Semantic search

Jump to navigation Jump to search
 Entered dateSiteRegionReactor typeEvent description
ENS 5091725 February 2020 09:04:00OconeeNRC Region 2B&W-L-LPAt approximately 0605 EDT on March 23, 2015, the Oconee Nuclear Station main control room and Security received an emergency call for an employee experiencing a non-work related medical issue. Site first responders were dispatched in conjunction with a request for off-site medical assistance. The individual was transported by ambulance to the Oconee Medical Center and was pronounced dead at 0717 EDT. The individual was outside of the protected area (within the owner controlled area) and no radioactive material or contamination was involved. The cause of death has not been determined. This notification is being made in accordance with 10 CFR 50.72(b )(2)(xi) for situations related to the health of on-site personnel for which a notification to other government agencies has been made. The South Carolina Occupational Safety and Health Administration (SCOSHA) was notified at 0920 EDT. The NRC Resident Inspector has been notified. The licensee notified Pickens County, South Carolina and Oconee County Emergency Managements.
ENS 5134025 February 2020 08:52:00Arkansas NuclearNRC Region 4CE
B&W-L-LP
This notification is being made in accordance with 10 CFR 50 72(b)(3)(xiii) as an event that will result in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g. a significant portion of control room indication, Emergency Notification System or offsite notification system.) The emergency preparedness plan requires seismic monitoring instruments to diagnose an earthquake for emergency actions levels (EAL) HU6 (Natural or destructive phenomena affecting protected area) and HA6 (Natural or destructive phenomena affecting vital areas). At 1020 CDT on August 24, 2015 the Semi-Annual Seismic System Functional Test commenced. While this test is in progress, seismic alarm capability is not available for EAL declaration purposes. ANO procedures provide compensatory measures of using offsite sources to obtain seismic data. It should be noted that seismic data will still remain capable of being recorded, only alarm capability is lost. The licensee notified the NRC Resident Inspector.
ENS 5169525 February 2020 08:52:00Three Mile IslandNRC Region 1B&W-L-LPOn December 1, 2015, at 2119 EST, with Unit 1 in power operation mode, during a planned maintenance activity, an invalid Heat Sink Protection System (HSPS) actuation occurred. At the time of the event, electrical maintenance technicians were verifying a HSPS relay contact state using an electrical test meter. The contact was being verified open by recording both voltage and resistance readings across the contact. The technicians first measured voltage. No voltage was found, indicating the relay contact was open, as expected. The technicians then measured for resistance across the open contact. Test meters have lower circuit impedance when measuring resistance as opposed to voltage, which can result in electrically bridging across open contacts. When the meter was installed across the open contact to obtain the resistance reading, the HSPS actuation circuit logic was completed and the inadvertent HSPS actuation occurred. The HSPS actuation resulted in the steam driven Emergency Feedwater (EFW) pump automatically starting and control valves receiving actuation set point signals. There was no emergency feed water injection into the steam generators. At the time of the inadvertent HSPS actuation, steam generator operating levels were above the HSPS actuation setpoint. The specific train and system that actuated was the Heat Sink Protection System, Emergency Feedwater System Actuation on Loss of All Reactor Coolant Pumps (RCP) Train A. The HSPS Loss of all RCP Train A actuation was complete. The EFW valves and EFW steam driven pump started and functioned successfully. This is reported under 10 CFR 50.73(a)(2)(iv)(A) for an invalid actuation of HSPS Loss of all RCP Train A and in accordance with 10 CFR 50.73(a)(1), this notification of the invalid actuation is provided in lieu of a written LER. The Licensee notified the NRC Resident Inspector.
ENS 5332913 April 2018 06:07:00OconeeNRC Region 2B&W-L-LPOn 4/13/2018 at 0227 (EDT), the Oconee Unit 1 Reactor was manually tripped from 24 percent power due to the inability to control main feedwater flow through the Main Feedwater Control Valves using the Integrated Control System. Due to the RPS actuation while critical, this event is being reported as a 4-hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B). Following the reactor trip, multiple Main Steam Relief Valves failed to reseat at the expected pressure. Using procedure guidance, Main Steam Pressure was lowered by 115 psig, resulting in the closing of all Main Steam Relief Valves. All other post-trip conditions are normal and all other systems performed as expected. Unit 1 is currently in Mode 3 and stable. Decay heat is being removed by the steam generators discharging steam to the main condenser using the turbine bypass valves. Units 2 and 3 are not affected by the Unit 1 reactor trip. The licensee notified the NRC Resident Inspector.
