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 Entered dateSiteRegionReactor typeEvent description
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 5502610 December 2020 10:58:00MillstoneNRC Region 1Westinghouse PWR 4-LoopThis 60-day telephone notification is being submitted in accordance with paragraphs 10 CFR 50.73(a)(1) and 50.73(a)(2)(iv)(A) to report an invalid actuation of the 'B' train High Head Safety Injection Pump (3SIH*P1B), the 'B' train Low Pressure Safety Injection Pump (3RHS*P1B) and four Steam Generator Blowdown Containment isolation valves at Millstone Nuclear Power Station Unit 3. At 1908 EST on November 6, 2020, with Unit 3 in Mode 3, a partial invalid actuation of 'B' train Emergency Core Cooling System (ECCS) components occurred. The 'B' train SIH pump and the 'B' train RHS pump had started, and ran successfully on recirculation. Four Steam Generator Blowdown Containment isolation valves also closed. Due to this condition the 'B' Emergency Diesel Generator and the 'B' Emergency Generator Load Sequencer (EGLS) were declared inoperable and the required Technical Specification action statements were entered. Troubleshooting determined that this actuation was caused by a failure of one of the circuit boards in the 'B' train EGLS that caused a partial 'B' train 'SIS only' signal. Other 'B' Train components received the 'SIS only' signal but did not start because they were already running or were a backup to an already running component. Troubleshooting discovered a failed NAND gate on the 'B' Train EGLS XA93 circuit card. The card was replaced, retested, and the Technical Specification action statements were exited. The pumps and valves responded in accordance with plant design. No other equipment was affected during this event. There were no safety consequences or impacts on the health and safety of the public. The event was entered into the station's corrective action program. The actuation was not due to actual plant conditions or parameters meeting design criteria for an ECCS actuation. Therefore, this is considered an invalid actuation. The NRC Resident Inspector was notified.
ENS 550203 December 2020 17:10:00Calvert CliffsNRC Region 1CEAt 0923 EST on December 3, 2020, with Unit 1 in Mode 1 at 100 percent power, an actuation of the Emergency AC Electrical Power System (Emergency Diesel Generator 1A) occurred during normal plant operations. The reason for Emergency Diesel Generator 1A auto start was due to Class 1E 4KV Bus 11 feeder breaker opening. The Emergency Diesel Generator 1A automatically started as designed when the loss of voltage signal on 4KV Bus 11 was received. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the Emergency AC Electrical Power System. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The cause of the 4KV Bus 11 Feeder Breaker opening is unknown at the present time and is under investigation.
ENS 5500016 November 2020 12:13:00LimerickNRC Region 1GE-4During normal plant start up on Limerick Unit 1, reactor pressure was raised above 200 psig prior to unisolating the Unit 1 high pressure coolant injection system (HPCI) which remained inoperable. Per TS 3.5.1, HPCI is required to be operable in Mode 2 above 200 psig. HPCI has since been restored to operable. The NRC Resident Inspector has been notified.
ENS 5499613 November 2020 05:32:00LimerickNRC Region 1GE-4At 0245 EST on November 13, 2020, the Limerick Unit 1 reactor automatically scrammed on a valid Reactor High Pressure signal (1096psig). The Reactor High Pressure signal was caused by the closure of the 1B Inboard Main Steam Isolation Valve (MSIV), causing reactor pressure to rise, exceeding the Reactor Protection System (RPS) setpoint of 1096psig. The shutdown was normal and the plant is stable in Hot Shutdown with normal pressure control via the Main Steam Bypass Valves to the Main Condenser and normal level control using the Feedwater System. The closure of the 1B Inboard MSIV appears to have been caused by a loss of Primary Containment Instrument Gas (PCIG) pneumatic supply to the valve. The licensee notified the NRC Resident Inspector, and will be notifying Berks, Chester, and Montgomery Counties, as well as the Pennsylvania Emergency Management Agency.
ENS 549888 November 2020 10:10:00MillstoneNRC Region 1CE
Westinghouse PWR 4-Loop

Millstone Units 2 & 3 declared an Unusual Event at 0921 EST after an earthquake was felt onsite. The earthquake monitoring instrumentation did not actuate, and there were no station system actuations. No damage has been detected at this time. Millstone has initiated their Abnormal Operating Procedure for an earthquake and performing station walkdowns. The State of Massachusetts has been notified. The Waterford Police and U.S. Coast Guard have contacted the station. The NRC resident has been notified. Notified DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

  • * * UPDATE ON 11/09/2020 AT 0715 EST FROM JASON HARRIS TO THOMAS KENDZIA * * *

At 1510 EST on November 8, 2020, Millstone Units 2 & 3 exited the Unusual Event due to the earthquake following plant walkdowns that revealed no damage to plant structures, systems, or components. Station and System walkdowns identified no issues due to the earthquake. Millstone notified the State and local authorities, and the NRC Resident Inspector. Notified R1DO (DeFrancisco), IRD (Grant), NRR (Nieh), R1RA (Lew), NRR EO (Miller), DHS SWO, FEMA Operations Center, CISA Central, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

ENS 549793 November 2020 08:00:00Calvert CliffsNRC Region 1CE

At 0011 EST on 11/03/20, it was discovered that BOTH trains of salt water were simultaneously INOPERABLE. While in a planned (limiting condition for operation) LCO window with the 21 salt water train INOPERABLE for post-maintenance testing, debris intrusion in the 22 salt water header rendered the redundant salt water train 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). One train of salt water was restored to operable at time 0026 EST. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. This event did not affect Unit 1.

