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| Entered date | Event description | |
|---|---|---|
| ENS 54726 | 26 May 2020 13:17:00 | A 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 54094 | 30 May 2019 00:10:00 | On 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 54092 | 27 May 2019 11:53:00 | On 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 52837 | 1 July 2017 17:35:00 | At 1420 EDT on 7/1/17, Fermi 2 determined that the site was in violation of its National Pollutant Discharge Elimination System (NPDES) permit due to chemical addition pumps (for the cooling tower reservoir) being out of service for approximately seventeen hours. This resulted in sodium hypochlorite concentrations exceeding state limits. As of 0855 EDT (on) 7/1/17, the levels of sodium hypochlorite were restored to less than measureable values. Reports will be made to the Michigan Department of Environmental Quality (MDEQ) and other local agencies. 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. The licensee also notified Monroe County. |
| ENS 52724 | 2 May 2017 18:34:00 | On May 2, 2017, while performing a past operability review associated with Combustion Turbine Generator (CTG) 11-1, it was determined that a past configuration of CTG 11-1 could not have assured all of the applicable Appendix R success criteria under all of the postulated scenarios described in the Updated Final Safety Analysis Report (UFSAR). From November 21, 2016 until March 18, 2017 when Mode 4 was entered, CTG 11-1 was in a configuration where it could not be started from the dedicated shutdown panel, although it could be started locally. One of the specific scenarios for Appendix R in the UFSAR credits CTG 11-1 to support a safe shutdown based on an assumed time required to start CTG 11-1 and then provide flow to the reactor pressure vessel using the Standby Feedwater System. During the time period where CTG 11-1 could only be started locally, this assumed time would have been exceeded. Therefore, this event is being reported as an 'unanalyzed condition that significantly affects plant safety' under 50.72(b)(3)(ii)(B). At the time of discovery, CTG 11-1 was fully operable and the described condition had already been corrected. The NRC Resident Inspector has been notified.
The purpose of this notification is to retract a previous report made on May 2, 2017 (EN 52724) under 10 CFR 50.72(b)(3)(ii)(B). The notification to the NRC involved an event where Combustion Turbine Generator (CTG) 11-1 could only be started locally such that required operator actions during an Appendix R safe shutdown scenario could be delayed. Subsequent to the initial notification, the event, additional site documentation, and the NRC guidance in NUREG-1022 pertaining to 10 CFR 50.72(b)(3)(ii)(B) were reviewed further. lt was verified that Fermi 2 procedures contained actions to ensure Appendix R safe shutdown capability under the plant conditions during the relevant time period. A time validation study was performed (May 9, 2017) which verified that the operator actions could have been completed within the time described in the Updated Final Safety Analysis Report (UFSAR) for initiating Standby Feedwater flow to the reactor pressure vessel. In addition, a review of the supporting design calculation identified margin in the required time described in the UFSAR. Based on this information, the condition of CTG 11-1 during the time period from November 21, 2016 until March 18, 2017 would not have prevented compliance with the Appendix R safe shutdown requirements. Under these circumstances, the event does not represent an 'unanalyzed condition that significantly affects plant safety' under 10 CFR 50.72(b)(3)(ii)(B) per the guidance in NUREG-1022. Therefore, EN 52724 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 (Cameron). |
| ENS 52437 | 15 December 2016 11:47:00 | On December 15, 2016, at 1010 EST, the startup of the Reactor Building HVAC (Heating Ventilation and Air Conditioning) system resulted in the Technical Specification (TS) for secondary containment pressure boundary not being met for approximately 1 second. The maximum secondary containment pressure observed during that time was approximately 0.044 inches of vacuum water gauge. Secondary containment pressure was returned to within the TS operability limit of 0.125 inches of vacuum water gauge (TS SR 3.6.4. 1.1) by Reactor Building HVAC and Standby Gas Treatment System already in operation. There were no radiological releases associated with this event. Declaring secondary containment inoperable is reportable under 10CFR50.72(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.
