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 Start dateSiteRegionReactor typeEvent description
ENS 5732516 September 2024 17:29:00FermiNRC Region 3GE-4The following information was provided by the licensee via phone and email: On September 16, 2024, at 1329 EDT, the Fermi 2 active seismic monitoring system provided indication of a potential seismic activity event. Plant abnormal procedures were entered and compensatory measures were met and remain in place. Neither the United States Geological Survey (USGS), nor the next closest nuclear power plant could confirm or validate the readings obtained at Fermi. The seismic monitoring system was declared inoperable to validate the calibration of the system. Fermi 2 has two active seismic monitors. One on the reactor pressure vessel pedestal and one in the high pressure core injection (HPCI) room. Only the HPCI room seismic monitor was declared inoperable. The HPCI room accelerometer is the sole 'trigger' for the seismic recording system (which outputs peak accelerations experienced during a seismic event) and the associated control room alarm. This is used in assessment of the magnitude of an earthquake for emergency action level HU 2.1. The loss of the active seismic monitoring system is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). No seismic activity has been felt onsite and the USGS recorded no seismic activity in the area. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The licensee confirmed alternative means of recognizing a seismic event for emergency plan entry are available.
ENS 5704623 March 2024 04:04:00FermiNRC Region 3GE-4

The following information was provided by the licensee via email: At 0004 EDT on March 23, 2024, with the unit in Mode 1 at 23 percent power, the reactor automatically scrammed due to high reactor pressure vessel pressure when the turbine bypass valves unexpectedly closed while attempting to lower generator MW to 55 MWe to support shutdown for a refueling outage. The scram was not complex, with systems responding normally post-scram, with the exception of the pressure control system. The transient occurred while lowering on turbine speed/load demand which caused a rise in pressure and power until the reactor protection system setpoint for reactor pressure high was exceeded and resulted in an automatic reactor scram. The plant was preparing to shut down for a refueling outage when the trip occurred. Operations responded and stabilized the plant. Reactor water level is being maintained at normal level. Decay heat is being removed by the main steam system to the main condenser using manual operation of the turbine bypass valves. All control rods inserted into the core. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CPR 50.72(b)(2)(iv)(B). Additionally, received expected (primary containment) isolations for Level 3: Group 13 drywell sumps, Group 15 (traverse in-core probe) TlPs (which was already isolated) and Group 4 (residual heat removal - shutdown cooling) RHR-SDC (which was already isolated). The primary containment isolation event is being reported under 10 CFR 50.72(b)(3)(iv)(A). Also, due to the main turbine bypass valves unexpectedly closing, this is also being reported under 10 CFR 50.72(b)(3)(v)(D). There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.

  • * * UPDATE ON 4/22/24 AT 1448 EDT FROM WHITNEY HEMINGWAY TO ADAM KOZIOL * * *

The purpose of this notification is to retract the 10 CFR 50.72(b)(3)(v)(D) reporting criteria of event notification 57046 reported on March 23,2024. Based on further evaluation, Fermi 2 has concluded that there was no event or condition that could have prevented fulfillment of a safety function that was needed to mitigate the consequence of an accident. Although discussed in Chapter 15 of the UFSAR, the turbine bypass valves do not provide a safety related function and are not credited safety related components for accident mitigation. Therefore, Fermi 2 is retracting the 10 CFR 50.72(b)(3)(v)(D) reporting criteria that was included on the March 23, 2024 event notification. Notified R3DO (Betancourt-Roldan)

ENS 5668520 August 2023 20:00:00FermiNRC Region 3GE-4The following information was provided by the licensee via email: On 8/20/2023 at 1600 EDT, during plant walkdowns in the drywell while in mode 3 to identify a cause of increasing unidentified leakage rate, reactor coolant system pressure boundary leakage (approximately 2 gpm) was identified on the reactor recirculation sample line between the reactor recirculation sample line inboard isolation valve (B3100F019) and where the sample line taps off the B reactor recirculation jet pump riser. This requires entry into technical specification 3.4.4 condition C, identification of pressure boundary leakage with a required action to be in mode 3 in 12 hours and mode 4 in 36 hours. At 1630 EDT, a technical specification required shutdown to mode 4, cold shutdown, was initiated. A press release by DTE is anticipated. This event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i), a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(xi), and an eight-hour, non-emergency notification 10 CFR 50.72(b)(3)(ii)(A) for the degraded condition of the pressure boundary. Investigation into the cause of the reactor coolant system pressure boundary leakage is still ongoing. There was no impact on the health and safety of the public or plant personnel. The NRC resident inspector has been notified.
ENS 566501 August 2023 13:55:00FermiNRC Region 3GE-4The following information was provided by the licensee via email: On 08/01/2023 at 0955 EDT, the Fermi 2 active seismic monitoring system provided indication of a potential seismic activity event. Plant abnormal procedures were entered, and compensatory measure were met and remain in place. Neither the (United States Geological Survey) (USGS) nor the next closest nuclear power plant could confirm or validate the readings obtained at Fermi. The seismic monitoring system was declared nonfunctional to validate the calibration of the system. Femi 2 has two active seismic monitors: one on the reactor pressure vessel pedestal and one in the high-pressure core injection (HPCI) room. Only the HPCI room accelerometer was declared inoperable. The HPCI accelerometer is the sole 'trigger' for the seismic recording system, which outputs peak accelerations experienced during a seismic event. This is used in assessment of the magnitude of an earthquake for EAL HU 2.1. The loss of the active seismic monitoring system is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). No seismic activity has been felt onsite and the USGS recorded no seismic activity in the area. The NRC Resident Inspector has been notified.
ENS 5657013 June 2023 03:33:00FermiNRC Region 3GE-4

The following information was provided by the licensee via email: At 2333 EDT on June 12, 2023, the division 2 Mechanical Draft Cooling Tower (MDCT) Fan `D' was declared inoperable due to a trip of the fan while running in high speed. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the division 2 Emergency Equipment Cooling Water (EECW) system. The EECW system cools various safety related components, including the High-Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on a loss of the HPCI room cooler. The cause of MDCT Fan `D' trip is currently unknown with trouble shooting being developed for remediation of the condition. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The NRC Senior Resident Inspector has been notified.

  • * * RETRACTION AT 1540 EDT ON 8/8/2023 FROM WHITNEY HEMINGWAY TO BILL GOTT * * *

The purpose of this notification is to retract a previous event notification (EN) 56570 reported on June 13, 2023, at 0602 EDT. The cause of the fan trip was a failed vibration switch. At 0429 EDT on June 14, 2023, the vibration switch was replaced, the MDCT fan "D" was tested satisfactory for operability, and the UHS, emergency diesel generator 13/14, and MDCT were declared operable. Following the initial EN, further analysis of the condition was performed utilizing a previously performed gothic analysis model (to perform HPCI room heat-up calculations) which bounded this condition. Based on the initial conditions at the time of the indication loss, specifically HPCI room and suppression pool temperature, it was determined that the resulting worst case post-accident room temperature was sufficiently low enough to provide margin to HPCI operability without the room cooler in service for the required mission time. No other concerns were noted during the event. HPCI remained operable and there was no loss of safety function. The fan trip did not involve a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident under 10 CFR 50.72(b)(3)(v)(D). Therefore, the NRC non-emergency 10CFR50.72(b)(3)(v)(D) report was not required and the NRC report 56570 can be retracted, and no licensee event report under 10 CFR 50.73(a)(2)(v)(D) is required to be submitted. The licensee notified the NRC Resident Inspector. Notified R3DO (Nguyen)