  • * * RETRACTION ON 11/20/2020 AT 1218 EST FROM BRIAN FOVEAUX TO OSSY FONT * * *

Following the eight hour 10 CFR 50.72 notification made on 11/03/2020 (EN 54979), further engineering analysis determined that 22 Saltwater subsystem flow remained at levels sufficient to fulfill its safety function based on the conditions existing at the time of the event. Despite flow in 22 Saltwater subsystem falling below the short term (four hour) minimum value for approximately 15 minutes, engineering analysis was able to determine the increased heat removal capacity associated with the lower bay temperatures was sufficient to offset the reduced heat removal capacity associated with the lower 22 Saltwater subsystem flow. This demonstrated that actual heat transfer to the saltwater subsystem was sufficient to ensure all safety functions were fulfilled during the event. Therefore, this event notification is being retracted as it is not reportable pursuant to 10 CFR 50.72(b)(3)(v)(A), (B) and (D). The NRC Resident has been informed. Notified R1DO (Greives)

ENS 5497129 October 2020 15:12:00Peach BottomNRC Region 1GE-4At 1030 EDT on Thursday, October 29, 2020, during the performance of Peach Bottom Atomic Power Station leakage testing of the reactor pressure vessel and associated piping, a through-wall leak (non-isolable) was identified on an instrument line connected to the N16A nozzle. The reactor will be maintained shutdown until pipe repairs and testing are complete. The NRC resident inspector has been informed.
ENS 549272 October 2020 12:35:00MillstoneNRC Region 1At 0945 hours (EDT) on 10/02/2020, with Millstone Unit 3 in Mode 4, Operations discovered a door in the Secondary Containment boundary blocked open. Investigation determined the door was blocked open at 1842 (EDT) on 10/01/2020, rendering Secondary Containment inoperable. The door was closed at 1002 ((EDT) on 10/02/2020), restoring Secondary Containment to operable status. Since Secondary Containment was rendered inoperable, Dominion Energy is reporting this as a condition that could have prevented the fulfillment of the safety function to control the release of radioactive material and mitigate the consequences of an accident. This condition is being reported as an eight hour report pursuant to 10 CFR 50.72 (b)(3)(v)(C) and (D). There was no release of radioactivity to the public. The NRC Senior Resident Inspector has been notified. With the door blocked open, the plant was in a 24-hour shutdown action statement. The state of Connecticut and local towns were notified.
ENS 5491728 September 2020 05:02:00Peach BottomNRC Region 1

EN Revision Imported Date : 10/12/2020 LOSS OF TECHNICAL SUPPORT CENTER VENTILATION SYSTEM DUE TO PLANNED MAINTENANCE: This is an eight-hour, non-emergency notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the planned maintenance affects the functionality of an emergency response facility. Planned maintenance activities are being performed on 09/28/20 to the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) HVAC. The work includes replacement of supply fan and roof-top unit. Work is scheduled to complete on 10/11/20. If an emergency is declared requiring PBAPS TSC activation during this period, the PBAPS TSC will be staffed and activated using existing Emergency Preparedness (EP) procedures. If the PBAPS TS becomes uninhabitable due to radiological, or other conditions, the TSC Station Emergency Director will relocate the TSC staff to an alternate location in accordance with EP procedures. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency. The NRC Resident Inspector will be notified by the licensee.

  • * * UPDATE ON 10/9/20 AT 1234 EDT FROM BRIAN BAILEY TO ANDREW WAUGH * * *

An eight-hour, non-emergency notification for a loss of Emergency Assessment Capability was made on 9/28/20 under Event Notification 54917 for planned maintenance activities to the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) ventilation system. This event was reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the planned maintenance affected the functionality of an emergency response facility. This update to EN 54917 is to notify applicable stakeholders that, following satisfactory completion of the planned supply fan and roof-top unit replacement work, the PBAPS TSC ventilation system has been returned to service with no remaining work or outstanding deficiencies related to this work. The licensee has notified the NRC Resident Inspector. Notified R1DO (Lally).