ENS 531066 December 2017 12:42:00Three Mile IslandNRC Region 1B&W-L-LPOn December 6, 2017, during evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornado generated missiles, Three Mile Island Nuclear Station identified a non-conforming condition in the plant design such that specific TS equipment is considered to not be adequately protected from tornado generated missiles. A tornado could generate a missile that could strike the emergency diesel generator (EDG) fuel oil supply tank (DFT) vent stack. This could result in crimping of the stack, which could affect the ability of the DFT to perform its design function if such a tornado would occur. This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v)(D) for 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 mitigate the consequences of an accident. This condition is being addressed in accordance with NRC enforcement guidance provided in EGM 15-002 and DSS-ISG-2016-01. Compensatory measures have been implemented in accordance with these documents. The NRC Resident Inspector has been informed of this notification.
ENS 529475 September 2017 17:16:00Three Mile IslandNRC Region 1B&W-L-LPOn September 5, 2017 at 1111 EDT, with the reactor at 100 percent core thermal power and steady state conditions, plant personnel identified that both doors of the emergency personnel airlock of the equipment hatch were open simultaneously due to failure of the interlock. Personnel were at both the outside and inside doors, personnel heard air movement through the air lock. Immediate action was taken to close the inner containment personnel airlock door and it was verified closed. Both doors of the emergency personnel airlock of the equipment hatch were open for less than one minute. There was no radioactive release as a result of the event. The cause of the interlock failure is under investigation. This condition requires an 8-hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(ii)(A), the condition of the nuclear power plant, including its principal safety barriers (primary containment), being seriously degraded. This condition is also reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material. The NRC Resident Inspector has been notified.
ENS 5292725 August 2017 14:42:00Three Mile IslandNRC Region 1B&W-L-LPOn August 24, 2017 a malfunction internal to the River Water Chemistry Control System resulted in measurable free available chlorine levels over a one-hour period at the station outfall to the Susquehanna River. The chlorine levels exceeded the station NPDES (National Pollutant Discharge Elimination System) permit effluent limitations. The River Water Chemistry Control System was shutdown until the condition is corrected. The concentrations released did not threaten the downstream users or the environment. Pennsylvania Department of Environmental Protection was notified of the NPDES non-compliance on August 25, 2017 at 1115 (EDT). Pursuant to 10 CFR 50.72(b)(2)(xi), this notification satisfies the requirement to notify the NRC of the occurrence of any event or situation related to the health and safety of the public or onsite personnel, or protection of the environment, for which notification to the other government agencies has been made. The NRC Resident Inspector has been notified. Notified DOE, EPA, USDA, HHS, and FEMA.
ENS 5276723 May 2017 11:34:00Three Mile IslandNRC Region 1B&W-L-LPOn March 24, 2017, at 1425 EDT, while performing Engineered Safeguards Actuation System (ESAS) quarterly High Pressure Injection/Low Pressure Injection Logic and Component testing, an unintended test signal was generated when a test switch was moved to the OFF position but went slightly past this position and engaged contacts for the Test no. 1 position. When examined, the test switch was found to be degraded which allowed the switch to move past the center position and engage the test no. 1 contacts. This resulted In a partial actuation of 'B'- train ESAS components. It also resulted in an injection to the reactor coolant system (RCS). The test signal was immediately removed by operators and the inadvertently started equipment secured. The plant was operating at 100% power when the event occurred. There were no valid signals or plant conditions present to warrant the safety system actuation. The 'B' Emergency Diesel Generator rolled on air start but did not get up to full speed. Decay Heat Removal Pump 'B' started and the Decay Heat Removal Injection valve 4B opened, Make-Up Pump 'C' started, Make-Up Pump suction valve 14B opened, Make-Up pump discharge valves 16C and 16D opened, Spent Fuel Pump 1B tripped off, Air Handling Fan 18 tripped off and Air Handling Fan 1C trip tripped off. These components properly functioned from the inadvertent test signal and were secured prior to any adverse impact to plant operation. There was a small injection of borated water into the RCS. The plant remained stable at 100% power operation. Pursuant to 10 CFR 50.73(a)(1) the following information is provided as a sixty (60) day telephone notification to the NRC. This notification, reported under 50.73(a)(2)(iv)(A), is being provided in lieu of the submittal of a written LER to report a condition that resulted in an invalid partial actuation of the 'B' train of the Engineered Safeguards Actuation System (ESAS) as it was not part of a pre-planned sequence. The Licensee notified the NRC Resident Inspector.
ENS 5248612 January 2017 18:25:00OconeeNRC Region 2B&W-L-LPA non-licensed supervisor has been found in violation of the Duke Energy Fitness for Duty Policy during a random fitness for duty test. The individual's access to the plant has been suspended. The licensee has notified the NRC Senior Resident Inspector.
ENS 5244117 December 2016 05:43:00Arkansas NuclearNRC Region 4B&W-L-LP