ENS 5654225 May 2023 04:00:00FermiNRC Region 3GE-4The following is a summary of the information provided by the licensee via email: As previously reported under Fermi LER 2023-001-00, submitted on May 22, 2023, at 1145 EDT on March 23, 2023, it was determined that all mechanical draft cooling tower (MDCT) fan brakes would not perform their design function during a tornado due to the speed switch not functioning over its published voltage and frequency ranges. The MDCT fan brakes are required to prevent fan overspeed from a design basis tornado. On May 25, 2023, Fermi completed its 10 CFR Part 21 discovery process and determined the need to perform a 10 CFR Part 21 evaluation. The vendor (Engine Systems Inc. (ESI)) was contacted and the purchaser (Fermi) assumed responsibility for performing the Part 21 evaluation for the supplied mechanism. This Part 21 evaluation is being tracked by Fermi CARD 23-20075. It has been determined the direct cause of the event was due to the Dynalco speed switch model SST-2400A-1, supplied by ESI, not functioning over its published voltage and frequency ranges. Corrective actions were taken to develop a design change to correct MDCT fan speed control system returning the MDCT fans, ultimate heat sink, and the service water subsystems to service on March 24, 2023. The root cause evaluation is ongoing, and written follow-up will be provided in 30 days by providing a supplement to the original LER by June 24, 2023. No new commitments are being made in this submittal.
ENS 5642923 March 2023 15:45:00FermiNRC Region 3GE-4The following information was provided by the licensee via fax: While in Mode 1 at 100 percent power at 1145 EDT on March 23, 2023, it was determined that all mechanical draft cooling Tower (MDCT) fan brakes would not perform their design function during a tornado due to a design flaw with the control system. The MDCT fan brakes are required to prevent fan overspeed from a design basis tornado. The MDCT fans are required to support the operability of the ultimate heat sink (UHS). At the time of discovery, the provisions of LCO 3.0.9 were being utilized for loss of the 'D' MDCT fan brake (barrier loss). When it was identified the condition was a design flaw common to all MDCT fan brakes, the 24-hour allowance for restoration was entered. A design change is currently being implemented to restore MDCT fan brake operability. This condition is reportable per 10 CFR 50.72(b)(3)(v)(A), (B), & (D). The NRC Resident Inspector has been notified.
ENS 562954 January 2023 06:48:00FermiNRC Region 3GE-4

The following information was provided by the licensee via email: At 0148 EST on January 4, 2023 it was identified that P4400F603B, Division 2 Emergency Equipment Cooling Water (EECW) Supply Isolation Valve, lost position indication. Division 2 EECW System was declared inoperable due to the potential that this valve may not be capable of performing its safety function to automatically isolate the safety related Division 2 EECW system from the non-safety related Reactor Building Closed Cooling Water (RBCCW) system. Because the Division 2 EECW system provides cooling to the High Pressure Coolant Injection (HPCI) room cooler, HPCI was also declared inoperable; therefore, this condition is being reported as an eight-hour, non--emergency notification per 10 CFR 50.72(b)(3)(v)(D). At 0240 EST, position indication was restored and Division 2 EECW and HPCI was returned to operable following inspection of the associated motor control center (MCC) and testing of the associated fuses. The cause of the loss of indication is under investigation. The Senior NRC resident inspector has been notified.

  • * * RETRACTION ON 3/6/23 AT 1740 EST FROM GREGORY MILLER TO KERBY SCALES * * *

The following retraction was received from the licensee via email: The purpose of this notification is to retract a previous Event Notification, EN 56295, reported on 1/4/2023. Following the initial EN, further analysis of the condition was performed utilizing a gothic analysis model to perform HPCI room heat-up calculations. Based on the initial conditions at the time of the indication loss, specifically HPCI room and Suppression Pool temperature, it was determined that the resulting worst case post-accident room temperature was sufficiently low enough to provide margin to HPCI operability without the room cooler in service for the required mission time. No other concerns were noted during the event. Therefore, HPCI remained operable and there was no loss of safety function. The event did not involve a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident under 10 CFR 50.72(b)(3)(v)(D). Therefore, the NRC non-emergency 10 CFR 50.72(b)(3)(v)(D) report was not required and the NRC report 56295 can be retracted and no Licensee Event Report under 10 CFR 50.73(a)(2)(v)(D) is required to be submitted. The NRC Senior Resident Inspector has been notified. Notified R3DO (Ruiz).

ENS 5624128 November 2022 09:00:00FermiNRC Region 3GE-4

The following information was provided by the licensee via email: At 0400 EST on November 28, 2022, during the performance of Division 2 Residual Heat Removal (RHR) cooling tower fan operability and RHR Service Water valve lineup verification, it was reported that the Mechanical Draft Cooling Tower (MDCT) Fan 'B' was making a loud metallic noise. The cause of the metallic noise is unknown at this time. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the Division 2 Emergency Equipment Cooling Water (EECW) system. The EECW system cools various safety related components including the High Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on inoperable cooling water to the HPCI room cooler, per LCO 3.0.6. Investigation into the Division 2 MDCT Fan 'B' abnormal noise is in progress. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The NRC Resident Inspector has been notified.

  • * * RETRACTION FROM JEFF MYERS TO LLOYD DESOTELL AT 1615 EST ON 12/09/2022 * * *

The following information was provided by the licensee via email: The purpose of this notification is to retract a previous Event Notification 56241 reported on 11/28/2022. On 11/28/22, an event notification to the NRC was made when mechanical draft cooling tower (MDCT) Fan B was declared inoperable and issued Limited Condition of Operation (LCO) 2022-0428 for Division 2 MDCT Fan B abnormal noise. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS) (Technical Specification (TS) 3.7.2). The UHS is required to support operability of the Division 2 Emergency Equipment Cooling Water (EECW) system (TS 3.7.2), which cools various safety related components, including the High-Pressure Coolant Injection (HPCI) system room cooler (TS LCO 3.0.6). Subsequent inspection and evaluation determined that the brake noise is expected while fans are running at low speeds. This is supported by plant technical procedure, 24.205.10 `Div. 2 RHR Cooling Tower Fan Operability and RHRSW Valve Line-up Verification' (line item 2.2 in Precautions and Limitations) which states `Chatter from the brakes of the MDCT Fans is expected and no cause for discontinuing the test.' The equipment vendor stated that brake chatter is possible and common given that the internal components are free to move along the splined connections. Internal Operating Experience from experienced station operators and maintenance technicians confirmed that the condition is normal and expected. Both Division 2 MDCTs exhibited the same behavior at low speed and passed surveillance testing satisfactorily. No other concerns were noted during fan operation. Therefore, HPCI remained operable and there was no loss of safety function. The event did not involve a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident under 10 CFR 50.72(b)(3)(v)(D). EN 56241 is retracted and no Licensee Event Report under 10 CFR 50.73(a)(2)(v)(D) is required to be submitted. The NRC Resident Inspector has been notified. Notified R3DO (Stoedter).