ENS 5491325 September 2020 15:28:00FitzPatrickNRC Region 1A non-licensed contract supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 5489510 September 2020 16:09:00PilgrimNRC Region 1A contract employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's rights to access the plant have been suspended. The licensee notified the NRC Region I Decommissioning Lead Inspector.
ENS 548741 September 2020 14:48:00Nine Mile PointNRC Region 1The following is a synopsis of information received from the licensee: On March 6, 2020, while at zero percent power and in Cold Shutdown - Mode 4, Nine Mile Point Unit 2 (NMP2) determined through surveillance testing that three Main Steam Isolation Valves (MSIVs) did not meet their Technical Specification closure time. The cause of the MSIV failures has been determined to be delayed Air Pack response. The delay was caused by a buildup of corrosion product and waxy foreign material believed to be dried pipe thread sealant or O-ring assembly lube that accumulated on the internal surfaces of the Air Pack during refurbishment by the vendor Trillium (previously Hiller). The following is action taken or planned to be taken to prevent recurrence: A note will be added to the procurement requirement evaluation form and purchase order for MSIV Air Pack refurbishments to minimize use of O-ring lubricant and thread sealant to limit likelihood of capturing foreign material on Air Pack valve internals. The Energy Industry Identification System (EIIS) component function identifier and system name of each component or system referred to above is: Component - Main Steam Isolation Valves, Air Pack. IEEE 803 Function Identifier - VOP. IEEE805 System Identification - SB. The licensee notified the NRC Resident Inspector. For further information contact: Todd Tierney Plant Manager Nine Mile Point Nuclear Station Exelon Generation Company, LLC Brandon Shultz Site Regulatory Assurance Manager Nine Mile Point Nuclear Station (315) 349-7012 .
ENS 5482911 August 2020 20:22:00Peach BottomNRC Region 1At 1334 EDT on Tuesday August 11th, the Peach Bottom Atomic Power Station (PBAPS) Technical Support Center (TSC) Ventilation System lost power due to a trip of the Station Blackout (SBO) electric power supply breaker. The trip was due to a fault at the Conowingo Dam and Conowingo was not able to realign electric power to the SBO within an hour. Power restoration is complete and TSC Ventilation was restored at 1725 EDT. This report is being submitted pursuant to 10CFR 50.72(b)(3)(xiii) as a Major Loss of Emergency Preparedness Capabilities due to a reduction in the effectiveness of the Onsite Technical Support Center (TSC). The NRC Resident Inspector has been notified.
ENS 548206 August 2020 13:10:00Peach BottomNRC Region 1This report is being made as required by 10 CFR 50.73(a)(2)(iv)(A) to describe an automatic actuation of containment isolation valves in more than one system. Because the actuation was invalid, this 60-day telephone notification is being made instead of a written LER (licensee event report), in accordance with 10 CFR 50.73(a)(1). On 06/08/2020, at approximately 0424 EDT, a trip of the Unit 3 'A' reactor protection system (RPS) MG-Set resulted in a partial activation of the primary containment isolation system and inboard containment isolation valves closed in multiple systems. All affected Group III containment isolation valves were verified to be closed. It was determined that the normal power supply for the Unit 3 'A' RPS had failed. Power was transferred from the normal to the alternate source and the RPS 'A' channel was reset. Investigation determined that the 3A RPS MG Set motor contactor coil winding had failed due to an internal short circuit. The motor contactor has been replaced. The containment isolation was not due to actual plant conditions or parameters meeting design criteria for containment isolation. Therefore, this is considered to be an invalid actuation. The NRC Resident Inspector has been informed of this notification.
ENS 548164 August 2020 22:43:00MillstoneNRC Region 1

EN Revision Imported Date : 8/20/2020 BOTH SERVICE WATER HEADERS DECLARED INOPERABLE On 8/4/20, at 1745 EDT, Millstone Unit 2 entered technical specification (TS) 3.0.3 due to both service water headers being declared inoperable because strainer differential pressures (D/Ps) were greater than 9 psid. The high service water strainer D/P was the result of heavy debris impingement caused by tropical storm Isaias. To reduce heat loads and service water flow, Unit 2 reduced power to 75 percent. One service water header was restored to operable at 1816 EDT, at which time TS 3.0.3 was exited. At 1843 EDT both service water headers were declared operable. The NRC Resident Inspector has been notified.

  • * * RETRACTION ON 8/19/2020 AT 1141 EDT FROM ERIC DONCH TO KIRBY SCALES * * *

The purpose of this call is to retract a report made on August 4, 2020, NRC Event Number EN 54816 describes a condition at Millstone Power Station Unit 2 (MPS2) in which both trains of service headers were declared inoperable due to service water strainer differential pressures greater than 9 psid. The condition was reported to the NRC pursuant to 10 CFR 50.72(b)(3)(v)(A), (B) and (D) via an 8 hour prompt report as an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to shutdown the reactor and maintain it in a safe shutdown condition, remove residual heat and mitigate the consequences of an accident. Upon further review, MPS2 determined that there was no loss of safety function. An engineering evaluation supports the conclusion that a strainer differential pressure of 16 psid would not challenge the system flow distribution during worst case conditions. The evaluation also demonstrates that flowrates on both headers were observed to be unaffected during the timeframe of the high strainer differential pressure conditions. Therefore, both service water headers would have provided the required flows to perform their safety function. Therefore, this condition is not reportable and NRC Event Number EN 54816 is being retracted. The basis for this conclusion has been provided to the NRC Resident Inspector. Notified R1DO (Greives).

ENS 5474918 June 2020 20:37:00Beaver ValleyNRC Region 1On June 18, 2020, Beaver Valley Power Station, Unit 1 determined that leakage from an outside out-of-service liquid waste pipe that is within a radiologically controlled area contains several isotopes. Analysis indicates greater than 2,000 picoCuries per liter of tritium, and isotopes of Mn-54, Co-58, Co-60, and Cs-137 are above the lower limit of detection. At 1725 EDT, in accordance with site procedures and NEI 07-07, 'Industry Ground Water Protection Initiative,' notification to the Commonwealth of Pennsylvania was planned. At 1930 EDT notification to the Commonwealth of Pennsylvania was completed. The leak is currently contained. The leakage did not exceed any NRC regulations or reporting criteria. This notification is being made solely as a four-hour, non-emergency notification for a planned 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 547406 June 2020 12:25:00SeabrookNRC Region 1At 0920 (EDT), with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to group 1 of control rod bank 'B' fully inserting into the core. All systems responded normally post trip. Operations has stabilized the plant in mode 3 at NOP/NOT (normal operating pressure and temperature). Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser. Emergency feedwater actuated due to low low steam generator level as expected. This event is being reported pursuant to 10CFR50.72(b)(2)(iv)(B) and 10CFR50.72(b)(3)(iv)(A) The senior NRC Resident Inspector has been notified. The plant response to the trip was uncomplicated. All safe shutdown equipment is available. There were no reliefs or safeties actuated during the transient. The licensee manually tripped eight days ago for the same condition. See EN #54731.
ENS 547385 June 2020 10:39:00MillstoneNRC Region 1

EN Revision Imported Date : 10/6/2020 CONTROL ROOM BOUNDARY DOOR FAILURE On June 5, 2020, at 0320 (EDT) a loss of control room envelope (CRE) was declared inoperable due to failure of door 204-36-007. The door was repaired at 0322 (EDT), restoring the CRE to operable. The NRC Resident Inspector, state, and local authorities were notified.