At approximately 1400 CST on 12/16/16, during the performance of VEF-38A Lead Penetration Room Ventilation System (PRVS) Exhaust Fan Monthly Test, flow was found to be at 2000 SCFM with an operability limit of 1620 to 1980 SCFM. VEF-38A was declared inoperable. Unit 1 entered Technical Specification Limiting Condition for Operation (LCO) 3.7.11 Condition C for both trains of PRVS inoperable. With VEF-38A aligned as the lead fan and capable of auto-start, the operable standby fan (VEF-38B) would not have started. During the time that VEF-38A was inoperable and capable of auto-starting, the Unit 1 PRVS was in a condition that could have prevented the control of the release of radioactive material. At 1546 CST on 12/16/16, Unit 1 rendered VEF-38A incapable of auto starting by placing its hand switch in PULL-TO-LOCK. Unit 1 Entered LCO 3.7.11 condition A for one PRVS train inoperable and Exited LCO 3.7.11 Condition C. This is a notification per 10 CFR 50.72(b)(3)(v) for a condition that could have prevented the control of the release of radioactive material. The licensee has notified the NRC Resident Inspector.

  • * * UPDATE ON 2/7/17 AT 1528 EST FROM BUCHANON DICKSON TO DONG PARK * * *

EN 52441 was initiated on December 16, 2016, when the VEF-38A fan flow was found to be in excess of the procedurally defined operability limit during the monthly lead penetration room ventilation system test. The revision of the procedure in use at the time had inadvertently included acceptance criterion for fan air flow in the monthly supplements. The monthly tests demonstrate the flow paths for the two trains are functional and open, but they are not performed in the designed Engineered Safeguards (ES) configuration. The monthly tests do not secure the normal supply and exhaust ventilation within the penetration room boundaries; therefore, flow may be outside limits required during the ES configuration. The 18 month surveillance, which measures the flowrate of the system while in the ES configuration, was completed in April 2016. The surveillance verified the system's operability. The systems have not been modified or altered since this surveillance; therefore the measured flowrate remains the same. The procedure has been revised subsequent to this event to remove the flowrate as an 'acceptance criterion' for the monthly test. Because the VEF-38A flow did not result in fan inoperability, both fan trains remained operable; therefore, ANO-1 did not lose a safety function to control a radioactive release. Based on that, conclusion EN 52441 is being retracted. The licensee will notify the NRC Resident Inspector. Notified R4DO (Warnick).

ENS 524157 December 2016 23:39:00Three Mile IslandNRC Region 1B&W-L-LPWhile TMI (Three Mile Island) Unit 1 was in a hot shutdown condition, leakage was identified coming from an RCS (reactor coolant system) pressure boundary on a welded connection on the 'A' Reactor Coolant Pump. The leakage is unisolable from the RCS and is less than 0.5 gpm. Planned actions are to cooldown Unit 1 to cold shutdown conditions in order to repair the leakage. The licensee will be notifying the Pennsylvania Emergency Management Agency and has notified the NRC Resident Inspector.
ENS 5223411 September 2016 17:44:00Arkansas NuclearNRC Region 4B&W-L-LPDuring performance of an extent of condition evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, Arkansas Nuclear One, Unit 1, identified non-conforming conditions in the plant design such that specific TS equipment on Unit 1 is considered not be adequately protected from tornado missiles. The reportable condition is postulated by tornado missiles entering the Unit 1 Controlled Access area, elevation 386', Upper North Electrical Penetration Room (UNEPR) through penetrating a hollow metal door and then striking safety related cables. A tornado could generate multiple missiles capable of striking the Unit 1 UNEPR and rendering both safety related emergency feedwater trains inoperable. This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v)(B) and (D) for 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 (B) Remove residual heat, or (D) Mitigate the consequences of an accident. This condition was identified as part of an on-going extent of condition review of potential tornado missile related site impacts. Licensee Event Report (LER) 50-313/2016-002-00 was recently submitted addressing previously identified tornado missile vulnerabilities at the Unit 1 plant. Enforcement discretion per Enforcement Guidance Memorandum EGM 15-002 has been implemented and required actions taken. Corrective actions will be documented in a follow-on licensee event report. The licensee has notified the NRC Resident Inspector. A similar evaluation is on going for Unit 2.
ENS 5209718 July 2016 21:41:00Three Mile IslandNRC Region 1B&W-L-LPAt 1600 EDT, testing of the Everbridge ERO (Emergency Response Organization) notification system identified the system was not able to notify all ERO individuals. This constitutes a loss of offsite communications capability. The issue was reported resolved by the vendor and site testing has verified resolution as of 2130. This event is reportable under 10 CFR 50.72(b)(3)(xiii) as a loss of communications capability. The NRC Resident Inspector has been notified. Some of the ERO personnel did not receive a test page. The requirement is to have all ERO personnel receive the page within ten minutes. Compensatory measures were instituted while the system was not functional.
ENS 5204928 June 2016 17:50:00Three Mile IslandNRC Region 1B&W-L-LP