ENS 5608031 August 2022 04:30:00FermiNRC Region 3GE-4A contract supervisor refused to provide a specimen during a fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 5605418 August 2022 01:08:00FermiNRC Region 3GE-4

The following information was provided by the licensee via email: At 2108 EDT on August 17, 2022 the Division 2 Mechanical Draft Cooling Tower (MDCT) fans were declared inoperable due to failure of the over speed fan brake inverter. The brakes prevent fan over speed from a design basis tornado. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the Division 2 Emergency Equipment Cooling Water (EECW) system. The Division 2 EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) room cooler and Division 2 Control Center HVAC (CCHVAC) chiller. An unplanned HPCI inoperability occurred based on a loss of the HPCI Room Cooler. At the time of the event, Division I CCHVAC was inoperable for maintenance (but was running for a maintenance run) and the event caused an inoperability of Division 2 CCHVAC. This resulted in an inoperability of both divisions of CCHVAC. Failure of the Division 2 MDCT Fan brake inverter occurred due to a trip of the DC input breaker. The breaker was reset at 2128 EDT restoring Division 2 UHS Operability. This report is being made pursuant to 10CFR50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfilment of the safety function of structures or systems that are needed to mitigate the consequences of an accident based on a loss of a single train safety system and loss of both divisions of a safety system. The Senior NRC Resident Inspector has been notified

  • * * RETRACTION ON 09/08/2022 AT 0856 EDT FROM JEFF MYERS TO MIKE STAFFORD * * *

The following information was provided by the licensee via email: On 8/17/22 at 2108 EDT the Division 2 (Div. 2) mechanical draft cooling tower (MDCT) brake inverter input breaker tripped for an unknown cause. The result of the loss of power was the inoperability of the MDCT fan brakes which impacts the ultimate heat sink (UHS) (TS 3.7.2). The UHS cascades to the EECW (emergency equipment cooling water) (TS 3.7.2) which is a support system for Div. 2 CCHVAC (Control Cell) Chiller A/C system (TS 3.7.4). This resulted in the inoperability of the Div. 2 CCHVAC Chiller. The cause for the breaker to trip is an intermittent electrical transient. Immediate corrective action was to reset the breaker, and the long-term action is to implement a modification to mitigate susceptibility to voltage variations. Div. 1 has implemented this long-term mod and no unexpected trips have occurred to date. Div. 1 CCHVAC Chiller was previously inoperable from equipment issues which was repaired, and the unit was in service for a 24-hour confidence run. Although licensed personnel had not completed the administrative actions for documenting operability during the 24-hour confidence run to monitor parameters, the (post maintenance test) PMT related to the maintenance was already completed, which included a 4-hour run in accordance with surveillance 24.413.01, Div. 1 and Div. 2 Chilled Water Pump and Valve, to verify normal operation and motor current. These PMT's were completed prior to the identified inoperability of the Div. 2 UHS due to the tripped breaker on the brake power supply. At the time of the MDCT brake inverter trip, the Operations' Senior License and the Night Shift Manager were aligned that, although still operating as part of the 24-hour confidence run, the unit was in service and capable of performing its safety function, but the administrative tasks were not completed, the Limited Condition of Operation (LCO) sheet had not been cleared, and no log entries were made. Since the Div. 1 Chiller was, in fact, operable at the time of the trip of the breaker on the inverter, this would allow the use of Technical Specification (TS) 3.0.9 'Barriers'. Per Operations Department Expectation (ODE)-12 `LCOs' (standard guidance and expectations for preparing and implementing an LCO), Operations determined that the MDCT brakes are barriers to a tornado event and TS 3.0.9 could be utilized. By invoking TS 3.0.9, as long as all other supported systems in the other division are operable, Div. 2 supported systems relying upon the UHS can remain operable and the Automatic Depressurization System (ADS) and Reactor Core Isolation Cooling (RCIC) system can be used as backup to the High Pressure Coolant Injection (HPCI) system. Based on this information, there was no loss of safety function with CCHVAC A/C system or HPCI. Therefore, the NRC non-emergency 10CFR50.72(b)(3)(v)(D) report was not required and the NRC report 56054 can be retracted. The NRC Resident Inspector has been notified. Notified R3DO (Orlikowski)

ENS 5596425 June 2022 03:38:00FermiNRC Region 3GE-4The following information was provided by the licensee via email: At 2338 EDT, on June 24, 2022, with the unit in Mode 1 at 100 percent power, the reactor automatically scrammed due to an RPS actuation following a Main Turbine Trip. The cause of the turbine trip is not known at this time. The scram was not complex, with systems responding normally post-scram. Operations responded and stabilized the plant. Reactor water level has been recovered and maintained at the normal level. Decay Heat is being removed by the Main Steam system to the main condenser using the Turbine Bypass Valves. All Control Rods inserted into the core. The transient occurred with no surveillances or activities in progress. Investigation into the cause of the Turbine Trip is in progress. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The low reactor water level caused an isolation of Primary Containment (Groups 4/13/15) as expected. The Primary Containment Isolation Event is being reported under 10 CFR 50.72(b)(3)(iv)(A). There was no impact to the health and safety of the public or plant personnel. The NRC resident has been notified.
ENS 5589411 May 2022 22:14:00FermiNRC Region 3GE-4The following information was provided by the licensee via email: During performance of High Pressure Coolant Injection (HPCI) Pump and Valve Operability surveillance in accordance with procedure 24.202.01, the turbine tripped without operator action. The plant was operating in Mode 1 at 10 percent power with the HPCI turbine running in a test mode at 5100 gpm with all surveillance criteria met. The surveillance was near completion at the point where the HPCI turbine is manually tripped. Before the manual trip was performed, the HPCI turbine tripped without operator action. Prior to performance of the surveillance, HPCI was provisionally operable with only satisfactory completion of Post Maintenance Testing (PMT) surveillance remaining to declare HPCI operable. HPCI surveillance testing was performed at low reactor pressure (165 psig) in Mode 2 satisfactorily. Investigation into the cause of this trip is in progress. HPCI has been declared inoperable from the time of release of the surveillance. Reactor Coolant Isolation Cooling (RCIC) was verified to be operable prior to and after the surveillance in accordance with Technical Specifications 3.5.1 condition E.1. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 557324 February 2022 22:00:00FermiNRC Region 3GE-4The following information was provided by the licensee via email: At 1700 EST, on February 4, 2022 with the unit in Mode 1 at 58 percent power, the reactor automatically scrammed due to low Reactor water level due to a transient on the Feedwater System while preparing to shutdown for a refueling outage. The scram was not complex, with systems responding normally post-scram. Operations responded and stabilized the plant. Reactor water level has been recovered and maintained at normal level. Decay Heat is being removed by the Main Steam system to the main condenser using the Turbine Bypass Valves. All Control Rods inserted into the core. The transient occurred while in the process of removing the South Reactor Feed Pump from service. While reducing speed on the South, the North Reactor Feed Pump increased in speed and tripped on low suction. The plant was preparing to shut down for a refueling outage when the trip occurred. Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Additionally, in preparation of plant shutdown, Primary Containment De-Inerting was in progress. The low Reactor water level caused an isolation of Primary Containment (Groups 4/13/15). The Primary Containment Isolation Event is being reported under 10 CFR 50.72(b)(3)(iv)(A). There was no impact to the health and safety of the public or plant personnel. The NRC resident has been notified.
ENS 5552214 October 2021 17:20:00FermiNRC Region 3GE-4

At 1320 EDT, during a Traversing In-Core Probe (TIP) run for a scheduled Local Power Range Monitors (LPRM) calibration, it was reported to the Main Control Room that TIP A would not fully retract to the In-Shield position. With TIP A unable to fully retract to the In-Shield position the TIP A Ball Valve was declared Inoperable due to not being able to close and meet its safety function in that configuration. Furthermore the TIP A Shear Valve was previously declared Inoperable due to the Firing Fuses being removed. With the two valves Inoperable the penetration could not be isolated and Primary Containment boundary isolation could not be established. TIP A was subsequently manually hand cranked and placed back into its In-Shield position at 1333 EDT restoring TIP A Ball Valve Operable. This report is being made pursuant to 10CFR50.72(b)(3)(v)(C) based on control the release of radioactive material. The Senior NRC Resident Inspector has been notified.

