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 Entered dateSiteRegionReactor typeEvent description
ENS 5742615 November 2024 16:29:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via phone and email: At 1305 CST, on November 15, 2024, it was determined that division 2 cables for the '12' emergency diesel generator start circuitry are routed through a division 1 area without adequate fire barrier separation. This condition is not bounded by existing design and licensing documents; however, it poses no impact to the health and safety of the public or plant personnel. A fire impairment and hourly fire watch have been established for the affected fire zones. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72 (b)(3)(ii)(B). The NRC Resident Inspector has been notified.
ENS 5741911 November 2024 16:49:00PilgrimNRC Region 1GE-3The following is summary of information provided by the licensee via phone and email: On November 11, 2024, at 1510 EST, site personnel identified what appeared to be water bubbling up from the pavement adjacent to the sanitary lift station 'C' outside of the facility industrial area. Less than 100 gallons of non-radiological sanitary water ran to a catch basin connected to permitted outfall number 007. Visual inspection did not identify any odor or indication of flow at outfall number 007 discharge. By 1530, the lift station pumps had been secured, sources of influent to the lift station were removed from service, and efforts were underway to pump the tank. At 1611, an offsite notification was made to the Environmental Protection Agency's Enforcement and Compliance Assurance Division in accordance with Section B of the station's National Pollutant Discharge Elimination System (NPDES) Permit No. 0003557. The event was associated with leakage from underground sewage system piping from a non-radiological underground tank and lift station. The NRC Resident Inspector will be notified.
ENS 574124 November 2024 09:02:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via phone and email: At 0500 CST, on November 4, 2024, the Monticello Nuclear Generating Plant was notified by Wright County dispatch of a spurious actuation of one emergency response siren that lasted approximately ten minutes. The cause of the actuation has not been determined and the vendor is investigating. The siren is no longer actuating. There was no impact to the health and safety of the public as a result of this event and the offsite response capabilities remain functional. No press release by the licensee is planned at this time. This event is being reported in accordance with 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified.
ENS 5734627 September 2024 12:10:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via email: On September 17, 2024, the site identified that an individual assigned to perform fitness for duty (FFD) program duties, who should have been part of the fitness for duty program random testing pool, had been inadvertently removed during a recent computer system upgrade. The individual was reprocessed and placed back into the FFD program on September 18, 2024. This was determined to be an isolated incident as it was confirmed that no other individuals required to be in the program were removed.
ENS 5719928 June 2024 16:28:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via email: This condition is being reported in accordance with 10 CFR50.72(b)(3)(v) as a condition that could have prevented fulfillment of a safety function. On 6/27/2024 at 2158 CDT, (technical specification) TS 3.5.1 condition 'D' (both divisions of (low pressure coolant injection) LPCI inoperable) was entered for surveillance testing. On 6/28/2024 at 0110 CDT, MO-2012 (residual heat removal) RHR Division 1 LPCI injection outboard valve was attempted to be cycled. It was discovered to be inoperable resulting in an inability to exit TS 3.5.1 'D'. Initial review of this condition for immediate reportability under 50.72(b)(3)(v) event or a condition that could have prevented fulfillment of a safety function, concluded the condition was not reportable based on the operability of other emergency core cooling systems (ECCS). Specifically, core spray and high pressure coolant injection were both operable to perform the function of emergency core cooling. Subsequent reviews determined that the reportability decision under 50.72(b)(3)(v) as an event or condition that could have prevented fulfillment of a safety function should be based on the safety function at the LPCI system level, rather than at the ECCS system level. The decision to report the inoperability of LPCI under 50.72(b)(3)(v) was made at 1030 CDT on 6/28/2024. The NRC Resident Inspector has been notified.
ENS 5714124 May 2024 02:08:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via email: At 2223 CDT on May 23, 2024, with Quad Cities Unit 2 at 38 percent power, the reactor automatically tripped due to a turbine trip signal resulting in main stop valve closure, creating a valid reactor protection system signal. Reactor vessel level reached the low-level set-point following the scram, resulting in valid Group II and Group III containment actuation signals. The trip was not complex with all systems responding as expected post-trip. 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) and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for the Group II and Group III isolation. Operations responded using their emergency operating procedures and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 1 remains at 100 percent power. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Unit 2 was at a reduced power for maintenance.
ENS 5705828 March 2024 01:52:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via email: At 2046 (CDT) on 3/27/24 with the unit 2 in Mode 5 at 0% power, an actuation of the Reactor Protection System occurred during testing of the scram discharge volume. The cause of the Reactor Protection System actuation was leakage of water into the scram discharge volume causing a high level condition while drains were isolated for testing. The Reactor Protection System automatically actuated as designed when the high scram discharge volume signal was received. All rods were previously fully inserted and the Control Rod Drive system was shutdown. No rod movement occurred due to the actuation. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Reactor Protection System. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 570021 March 2024 17:27:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via email: At 1330 CST, on March 1, 2024, an equipment vendor was coordinating with Wright County performing maintenance on an emergency siren when the county operator mistakenly sent an alarm signal instead of cancel signal, activating all Wright County emergency sirens for approximately 17 seconds. At 1345 CST, the Monticello Nuclear Generating Plant (MNGP) emergency planning coordinator received a notification from the vendor and notified the duty shift manager (of the inadvertent activation). Wright County officials are planning to make a public notification via social media to local residents. No press release by the licensee is planned at this time. This event is reportable per 10 CFR 50.72(b)(2)(xi), 'News Release or Notification of Other Government Agencies.' This is a 4-hour Reporting requirement. The NRC Resident has been notified.
ENS 5699528 February 2024 13:25:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via fax and email: At approximately 0839 (CST) with Unit 1 in Mode 1 at 100 percent power, the reactor automatically scrammed due to the depressurization of the SCRAM air header caused by an invalid signal that (occurred) during system testing. The SCRAM was uncomplicated with all systems responding as expected. The cause and details of the event are under investigation. Containment isolation valves actuated and closed on a valid Group 2 signal. 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), and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for the Group 2 isolation signal. Operations responded using the emergency operating procedure and stabilized the plant in Mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. State as well as Wright and Sherburne Counties will be notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The Anticipated Transient Without Scram (ATWS) circuit was being tested when an invalid signal was sent to depressurize the SCRAM air header.
ENS 569548 February 2024 17:59:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via email: A supervisor had a confirmed positive for alcohol during a random fitness for duty test. The supervisor's access to the plant has been terminated.
ENS 5686620 November 2023 17:53:00DresdenNRC Region 3GE-3