At 1055 (EDT) on 06/28/16 a gas void was found during the monthly surveillance inspection located in the common suction line to the High Pressure Injection / Makeup (HPI / MU) pumps. At 1150 on 06/28/16 the HPI suction line cross-connect valves were closed to isolate and separate the 'A' & 'B' Trains of HPI. The 'A' train of HPI was declared degraded and initiated a 72 hour LCO (Limiting Condition of Operation) under TS (Technical Specification) 3.3.2. Investigation and analysis by Engineering determined that the size of the void did not meet the acceptance criteria for system operability. Due to the size of the void and location at time of discovery, both trains of HPI were determined to be inoperable until the suction cross connect valves were closed. This condition is reportable under 10 CFR 50.72(b)(3)(v)(D) as a Condition That Could Have Prevented Fulfillment of a Safety Function to mitigate the consequences of an accident. The void is being vented to restore a water-solid condition. The last successful surveillance was conducted on 05/31/16. The cause of the void is being investigated. The NRC Resident Inspector has been informed.

  • * * RETRACTION FROM CRAIG SMITH TO DANIEL MILLS AT 1056 EDT ON 08/22/16 * * *

Following the 8-hour 10 CFR 50.72 notification made on 06/28/16 (EN 52049), further engineering analysis determined that the as-found void size was insufficient to cause the high pressure injection pumps to become inoperable or unable to fulfill their safety function. The cause for the void continues to be under investigation including the development of actions to prevent recurrence. Void checks are being performed at an increased frequency until cause is determined, and actions to prevent recurrence are in place. As determined through analysis, both trains of HPl were operable and available such that the safety function was never lost. Therefore, this event notification is being retracted as it is not reportable pursuant to 10 CFR 50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector. Notified R1DO (Dimitriadis).

ENS 5194923 May 2016 15:36:00Arkansas NuclearNRC Region 4CE
B&W-L-LP
A 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 5189129 April 2016 10:48:00Arkansas NuclearNRC Region 4CE
B&W-L-LP
The licensee notified the Arkansas Department of Emergency Management, National Response Center, and Local Emergency Planning Committee regarding an onsite spill of 12 (percent) Sodium Hypochlorite (bleach solution). Approximately 2000 gallons of Sodium Hypochlorite solution leaked from a bulk tank within the protected area, outside the tank containment berm. Approximately 100 gallons were estimated to have entered the nearby storm drain. The estimate was based on preliminary chemistry samples. The quantity released exceeded the Reportable Quantity (RQ) for Sodium Hypochlorite (RQ of 100 pounds) and was therefore reported. There is no impact to the operation of the ANO units or personnel onsite or offsite. No harm to the environment is expected. No offsite emergency response is required. This event is reportable under 10 CFR 50.72(b)(2)(xi) as an event or situation related to the protection of the environment for which a notification to other government agencies have been made. The NRC Resident Inspector has been notified.
ENS 5178510 March 2016 09:44:00Arkansas NuclearNRC Region 4CE
B&W-L-LP
This notification is being made due to planned maintenance during the Semi-Annual Seismic System Functional Test. This test will result in a major loss of emergency assessment capability for emergency action levels (EAL) HA6 (Natural or destructive phenomena affecting VITAL AREAS), while the control room 0.1g acceleration alarm is non-functional. The emergency preparedness plan requires the 0.1g acceleration alarm indication to declare EAL HA6 during a seismic event > Operating Basis Earthquake (OBE). This condition requires an 8 hour nonemergency immediate reportability to the NRC in accordance with 10 CFR 50.72(b)(3)(xiii), Major Loss of Assessment, Response, or Communication Capability. At approximately 0840 CST on March 10, 2016 the Semi-Annual Seismic System Functional Test commenced. While this test is in progress, seismic alarm capability is not available for EAL declaration purposes. ANO procedures provide compensatory measures of using offsite sources to obtain seismic data. It should be noted that seismic data will still remain capable of being recorded and only alarm capability is lost. The Semi-Annual Seismic System Functional Test is scheduled to be completed in less than 24 hours. The licensee will inform the NRC Resident Inspector.
ENS 517706 March 2016 16:09:00OconeeNRC Region 2B&W-L-LP

At 1512 EST, a fire/explosion occurred in the Unit 1 Main Transformer which resulted in a reactor trip. At 1520 EST, the licensee declared a Notification of Unusual Event. Offsite assistance was requested. At 1633 EST, smoke and flame were no longer visible. Fire brigade personnel were applying additional foam to prevent a re-flash. No personnel injuries occurred. Offsite assistance was requested with three local fire departments responding. All rods inserted on the trip. Steam generator feed is by the normal path. The plant is in its normal shutdown electrical lineup. The licensee has notified state and local authorities and the NRC Resident Inspector. Notified DHS SWO, FEMA, and DHS NICC. Notified FEMA NWS and Nuclear SSA via email.