  • * * RETRACTION ON NOVEMBER 24, 2021 AT 1232 EST FROM LEVI SMITH TO BRIAN P. SMITH * * *

The purpose of this notification is to retract a previous report made on October 14, 2021 (EN 55522). At 1320 EDT on October 14, 2021 while performing Traversing In-Core Probe (TIP) Machine Gain Adjustment in support of Local Power Range Monitor (LPRM) calibration, an unplanned inoperability of the TIP 'A' Primary Containment Isolation Valve (PCIV) was reported pursuant to 10CFR50.72(b)(3)(v)(C) by EN 55522. On October 14, it was reported to the Main Control Room that TIP 'A' would not fully retract to the In-Shield position. With TIP 'A' unable to fully retract to the In-Shield position, the TIP 'A' Ball Valve PCIV was declared Inoperable due to not being able to close and meet its safety function in that configuration. The TIP 'A' Shear Valve PCIV was previously declared inoperable due to firing fuses being removed. Further investigation determined that a "FAULT: MOVEMENT LIMITED" error was received. This TIP error condition did not present a primary containment isolation issue in the event of a primary containment isolation signal. The Automatic TIP Control Unit (ATCU) is designed to command the TIP drive mechanism to continuously retract a TIP probe to the in-shield position in the event of a containment isolation signal with this condition. In the event of a containment isolation signal, the TIP machine would withdraw the TIP detector back to the in-shield position and the TIP A ball valve PCIV would have closed to perform its safety function. Therefore, the inoperability of TIP 'A' ball valve reported under criterion 10CFR50.72(b)(3)(v)(C) was not met, and EN 55522 is hereby retracted. The NRC Resident Inspector has been notified. Notified R3DO (Peterson)

ENS 5542322 August 2021 09:29:00FermiNRC Region 3GE-4At 0529 EDT on August 22, 2021, HPCI ((High Pressure Coolant Injection System)) was declared inoperable due to receiving the HPCI Inverter Circuit Failure annunciator. The cause of the annunciator was a fuse failure. The cause of the fuse failure is unknown at this time and is under investigation. Concurrent with the HPCI fuse failure was a similar fuse failure within the Division 2 EDG ((emergency diesel generators)) Load Sequencer which renders the Division 2 EDGs inoperable. Relation to the HPCI issue is unknown and is part of the investigation. The RCIC ((Reactor Core Isolation Cooling System)) was verified operable per Tech Spec 3.5.1 E.1. In addition, offsite circuits were verified operable per Tech Spec 3.8.1.B. Division 1 EDGs remain operable. This report is being made pursuant to 10CFR50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. There was no impact on the health and safety of the public or plant personnel. The Senior NRC Resident Inspector has been notified.
ENS 5540311 August 2021 10:34:00FermiNRC Region 3GE-4

At 0634 EDT on August 11, 2021 (high pressure coolant injection) HPCI was declared inoperable due to a pump flow controller problem. The cause of the controller problem is unknown at this time and is under investigation. (Reactor core isolation cooling) RCIC was verified operable per Tech Spec 3.5.1 E.1. This report is being made pursuant to 10CFR50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.

  • * * RETRACTION FROM WHITNEY HEMMINGWAY TO KAREN COTTON ON 10/6/2021 AT 1036 EDT * * *

The purpose of this notification is to retract a previous report made on August 11, 2021 (EN 55403). At 0634 EDT on August 11, 2021, an unplanned inoperability of the High Pressure Coolant Injection system (HPCI) was reported pursuant to 10 CFR 50.72(b)(3)(v)(D) by EN 55403. HPCI was declared inoperable due to receipt of an alarm associated with the pump flow controller. The HPCI system operating procedure states that HPCI should be declared inoperable when this alarm is received. The cause of the alarm, a loose transmitter connection, was identified and corrected. Following clearance of the alarm, HPCI was declared operable at approximately 1930 EDT on August 11, 2021. This alarm indicated a fault in the signal from the transmitter to the HPCI flow controller; in this case, the HPCI flow controller would have continuously called for maximum HPCI flow. The controller is configured with a high limiter to prevent an overspeed trip. An engineering evaluation of the event identified that HPCI was capable of performing its required safety functions while this alarm was present. The condition was that the HPCI flow controller would have continuously called for maximum HPCI flow upon HPCI initiation, however operators would be able to manually control HPCI flow upon HPCI initiation. Additionally HPCI would have run until Reactor Pressure Vessel (RPV) level reached Level 8 where it would trip until RPV level decreased to Level 2 then automatically restart. The licensee notified the NRC Resident Inspector. Notified R3DO (Peterson).

ENS 5535715 July 2021 21:40:00FermiNRC Region 3GE-4

While preparing for the June 2021 Discharge Monitoring Report (DMR), Environmental was entering data per the lab results that were sent from Pace Analytical for the June DMRs. On June 1, 2021, a National Pollutant Discharge Eliminating System (NPDES) sample was collected at outfall 001A to test for copper, there is a NPDES permit condition to monitor for copper on a quarterly basis. The lab report was returned to Fermi Environmental on June 15, 2021. The results came back at 41.2 micrograms/liter. Fermi's NPDES permit maximum limit is 40 micrograms/liter for outfall 001A. Due to the June 1, 2021 sample exceeding the permit limit, a second sample was collected on June 21, 2021 as a verification sample and the copper results came back July 13, 2021. Those results came back at 5.9 micrograms/liter which is within the permit limit. Environmental was aware of the June 1, 2021 copper exceedance limit but failed to recognize the reporting requirement at the time of the discovery because it was thought that the exceedance would be reported through the DMR submittal. The June DMRs are due on July 20, 2021. At approximately 1740 EDT on July 15, 2021, a Fermi environmental engineer was preparing and reviewing the Discharge Monitoring Report and identified that a recent sample result for outfall 001A was outside of the NPDES permit limit for Copper. The Copper sample result was 41.2 micrograms/liter with a limit of 40 micrograms/liter. Subsequent discussions with Environmental personnel determined that this issue should be reported to the state of Michigan Department of Environment, Great Lakes and Energy (EGLE). A discussion is planned with EGLE on July 16, 2021. This notification is being made pursuant to 10 CFR 50.72(b)(2)(xi) based on the planned notification to EGLE. The licensee notified the NRC Resident Inspector.

  • * * UPDATE ON 07/22/2021 AT 2141 FROM MARGARET OFFERLE TO OSSY FONT * * *

The licensee initially reported the lab report was returned to Fermi Environmental on June 15, 2021. The date of receipt was June 16, 2021. The licensee will notify the NRC Resident Inspector. Notified R3DO (Pelke).

