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EN Revision Imported Date : 3/19/2020 POTENTIALLY CONTAMINATED INDIVIDUAL TRANSPORTED TO AN OFFSITE MEDICAL FACILITY At 2340 CDT, on October 09, 2019, a site contractor was transported offsite for treatment at an offsite medical facility. Due to the nature of the medical emergency, the individual was not thoroughly surveyed prior to being transported offsite. 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). Following the individual being transported offsite, but prior to the individual arriving at the offsite medical facility, the individual was confirmed to not be contaminated. This occurred at approximately 2350 CDT, on October 09, 2019. The NRC Resident Inspector has been notified.

• * * RETRACTION ON 3/18/2020 AT 1350 EST FROM RICHARD LENGFORD TO BRIAN LIN * * *

Farley Nuclear Plant is retracting this notification based on the information available at the time of the notification: Health Physics personnel had completed surveys that determined that the contract worker, ambulance, and responders were free of contamination prior to reaching the hospital. The initial report was made to alert the NRC based on the individual being potentially contaminated due to radioactive surveying being deferred to support prompt medical attention. Based on the subsequent determination that the individual was not contaminated the reporting requirements of 10CFR50.72(b)(3)(xii) are not met and this event report is being retracted. The NRC Resident Inspector has been notified. Notified R2DO (Miller).

EN Revision Text: MANUAL REACTOR TRIP DUE TO MISALIGNED CONTROL ROD At 1643 (CDT), with Unit 2 in Mode 2 during low power physics testing, the reactor was manually tripped per procedure due to a misaligned control rod. The trip was not complex, with all systems responding normally post-trip. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the atmosphere using the atmospheric relief valves. Unit 1 is not affected. Due to the Reactor Protection System actuation, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.

• * * UPDATE ON 05/08/2019 AT 1212 EDT FROM MIKE CONNER TO JEFFREY WHITED * * *

This Event Notification is being updated to clarify that the reactor was not critical when this event occurred. Therefore, the reporting requirement is changed from 10 CFR 50.72(b)(2)(iv)(B) to 10 CFR 50.72 (b)(3)(iv)(A). The reactor was tripped during low power physics testing. The misaligned rod was encountered during rod group insertion and the affected bank had been inserted to the extent that the reactor was subcritical when the operators tripped the reactor. The licensee notified the NRC Resident Inspector. Notified R2DO (Lopez)

On January 9, 2018, at 1759 CST, during review of NFPA 805 requirements and circuit analysis, it was determined that the NFPA 805 analysis and Fire Safe Shutdown Modeling did not consider all fire-induced failures. As such, a condition could possibly exist during a postulated fire where both safety related electrical trains could be impacted. This notification is to report a condition involving the fire safe shutdown analysis. The condition could result in an adverse impact on the ability of operators to respond to a postulated fire in these areas. Therefore, this notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(B), any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. Compensatory fire watches have been established in the affected areas. The licensee notified the NRC Resident Inspector.

• * * RETRACTION FROM ANTONIO BENFORD TO HOWIE CROUCH AT 1752 EST ON 2/28/18 * * *

Following additional refinements to the NFPA 805 Fire PRA Model, the circuits which initiated the initial report of an unanalyzed condition have now been evaluated and have proven that no significant degradation to plant safety existed. Therefore, EN 53159 is being retracted. The NRC Resident Inspector has been notified. Notified R2DO (Michel).

At 1743 CDT on 11/1/16, readings were obtained that indicated ammonia above IDLH (Immediately Dangerous to Life and Health) values in the Unit 1 Auxiliary Building and an Alert was declared by the Emergency Director. The plant is stable with Unit 1 at 2% power. Unit 2 is at 100% power (and stable). The site is currently investigating to determine the source and ventilate the area." The licensee has informed the NRC Resident Inspector. Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, FEMA National Watch Center (email), FDA EOC (email), Nuclear SSA (email).