The following information was provided by the licensee via email: At 0956 (CST) on November 20, 2023, accumulated gas was identified in the Dresden Unit 2 high pressure coolant injection (HPCI) system discharge header. As a result, the HPCI system was declared inoperable. Since HPCI is a single-train system, this is a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). The HPCI system was subsequently vented, and the accumulated gas has been removed, restoring the Dresden Unit 2 HPCI system to an operable status. All other emergency core cooling systems remained operable during this time period. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The licensee administratively verified the isolation condenser was operable after declaring HPCI inoperable as required by technical specifications. The licensee stated there was no increase in plant risk. The cause of gas accumulating in the Dresden Unit 2 HPCI discharge header is under investigation, and this issue has been entered into the licensees corrective action program.

  • * * RETRACTION ON 4/5/2024 AT 1544 EDT FROM JON CHAPMAN TO IAN HOWARD * * *

Further analysis demonstrated that the Unit 2 high pressure coolant injection (HPCI) system remained operable with the level of voiding found in the HPCI discharge line. This analysis also found that the additional loads that would be present if the HPCI system were actuated with this level of voiding are within design limits of the HPCI system piping and supports. Based on these results, this event is not reportable under 10 CFR 50.72(b)(3)(v)(D), `Any event or 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. Therefore, EN 56866 submitted on November 20, 2023, is being retracted. The NRC Resident Inspector has been notified. Notified R3DO (Havertape)

ENS 5686519 November 2023 14:44:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via phone and fax: On November 18, 2023, the presence of alcohol was discovered inside the protected area. In accordance with the Constellation Fitness For Duty (FFD) Program, the individual has been escorted offsite and access to the plant denied pending the results of an investigation. This event is being reported under 10 CFR 26.719(b)(1) as it represents a significant FFD violation. The NRC Resident Inspector has been notified.
ENS 5681525 October 2023 15:09:00PilgrimNRC Region 1GE-3The following information was provided by the licensee via phone and email: This is a non-emergency 30-day notification for missing licensed material. This event is reportable in accordance with 10 CFR 20.2201(a)(1)(ii). On September 25, 2023, while performing the required semi-annual source leak check and inventory, radiation protection personnel could not locate seven sealed radioactive sources. Five of the sources exceed the reporting threshold of ten times the activity listed in 10 CFR 20 Appendix C. Of the five sources, four were Ni-63 sources previously utilized in security bomb detection equipment with a current source radioactivity of between 7.1 and 8.7 mCi. The fifth sealed source exceeding the reporting threshold is an Am-241 former lab calibration standard with a source radioactivity of 0.97 microcuries. These sources were last accounted for on July 6, 2022. Pilgrim's accountability process does not require leak checks or physical inventory of sources that are out of service. A search was conducted for the missing sources; however, they could not be located. These sealed sources are classified as Category 5 radioactive sources in accordance with the International Atomic Energy Agency (IAEA) Safety Guide No. RS-G-1.9. Sources that are less than Category 3 (Cat 4 and 5 sources) are very unlikely to cause permanent injury to individuals. Based on the activity of Ni-63 and Am-241 present in the sources, this 30-day phone notification to NRC is provided pursuant to 10CFR20.2201(a)(1)(ii). The required written report pursuant to 10CFR20.2201(b)(1) will be provided to NRC within 30 days. The Resident Inspector has been notified. The licensee will notify State and local authorities. THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
ENS 5675927 September 2023 15:28:00MonticelloNRC Region 3GE-3

The following information was provided by the licensee via fax: (On 09/27/2023) at 1041 CDT, with the plant at 75 percent power and main turbine control valve testing in progress, a reactor pressure transient resulted in a reactor steam dome high pressure scram and subsequent group 1 primary containment isolation of the main steam lines (MSL). All main steam isolation valves closed as a result of the group 1 isolation signal. Additionally, a group 2 containment isolation signal was received due to reactor pressure vessel (RPV) level less than plus 9 inches during the transient. Operations personnel responded and stabilized the plant. The high-pressure coolant injection (HPCI) system was placed in service to control RPV pressure. HPCI did not inject into the RPV and was not needed to control RPV water level. The cause of the initial pressure transient is under investigation. The NRC Resident Inspector has been notified.