  • * * UPDATE FROM DAVID HALE TO HOWIE CROUCH AT 1711 EST ON 03/06/16 * * *

At 1658 EST, the licensee declared an Alert based on EAL Alert A.1. The cause of entry was that the fire damaged an overhead power line that supplies emergency power to all three units at Oconee. Offsite power is still available to all units. At 1708 EST, the fire is declared out. The licensee has notified the NRC Resident Inspector. Notified DHS SWO, FEMA, DHS NICC, USDA, HHS, DOE, and EPA. Notified FEMA NWS, FDA and Nuclear SSA via email.

  • * * UPDATE FROM DAVID HALE TO HOWIE CROUCH AT 1805 EST ON 03/06/16 * * *

The licensee made notification of the RPS actuation as a result of the transformer fault. The licensee has notified the NRC Resident Inspector. Notified R2DO (Sykes).

  • * * UPDATE FROM DAVID HALE TO HOWIE CROUCH AT 2026 EST ON 03/06/16 * * *

At 2016 EST, the licensee terminated all emergency declarations. The licensee has notified the NRC Resident Inspector. Notified R2DO (Sykes), IRD (Gott), NRR EO (Morris), DHS SWO, FEMA, DHS NICC, USDA, HHS, DOE, and EPA. Notified FEMA NWS, FDA and Nuclear SSA via email.

ENS 517114 February 2016 18:50:00Arkansas NuclearNRC Region 4CE
B&W-L-LP
A non-licensed supervisor tested positive for a drugs during a random Fitness for Duty test. The individual's access to the plant has been suspended. The NRC Resident Inspector has been informed.
ENS 5154317 November 2015 12:11:00Arkansas NuclearNRC Region 4CE
B&W-L-LP

This notification is being made due to planned maintenance during the Semi-Annual Seismic System Functional Test. This test will result in a major loss of emergency assessment capability for emergency action level (EAL) HA6 (natural or destructive phenomena affecting VITAL AREAS), while the control room 0.1g acceleration alarm is non-functional. The emergency preparedness plan requires the 0.1g acceleration alarm indication to declare EAL HA6 during a seismic event greater than the Operating Basis Earthquake (OBE). This condition requires an 8 hour non-emergency immediate reportability to the NRC in accordance with 10 CFR 50.72(b)(3)(xiii), Major Loss of Assessment, Response, or Communication Capability. At approximately 1200 CST on November 17, 2015, the Semi-Annual Seismic System Functional Test will commence. While this test is in progress, seismic alarm capability is not available for EAL declaration purposes. ANO procedures provide compensatory measures of using offsite sources to obtain seismic data. It should be noted that seismic data will still remain capable of being recorded and only alarm capability is lost. The Semi-Annual Seismic System Functional Test will occur intermittently over the next four days. The licensee has notified the NRC Resident Inspector.

  • * * UPDATE FROM STEVE KIRSCHBERGER TO VINCE KLCO ON 11/18/15 AT 1940 EST * * *

The licensee returned the Seismic System to service at 1347 CST on 11/18/15. The licensee notified NRC Resident Inspector. Notified the R4DO (Warnick).

ENS 514555 October 2015 21:47:00Three Mile IslandNRC Region 1B&W-L-LP

At 2115 (EDT) on 10/05/15, an Alert was declared due to a fire in the Auxiliary building affecting DC-P-1A (Decay closed cooling pump 1A) and A-Train safety equipment. The fire is out. The licensee reported the fire was extinguished at approximately 2201 EDT. The fire did not hamper operations personnel responding to the fire. Offsite fire assistance was requested. The NRC Resident Inspector will be notified. The licensee notified the York Haven Power Station, PEMA (Pennsylvania Emergency Management Agency), and the counties of Cumberland, Lebanon, Lancaster, York, and Dauphin. Notified DHS, FEMA, USDA, HHS, DOE, DHS NICC, EPA EOC, FEMA NWC (via email), FDA EOC (via email) and Nuclear SSA (via email).

