supply. The plant is in a normal electrical lineup. There was no impact on Unit 1.


Power Reactor
Event Number: 55693
Facility: Saint Lucie
Region: 2     State: FL
Unit: [2] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: Stacey Dyer
HQ OPS Officer: Thomas Kendzia
Notification Date: 01/06/2022
Notification Time: 20:51 [ET]
Event Date: 01/06/2022
Event Time: 19:37 [EST]
Last Update Date: 01/06/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts
Person (Organization):
Miller, Mark (R2)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 68 Power Operation 35 Power Operation
Event Text
EN Revision Imported Date: 1/10/2022

EN Revision Text: SHUTDOWN INITIATED IN ACCORDANCE WITH TECHNICAL SPECIFICATIONS

"On January 6, 2022 at 1937 [EST], St Lucie Unit 2 commenced a reactor shutdown as required by Technical Specification 3.1.3.1 Action 'e', due to Control Element Assembly number 27 slipping from 133 inches to 120 inches withdrawn and unable to be recovered within the prescribed time limits."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

Unit 2 entered 6 hour LCO to shutdown to mode 3 at 1539 EST as required by Technical Specification 3.1.3.1 Action 'e'. There was no impact on Unit 1.


Power Reactor
Event Number: 55694
Facility: Comanche Peak
Region: 4     State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Sean Woods
HQ OPS Officer: Brian P. Smith
Notification Date: 01/07/2022
Notification Time: 09:32 [ET]
Event Date: 01/07/2022
Event Time: 01:20 [CST]
Last Update Date: 01/07/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(xiii) - Loss Comm/Asmt/Response
Person (Organization):
Lizette Roldan-Otero (R4DO)
Power Reactor Unit Info
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
Event Text
LOSS OF METEOROLOGICAL EMERGENCY ASSESSMENT CAPABILITY

The following information was provided by the licensee via fax or email:

"At 0120 [CST] on 01/07/2022, a partial loss of the 25KV Power Distribution System caused a loss of both the Primary and Backup Meteorological Towers at the Comanche Peak Nuclear Power Plant. This resulted in a loss of emergency assessment capability with regard to meteorological conditions.

"A backup diesel generator for the primary Meteorological Tower did not start due to a dead battery. After the battery issue was resolved, the diesel generator started but it subsequently tripped due to a loose fuse.

"The 25 KV Plant Support Power Loop feeds certain non-safety-related equipment and does not affect plant operation. Power was restored to both Meteorological Towers at 0305 [CST] on 01/07/2022 and proper operation was verified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The NRC Resident Inspector was notified.


Power Reactor
Event Number: 55698
Facility: Callaway
Region: 4     State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: Robert Shadbolt
HQ OPS Officer: Thomas Kendzia
Notification Date: 01/07/2022
Notification Time: 16:29 [ET]
Event Date: 01/07/2022
Event Time: 12:23 [CST]
Last Update Date: 01/07/2022
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
Person (Organization):
Roldan-Otero, Lizette (R4)
Power Reactor Unit Info
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
Event Text
AUTOMATIC TURBINE TRIP / REACTOR TRIP

The following information was provided by the licensee via email:

"At 1223 CST on January 7, 2022, Callaway Plant was in Mode 1 at approximately 100 percent power when a turbine trip / reactor trip occurred. All safety systems responded as expected with the exception of an indication issue with the 'B' Feedwater Isolation Valve, which was confirmed closed. A valid Feedwater Isolation Signal and Auxiliary Feedwater Actuation Signal were also received as a result of the reactor trip. The plant is being maintained stable in Mode 3.

"All control rods fully inserted from the reactor trip signal, and decay heat is being removed via the Auxiliary Feedwater and Steam Dump Systems.

"The NRC Senior Resident Inspector was notified."

The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:

The plant is in a normal shutdown electrical lineup.

Page Last Reviewed/Updated Monday, January 10, 2022