      • UPDATE ON 9/27/2023 AT 2350 EDT FROM NATHAN PIEPER TO LAWRENCE CRISCIONE***

The utility notified the State of Minnesota and Wright and Sherburne counties. Notified R3DO (Orlikowski)

ENS 567071 September 2023 18:05:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via email: On 9/1/23 at 0900 hours, site personnel identified a 1 ounce bottle of vanilla extract in the protected area. Alcohol was identified as an ingredient on the ingredients label. It was determined that the alcohol by volume (ABV) for vanilla extract was 35 percent, above the 0.5 percent ABV considered low alcohol content.
ENS 5667611 August 2023 08:03:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via phone and email: At 0329 (CDT) on August 11, 2023, with Unit 2 in Mode 1 at 90 percent power, the reactor automatically tripped due to a turbine trip. The trip was uncomplicated with all systems responding normally post-trip. The cause and details of the event are under investigation. Containment isolation valves actuated closed in multiple systems on a valid Group II signal. 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), and an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for the Group II isolation. Operations responded using the emergency operating procedure and stabilized the plant in Mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 1 is not affected. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 566063 July 2023 17:03:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via phone and email: At 1530 (EDT) on July 3, 2023, Constellation Generation Company, LLC reported to the Illinois Environmental Protection Agency and the Illinois Emergency Management Agency and Office of Homeland Security (IEMA-OHS) that tritium concentrations in existing monitoring wells in a known (10 CFR) 50.75(g) recovery area were found higher than normal (at Quad Cities Nuclear Generating Station). This higher than normal tritium concentration did not exceed any NRC regulations or reporting criteria and there is no indication of a liquid release beyond the site boundary. This notification is being made solely as a four-hour, non-emergency notification for a notification of other government agency in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5658422 June 2023 09:44:00MonticelloNRC Region 3GE-3The following information was provided by the licensee email: This telephone notification is provided in accordance with 10 CFR 50.73(a)(1) and 10 CFR 50.73(a)(2)(iv)(A) to report an invalid actuation of Division 2 Primary Containment Isolation logic at the Monticello Nuclear Generating Plant (MNGP) that occurred while in a refueling outage. At approximately 0402 Central Daylight Time (CDT) on April 28, 2023 and at approximately 1611 and 2143 CDT on May 4, 2023, momentary losses of 'Y80 Division 2 Uninterruptible 120VAC Class 1E Distribution Panel', which provides power to Division 2 Primary Containment Isolation logic, resulted in a partial Primary Containment Group 2 Isolation (gas systems), initiation of the Standby Gas Treatment system, and the shift of Control Room ventilation to the high radiation mode. The momentary losses of 'Y80' were due to an intermittent, age-related degradation issue with the 'Uninterruptible Power Supply Y81, Division 2 120VAC Class 1E Inverter', which resulted in a temporary loss of output plus a lack of static switch transfer from the inverter supply to the alternate source as designed. The actuations were not initiated in response to actual plant conditions, these were not intentional manual initiations, and there were no parameters satisfying the requirements for initiation. Therefore, these events have been determined to be invalid actuations that were attributed to the same cause. All systems responded as designed to the actuation signal. Operations reset the partial Primary Containment Group 2 Isolation signal, shutdown the Standby Gas Treatment system, and restored Control Room ventilation per the procedure. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5653523 May 2023 22:13:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via phone and fax: On 5/22/23, Xcel Energy performed a notification to the state of Minnesota Duty Officer, in accordance with Minnesota Statute 115.061, regarding 300-600 gallons of pumped ground water that overflowed from a holding tank and returned to the ground area from which it was pumped. The groundwater being pumped is related to recovery activities associated with the event reported on November 22, 2022 (EN 56236). This notification is being made solely as a four-hour, non-emergency report for notification to other government agency. An update is being provided to the Monticello community and published on Xcel Energy's website. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of public or plant personnel. The NRC Resident Inspector has been notified.
ENS 563616 February 2023 13:26:00DresdenNRC Region 3GE-3The following information was provided by Constellation via email: On 02/06/2023 at 0416 EST, the Constellation Emergency Response Organization (ERO) Notification Database System uploaded data files into the Mass Notification System (Everbridge) which is used to notify ERO personnel when activated. At 0630, the individual reviewing the uploaded files discovered that the data files did not upload properly and that Everbridge may not notify all ERO individuals within the required 10 minutes of system initiation. Constellation resolved the issue by 0752. During the time period of 0416 to 0752, control room operators would have been unaware that the ERO notification was not successful. Therefore, this issue constitutes a loss of offsite communications capability and is reportable under 10 CFR 50.72(b)(3)(xiii), 'The licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).' This loss of offsite communications capability affected all Constellation nuclear stations. There was no impact on the health and safety of the public or plant personnel. Each affected station NRC Resident Inspectors have been or will be notified.
ENS 563576 February 2023 13:26:00Quad CitiesNRC Region 3GE-3The following information was provided by Constellation via email: On 02/06/2023 at 0416 EST, the Constellation Emergency Response Organization (ERO) Notification Database System uploaded data files into the Mass Notification System (Everbridge) which is used to notify ERO personnel when activated. At 0630, the individual reviewing the uploaded files discovered that the data files did not upload properly and that Everbridge may not notify all ERO individuals within the required 10 minutes of system initiation. Constellation resolved the issue by 0752. During the time period of 0416 to 0752, control room operators would have been unaware that the ERO notification was not successful. Therefore, this issue constitutes a loss of offsite communications capability and is reportable under 10 CFR 50.72(b)(3)(xiii), 'The licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).' This loss of offsite communications capability affected all Constellation nuclear stations. There was no impact on the health and safety of the public or plant personnel. Each affected station NRC Resident Inspectors have been or will be notified.
ENS 5623622 November 2022 17:35:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via email: On 11/22/2022, Monticello Nuclear Generating Plant initiated a voluntary communication to the State of Minnesota after receiving analysis results for an on-site monitoring well that indicated tritium activity above the (Offsite Dose Calculation Manual) ODCM and Nuclear Energy Institute (NEI) Groundwater Protection Initiative (GPI) reporting levels. The source of the tritium is under investigation and the station will continue to monitor and sample accordingly. This notification is being made solely as a four-hour, non-emergency report for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 562104 November 2022 17:10:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via email: On November 4, 2022, at 1400 hours, with Unit 2 (U2) in Mode 1 at 100 percent power, a manual scram was inserted on U2 due to rising reactor water level, which occurred following an unexpected opening of the 2B Feedwater Regulating Valve. Following the reactor scram, reactor water level decreased to approximately 0 inches, which resulted in an automatic Group II and Group III isolation (expected response). Reactor Water Level control has been established in a normal band. The cause and details of the event are under investigation. The Unit 2 scram was not complicated. Operations responded using the Emergency Operating Procedures and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 1 was unaffected by the event and remains at 100 percent power. 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). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5602330 July 2022 04:00:00DresdenNRC Region 3GE-3