  • * * RETRACTION ON 07/09/2020 AT 1443 EDT FROM GERALD A. BAKER TO OSSY FONT * * *

The purpose of this call is to retract a report made on June 5, 2020, NRC Event Number EN54738. NRC Event Report number EN54738 describes a condition at Millstone Power Station Unit 2 (MPS2) in which a control room envelope boundary door was discovered to not be able to fully close due to the latching mechanism being stuck in the extended position. The condition was reported to the NRC pursuant to 10 CFR 50.72(b)(3)(v)(D) via an 8 hour prompt report as an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident. Upon further review, MPS2 determined that there was no loss of safety function. An engineering evaluation determined that even with the control room boundary door unable to be fully closed due to the latching mechanism being stuck in, the extended position, control room air in-leakage would not have been sufficient to prevent the control room emergency ventilation system from performing its safety function. Therefore, this condition is not reportable and NRC Event Number EN54738 is being retracted. The basis for this conclusion has been provided to the NRC Resident Inspector. Notified R1DO (Dimitriadis).

  • * * UPDATE FROM MICHAEL GAGNON TO BRIAN P. SMITH AT 1444 EDT ON 10/01/2020 * * *

The purpose of this call is to provide an update to the retraction for a report made on June 5, 2020, NRC Event Number EN54738. The retraction being updated was made on 7/9/2020 at 1443 hours. NRC Event Report number EN54738 describes a condition at Millstone Power Station Unit 2 (MPS2) in which a control room envelope boundary door was discovered to not be able to fully close due to the latching mechanism being stuck in the extended position. The condition was reported to the NRC pursuant to 10 CFR 50.72(b)(3)(v)(D) via an 8 hour prompt report as an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident (the Control Room Envelope). A subsequent engineering evaluation of the conditions that existed at the time, determined that the inability of the control room boundary door to fully close due to the latching mechanism being stuck in the extended position did not have an adverse impact upon the ability of the CRE to perform its safety function. The CRE remained operable throughout this event, and the ventilation system would have performed its safety function. Therefore, this condition is not reportable and NRC Event Number EN54738 is being retracted. The basis for this conclusion has been provided to the NRC Resident Inspector. Notified R1DO (Lally).