ENS 555583 June 2021 06:41:00FermiNRC Region 3GE-4At 0241 (EDT) on June 3, 2021, during performance of a High Pressure Coolant Injection (HPCI) Condensate Storage Tank (CST) level functional surveillance, the HPCI torus suction inboard isolation valve was slow to open during swap of suction from the CST to the Torus. On June 9, 2021, it was determined that as a result of the June 3, 2021, slow swap condition, TS 3.3.5.1 Required Action D.1 to declare HPCI inoperable within 1 hour was applicable due to inoperable CST low level instrumentation channels. At 1817 (EDT) on June 3, 2021, HPCI suction was swapped to the torus, making TS Required Action D.1 no longer applicable. Reactor Core Isolation Cooling (RCIC) was available throughout this condition. At 0900 (EDT) on November 3, 2021, it was determined that an NRC event report due to HPCI inoperability should have been made. This event is being reported as a late 8-hour non-emergency notification pursuant to 10CFR50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The cause of the slow valve opening was later determined to be corrosion products on contacts of a relay in the CST low level instrumentation logic. On June 4, 2021 at 1451 (EDT), the HPCI CST Level Functional Test was completed Satisfactorily, restoring HPCI Instrumentation to Operable. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 552313 May 2021 13:30:00FermiNRC Region 3GE-4At 0930 EDT on 5/3/2021, it was determined that during entries into the Fermi 2 Reactor Building Steam Tunnel (RBST) on 4/17/2021, 4/18/2021, and 4/21/2021 that the door was not controlled according to site procedures. The RBST door is credited as a hazard barrier for various high-energy line break (HELB) scenarios. On the identified dates, the RBST door was left open for brief periods during maintenance related activities in the RBST. This condition is not bounded by existing analyses as the door is assumed to be closed throughout a HELB event. The time period that the door was open was less than one hour in each case, as stay times in the room are inherently limited by industrial and radiological conditions. Individuals remained in the area to close the door if needed, but existing analyses do not address the ability to perform those actions under all HELB scenarios. There is no impact to the health and safety of the public or plant personnel as the door is currently closed and latched and access into the area has been restricted to normal ingress and egress per site procedures, which ensures consistency with existing analyses. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). Investigation into the cause is ongoing. Preliminary review of the extent of this condition identified entries into the RBST on other occasions during the past three years where the conditions may also have not been bounded by existing analyses. The additional occasions where the door may have been held open were on 9/22/2018 (MODE 3), 10/26/2018 (MODE 1 ), 11/2/2018 (MODE 1), and 3/21/2020 (MODE 3). Each of these instances was also less than one hour with the exception of the occurrence beginning on 10/26/2018 which lasted approximately 10 hours to support packing leak repairs on a HPCI (High Pressure Coolant Injection) Outboard Isolation Valve. The licensee notified the NRC Resident Inspector.
ENS 5516030 March 2021 14:58:00FermiNRC Region 3GE-4At 1058 EDT on 3/30/2021, during routine pump down activities from the sites Equalization Basin, open to the environment (consisting of groundwater and runnoff), to a sanitary system manhole, there was a backflow from the sanitary system to the environment (nearby grassy area). The total amount of overflow is estimated to be 150 gallons. Fermi 2 Environment is currently investigating and clean-up is in progress and the backflow has stopped. The cause of the backflow is under investigation. As a result of the backflow reaching the environment, reports are being made to the Michigan Department of Environment, Great Lakes, and Energy (EGLE), the Monroe County Health Department, and the local news media. Since these reports are in the process of being made, this is considered a News Release or Notification to Other Government Agencies, therefore this event is reportable under 10 CFR 50.72(b)(2)(xi). The licensee has notified the NRC Resident Inspector.
ENS 547612 July 2020 03:05:00FermiNRC Region 3At 2305 EDT on July 1, 2020, while in Mode 5 for Refueling Outage 20 with no core alterations in progress, Fermi 2 experienced a loss of Division 2 offsite power (345 kV) which resulted in a valid automatic initiation of the Division 2 Emergency Diesel Generators (EDG) 13 and 14. EDG 13 and 14 started as expected to supply their associated busses. Division 1 offsite power remains operable and powering the Division 1 Residual Heat Removal (RHR) system in Shutdown Cooling (SDC) mode of operation. Division 1 EDGs 11 and 12 remain operable and available. The cause of the loss of Division 2 offsite power is under review and has preliminarily been determined to be caused by Mayfly accumulation in and around the Division 2 (345 kV) switchyard. Actions have been put in place to minimize and deter Mayflies from gathering near plant switchyards. All systems responded as expected for the loss of Division 2 offsite power and no loss of SDC occurred. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The event is reportable pursuant to 10 CFR 50.72(b)(3)(iv)(A), as a valid specified system actuation.
ENS 5472626 May 2020 14:04:00FermiNRC Region 3A non-licensed employee supervisor had a confirmed positive for alcohol during a follow-up fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 545675 March 2020 17:35:00FermiNRC Region 3On March 05, 2020, at 1235 EST, with the reactor at 100 percent core thermal power and steady state conditions, plant personnel notified the main control room that both doors in the secondary containment airlock on the reactor building fifth floor were opened simultaneously for a period of approximately three seconds (i.e., from 12:35:00 to 12:35:03 EST). The failure of this interlock, which is intended to prevent both doors from being opened simultaneously, resulted in the Technical Specification (TS) Surveillance Requirement (SR) 3 .6.4.1.3 not being met. The maximum secondary containment pressure observed during that time remained within TS limits. There were no radiological releases associated with this event. Declaring secondary containment inoperable as a result of not meeting TS SR 3.6.4.1.3 is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector.
ENS 5447413 January 2020 15:13:00FermiNRC Region 3A non-licensed contract employee supervisor tested positive for alcohol at another facility. The employee's access to Fermi 2 has been terminated. The NRC Resident Inspector has been notified.
ENS 5445218 December 2019 14:08:00FermiNRC Region 3On December 18, 2019, at 0908 EST, with the East and Center Reactor Building HVAC (RBHVAC) trains in service, secondary containment pressure degraded to the point where the Technical Specification (TS) requirement for secondary containment pressure was not met and secondary containment was declared inoperable. Secondary containment pressure did not meet the TS required limit for approximately four minutes. The maximum secondary containment pressure observed during that time was approximately 0.064 inches of vacuum water gauge. Secondary containment pressure was returned to within the TS operability limit of greater than or equal to 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) by starting Division 1 of the Standby Gas Treatment System (SGTS). Secondary containment was declared Operable at 0912 EST. A modulating damper associated with the Center train of RBHVAC was identified as not properly controlling; an investigation is in progress. RBHVAC was manually secured to support problem identification and resolution. Secondary containment pressure is currently stable with Division 1 SGTS in service. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The NRC Resident Inspector has been notified.
ENS 5429930 September 2019 02:28:00FermiNRC Region 3On September 29, 2019 at 2228 EDT, during a planned swap of Reactor Building HVAC trains, the exhaust fan discharge damper for the train being removed from service failed to close when the train was shutdown, which resulted in the Technical Specification (TS) for secondary containment pressure not being met for approximately 2 minutes and 15 seconds. The maximum secondary containment pressure observed during that time was approximately 0.1 inches of water gauge (positive). Secondary containment pressure was returned to within the TS operability limit of greater than or equal to 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) by restarting the train of RBHVAC. Secondary containment pressure is currently stable. Secondary containment was declared Operable at 2235 EDT. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The Licensee has notified the NRC Resident Inspector.
ENS 5429325 September 2019 16:03:00FermiNRC Region 3

At 1203 EDT, on September 25, 2019, during a Division 2 Emergency Equipment Service Water (EESW) pump and valve surveillance test, the Division 2 Emergency Equipment Cooling Water (EECW) Temperature Control Valve was found to be approximately 80 percent open rather than in its required full open position during fail safe testing. The Division 2 EESW system is required to support operability of the Division 2 EECW system. The Division 2 EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on a loss of the HPCI Room Cooler. An investigation is underway into the cause of the failure. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The NRC Senior Resident Inspector has been notified. The licensee is in 72-hour shutdown action statement.