The following information was provided by the licensee via email: At 2217 CDT on 7/29/22, cribhouse suction bay levels were reported less than 501.5 feet due to buildup of grass on bar racks. Ultimate Heat Sink (UHS) is INOPERABLE due to Surveillance Requirement 3.7.3.1 not met. ENTER Technical Specification (TS) 3.7.3 condition A (Required Action (RA) A.1 mode 3 in 12 hours, RA A.2 mode 4 in 36 hours). Dresden Lockmaster reports river level normal at 504.89 feet. Commenced trash rake operations to clear grass debris off of intake bar racks. At 0135 CDT on 7/30/22, cribhouse suction bay levels were reported at greater than 501.5 feet. Exit TS 3.7.3 condition A. Due to this INOPERABILITY, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(B). There was no impact on the health and safety of the public or plant personnel. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The licensee notified the NRC Resident Inspector.

  • * * UPDATE ON 7/30/22 AT 1934 EDT FROM COLLIN GRISCHOTT TO BRIAN LIN * * *

At 1116 CDT on 7/30/22, a repeat condition occurred where cribhouse suction bay levels were reported < 501.5 feet due to buildup of grass on bar racks. Entered TS 3.7.3 condition A (RA A.1 mode 3 in 12 hours, RA A.2 mode 4 in 36 hours). Actions are in-progress to clear grass debris off the intake bar racks. Due to this INOPERABILITY, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(B). At 1745 CDT on 7/30/22, cribhouse suction bay levels were reported at >501.5 feet. Exit TS 3.7.3 condition A. The station continues to monitor for intake grass buildup and taking appropriate actions to maintain UHS operability. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The licensee notified the NRC Resident Inspector. Notified R3DO (Peterson).

ENS 5598812 July 2022 11:47:00DresdenNRC Region 3GE-3The following information was provided by the licensee via fax or email: At 0803 EDT on 7/12/2022, with the Unit 2 in Mode 1 at 100% power, an automatic scram was received on Unit 2 following a turbine trip due to high reactor water level. The trip was uncomplicated with all systems responding normally post trip. All rods inserted to their full-in positions. 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 cause of the transient is under investigation. Operations responded using the Emergency Operating Procedure and stabilized the plant in Mode 3. Decay heat is being removed using the steam bypass valves to the condenser and the safety relief valves did not lift as a result of the trip. Reactor vessel inventory and pressure are being maintained in normal control bands. Unit 3 was not affected by this transient. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 559764 July 2022 09:53:00Quad CitiesNRC Region 3GE-3The following information was received from the licensee via email: At 0130 CDT on July 4 2022, it was discovered both trains of Standby Gas Treatment System were simultaneously inoperable due to failure to reach required flow rates. Both trains were capable of starting but failed to reach the required flow of 4000 SCFM. Secondary Containment differential pressure was not able to be maintained at greater than or equal to 0.25 inches of vacuum water gauge, causing Secondary Containment to also be inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 559754 July 2022 05:57:00Quad CitiesNRC Region 3GE-3The following information was received from the licensee via facsimile: On July 4, 2022 at 0104 CDT, with Unit 2 in Mode 1 at 100 percent power, a manual scram was inserted on U2 due to lowering reactor water level, which occurred following an unexpected closure of the 2A Feedwater Regulating Valve. Following the reactor scram, reactor water level decreased to approximately minus 16 inches, which resulted in an automatic Group II and Group III isolation (expected response). Following the scram, reactor water level rose to plus 75 inches resulting in a trip of all three Reactor Feedwater Pumps. At 0114 CDT, Reactor Water Level lowered to less than the Feedwater Pump High Level Trip setpoint and the 2C Reactor Feedwater Pump was restarted. Reactor Water Level control has been established in a normal band. The cause and details of the event are under investigation. The Unit 2 scram was not complicated. Operations responded using the Emergency Operating Procedure and stabilized the plant in mode 3. Decay heat is being removed by discharging steam to the main condenser using the turbine bypass valves. Unit 1 was unaffected by the event and remains at 100 percent power. 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). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The licensee will notify the Illinois Emergency Management Agency.
ENS 559221 June 2022 13:58:00Quad CitiesNRC Region 3GE-3The following information was provided by the licensee via email followed by phone call: At approximately 1043 CDT, the Quad Cities Main Control Room was notified that the Scott County Iowa warning sirens were activated in error at 1001 CDT. The sirens were not intentionally activated to notify the public of severe weather or pending emergency. This event is reportable per 10 CFR 50.72(b)(2)(xi), News Release or Notification of Other Government Agencies. This is a 4-Hour Reporting requirement. The Quad Cities NRC Resident has been notified.
ENS 5589613 May 2022 17:47:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via email: On 5/13/22 at 1111 CDT the station entered LCO 3.7.4 Condition B for Control Room Envelope being inoperable. This was due to results from an inspection in the Steam Jet Air Ejector room that identified steam leakage exceeding the leakage rate assumptions made in the Alternate Source Term (AST) dose analysis calculation. Therefore, this is being reported in accordance with 10CFR50.72(b)(3)(ii)(B) for an unanalyzed condition that significantly degrades plant safety and 10CFR50.72(b)(3)(v)(D) for any event or condition that at the time of discovery could have prevented fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. There is no impact to the health and safety of the public. NRC Resident has been notified.
ENS 5589110 May 2022 23:42:00Quad CitiesNRC Region 3GE-3