  • * * UPDATE AT 0015 EDT ON 10/06/15 FROM JAMES CREIGHTON TO S. SANDIN * * *

The licensee is terminating the Alert at 0009 EDT on 10/06/15 based on the following: At 2115 (EDT) on 10/05/15, an Alert (HA3) was declared due to a fire in the Decay Closed Cooling Water Pump '1A' motor and breaker. The fire was extinguished at 2201 (EDT). Following inspection by electrical maintenance the 'P' 480V bus was re-energized at 2305 (EDT) and restoration of previously running loads is in progress. Station (TMI) is in a 72-hour LCO for repairs to the Decay Closed Cooling Water Pump '1A' (DC-P-1A). TMI (Three Mile Island) is terminating the event based upon the above information. The licensee notified the York Haven Power Station, PEMA (Pennsylvania Emergency Management Agency), and the counties of Cumberland, Lebanon, Lancaster, York, and Dauphin. The licensee will issue a press release. The licensee informed the NRC Resident Inspector. Notified R1DO (Bickett), NRR (Howe) and IRD (Gott). Notified DHS, FEMA, USDA, HHS, DOE, DHS NICC, EPA EOC, FEMA NWC (via email), FDA EOC (via email) and Nuclear SSA (via email).

ENS 5126827 July 2015 16:31:00OconeeNRC Region 2B&W-L-LPAt approximately 0956 EDT on July 27, 2015, Oconee Nuclear Station Unit 2 experienced a valid actuation of the Emergency Feedwater System (EFW). At the time of the event, Unit 2 was in Mode 1 at approximately 17% power and increasing with preparations in progress for placing the main turbine on line during a unit startup. The (EFW) actuation was due to a low level on the 2B steam generator, which resulted from failure of 2B Main Feedwater Block Valve 2FDW-40 to automatically open upon demand. All systems operated as expected with no problems observed. Unit 2 is currently stable at approximately 16% power while troubleshooting valve 2FDW-40 (and the 2B Steam Generator level stable at the normal operating level). Units 1 and 3 were unaffected and remain on line and stable at 100% power. Public health and safety were not impacted by this event. This event is being reported as an 8 hour non-emergency in accordance with 10 CPR 50.72(b)(3)(iv) for a valid actuation of the Emergency Feedwater System. The NRC Resident Inspector has been notified. Corrective Action: Troubleshooting of valve 2FDW-40 is on-going.
ENS 5118427 June 2015 06:40:00Arkansas NuclearNRC Region 4CE
B&W-L-LP

This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) as an event that will result 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.) The emergency preparedness plan requires seismic monitoring instruments to diagnose an earthquake for emergency action levels (EAL) HU6 (Natural or destructive phenomena affecting Protected Area) and HA6 (Natural and destructive phenomena affecting Vital Areas). At 2149 CST on June 26, 2015, (the) ACS-8003 seismic monitor was declared non-functional due to having a fault light indicated on the C529 seismic cabinet. (The) ACS-8001 seismic monitor had previously been declared non-functional due to the same condition. With these 2 monitors out of service the seismic alarm capability is not available. ANO procedures provide compensatory measures of using offsite sources to obtain seismic data. The NRC Resident Inspector has been notified.

  • * * UPDATE ON 6/28/15 AT 1552 EDT FROM KENYON MCNEAILL TO DONG PARK * * *

On 6/28/15 at 1232 CDT, batteries have been replaced in ACS-8001 and ACS-8003 seismic monitors. Both monitors have been restored to a fully functional status. Seismic alarm capability is restored and Emergency Assessment Capability has been restored. The licensee will notify the NRC Resident Inspector. Notified R4DO (Campbell).

ENS 510291 May 2015 16:14:00Arkansas NuclearNRC Region 4CE
B&W-L-LP
This notification is conservatively being made in accordance with 10 CFR 50.72(b)(3)(xiii) as an event that will result 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.) The emergency preparedness plan requires seismic monitoring instruments to diagnose an earthquake for emergency action levels (EAL) HU6 (Natural or destructive phenomena affecting PROTECTED AREA) and HA6 (Natural and destructive phenomena affecting VITAL AREAS). At approximately 1600 (CDT) on May 1, 2015, ANO plans to remove Motor Control Center B33 from service for maintenance. This will render the alarm functions for the seismic monitors nonfunctional. It is expected that this maintenance will take approximately 72 hours to complete. ANO procedures provide compensatory measures of using offsite sources to obtain seismic data. The NRC Resident Inspector has been notified.
ENS 5102630 April 2015 19:38:00OconeeNRC Region 2B&W-L-LPUnusual Event (4.6.U.1) was declared by the Shift Manager at Oconee Nuclear Station at 1840 EDT on 4/30/15 due to scorched 4160V cable and a hole created in metal connector coming into the top of 1C condensate booster pump motor electrical junction box. Unit 1 experienced a decrease in power to approximately 98.6% power due to the perturbation in condensate flow from the loss of 1C condensate booster pump. Unit 1 is currently stable at 98.6%. 1A condensate booster pump auto-started as expected. Smoke was observed and quickly dissipated. No visible fire or flame was observed. No Fire Brigade response required. The Unusual Event was terminated at 1945 EDT on 4/30/15. The licensee informed state/local agencies and the NRC Resident Inspector and does not plan to issue a press release. Notified other Federal Agencies (DHS SWO, FEMA Ops, FEMA NWC, NICC Watch Officer and NuclearSSA).
ENS 5093227 March 2015 16:57:00Three Mile IslandNRC Region 1B&W-L-LP