  • * * RETRACTION ON 11/21/19 AT 1547 EST FROM PAUL ANGOVE TO BRIAN LIN * * *

Subsequent engineering evaluation has determined that the EECW TCV was capable of passing sufficient flow to perform its design basis functions, including supporting the HPCI room cooler, while approximately 80% open. Therefore, HPCI remained operable and there was no loss of safety function. The event did not involve a condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident under 10 CFR 50.72(b)(3)(v)(D). EN 54293 is retracted and no Licensee Event Report under 10 CFR 50.73(a)(2)(v)(D) is required to be submitted. The NRC Resident Inspector has been notified. Notified R3DO (Cameron).

ENS 5418830 July 2019 14:14:00FermiNRC Region 3On July 30, 2019, at 1014 EDT, the Division 2 Mechanical Draft Cooling Tower (MDCT) Fan D was declared inoperable due to a trip of the fan while placing in it high speed. The MDCT Fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the Division 2 Emergency Equipment Cooling Water (EECW) system. The EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on a loss of the HPCI Room Cooler. Investigation revealed that a high speed breaker control power fuse had blown. The control power fuse was replaced, the MDCT Fan D was tested satisfactorily, and HPCI was declared operable at 1431 EDT. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The licensee has notified the NRC Senior Resident Inspector
ENS 5416816 July 2019 18:45:00FermiNRC Region 3At 1445 EDT, on 7/16/2019, during routine maintenance activities on the sanitary sewage system, a leak from an overflow line to a parking lot was discovered. The total amount leaked is estimated to be 20 gallons. Approximately 2 gallons reached gravel in an excavated section of the parking lot. A local sanitary contractor is currently responding to the site to clean the affected areas. The cause of the leak is under investigation. As a result of some of the sewage reaching gravel, environmental reports are being made to the Michigan Department of Environmental Quality (MDEQ), the Monroe County Health Department, and the local news media. Since these reports are in the process of being made, this is considered a News Release or Notification to Other Government Agencies, therefore this event is reportable under 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified.
ENS 5416315 July 2019 17:35:00FermiNRC Region 3At 1335 EDT on 7/15/2019, during dredging activities in Fermi 2's General Service Water (GSW) intake canal, a hydraulic line on the dredging machine became disconnected and approximately one quart of hydraulic oil spilled into Lake Erie. The oil leak to navigable waters has been stopped. The oil was contained within a boom, cleanup activities commenced immediately, and cleanup was completed at 1500 EDT. The cause of the oil leak is under investigation. Environmental spill reports were made to local, state, and federal government agencies. This is considered a news release or notification to other government agencies, therefore this event is reportable under 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified. The State agencies notified were Michigan Department of Environmental Protection and the Michigan Pollution Emergency Alerting System. The licensee also notified the National Response Center.
ENS 5409430 May 2019 02:10:00FermiNRC Region 3On May 29, 2019, at 2210 EDT, plant personnel notified the Main Control Room that both doors in the Secondary Containment Airlock on the Reactor Building First Floor were opened simultaneously for a period of approximately two seconds. This resulted in Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.1.3 not being met. Secondary Containment pressure observed during that time remained unchanged and within TS limits. There were no radiological releases associated with this event. Declaring Secondary Containment inoperable as a result of not meeting TS SR 3.6.4.1.3 is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector.
ENS 5409227 May 2019 13:40:00FermiNRC Region 3On May 27, 2019 at 0940 EDT, a portable chemical toilet was found tipped over. Approximately one gallon of contents spilled to the gravel only and did not reach any waterways or storm drains. Cleanup efforts are in progress. A notification to the Michigan Department of Environmental Quality and local health department is required, as well as a press release. This event is being reported pursuant to 10 CFR 50.72(b)(2)(xi). The licensee has notified the NRC Resident Inspector.
ENS 539825 April 2019 15:25:00FermiNRC Region 3

EN Revision Text: FITNESS-FOR-DUTY: FALSIFIED PRE-EMPLOYMENT INFORMATION A non-licensed employee falsified pre-employment information. The employee's access to the plant has been terminated.

  • * * RETRACTION FROM ETHAN HAUSER TO DONALD NORWOOD AT 1456 EDT ON 5/21/2019 * * *

The following event notifications are retracted: EN 53822 reported on 1/11/2019 and EN 53982 reported on 4/5/2019. Subsequent to the initial notification, further investigation revealed that no new information was discovered that would meet the criteria for reporting under RG 5.62 or NUREG-1304. Further the events were also determined to be limited to an act of personal deception by those applying for unescorted access, without intent to commit or cause events identified in paragraphs I (a) and (d) of Appendix G to Part 73, and is not a programmatic breakdown. Based on this information, and consistent with the NRC memorandum dated May 19, 1995, 'Access Authorization Reportability and Enforcement Issues,' this event does not meet the threshold for reporting. The NRC Resident Inspector has been notified. Notified R3DO (Cameron) and via E-mail the FFD E-mail group.

ENS 5388319 February 2019 17:53:00FermiNRC Region 3On February 19, 2019, at 1307 EST, with the reactor at 100 percent Core Thermal Power and steady state conditions, plant personnel notified the Main Control Room that both doors in the Secondary Containment Airlock on the Reactor Building Fifth Floor were opened simultaneously for a period of approximately five minutes (i.e., from 1253 to 1258 EST). The failure of this interlock, which is intended to prevent both doors from being opened simultaneously, resulted in the Technical Specification (TS) Surveillance Requirement (SR) 3.6.4.1.3 not being met. The maximum Secondary Containment pressure observed during that time remained within TS limits. There were no radiological releases associated with this event. Declaring Secondary Containment inoperable as a result of not meeting TS SR 3.6.4.1.3 is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material. The licensee has notified the NRC Resident Inspector. The repair to the failed interlock is in progress. As a compensatory measure signs are posted on the doors to notify personnel to not access the Reactor Building via those doors.
ENS 5383016 January 2019 05:00:00FermiNRC Region 3At 0900 EST on 01/16/2019, it was discovered that a licensee manager intentionally failed to re-approve the list of individuals granted unescorted access to verify each individual was subject to a behavioral observation program. Compensatory actions have been taken in response to this event. Personnel affected have had their access authorization suspended. This is reportable under the provisions of 10 CFR 26.719(b)(3) as an intentional act that casts doubt on the integrity of the Fitness-For-Duty program. The licensee notified the NRC Resident Inspector.
ENS 5382514 January 2019 05:00:00FermiNRC Region 3

On 01/11/2019 at 0958 EST, the Fermi 2 Active Seismic Monitoring system was taken out of service for planned maintenance. During the maintenance activity, the Active Seismic Monitoring System failed a planned surveillance test and was not restored to operability within 72 hours. Compensatory measures to provide alternative methods for event classification of a seismic event were implemented in accordance with the Fermi 2 Emergency Plan procedures prior to the start of the planned maintenance outage. The planned outage time to restore operability exceeded 72 hours on January 14th, 2019, at 0958 EST. Repairs have been completed, the Active Seismic Monitoring System has been declared Functional at 1037 EST, January 14th, 2019, and declared Operable at 1109 EST, January 14th, 2019.

The loss of the Active Seismic Monitoring System is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). No seismic activity has been felt onsite and the United States Geological Survey (USGS) recorded no seismic activity in the area. The NRC Resident Inspector has been notified. Femi 2 has two seismic monitors, one on the Reactor Pressure Vessel Pedestal and one in the High Pressure Core Injection (HPCI) room. Only the HPCI room monitor was inoperable.