The following information was provided by the licensee via fax: At 1359 CDT on May 10, 2022, the 1B LPCI Loop Upstream Injection valve (1-1001-28B) was found to have a motor operated torque switch issue and inadequate lubrication. This issue called into question the ability of the valve to close when required. At 1746 CDT on May 10, 2022, both trains of Unit 1 LPCI were made simultaneously inoperable. TS 3.6.1.3 Condition A required de-activation of 1B LPCI Loop Downstream Injection valve (1-1001-29B) which was completed at 1746 CDT. Because of the de-activation of the 1B LPCI Loop downstream injection valve and LPCI Loop select logic, both trains of LPCI were made inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(V). Unit 1 HPCI and both loops of Core Spray are operable. After further engineering review, it was determined that 1B LPCI Loop Upstream injection valve condition was minor in nature and would not have affected the ability of the valve to close when required. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.

  • * * UPDATE AT 12:32 EDT ON 05/11/22 FROM MARK HUMPHREY TO BRIAN P. SMITH * * *

The following information was provided by the licensee via phone call and email: The last sentence in the second paragraph, "After further engineering review, it was determined that 1B LPCI Loop Upstream injection valve condition was minor in nature and would not have affected the ability of the valve to close when required," has been deleted. The licensee is continuing to follow up on the issue and believes that sentence to be unclear and premature. Notified R3DO (Skokowski).

ENS 5584415 April 2022 11:31:00PilgrimNRC Region 1GE-3The following information was provided by the licensee via email: On April 15, 2022 at 1000 hours (EDT), four off-site notifications were made to the Commonwealth of Massachusetts Department of Environmental ÿProtection (MADEP) in accordance with the Massachusetts Contingency Plan (310 CMR 40.0000). ÿThe notifications document non-radiological contaminants found slightly above reportable concentrations in select soil and groundwater samples collected during site characterization efforts, as part of the decommissioning process, from four parcels of land at the property.ÿ ÿReportable concentrations in soil were identified in a composite sample for Polychlorinated Biphenyls (PCBs). ÿReportable concentrations in groundwater were identified in samples for per- and polyfluoroalkyl substances (PFAS) and Semi Volatile Organic Compound (SVOC). Additionally, the reports include sample results where laboratory reporting limits equaled or exceeded reporting thresholds. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency in accordance with 10 CFR 50.72(b)(2)(xi).ÿ There was no impact on the health and safety of the public or plant personnel. The NRC Lead Decommissioning Inspector and NMSS Project Manager assigned to Pilgrim have been notified.
ENS 557211 February 2022 15:23:00DresdenNRC Region 3GE-3The following information was provided by the licensee via fax or email: At approximately 1025 CST, the Dresden Main Control was notified of Grundy County warning sirens issues during the intended monthly test. The Grundy County scheduled monthly siren test had issues with siren activation from the County's primary controller. The buttons to activate were being pressed but the intended sirens were not initiating. The Grundy County operator continued to attempt activation unknowingly activating the sirens in the northeast quadrant between 1000-1015 CST. This event is reportable per 10 CFR 50.72(b)(2)(xi), News Release or Notification of Other Government Agencies. This is a 4-Hour Reporting requirement. The Dresden NRC Resident has been notified.
ENS 5570821 January 2022 10:25:00MonticelloNRC Region 3GE-3The following information was provided by the licensee via email: This telephone notification is provided in accordance with 10 CFR 50.73(a)(1) to report an invalid actuation of secondary containment relays in accordance with 10 CFR 50.73(a)(2)(iv)(A). On November 29, 2021, the `B' Fuel Pool radiation monitor spiked high during restoration following the performance of the 0068 procedure `Spent Fuel Pool & Reactor Building Exhaust Plenum Monitor Calibration' due to cable to radiation monitor connector degradation from handling. This resulted in a Partial Primary Containment Group II isolation (gas systems), initiation of Standby Gas Treatment system, and isolation of the Reactor Building Ventilation system. All systems responded as designed to the actuation signal. Operations reset the Partial Primary Containment Group II isolation signal, shutdown Standby Gas Treatment System, and restored Reactor Building Ventilation system per procedures. At the time of the occurrence, the `A' Fuel Pool radiation monitor was reading normal at approximately 1.5 mr/hr. The `B' Fuel Pool radiation monitor spiked above the 50 mr/hr setpoint and continued to read erratically. Work was performed to clean and reconnect the connector and testing per 0068 procedure verified the condition was corrected. The `B' Fuel Pool radiation monitor returned to service. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 556192 December 2021 00:58:00Quad CitiesNRC Region 3GE-3At 1847 CST on December 1, 2021, it was discovered that the HPCI (high pressure coolant injection) system was inoperable. Due to this inoperability, the system was in a condition that could have prevented the fulfillment of a safety function; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v)(D). The Unit 1 RCIC (reactor core isolation cooling) system was Operable during this time period. There was no impact on the health and safety of the public or plant personnel. The NRC Resident has been notified. Unit 1 HPCI operability was restored at 2110 CST.
ENS 555679 November 2021 13:33:00PilgrimNRC Region 1GE-3At 1040 hours EST, November 9, 2021, the site reported a violation of the station National Pollutant Discharge Elimination System permit. The 24-hour environmental report addressed an unauthorized discharge of 7,245 gallons of non-radiological water that was pumped into a storm drain to de-water an on-site electrical vault located outside of the protected area. This discharge occurred from 0800 to 1230 hours on November 8, 2021. Sampling and analysis of the vault water is in progress to assess for the presence of pollutants. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The licensee notified the U.S. Environmental Protection Agency and the Commonwealth of Massachusetts Department of Environmental Protection.
ENS 5552816 October 2021 09:10:00DresdenNRC Region 3GE-3On October 16, 2021 at 0428 CDT, an automatic scram was received on Unit 3 following a turbine trip. All Rods inserted to their full in position. All systems actuated and operated as expected. Unit 3 is being maintained in Mode 3, hot standby. This event is being reported pursuant to 10CFR 50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical. The NRC Resident Inspector has been notified. The event is related to Event Number 55527.
ENS 5552716 October 2021 07:22:00DresdenNRC Region 3GE-3