Three Mile Island Station has completed a review of seismic monitor performance. The seismic monitor is currently operable however, this review identified 1 time in the past 3 years that the seismic monitor was inoperable such that emergency classification at the ALERT level could not be obtained with site instrumentation. The seismic monitor was determined to be inoperable on the following date:

1) August 7, 2012

This unplanned inoperable condition of the seismic monitor was entered into the Three Mile Island Corrective Action Program when it occurred. While Exelon procedural direction allowed the use of offsite sources to obtain seismic data when the seismic monitor is incapable of assessing emergency plan Emergency Action Levels (EALs), this was not explicitly referenced in the approved EALs. The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery. The licensee has notified the NRC Resident Inspector.

ENS 506544 December 2014 14:42:00Three Mile IslandNRC Region 1B&W-L-LPAt 1150 (EST), the Shift Manager was notified that TMI (Three Mile Island) emergency plan siren 128 was inadvertently sounding. This siren is no longer alarming. Repairs to the siren have been completed. This notification is being made under 10 CFR 50.72(b)(2)(xi), 'News release or notification of other government agency'. The licensee has notified the NRC Resident Inspector. The licensee notified applicable state and local authorities.
ENS 5064125 November 2014 17:07:00Arkansas NuclearNRC Region 4B&W-L-LP

On Tuesday November 25, 2014, at 1211 CST, Arkansas Nuclear One, Unit 1 (ANO-1) reviewed AREVA 10 CFR 50.46 Notification Letter FAB14-00632. This letter indicates that a deficiency was discovered in the uranium thermal conductivity models used in the ANO-1 Loss of Coolant Accident (LOCA) analysis of record. When the deficiency is corrected, the LOCA Peak Cladding Temperature (PCT) limits may be in excess of 2200 degrees Fahrenheit (F). 10 CFR 50.46 paragraph (b) defines the acceptance criteria for the LOCA analysis process. The ANO-1 licensing basis PCT is evaluated for compliance with the criterion 10 CFR 50.46(b)(1) and must not exceed a PCT of 2200 degrees F.

During AREVA's review of the issue, AREVA had provided compensatory measures in the form of reductions in LOCA linear heat rates as a contingency in case the errors were found to be substantiated, which were then translated into reduced axial imbalance limits so that ANO-1 would operate within 10 CFR 50.46 limits. As a precautionary measure pending the completed analysis, ANO-1 implemented the compensatory measures on October 20, 2014, and as a result, the errors reported have no impact on current plant operation or public health and safety. This event is being conservatively reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). Based on 50.46(a)(3)(ii) criteria, ANO-1 will submit a written report within 30 days. ANO-1 has notified the NRC Senior Resident Inspector.