ENS 5473129 May 2020 16:41:00SeabrookNRC Region 1At 1403 EDT, with the unit in Mode 1 and 100 percent power, the reactor was manually tripped due to Group 1 of Control Rod Bank 'B' unexpectedly inserting. All systems responded normally post-trip. Operations stabilized the plant in Mode 3 at 557 degrees Fahrenheit. Decay heat removal is being accomplished via the steam dumps in the steam pressure mode to the main condenser. Emergency feedwater actuated due to low low steam generator level as expected. This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR (b)(3)(iv)(A). The NRC Senior Resident Inspector has been notified.
ENS 5471615 May 2020 13:25:00SalemNRC Region 1At 0947 (EDT) on 5/15/20, Salem reported to the New Jersey Department of Environmental Protection a sheen on the Delaware River. This discovery did not violate any NRC (Nuclear Regulatory Commission) regulations or reporting criteria. 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 will be notifying the National Response Center and Lower Alloways Creek Township. The substance spilled was less than one pint of hydraulic oil.
ENS 546923 May 2020 22:28:00Nine Mile PointNRC Region 1On 5/3/2020 at 1100 EDT, Operations identified a step change in the Main Control Room ambient noise. The cause of the noise was a rise in vibrations on the Number 11 fan motor of the Main Control Room Ventilation Circulating Fan. Another step change in noise occurred and Operations swapped from the Number 11 fan motor to its redundant Number 12 fan motor, but the noise and vibrations did not improve. The two independent motors are connected to the blower shaft with belts on either end of the shaft. This entire fan and motor assembly is contained within the Main Control Room ventilation ducting and is not visible. At 1118 EDT, Operations shut off the Main Control Room Ventilation Circulating Fan due to Number 11 fan motor vibrations, declared the Main Control Room Air Treatment System inoperable, and entered the Technical Specification 3.4.5.e, 7-day action statement. At 1750 EDT, Maintenance entered the ductwork and informed Operations that the Number 11 fan bearing had catastrophically failed and because of the extent of damage and close physical proximity to the Number 12 fan motor, jeopardized its continued operation. As a result, Operations also declared the Number 12 fan motor inoperable and determined the event was reportable as a loss of safety function per 10 CFR 50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector.
ENS 546913 May 2020 11:43:00SusquehannaNRC Region 1At 0821 EDT on May 3, 2020, the Susquehanna Steam Electric Station Unit 1 reactor automatically scrammed due to a trip of the Main Turbine. The Unit 1 reactor was operating at 76 percent reactor power following a ramp schedule to full power subsequent to a maintenance outage. The Control Room received indication of a Main Turbine trip with both divisions of the Reactor Protection System actuated and all control rods inserted. The Reactor Recirculation Pumps tripped on End of Cycle - Recirculation Pump Trip. Reactor water level lowered to -1 inch causing Level 3 (+13 inches) isolations. No Emergency Core Cooling System or Reactor Core Isolation Cooling actuations occurred. The operations crew subsequently maintained reactor water level at the normal operating band using Reactor Feed Water. No Steam Relief Valves opened. The reactor is currently stable in Mode 3. Investigation into the trip of the Main Turbine is in progress. The NRC Resident Inspector was notified. A voluntary notification to the Pennsylvania Emergency Management Agency and press release will occur. This event requires a 4-hour Emergency Notification System (ENS) notification in accordance with 10 CFR 50.72(b)(2)(iv)(B) and an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(3)(iv)(B).
ENS 5468024 April 2020 07:00:00Beaver ValleyNRC Region 1At 0130 (EDT) on April 24, 2020, during the Beaver Valley Power Station, Unit 2 refueling outage, while performing examinations of the 66 reactor vessel head penetrations, it was determined that one penetration could not be dispositioned as acceptable per ASME Code Section XI. Penetration 37 will require repair prior to returning the vessel head to service. The indication was not through wall and there was no evidence of leakage based on inspections performed on the top of the reactor vessel head. The examinations were being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 to find potential flaws/indications before they grow to a size that could potentially jeopardize the structural integrity of the reactor vessel head pressure boundary. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5466313 April 2020 19:33:00MillstoneNRC Region 1At 1550 EDT on 4/13/2020, with Millstone Power Station Unit 3 operating at approximately 82 percent reactor power, an automatic reactor trip occurred following a turbine trip due to low condenser vacuum caused by the trip of multiple circulating water pumps. Due to the loss of the circulating water pumps, decay heat removal was established by the steam generator atmospheric dump valves. All other systems responded as expected to the trip. Auxiliary feedwater actuated automatically as expected following the trip due to low-low levels in the steam generators. There was no risk to the public. There was no impact to Millstone Unit 2. The Senior Resident Inspector has been informed. This event is being reported as a four hour report under 10 CFR 50.72(b)(2)(iv)(B) as a condition that resulted in actuation of the reactor protection system while the reactor was critical, and as an eight hour report under 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(3)(iv)(B) for actuation of the auxiliary feedwater system. The licensee also notified the state of Connecticut, the Connecticut Department of Energy and Environmental Protection, and the city of Waterford.
ENS 5465710 April 2020 10:58:00FitzPatrickNRC Region 1On April 10, 2020, at 0300 (EDT), an oil leak from 23PCV-12, HPCI (High Pressure Core Injection) Trip System Pressure Control Valve (PCV), resulted in the system being declared inoperable. This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10 CFR 50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector.
ENS 546311 April 2020 19:11:00MillstoneNRC Region 1On April 1, 2020, at 1625 EDT, Milllstone Unit 3 was in Mode 1, at 100 percent power, when an automatic reactor trip occurred following a main generator trip. The cause was due to a circuit fault between the main generator breaker and the offsite switchyard. The reactor trip was not complicated and the reactor remains stable in Mode 3. One of the two offsite electrical sources remain inoperable with an investigation of the circuit fault underway. Decay heat removal is maintained by the main condenser. There was no effect on Unit 2. The NRC Resident Inspector was notified. The licensee notified State and local government agencies.
ENS 5460725 March 2020 03:30:00SalemNRC Region 1At 0056 EDTon March 25, 2020, with Unit 1 at 17 percent power during a unit power ascension, the reactor was manually tripped due to the failure of the 11 Rod Control Motor Generator caused by a malfunction of its associated Voltage Regulator. The trip was not complex, with all systems responding normally post-trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. Decay heat is being removed by the Atmospheric Steam Dumps and Auxiliary Feedwater System. Salem Unit 2 was not affected. Due to the actuation of 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), This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System. There was no impact to the health and safety of the public or plant personnel. The NRC Resident lnspector has been notified.
ENS 545695 March 2020 21:14:00SeabrookNRC Region 1On March 05, 2020, at 2100 EST, the site commenced a planned upgrade of the main plant computer system (MPCS). During this upgrade, the normal computer data will not be available to the emergency response facilities, but compensatory capabilities will be in place. The scheduled duration for the MPCS upgrade is 96 hours. Since the compensatory measures will be in place in excess of 72 hours, this condition is being reported pursuant to 10 CFR 50.72(b)(3)(xiii). The NRC Resident Inspector has been notified.
ENS 545624 March 2020 15:35:00Nine Mile PointNRC Region 1At 1205 EST, on March 4, 2020, Nine Mile Point Unit 2 initiated a manual reactor scram due to lowering Electrohydraulic Control System (EHC) level in the turbine control system. The cause of the lowering level was a leak in the EHC system piping. All control rods inserted. There were no safety system actuations. The cause of the EHC leak is being investigated. The NRC Resident has been notified. Additionally, the licensee notified the New York State Public Service Commission.
ENS 5453320 February 2020 15:04:00FitzPatrickNRC Region 1(On February 20, 2020, at 1240 EST, the Licensee determined the following information:) This notification is in reference to reports EN 54130 and LER 2019-002, which were retracted. James A. FitzPatrick Nuclear Power Plant received additional information on the technical basis for the retraction. Further review, including testing of the terminal blocks, demonstrated that the short circuit current would result in heat levels in excess of cable insulation ratings. Unprotected DC control circuits for non-safety related DC motors are routed between separate fire areas. A postulated fire in one area can cause a short circuit and potentially result in secondary fires or cable fires in other fire areas where the cables are routed. The secondary fires or cable failures degrade the degree of separation for redundant safe shutdown trains and are outside the assumptions of the 10 CFR 50 Appendix R Safe Shutdown Analysis. This condition is reportable in accordance with 10 CFR 50.72(b)(3)(ii)(B). Compensatory actions per the Technical Requirements Manual (TRM) for affected fire areas have been implemented. A modification to install fuses in the control circuits for 94P-2(M), 31P-7A(M), 31P-7B(M), and 94P-13(M) has been scheduled and shall correct this condition. The NRC Resident Inspector has been notified.
ENS 5452514 February 2020 03:36:00SusquehannaNRC Region 1At 0025 EST on February 14, 2020, Susquehanna Steam Electric Station Unit 2 reactor was manually scrammed due to rising Main Condenser backpressure caused by a loss of the Unit 2 Offgas Recombiner. Unit 2 reactor was being operated at maximum facility output, approximately 98% RTP, when at 0012 EST, Unit 2 Recombiner 0C145 Panel Trouble and 2C198 HWC Panel Trouble alarms were received along with rising Main Condenser backpressure. Initial Main Condenser backpressure was 2.6 in HgA and was rising at approximately 0.3 HgA/min. A Recirc Lim 2 was inserted to lower reactor power and condenser backpressure continued to rise following the reduction in reactor power. A manual scram was inserted at 0025 EST by placing the Mode Switch to Shutdown when condenser backpressure rose to 6 in HgA. All control rods inserted. Reactor water level lowered to -30 inches causing Level 3 (+13 inches) isolation and partial (Division 2) Level 2 (-38 inches) isolation. No ECCS actuations occurred and RCIC initiated. The Operations crew subsequently maintained reactor water level at the normal operating band using Reactor Feed Water. No steam relief valves opened. The Reactor Recirculation Pumps remained in service. The reactor is currently stable in Mode 3. Investigation into the cause of the loss of Unit 2 recombiner is underway. The NRC Senior Resident Inspector was notified. A voluntary notification to PEMA and press release will occur.
ENS 5450331 January 2020 09:46:00FitzPatrickNRC Region 1At 0555 (EST), on January 31, 2020, James A. FitzPatrick was at 38 percent power when an automatic scram occurred as a result of a main turbine trip on high Reactor Pressure Vessel (RPV) water level. The plant was at reduced power in preparation for maintenance activities. The 'A' Reactor Feed Pump (RFP) was being removed from service when a perturbation in reactor water level reached the high RPV water level setpoint. This resulted in a main turbine trip and 'B' RFP trip. The automatic scram inserted all control rods. A subsequent low water level resulted in a successful Group 2 isolation. The plant is stable in Mode 3 with the 'B' RFP maintaining RPV water level. The initiation of the reactor protection systems (RPS) due to the automatic scram signal at critical power is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The general containment Group 2 isolations are reportable per 10 CFR 50.72(b)(3)(iv)(A). The licensee notified the NRC Resident Inspector, and the State and Local government for the scram. Decay heat is being removed via the main condenser.
ENS 5445727 December 2019 07:53:00MillstoneNRC Region 1