(An) Unusual Event (was declared) due to a fire in the protected area not extinguished in less than 60 minutes. Main power transformer 3 faulted, the unit auto scrammed, all rods are in. The fire went out at 0622 CDT. (The licensee) is monitoring for re-flash. The unit automatically scrammed and all rods fully inserted. Decay heat removal is through the condenser. Unit 2 is unaffected and remains at 100 percent power. The licensee notified the NRC Resident Inspector and R3 Branch Chief (Riemer). Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), and DHS Nuclear SSA (email).

  • * * UPDATE ON 10/16/21 AT 0848 EDT FROM DAVID KIJOWSKI TO BETHANY CECERE * * *

The Unusual Event was terminated at 0709 CDT. Notified R3DO (Pelke), NRR EO (Felts), IR MOC (Kennedy), DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), and DHS Nuclear SSA (email).

ENS 553963 August 2021 19:48:00DresdenNRC Region 3GE-3At approximately 1539 CDT on 8/3/2021, the Dresden Station Main Control was notified of the inadvertent actuation of 17 full sounding emergency response sirens affected Dresden Station in Will County Illinois, while testing other sirens. Will County EMA inadvertently actuated the sirens on 8/3/2021 at 1440 CDT. This event is reportable per 10 CFR 50.72(b )(2)(xi), News Release or Notification of Other Government Agencies. This is a 4-Hour Reporting requirement. The Dresden NRC Resident has been notified. See related Event Notification #55395.
ENS 552447 May 2021 17:21:00MonticelloNRC Region 3GE-3The following is a summary of information received via email from Monticello Nuclear Generating Plant (MNGP): On March 9, 2021, GE Hitachi (GEH) issued Safety Communication SC 21-02 for PRC 21-02, Transfer of Information, Revision 0, pursuant to 10 CFR 21.21(b). Monticello Nuclear Generating Plant (MNGP) was listed as a potentially affected plant. This is a deviation from the Power Range Nuclear Monitor (PRNM) Licensing Topical Report, NEDC 32410P-A. On May 5, 2021, MNGP completed an evaluation of this deviation and concluded this condition represents a substantial safety hazard in that the condition could result in an Average Power Range Monitoring (APRM) flux reading either below or above the Technical Specification (plus/minus) 2% band. The condition is a defect that is reportable pursuant to 10 CFR 21.21(d)(4). The GEH NUMAC PRNMS was installed in 2009 with System Part No. 299X739NF. Name and Address of the Individual or Individuals Informing the Commission: Thomas A. Conboy, Site Vice President Monticello Nuclear Generating Plant Northern States Power Company - Minnesota 2807 West County Road 75 Monticello, MN 55362 The licensee notified the NRC Resident Inspector.
ENS 5520221 April 2021 09:45:00PilgrimNRC Region 1GE-3On April 21, 2021, at 0752 hours (EDT), an offsite notification was made to the Commonwealth of Massachusetts Department of Environmental Protection (MADEP) in accordance with Regulation 310 CMR 40.0000: Massachusetts Contingency Plan (MCP). The notification documents non-radiological contaminants found above reportable concentrations in select samples collected during site characterization efforts. The reported reportable concentrations were slightly above reporting limits in a soil sample for Per and Polyfluoroalkyl Substances (PFAS), two groundwater sampling locations for PFAS, and isolated instances of metals in groundwater including Arsenic, Vanadium, Lead, Antimony, Beryllium, Cadmium, Chromium, Nickel, and Thallium. This report is being submitted in accordance with 10CFR50.72(b)(2)(xi) based on notification being made to another government agency. Concentrations above reporting limits have been entered into the site's corrective action program. As per MCP, the site will proceed with requirements to implement the phased MCP process. This condition does not represent a threat to station personnel or to members of the general public.