ENS 5382211 January 2019 14:11:00FermiNRC Region 3

EN Revision Text: FITNESS FOR DUTY A non-licensed employee disclosed that he had previously used illegal drugs. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.

  • * * RETRACTION FROM ETHAN HAUSER TO DONALD NORWOOD AT 1456 EDT ON 5/21/2019 * * *

The following event notifications are retracted: EN 53822 reported on 1/11/2019 and EN 53982 reported on 4/5/2019. Subsequent to the initial notification, further investigation revealed that no new information was discovered that would meet the criteria for reporting under RG 5.62 or NUREG-1304. Further the events were also determined to be limited to an act of personal deception by those applying for unescorted access, without intent to commit or cause events identified in paragraphs I (a) and (d) of Appendix G to Part 73, and is not a programmatic breakdown. Based on this information, and consistent with the NRC memorandum dated May 19, 1995, 'Access Authorization Reportability and Enforcement Issues,' this event does not meet the threshold for reporting. The NRC Resident Inspector has been notified. Notified R3DO (Cameron) and via E-mail the FFD E-mail group.

ENS 538111 January 2019 05:00:00FermiNRC Region 3On January 1, 2019 at approximately 0454 EST, while performing planned maintenance activities on the Feedwater Distributed Control System (FW DCS), it was discovered that the automatic trip instrumentation of the Gland Seal Exhauster (GSE) was inoperable. The automatic GSE trip is assumed in the safety analysis for the Control Rod Drop Accident (CRDA) and is required when Thermal Power is less than or equal to 10%. The automatic trip function of the GSE was inoperable for 1 minute, 19 seconds. No Control Rod movement occurred while the automatic trip of the GSE was inoperable. There was no adverse impact to public health and safety or to plant employees and there was no radiological release. This report is being made pursuant to 10CFR50.72(b)(3)(v)(C) and 10CFR50.72(b)(3)(v)(D). The NRC Resident Inspector has been notified.
ENS 537724 December 2018 14:35:00FermiNRC Region 3

EN Revision Text: HPCI INOPERABLE DUE TO MECHANICAL DRAFT COOLING TOWER FAN BRAKE INVERTER FAILURE At 0935 EST on December 4, 2018, the Division 2 Mechanical Draft Cooling Tower (MDCT) fans were declared inoperable due to failure of the over speed fan brake inverter. The brakes prevent fan over speed from a design basis tornado. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the Division 2 Emergency Equipment Cooling Water (EECW) system. The EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on a loss of the HPCI Room Cooler. Investigation into why the Division 2 MDCT fan over speed brake inverter failed is in progress. This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The NRC Resident Inspector has been notified. Fermi 2 is in a 14-day LCO for inoperability of HPCI and a 72-hour LCO for UHS inoperability.

  • * * RETRACTION ON 1/30/19 AT 1605 EST FROM CHRIS ROBINSON TO BETHANY CECERE * * *

The purpose of this notification is to retract EN 53772 made on December 4, 2018. Subsequent to the initial notification, the event and site Technical Specifications (TS) were reviewed further. An evaluation determined that TS Limiting Condition for Operation (LCO) 3.0.9 for barriers could be applied to the MDCT fan brakes. As a result of applying TS LCO 3.0.9 to the MDCT fan brakes, it was not necessary to declare the UHS inoperable. With the Division 2 UHS operable on December 4, 2018, the HPCI system was also operable. With HPCI operable, there was no event or condition that could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident under 10 CFR 50.72(b)(3)(v)(D). Therefore, EN 53772 is retracted and no Licensee Event Report (LER) under 10 CFR 50.73(a)(2)(v)(D) is required to be submitted. The licensee has notified the NRC Resident Inspector. Notified R3DO (Cameron).

ENS 537121 November 2018 04:00:00FermiNRC Region 3

EN Revision Text: UNANALYZED CONDITION DUE TO MODIFICATION NOT ADDED TO PROCEDURE On November 1, 2018, at approximately 1300 EDT, Fermi 2 identified that a Station Blackout (SBO) procedure was deficient as a result of a modification installed during a recent refueling outage. A review identified that the performance of the SBO procedure could have resulted in a challenge to having an alternate AC source available within one hour as outlined in the Updated Final Safety Analysis Report (UFSAR) 8.4.2. The alternate AC source was always available to be manually aligned in accordance with other standard operating procedures. The modification did not affect the function for Appendix R alternative shutdown. Immediate actions are underway to revise the impacted procedure. The health and safety of the public was not affected as offsite power has remained available since the modification was installed. Investigation into the cause and corrective actions is ongoing. Fermi 2 is reporting this event as an unanalyzed condition pursuant to the requirements of 10 CFR 50.72(b)(3)(ii)(B). The licensee notified the NRC Resident Inspector.

  • * * RETRACTION ON 12/28/18 AT 1228 EST FROM JEFFREY MYERS TO JEFFREY WHITED * * *

The purpose of this notification is to retract a previous report made on November 1, 2018 (EN 53712) under 10 CFR 50.72(b)(3)(ii)(B). Subsequent to the initial notification, the event, site procedures, and the NRC guidance in NUREG-1022 pertaining to 10 CFR 50.72(b)(3)(ii)(B) were reviewed further. The evaluation determined that at the time of the event, there were multiple methods defined in existing station procedures to establish an available alternate AC source within one hour as outlined in the Updated Final Safety Analysis Report (UFSAR) 8.4.2. Under these circumstances, the event does not represent an unanalyzed condition under 10 CFR 50.72(b)(3)(ii)(B). Therefore, EN 53712 can be retracted and no Licensee Event Report (LER) under 10 CFR 50.73(a)(2)(ii)(B) is required to be submitted. The licensee has notified the NRC Resident Inspector. Notified R3DO (Riemer).

ENS 5367419 October 2018 04:00:00FermiNRC Region 3On 10/19/2018, at approximately 0400 EDT, during an investigation into a failed surveillance test for a Loss of Offsite Power (LOP) coincident with a Loss of Coolant Accident (LOCA), it was identified that the Engineered Safety System Bus degraded voltage relay scheme contained a time delay setting that could inhibit all Low Pressure Core Injection (LPCI) pumps from automatically starting and operating during a LOP/LOCA, thus making LPCI incapable of meeting its functional requirement of automatic startup and operation regardless of the availability of offsite power supply (UFSAR Section 6.3.1.4 and Tech. Spec. Surveillance Requirement 3.8.1.17). The condition was identified during the first-time performance of a revised surveillance procedure for a LOP coincident with a LOCA signal. Fermi is currently in Mode 4 (Cold Shutdown) and LPCI auto start on a LOP/LOCA signal is not required. However, the initial investigation identified the condition likely existed in the past during modes of operation where LPCI auto start on LOP/LOCA was required. Investigation into the cause and corrective actions is ongoing. Since LPCI auto start is not required at the time of discovery (Mode 4), this event is being reported pursuant to 50.72(b)(3)(ii)(b). The NRC Resident Inspector has been notified.
ENS 5356224 August 2018 04:00:00FermiNRC Region 3

At 0745 EDT on August 24, 2018, the Active Seismic Monitoring System failed a planned surveillance test and was declared inoperable. Compensatory measures to provide alternative methods for event classification of a seismic event have been implemented in accordance with the Fermi 2 Emergency Plan procedures. The compensatory measures include the use of information provided by the United States Geological Survey (USGS) to confirm if an earthquake has occurred within a 100 mile radius. The loss of the Active Seismic Monitoring System is reportable to the NRC within 8 hours of discovery in accordance with 10CFR50.72(b)(3)(xiii). No seismic activity has been felt onsite and the USGS recorded no seismic activity in the area. The NRC Resident Inspector bas been notified.