In this event notification, DTE Electric Company (DTE) reported conditions whereby the Fermi 2 secondary containment was believed to have exceeded Technical Specification Surveillance Requirements due to high winds. DTE hereby retracts this event notification as the Fermi 2 secondary containment has been determined to have been operable during this event as described below. The Fermi 2 secondary containment pressure is maintained at a pressure less than the external pressure to contain, dilute, hold up, and reduce the activity level of fission products prior to release to the environment, and to isolate and contain fission products that are released during a Design Basis Accident or certain operations. Secondary containment pressure is monitored by a number of differential pressure (dP) sensors. High wind gusts have resulted in momentary negative pressure on the leeward side of the building, causing a more positive pressure indication from one or more dP sensors. The secondary containment building pressure remains relatively constant during these 'wind events.' In December 2016, DTE implemented a software design change to display a 120-second rolling average for secondary containment dP indication. A 120-second rolling average recorded every second provides the operator a more accurate report of actual secondary containment conditions, while mitigating the signal noise and wind gust effects. The conditions associated with the subject event notification were re-reviewed in light of the improved secondary containment dP indication and it was determined that the Fermi 2 secondary containment was operable during this event. Specifically, the secondary containment pressure did not exceed Technical Specification Surveillance Requirements during this event. In summary, the above event notification is retracted because the Fermi 2 secondary containment was determined to have been fully operable during the conditions identified in the subject report. The licensee notified the NRC Resident Inspector. Notified R3DO (Stoedter). |
| ENS 52430 | 14 December 2016 11:20:00 | At 0945 EST on 12/14/16, Fermi 2 discovered a sanitary sewer system leaking through a covered manhole in the Owner Controlled Area. Approximately 100 gallons of the sewage has entered the storm drain system. The sewage leak was stopped at 1030. A local sanitary contractor is currently responding to the site to clean the affected areas. The cause and extent of the sewage teak is under investigation. Reports to the Michigan Department of Environmental Quality (MDEQ), the local health department (Monroe County), and the local news media are in progress. 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 10CFR50.72(b)(2)(xi). The licensee has notified the NRC Resident Inspector. |
| ENS 49451 | 18 October 2013 15:52:00 | At 1505 EDT on October 18, 2013, Fermi 2 experienced an oil spill to navigable waters, requiring notification of the Nuclear Regulatory Commission, Pollution Emergency Alert System, Detroit Edison Corporate Environmental Management and Resources, and the Primary Public Safety Answering Point. The spill has not left site. Oil leaked from a fitting on a pump during the performance of fire truck testing. It is estimated that the volume of the overflow was less than four gallons. The overflow entered the on-site quarry. The source of the spill has been terminated. Media interest is anticipated. The NRC Resident Inspector has been notified. * * * UPDATE FROM DEREK ETUE TO PETE SNYDER ON 10/21/13 AT 1445 EDT * * * In the first sentence of the second paragraph in the original report above the words 'fire truck' were replaced with 'FLEX pump.' Additionally, "as of 10/18/2013 at 1820 EDT the oil cleanup was completed with no waste generated due to oil dissipation." The licensee also notified the Michigan State Police, Monroe County Sheriff, and the Michigan Department of Environmental Quality. The licensee notified the NRC Resident Inspector. Notified R3DO (Orlikowski). |
| ENS 48887 | 4 April 2013 08:35:00 | At 0406 (EDT) on April 4, 2013, the Fermi 2 Integrated Plant Computer System (IPCS) failed. This resulted in a loss of approximately 60 percent of data on the Safety Parameters Display System (SPDS). While IPCS and SPDS are not fully functional, the Emergency Plan can still be implemented if a plant emergency does occur, as assessment capabilities are available under alternate means. Investigation is in progress. A follow up message will be made when IPCS and SPDS are restored to fully functional status. This notification is being made per the requirements of 8 Hour Non-Emergency Notification 10CFR50.72(b)(3)(xiii), any event that results in a major loss of emergency assessment capability. The licensee has notified the NRC Resident Inspector.
At 1627 (EDT) on April 4, 2013, plant personnel were able to restore full functionality of IPCS and SPDS. This restored full assessment capabilities to all onsite emergency response faculties. The licensee notified the NRC Resident Inspector. Notified the R3DO (Daley). |
| ENS 48886 | 3 April 2013 16:51:00 | At 1053 (EDT) on April 3, 2013, during the performance of a surveillance test on the Division 2 Emergency Equipment Cooling Water (EECW) system the EECW system was declared inoperable due to the Division 2 EECW makeup pump failing to start during the surveillance. The EECW system cools various safety related components, including the High Pressure Coolant Injection (HPCI) room cooler. A 14 day Limiting Condition for Operation (LCO) was entered for HPCI via (Technical Specification) LCO 3.5.1. Investigation into why the makeup pump did not start is currently in progress. This report is being made pursuant to 10 CFR 50.72 (b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident, based on a loss of a single train safety system. The NRC Resident Inspector has been notified.
An evaluation of Event 48886 has determined that the Division 2 Emergency Cooling Water (EECW) system was capable of supporting HPCI Room Cooler and HPCI operation for a period of time in excess of that required to perform the required safety functions as assumed in the accident analysis. Therefore, this event is retracted. The licensee notified the NRC Resident Inspector. Notified the R3DO (Orth). |