ENS 5514620 March 2021 04:55:00Quad CitiesNRC Region 3GE-3At 20:30 CDT on March 19, 2021, with the Unit 1 in Mode 5 at 0 percent power, an actuation of the Unit 1 Emergency Diesel Generator (EDG) occurred during outage activities on Transformer 12 (T-12) resulting in a trip. The cause of the Unit 1 EDG auto-start was bus undervoltage as a result of the T-12 trip. The Unit 1 EDG automatically started as designed when the Bus 14-1 undervoltage signal was received. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Unit 1 EDG. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5513210 March 2021 18:26:00Quad CitiesNRC Region 3GE-3On March 10, 2021, Exelon reported an unpermitted release of a radionuclide (i.e., tritium) into the groundwater within the site boundary at Quad Cities Nuclear Power Station to the Illinois Environmental Protection Agency (IEPA) and the Illinois Emergency Management Agency (IEMA) in accordance with Illinois state regulations. There has been no detection of the release beyond the site boundary. The suspected source for the increased groundwater tritium levels is an onsite water storage tank or pipe; however, an investigation is in progress and the exact cause and source is not yet known. The increase in groundwater tritium concentration does not exceed any NRC regulations or reporting criteria. This notification is being made solely as a four-hour, non-emergency notification for a Notification of Other Government Agency. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5507118 January 2021 17:31:00PilgrimNRC Region 1GE-3On January 18, 2021 at 1600 hours (EDT), Holtec Decommissioning International (HDI) made an off-site notification to the Environmental Protection Agency's Enforcement and Compliance Assurance Division in accordance with Section B of the station's National Pollutant Discharge Elimination System (NPDES) Permit No. 0003557. The event was associated with an underground sewage water system holding tank. The specific details of the occurrence are as follows: On January 13, 2021 at 1000 hours (EDT) site personnel identified what appeared to be water bubbling up from an unidentified cover within the security protected area of the site. The water emanating from the cap had no visible color or solid material and no odor. The water estimated at 25 gallons per hour or less was flowing to a site storm drain connected to permitted outfall number 007. Initial indication was that the water was potable water as part of the station's fire protection system. Further investigation determined that a back-up in an underground sewage holding tank inlet was the source of the leakage. By 1400 hours (EDT) when bathrooms including toilets on site were shutdown and removed from service, efforts were underway to pump the tank and remove the blockage, and the bubbling from the cover had stopped. The licensee has notified the Massachusetts Environmental Protection Agency, the Massachusetts Emergency Management Agency and the NRC Resident Inspector.
ENS 549388 October 2020 13:14:00MonticelloNRC Region 3GE-3

At 1125 CDT on 10/8/20 Monticello Nuclear Generating Plant declared a Notification of an Unusual Event (NOUE) due to a Security Condition that did not involve a hostile action, due to a helicopter that hovered over the site for approximately 10 minutes. The unit remained at 100 percent power during the event. The licensee notified the NRC Resident Inspector, the Minnesota State Duty Officer and the Wright County and Sherburne County Sherriff departments of the event. Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE ON 10/8/2020 AT 2013 EDT FROM JEFF OLSON TO JEFFREY WHITED * * *

At 1715 CDT Monticello Nuclear Generating Plant terminated the Notice of Unusual Event (HU1.1), upon confirmation through federal law enforcement and conversation with the aircraft owner that the aircraft in question was performing power line inspections for a different utility and was not a threat to the plant. Monticello determined that this condition did not meet the 1-hour reporting requirements of 10 CFR 73.71. Notified R3DO (Orlikowski), NRR EO (Miller), and IRD MOC (Gott). Additionally, notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * RETRACTION ON 10/28/20 AT 1436 EDT FROM JACOB BURSKI TO BETHANY CECERE * * *

Monticello Nuclear Generating Plant (MNGP) is retracting this event notification based on subsequent information received that was not available at the time of the original notification. Following review of the additional information collected by the site through an investigation performed with input from local and federal law enforcement, Xcel Energy determined the helicopter did not constitute a credible threat or compromise site safety or security. There was no impact to public health or safety. The NRC Resident Inspector has been notified. The licensee will notify the State and county. Notified R3DO (Peterson).