  • * * RETRACTION FROM JEFF GROFF TO VINCE KLCO ON SEPTEMBER 13, 2018 AT 1524 EDT * * *

After further review the Active Seismic Monitoring system was removed from service for planned maintenance for a duration less than 72 hours with appropriate compensatory measures established. Therefore, no major loss of emergency assessment capability occurred. In addition, the surveillance tests were re-performed and the Active Seismic Monitoring System was declared Operable. Therefore, no reportable condition existed and EN 53562 reported on August 24, 20I8 is being retracted. The NRC Resident Inspector has been notified. Notified the R3DO (Hanna).

ENS 5355420 August 2018 04:00:00FermiNRC Region 3At 08/20/2018 at 1856 (EDT), it was determined that a contract supervisor failed a test specified by the FFD (fitness for duty) testing program. The individual's authorization for site access has been terminated. The NRC Resident Inspector has been notified.
ENS 535373 August 2018 04:00:00FermiNRC Region 3At 0940 EDT on August 3, 2018, the Division 2 Mechanical Draft Cooling Tower (MDCT) fans were declared inoperable due to failure of the over speed fan brake inverter. The brakes prevent fan over speed from a design basis tornado. The MDCT fans are required to support operability of the Ultimate Heat Sink (UHS). The UHS is required to support operability of the Division 2 Emergency Equipment Cooling Water (EECW) system. The EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) system room cooler. An unplanned HPCI inoperability occurred based on a loss of the HPCI Room Cooler. Investigation into why the Division 2 MDCT fan over speed brake inverter failed is in progress. This report is being made pursuant to 10CFR50.72(b)(3)(v)(D) based on an unplanned HPCI inoperability. The NRC Resident Inspector has been notified.
ENS 5343531 May 2018 18:20:00FermiNRC Region 3On May 31, 2018 at 1420 EDT, the Reactor Water Cleanup (RWCU) System Isolation Differential Flow - High function was declared inoperable as a result of indicating downscale. This condition would have prevented the primary containment isolation valves for the RWCU system from automatically isolating on a high differential flow condition. At 1519 EDT, RWCU was shutdown and the affected penetration flow paths were isolated in accordance with station procedures per Fermi Technical Specifications. The cause of the event is under investigation. There was no radiological release associated with this event. All other RWCU primary containment isolation instrumentation functions remained operable and the associated RWCU system primary containment isolation valves were capable of being remotely closed by the control room operators throughout the event. However, the condition is reportable pursuant to 10 CFR 50.72(b)(3)(v)(C), and 10 CFR 50.72(b)(3)(v)(D). The NRC Resident Inspector was notified.
ENS 5342927 May 2018 10:30:00FermiNRC Region 3GE-4On May 27, 2018 at 0630 EDT, the Reactor Water Cleanup (RWCU) System Isolation Differential Flow - High function was declared inoperable as a result of indicating downscale. This condition would have prevented the primary containment isolation valves for the RWCU system from automatically isolating on a high differential flow instrumentation signal. At 0753, RWCU was shutdown and the affected penetration flow paths were isolated in accordance with station procedures per Fermi Technical Specifications. The cause of the event is under investigation. There was no radiological release associated with this event. All other RWCU primary containment isolation instrumentation functions remained operable and the associated RWCU system primary containment isolation valves were capable of being remotely closed by the control room operators throughout the event. However, the condition is reportable pursuant to 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D). The NRC Resident Inspector was notified.
ENS 533854 May 2018 18:12:00FermiNRC Region 3GE-4At 1412 EDT, a portable chemical toilet was found tipped over. Approximately 1 gallon of contents spilled to gravel only. A notification to the Michigan Department of Environmental Quality and local health department is required, as well as a press release. This event is being reported pursuant to 10CFR50.72(b)(2)(xi). The licensee will notify the NRC Resident Inspector.
ENS 5333614 April 2018 14:40:00FermiNRC Region 3GE-4

At 1040 EDT, Fermi 2 automatically scrammed on RPV (Reactor Pressure Vessel) Level 3 following a loss of the Division 1 Station System Transformer (SST) #64. All control rods fully inserted. HPCI (High Pressure Coolant Injection) and RCIC (Reactor Core Isolation Cooling) automatically started as designed on Reactor Water Level (RWL) 2 and restored RWL. The lowest RWL reached was 101.8 inches (above Top of Active Fuel). HPCI injected for approximately 35 seconds. RWL is currently being maintained in the normal level band with RCIC. No Safety Relief Valves (SRVs) actuated. All isolations and actuations for RWL 3 and 2 occurred as expected. Investigation into loss of SST #64 continues. At the time of the scram, all Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generators (EDGs) were operable, and no safety related equipment was out of service. This report is being made in accordance with 10CFR50.72(b)(2)(iv)(A), any event that results in ECCS discharge into the reactor coolant system as a result of a valid signal and 10CFR50.72(b)(2)(iv)(B), any event that results in the actuation of the Reactor Protection System (RPS) when the reactor is critical. Following the loss of power and reactor scram, the Division 2 EECW (Emergency Equipment Cooling Water) Temperature Control Valve (TCV) controller was in Emergency Manual and maintaining max cooling. Operators placed the controller in Auto and the TCV is controlling normally. The NRC Senior Resident has been notified. Decay heat is being removed via Division 2 steam dumps to the condenser. The plant is in a modified shutdown electric lineup with offsite power available and stable. Emergency diesel generators did automatically start and load.

  • * * UPDATE ON 4/14/2018 AT 1838 EDT FROM JEFF MYERS TO HOWIE CROUCH * * *

This update provides additional clarification of the applicable reporting criteria for this event associated with Primary Containment Isolation Actuations. All isolations and actuations for RWL (Groups 4, 13, and 15) and RWL 2 (Groups 2, 10, 11, 12, 14, 16, 17, and 18) occurred as expected. This report is also being made in accordance with 10CFR50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any systems listed in paragraph (b)(3)(iv)(B): RPS, HPCI, and RCIC. RPV pressure is being maintained by the bypass valves to the main condenser. All actuations that occurred were fully completed and restored. The licensee notified the NRC Resident Inspector. Notified R3DO (Stone).

  • * * UPDATE ON 4/15/2018 AT 1950 EDT FROM KELLEY BELENKY TO DAVID AIRD * * *

This update provides additional information regarding the specified system actuations and an additional applicable reporting criteria. The loss of Division 1 Station System Transformer (SST) #64 at 1040 EDT on 4/14/2018 resulted in the automatic initiation of Emergency Diesel Generators (EDG) 11 and 12. The EDGs started as expected and continue to supply their associated busses. This is reportable pursuant to 10CFR50.72(b)(3)(iv)(A), as an event or condition that resulted in a valid actuation of any system listed in paragraph (b)(3)(iv)(B), including EDGs. In addition, the loss of the Division 1 SST #64 resulted in the expected transfer from the normal to alternate power source for the Low Pressure Coolant Injection (LPCI) swing bus, rendering LPCI loop select inoperable. The alternate power source continued to energize the LPCI swing bus throughout the event until the system was realigned to the normal power source at 1239 EDT on 4/14/2018. This condition is reportable pursuant to 10CFR50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector. Notified R3DO (Stone).

ENS 532361 March 2018 12:51:00FermiNRC Region 3GE-4A non-licensed, supervisory employee was determined to be under the influence of alcohol during a random test. The employee's unescorted access was terminated. The NRC Resident Inspector has been notified.