This is a synopsis of initial information received via phone: On December 27, 2019, at 0705 EST, while Unit 2 was at 100 percent (Mode 1), the 'A' Main Feedwater Pump tripped due to an unknown cause. The reactor was manually tripped and is currently at zero (0) percent power (Mode 3). Decay heat is being removed via Auxiliary Feedwater. The 'B' Feedwater pump is operable. There was no impact on Unit 3. The licensee notified the NRC Resident Inspector. Additionally, Connecticut Department of Environmental Protection, Waterford Dispatch, and East Lyme Emergency Management Division will be notified.

  • * * UPDATE ON 12/27/2019 AT 1330 EST FROM JASON PARIS TO CATY NOLAN * * *

This is an update to NRC Event Number 54457. At 0704 EST, on 12/27/2019, with Millstone Unit 2 operating at 100 percent power, operators inserted a manual reactor trip. The trip was initiated due to a trip of the 'A' Main Feedwater Pump. The Auxiliary Feedwater System (AFW) automatically actuated as required. All control and shutdown rods fully inserted. All safety systems responded as designed. No primary or secondary safety valves actuated during or after the transient. Unit 2 is currently stable at normal operating pressure and temperature in Mode 3, Hot Standby. Reactor Coolant System (RCS) temperature is being maintained by the steam dump system with all Reactor Coolant Pumps (RCPs) in service. Main Feedwater has been secured, and Auxiliary Feedwater is in service. The electrical system is in normal alignment. There was no impact on Unit 3. There was no impact to the health and safety of the public or plant personnel. Due to Reactor Protection System (RPS) actuation while critical, this event was reported as a four hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B); and an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that resulted in a valid actuation of the AFW system. The licensee will notify the NRC Resident Inspector of the update. Notified R1DO (Cherubini).