ENS 5329929 March 2018 16:42:00Quad CitiesNRC Region 3GE-3On March 29, 2018, Exelon Generation Company, LLC notified the Illinois Environmental Protection Agency (IEPA) and the Illinois Emergency Management Agency (IEMA) in accordance with state regulations of an unpermitted release of radionuclides at the Quad Cities Nuclear Power Station within the site boundary. There has been no detection of the liquid release beyond the site boundary. No impact to human health or the environment are anticipated. This notification is being made to satisfy 10CFR50.72(b)(2)(xi), notification of the NRC for any event related to the health and safety of the public for which a notification to other government agencies has been or will be made. The source of the Tritium release was from the Rad waste system. The spill was reported to be within the protected area which is within the site boundary. The quantity of the release is unknown at this point as the investigation and spill cleanup is in progress. The Licensee Notified the NRC Resident Inspector.
ENS 5328725 March 2018 23:43:00PilgrimNRC Region 1GE-3

On March 25, 2018 at 1616 hours (EDT), with the reactor in cold shutdown condition, two control rod drive piping lines were determined to be potentially inoperable in the event of a design basis earthquake due to support defects. The control rod drive piping forms a portion of the reactor coolant pressure boundary and primary containment boundary. The supports will be repaired prior to plant startup. This event had no impact on the health and/or safety of the public. The NRC Resident Inspector has been notified. The licensee will notify the Commonwealth of Massachusetts.

  • * * RETRACTION FROM JOE FRATTASIO TO HOWIE CROUCH AT 1500 EDT ON 4/13/18 * * *

The purpose of the notification is to retract ENS notification 53287 made on 03/25/18 for Pilgrim Nuclear Power Station. The previous notification reported that control rod drive (CRD) piping could be potentially inoperable in the event of a design basis earthquake, at the time of discovery, due to piping support defects. Subsequent evaluation has demonstrated that the piping was not inoperable. Specifically, after an engineering evaluation, it has been determined that the CRD Hydraulic System operability was never lost and the system was operable, although non-conforming, based on the support configuration not conforming to the pipe support drawings. The affected pipe supports have been restored or reworked to the proper design condition in accordance with the design drawings. The CRD System has subsequently been restored to a fully operable status. Notified R1DO (Jackson) and IRD MOC (Pham).

ENS 5328523 March 2018 21:07:00MonticelloNRC Region 3GE-3This report is made for a loss of Emergency Assessment Capability associated with Emergency Action Levels for Toxic and Flammable Gas and is reportable under 10 CFR 50.72(b)(3)(xiii). During an emergency equipment inventory, it was identified that methods were not available to detect levels of toxic or flammable gas at the IDLH (Immediately Dangerous to Life and Health) level for a number of substances due to the detector having an unsuitable range. The IDLH is used to assess the Emergency Action Level Alert Range. The ability of the Control Room Staff to detect and respond to the presence of toxic or flammable gas is unaffected. Because there have been no chemical spills or releases that would require sampling to be performed, the health and safety of the public was not affected. The resident NRC Inspector has been notified. The licensee will be notifying the state of Minnesota.
ENS 5325913 March 2018 15:54:00PilgrimNRC Region 1GE-3On March 13, 2018 at 1000 hours (EDT), with the reactor in Cold Shutdown condition, both 345kV incoming power lines and 23 kV Shutdown Transformer became unavailable during the Northeast winter storm. Per procedures, the emergency on-site emergency power supplies (Emergency Diesel Generators) were running and providing power to essential systems. In addition, the back-up Diesel Air Compressor was in service and one Reactor Protection System bus was on the back-up power supply prior to the loss. With both 345kV incoming power lines and 23 kV Shutdown Transformer unavailable, Pilgrim Nuclear Power Station procedures direct a report be made to the NRC per the requirements of Title 10 Code of Federal Regulations 50.72(b)(3)(v), any event that could have prevented the fulfillment of the safety function. No actual loss of safety function has occurred since the on-site emergency power supplies are maintaining the reactor in a safe shutdown condition and removing residual heat. The loss of incoming power is under investigation. This event had no impact on the health and/or safety of the public. The NRC Resident Inspector has been notified.
ENS 532423 March 2018 02:19:00PilgrimNRC Region 1GE-3At 2315 EST on March 2, 2018, Pilgrim Nuclear Power Station (PNPS) determined, based on information received from the Commonwealth of Massachusetts, that there may be a potential loss of offsite response capabilities due to ongoing severe natural hazard conditions (i.e., major winter storm) along the coast of Massachusetts. According to information received by PNPS, towns within the 10 Mile EP Radius could be hampered in implementing some protective actions specified in the emergency plan in the unlikely event an emergency were to occur. There is no condition at the Station that would warrant implementation of any emergency plan at this time. PNPS continues to operate safely and is monitoring the weather conditions closely. The Station maintains emergency assessment, response, and communication capability. This report is being made conservatively in accordance with 10 CFR 50.72(b)(3)(xiii) which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. As stated previously, the Station maintains emergency assessment, response, and communication capability. The licensee notified the NRC Resident Inspector.
ENS 531987 February 2018 15:04:00DresdenNRC Region 3GE-3At approximately 1040 CST, seven (7) Dresden Nuclear Power Station Offsite Emergency Notification sirens (i.e., Siren Nos. DR1, DR4, DR5, DR6, DR9, DR10, and DR11) were inadvertently activated. The Kendall County, IL Emergency Management Agency notified the Exelon Generation Company, LLC. Emergency Response Organization that at 1040 CST, a contract individual inadvertently cut a wire that resulted in the actuation of these seven sirens for three minutes. The contract organization personnel are addressing the issue with the sirens. The Kendall and Will County Emergency Management Agency contacted Exelon Generation Company regarding this event. This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi) as an event where other government agencies were notified. The NRC Resident Inspector has been informed of this notification. The sirens are operable.