• * * UPDATE FROM BLAKE MITCHELL TO STEVEN VITTO ON 11/02/2016 AT 0443 EDT * * *

The following is the Emergency Preparedness 8-hour report for the Plant Farley ALERT declaration. An ALERT was declared at 1743 CDT on November 1, 2016, based on Emergency Action Level (EAL) HA3 (Release of toxic, asphyxiant, or flammable gases within vital areas which jeopardizes operation of systems required to maintain safe operations or establish or maintain safe shutdown) due to an ammonia discharge into the Auxiliary Building. Farley Unit 1 was in Mode 2 at 2 percent power and Unit 2 was in Mode 1 at 100 percent power throughout the event. Actions completed during and leading up to termination from the event included walkdown of the area to locate the ammonia source, and isolating the ammonia source while atmospheric monitoring was performed in all affected and adjacent areas. Installation of additional ventilation fans was completed. This event has been entered into the Farley Corrective Action Program under Condition Report 10293519 (Ammonia levels in 100 Feet Radside). A review of the Alert classification has determined that the classification was timely and accurate. All required notifications were completed accurately and in a timely manner. The ERO (Emergency Response Organization) notification system functioned as expected and all emergency response facilities were activated in a timely manner. There were no missing or injured personnel during the event. There is no evidence of tampering or sabotage of plant equipment leading to this event. At 2202 CDT on 11/1/2016, the ammonia source was identified as Valve N1P20V913. At 2228 CDT, the ammonia source was isolated. Final assessment of the Auxiliary Building showed that the ammonia levels were less than 5 ppm. It was determined that a deficiency in the valve component was the cause of the ammonia leak. The Alert was terminated on 11/1/2016 at 2340 CDT. The Licensee has notified the NRC Resident Inspector. Notified R2DO(Ernstes), IRD (Stapleton), NRR EO (Miller). Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, FEMA National Watch Center (email), FDA EOC (email), Nuclear SSA (email).

At 1209 CDT on 8/5/16, during testing of Unit 2 Auxiliary Building Pre-action Sprinkler Systems, all zones on the Unit 2 Pyrotronics Fire Detection Panel went into an alarm state and were unable to be reset. This condition is reportable per 10 CFR 50.72(b)(3)(xiii) as a Major Loss of Assessment capability. The NRC Resident has been notified. The licensee has initiated all necessary compensatory and corrective actions.

• * * UPDATE FROM BLAKE MITCHELL TO VINCE KLCO AT 1718 EDT ON 8/6/2016 * * *

At 1600 CDT on 8/6/16, the Unit 2 Pyrotronics Fire Detection Panel was declared functional following repair of master override reset test switch and supply fuse. The Pyrotronics Fire Detection Panel was successfully tested following maintenance. The emergency assessment capability for the site's Emergency Plan has been fully restored. The NRC Resident has been notified Notified the R2DO (Suggs).

This notification is being made due to a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). At 0600 CDT on 4/14/14, it was determined that the ability to obtain a post-accident hydrogen sample from Unit 1 containment was lost. With both trains of Post-Accident Hydrogen Analyzers (PAHA) out of service, it was discovered that there was reduced sample flow indicated on the backup methodology through a containment sample port (R67). Repair efforts are underway. A follow-up notification will be sent when assessment capability is restored. The NRC Resident Inspector has been notified.

• * * UPDATE FROM DARRIN GARD TO CHARLES TEAL AT 1425 EDT ON 4/15/14 * * *

Assessment capability has been restored as of 1933 EDT on April 14, 2014 utilizing the containment particulate rad monitor sample port R-67. The licensee has notified the NRC Resident Inspector. Notified R2DO (Widmann).

At 0842 CST on February 28, 2014, the Unit 1 Pyro Panel (fire/smoke detection panel) was removed from service for required maintenance. The Pyro Panel was declared non-functional when it was removed from service. Compensatory measures have been established for all affected areas except the Unit 1 Containment Building. Since a fire in the Containment Building is an entry condition for the site's Emergency Plan, this is considered a loss of emergency assessment capability and is being reported per 10CFR50.72(b)(3)(xiii). Containment temperature is being monitored while the pyro panel is out of service, however this is not considered a satisfactory compensatory measure for maintaining effective assessment capability. A courtesy follow up notification will be sent when the pyro panel is returned to service and functional. The NRC Resident Inspector has been informed.