ENS 5444917 December 2019 21:10:00MillstoneNRC Region 1At 1929 EST, on 12/17/19, Millstone Unit 3 began preparations for shutting down the reactor as the 'A' Emergency Diesel Generator (EDG) could not be restored to operable status within the 14-day outage time, requiring a Technical Specification (Tech Spec) shutdown. Per Tech Spec 3.8.1.1., the reactor must be in Hot Standby in six (6) hours, and Cold Shutdown within the following 30 hours. Hot Standby is estimated by midnight, and Cold Shutdown by 1800 EST on 12/18/19. All other safety and shutdown systems are operable. Decay heat removal will be through the Shut Down Cooling and Residual Heat Removal systems. There was no impact to Unit 2. There was no impact to the health and safety of the public or plant personnel. The licensee notified the state of Connecticut, Waterford County, and the NRC Resident Inspector.
ENS 543694 November 2019 09:06:00Beaver ValleyNRC Region 1At 0535 (EST) on November 4, 2019, with Unit 1 in mode 1 at 15 (percent) power, the reactor was manually tripped due to the lifting of an 'A' Main Steamline Safety Valve following a Condenser Steam Dump transient. The trip response was not complex, with all systems responding normally post-trip, and all control rods fully inserted into the core. Operations responded and stabilized the plant. Decay heat is being removed by discharging steam to the Main Condenser by using the Condenser Steam Dump Valves. Offsite power is available and is currently supplying Normal and Emergency busses. The plant is currently stable in mode 3. Unit 2 is unaffected by this event and remains at 100 (percent) power in mode 1. 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 543662 November 2019 23:03:00Beaver ValleyNRC Region 1At 1515 on November 2, 2019, the Refueling Water Storage Tank (RWST) was declared inoperable due to a Low Head Safety Injection relief valve discharging to the Safeguards Sump during routine surveillance testing. The leakage from the Low Head Safety Injection system in conjunction with a postulated Design Basis Accident (DBA) Loss of Coolant Accident (LOCA) with transfer to Safety Injection Recirculation may result in dose exceeding the Dose Analysis of the Exclusion Area Boundary (EAB) and the Control Room, which is common to both Unit 1 and Unit 2. This condition may not be bounded by existing design and licensing documents; however, it poses no impact to the health and safety of the public or plant personnel. The Low Head Safety Injection relief valve has been isolated to prevent further leakage, and makeup to the RWST completed. At 1602 on November 2, 2019 the RWST was declared Operable. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(B), (C), (D) as an Unanalyzed Condition and a condition that could have prevented the Fulfillment of a Safety Function." The licensee notified the NRC resident inspector.
ENS 543641 November 2019 10:03:00Nine Mile PointNRC Region 1On November 1, 2019 at 0316 EDT, Nine Mile Point Unit 2 (NMP2) received Control Room annunciation for HPCS SYSTEM INOPERABLE and inoperable status light indication for TRIP UNITS OUT OF FILE/POWER FAIL. Initial investigation has identified a potential failed 24 vdc power supply which supplies power to the HPCS trip units for system initiation and control. The HPCS system has been declared inoperable per TS 3.5.1 resulting in an unplanned 14 day LCO. All other plant systems functioned as required. NMP2 is currently at 100 percent power in Mode 1. This condition is reportable under 10 CFR 50.72(b)(3)(v)(D) as, 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (D) Mitigate the consequences of an accident.' The licensee notified the NRC Resident Inspector.
ENS 5434724 October 2019 16:24:00Oyster CreekNRC Region 1Holtec Decommissioning International has notified the State of New Jersey that during the conduct of Industrial Site Remediation Act (ISRA) non-radiological site investigation field sampling and analysis activities at the Oyster Creek site, soil and groundwater exceedances to New Jersey Default Impact to Groundwater Soil Levels, Residential Direct Contact Soil Remediation, Non-Residential Direct Contact Soil Remediation and Class IIA Groundwater Quality Standards were identified. These exceedances are reportable under New Jersey Administrative Code NJAC 7:26C. That notification was made at 1524 EDT. The NRC Regional Inspector and the State of New Jersey were notified.
ENS 5434021 October 2019 01:23:00Peach BottomNRC Region 1

While Unit 3 was shutting down for 3R22 refueling outage, the mode switch was taken to shutdown position which is a manual scram signal. The manual scram signal was not received from the mode switch. A subsequent manual scram was inserted with the use of the manual scram push buttons. The Unit 3 reactor is shutdown with all rods inserted. Unit 2 was unaffected by the event and remains in Mode 1 at 100 percent power. The licensee notified the NRC Resident Inspector, Pennsylvania and Maryland State Agencies, local government. A media press release is planned. Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email), FEMA Region 3 Watch Office (email).

  • * * UPDATE AT 0316 EDT ON 10/21/19 FROM KEVIN GROMANN TO BETHANY CECERE * * *

Conditions no longer meet an Emergency Actuation Level and will not deteriorate. Unit 3 reactor is shutdown with all control rods fully inserted. The NOUE was terminated at 0230 EDT." The licensee notified the NRC Resident Inspector, Pennsylvania and Maryland State Agencies, local government. Notified the R1DO (Jackson), NRR EO (Miller), IRDMOC (Gott), R1RA (Lew via email), NRR (Nieh via email), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email), FEMA Region 3 Watch Office (email).

ENS 5433718 October 2019 02:28:00Beaver ValleyNRC Region 1

At 1951 (EDT) on October 17, 2019, fretting indications on the reactor coolant system pressure boundary piping (pressurizer spray line) were identified. This condition does not appear to meet original construction code, ANSI B31.1, 1967 Edition thru summer 1971 Addenda. The condition will be resolved prior to plant startup. This event is being reported as an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. This condition will be corrected prior to the plant entering Mode 4.

  • * * RETRACTION ON 10/31/19 AT 1450 EDT FROM JIM SCHWER TO BETHANY CECERE * * *

An engineering evaluation has determined that the subject fretting is not considered a flaw, but instead is considered wear. Appendix F of Section III of the ASME Boiler and Pressure Vessel Code was applied and it was determined that the pressurizer spray line piping maintained its required design safety functions in the as-found condition. The wear has been repaired during the current refueling outage in accordance with the original construction code (ANSI B3l.l, 1967 Edition through summer 1971 Addenda) as well as Owner's Requirements. The NRC Resident Inspector has been notified. Notified R1DO (Young).

ENS 5433015 October 2019 19:14:00Peach BottomNRC Region 1

On 10/15/19 at 1210 (EDT) Peach Bottom discovered a degraded spring hanger (23DBN-H39) associated with Unit 3 High Pressure Coolant Injection (HPCI) system. The hanger is located downstream of MO-3-23-14 HPCI Steam Supply Valve before the HO-3-23-4513 Turbine Stop Valve. A review of the piping and support design analysis were performed and concluded the U3 HPCI turbine inlet nozzle would potentially exceed its allowable stresses. Following Engineering review, U3 HPCI was declared inoperable at 1743 (EDT). This report is being submitted pursuant to 10 CFR 50.72(b)(3)(v)(D). The NRC Resident Inspector has been notified.

  • * * RETRACTION ON 11/22/19 AT 0851 EST FROM DAN DULLUM TO BETHANY CECERE * * *

Additional evaluation by Engineering personnel determined that the degraded spring hanger would have no adverse effect on the subject piping or HPCI turbine nozzle structural integrity. Pressure, deadweight, and seismic stresses were within allowable limits. Non-destructive examination (NDE) of the piping and nozzle was performed to identify any signs of cracking, yielding, or defects. NDE results were satisfactory. The degraded spring hanger did not effect the Unit 3 HPCI system operability and this call is being retracted. The NRC Resident Inspector has been notified. Notified R1DO (Cahill).

ENS 5432511 October 2019 14:22:00Calvert CliffsNRC Region 1At 1300 EDT, a Technical Specification required shutdown was initiated at Calvert Cliffs Unit 1. Technical Specification Action 3.1.4.C (Restore Control Element Assembly (CEA) alignment) was entered on 10/11/2019 at 1100 EDT, with a Required Action to reduce thermal power to less than 70 percent Rated Thermal Power and restore CEA alignment within 2 hours. This Required Action was not completed within the Completion Time; therefore, a Technical Specification required shutdown was initiated, and this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(i). At 1345 EDT, CEA alignment was restored and Technical Specification 3.1.4 (Control Element Assembly Alignment) was met. Reactor Power is being stabilized. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5428317 September 2019 14:08:00Three Mile IslandNRC Region 1Event of Public Interest performed to notify State and Local agencies for emergency vehicle response required due to an on-site non-work related illness. The individual was unresponsive and was unable to be resuscitated due to the medical issue. The individual was outside the Radiological Controlled Area (RCA) and no radioactive material or contamination was involved. The NRC Resident Inspector was notified. Responding to the site were emergency medical services, fire, and police. The licensee notified Pennsylvania Emergency Management Agency, Dauphin County Emergency Management Agency, Cumberland County Emergency Management Agency, Lancaster County Emergency Management Agency, York County Emergency Management Agency, and Lebanon County Emergency Management Agency.
ENS 5421111 August 2019 11:40:00SalemNRC Region 1At 0814 EDT on 8/11/19, with Unit 2 at 83 percent power during a planned load reduction, the reactor was manually tripped due to degraded feedwater flow control to the 23 Steam Generator caused by a malfunction of the associated Feedwater Regulating Valve, 23BF19. The trip was not complex, with all systems responding normally post trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit is stable in Mode 3. Decay heat is being removed by the Main Steam Dumps and Auxiliary Feedwater System. Due to the actuation of 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). This event is also being reported as an eight-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater System. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The licensee notified the State of New Jersey. Unit 1 remains at 100 percent power.
ENS 541995 August 2019 01:28:00Nine Mile PointNRC Region 1On August 4, 2019 at 1745 (EDT), Reactor Recirculation Pump (RRP) 11 tripped. The cause for the trip is under investigation. Following the RRP trip, the Average Power Range Monitors (APRMs) flow bias trips are inoperable due to reverse flow through RRP 11. The APRMs were restored to operable on August 4, 2019 at 1807, when the RRP 11 Discharge Blocking Valve was closed. This 8-hour non-emergency report is being made based upon requirements of 10CFR50.72(b)(3)(v)(A) which states: 'Licensee shall notify the NRC of any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (A) Shut down the reactor and maintain it in a safe shutdown condition.' The licensee has notified the NRC Resident Inspector.
ENS 541983 August 2019 23:33:00Hope CreekNRC Region 1At 1947 (EDT) on 8/3/19, with Hope Creek in Mode 1 at 37 percent power, the reactor was manually scrammed due to loss of condenser vacuum. All control rods fully inserted into the core. All safety systems responded as designed and expected. Reactor level was stabilized using Reactor Core Isolation Cooling (RCIC) and Reactor Feedwater Pumps. Currently reactor water level is being maintained by the feedwater system and decay heat is being removed by the main condenser using the main turbine bypass valves. 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). Due to the manual actuation of RCIC, this event is also being reported as an eight-hour, non-emergency notification per 10 CFR 50. 72(b )(3)(iv)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The plant is in its normal shutdown electrical lineup with all safe shutdown equipment available. The licensee will be notifying the state of Delaware, state of New Jersey and the Lower Alloway Creek township.
ENS 5418326 July 2019 13:27:00Beaver ValleyNRC Region 1A non-licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 541484 July 2019 12:36:00SusquehannaNRC Region 1A licensed supervisor had a confirmed positive for alcohol on a random fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Senior Resident Inspector.
ENS 5413727 June 2019 16:06:00SusquehannaNRC Region 1At 0937 EDT on 6/27/19, Susquehanna Unit 2 had a control power fuse fail that caused a loss of power to one of two power distribution systems of the Reactor Protection System. This loss of power resulted in a valid isolation signal and actuation of the Primary Containment Isolation System that affected multiple systems, and is reportable per 10 CFR 50.72(b)(3)(iv)(A). The situation has been resolved and the plant is currently using an alternate power source. Offsite power and the Emergency Diesel Generators are still available. The licensee notified the NRC Resident Inspector.