• * * UPDATE FROM RICHARD LULLING TO CHARLES TEAL AT 2215 EST ON 2/28/14 * * *

At 1704 CST on 2/28/2014 the Unit 1 Pyro Panel was declared functional following the return of the fire indicating unit (FIU) to the original status. The Pyro Panel fire detection system was successfully tested following the maintenance. The emergency assessment capability for the site's Emergency Plan has been fully restored concerning a containment fire. The Senior NRC Resident Inspector has been informed. Notified R2DO (McCoy).

At 10:20 (CST) on January 18, 2014, the Unit 2 Pyro Panel (fire/smoke detection panel) was declared non-functional due to an unknown equipment problem. Compensatory measures (e.g. continuous roving fire watches) have been established for all affected areas with the exception of the Unit 2 Containment Building. Containment fire watches have been established per the FSAR, which includes monitoring various temperatures, pressures, and other parameters for Containment, and systems associated with containment. However, this is not considered a satisfactory compensatory measure for maintaining effective assessment capability. Since a fire in Containment is an entry condition for the site's Emergency Plan, this is considered a loss of emergency assessment capability, and is being reported per 10CFR50.72(b)(3)(xiii). The NRC Senior Resident Inspector has been informed.

• * * UPDATE FROM RICK LULLING TO DANIEL MILLS AT 0700 EST ON 1/20/14 * * *

At 0404 CST on 1/20/14 the Unit 2 Pyro panel was declared functional following the replacement of the fire indicating unit (FIU) and the power supply, and successful post maintenance testing. The emergency assessment capability for the site's Emergency Plan has been fully restored concerning a Containment fire. The licensee notified the NRC Resident Inspector. Notified R2DO (King).

At 1454 CST on December 16, 2013, the Unit 1 pyro panel (smoke detection panel) was declared non-functional due to an unexpected failure. Viable compensatory measures have been established for all affected areas except the Unit 1 Containment Building. Since a fire in Containment is an entry condition for the site's Emergency Plan, this is considered a loss of emergency assessment capability and is being reported per 10CFR50.72(b)(3)(xiii). Containment temperatures are being monitored while the pyro panel is out of service, however, this is not considered a satisfactory compensatory measure for maintaining effective assessment capability. The NRC Resident Inspector has been notified.

• * * UPDATE AT 2046 EST ON 12/17/13 FROM DARRIN GARD TO DANIEL MILLS * * *

The Unit 1 pyro panel has been returned to service as of 1554 CST on 12/17/13, which restores Unit 1 containment fire detection capability. The NRC Resident Inspector has been notified. Notified R2DO (Freeman).

This is a report of a loss of emergency assessment capability as required by 10CFR50.72(b)(3)(xiii). On October 7, 2013 at 1804 CDT, with Unit 1 in Mode 6 during a refueling outage, power was interrupted to all Unit 1 vent stack radiation monitors and area radiation monitors as part of a pre-planned activity to connect the radiation monitors to an alternate temporary power supply to support deenergizing the normal power source for preventative maintenance. The connection to the alternate supply was completed and power was restored to the vent stack radiation monitors and area radiation monitors at 1833 CDT. While the radiation monitors were without power, pre-planned compensatory measures were implemented where possible to monitor vent stack discharge and to minimize activities that posed a potential for release. At the completion of the preventive maintenance on the normal power supply, power to the vent stack radiation monitors and area radiation monitor will again be briefly interrupted to reconnect the normal power source to the monitors. The pre-planned compensatory measures will again be utilized during this power interruption. An update to this report will be provided following the restoration of normal power to the radiation monitors. The NRC Resident Inspector has been informed.

• * * UPDATE FROM DARRIN GARD TO JOHN SHOEMAKER AT 0419 EDT ON 10/13/13 * * *

On October 13, 2013 at 0217 CDT, with Unit 1 in defueled mode during a refueling outage, power was interrupted to all Unit 1 vent stack radiation monitors and area radiation monitors as part of a pre-planned activity to transfer the radiation monitors back to their normal power supply. The connection to the normal supply was completed and power was restored to the vent stack radiation monitors and area radiation monitors at 0245 CDT. Pre-planned compensatory measures were implemented where possible to monitor vent stack discharge and to minimize activities that posed a potential for release. Notified R2DO (Widmann) and the licensee will notify the NRC Resident Inspector.