ENS 5064025 November 2014 16:35:00OconeeNRC Region 2B&W-L-LPOn Tuesday, November 25, 2014, at 1212 EST, Duke Energy Carolinas, LLC (Duke Energy) reviewed AREVA 10CFR50.46 Notification Letter FAB 14-00631. This letter indicates that a deficiency was discovered in the uranium thermal conductivity models used in the Oconee Nuclear Station Loss of Coolant Accident (LOCA) analysis of record. When the deficiency is corrected, the LOCA Peak Cladding Temperature (PCT) limits may be in excess of 2200 degrees F. 10CFR50.46 paragraph (b) defines the acceptance criteria for the LOCA analysis process. The Oconee licensing basis PCT is evaluated for compliance with the criterion 10CFR50.46(b)(1) and must not exceed a PCT of 2200 degrees F. On October 20, 2014, AREVA recommended actions in the form of reductions in LOCA linear heat rates, which were then translated into reduced axial imbalance limits for the excore and backup incore detector systems. This was done to ensure that Duke Energy operated within 10CFR50.46 limits in the event of a loss of the full incore detector system. The full incore detector system is the primary method for evaluating imbalance and the imbalance limits are unaffected by the reduction in LOCA linear heat rates. The full incore detector system is operable and meets Technical Specification 3.2.2. In addition, the Reactor Protection System (RPS) trip limits for imbalance are not derived from the LOCA analysis and are not affected. When AREVA notified Duke Energy of the deficiency, Duke Energy confirmed that existing administrative limits bound the AREVA recommended actions and as a result, the errors reported have no impact on plant operation or public health and safety. This event affects all three (3) units and is being reported in accordance with 10CFR50.72(b)(3)(ii)(B). Based on 10CFR50.46(a)(3)(ii) criteria, Duke Energy will submit a written report within 30 days. Duke Energy has notified the NRC Senior Resident Inspector.
ENS 5045412 September 2014 20:42:00Arkansas NuclearNRC Region 4B&W-L-LPArkansas Nuclear One (ANO) identified the potential for stored fuel that does not meet the fuel specifications or loading conditions of the Certificate of Compliance (CoC) for the HI-STORM 100 Cask System. Investigation into the cause of a Control Room Emergency Ventilation System (CREVS) actuation on the morning of 9/12/2014 led to sampling of helium circulating through the Multi-Purpose Canister (MPC-24-060) as part of the Forced Helium Dehydration process in the final stages of cask loading. Sample results indicated the presence of Kr-85. Kr-85 is a fission product that indicates the potential for the fuel that does meet the selection criteria for the HI-STORM 100 Cask System. All fuel assemblies loaded into MPC-24-060 were checked to confirm their intact status (a cask Certificate of Conformance requirement) as part of the selection process. Each assembly's status as intact is based on in-mast sipping and/or ultrasonic testing performed subsequent to their final operating cycle. Results of these sipping and ultrasonic test campaigns are maintained in a comprehensive engineering report used to verify assembly status during cask fuel selection. Per the CoC for the Hi-STORM 100 Cask System, Appendix B, Section 1.0, the definition of 'INTACT FUEL ASSEMBLY' is a fuel assembly without known or suspected cladding defects greater than pinhole leaks or hairline cracks, and which can be handled by normal means. Given the presence of Kr-85 along with the fuels history, it cannot be confirmed that all fuel assemblies meet the definition of 'Intact' and would not meet the CoC Requirements for Fuel to be stored in the HI-STORM 100 SFSC System (Section 2.1.1). The NRC Resident Inspector has been notified.
ENS 5028820 July 2014 21:12:00OconeeNRC Region 2B&W-L-LPOn 7/20/2014, at 1700 hours EDT, a spill of approximately five (5) gallons of Teresstic 68 lube oil was identified in the Keowee Hydroelectric Station (KHS) tailrace. Teresstic 68 oil is used at the station as an equipment lubricant. The KHS tailrace feeds into the Keowee River that leads into Lake Hartwell. The estimated area of the oil sheen is approximately 30x50 feet and a cleanup response is currently in progress. The cause of the spill was attributed to a faulty oil float switch in the KHS unwatering pump that allowed the oil to spill into the KHS tailrace (Keowee River). South Carolina Department of Health and Environmental Control (SCDHEC) and the National Response Center were notified of the spill on 7/20/2014 at approximately 2002 and 1953 hours (EDT) respectively. This event was determined to be reportable pursuant to 10CFR50.72(b)(2)(xi) due to the notifications to the SCDHEC and the National Response Center. The licensee notified the NRC Resident Inspector. Initial Safety Significance: The oil did not contain any plant produced radiological material and while contained, poses no safety risk with respect to the health and safety of the public. Corrective Action(s): The oil spill sheen is isolated to an approximate 30x50 foot area of the Keowee River. Because the KHS is currently not operating, the water spill area is stagnant, i.e., there is little or no movement of the water containing the oil sheen. The source of the leak has been contained and an investigation is underway to determine the actual cause of the spill. There was no impact on plant operations. The event was entered into the station's corrective action program.
ENS 5026910 July 2014 16:41:00Crystal RiverNRC Region 1B&W-L-LPA non-licensed employee supervisor has been found in violation of the Duke Energy Fitness for Duty Policy. The individual's access to the plant has been suspended. The licensee has notified the NRC Region 1 (Hammann).
ENS 5010812 May 2014 14:48:00Three Mile IslandNRC Region 1B&W-L-LPDuring a review from industry operating experience it was identified that there are three additional unprotected DC control circuits for non safety related DC motors which are routed from the turbine building to other separate fire areas (this is in addition to the one circuit that was previously identified and submitted under event #50059). Fuses used to protect the motor power conductors appear to be inadequate to protect the control conductors. The concern is that under fire safe shutdown conditions, it is postulated that a fire in one area can cause short circuits potentially resulting in secondary fires or cable fires in other areas where the cables are routed. The secondary fires or cable failures are outside the assumptions of the 10 CFR 50 Appendix R Safe Shutdown Analysis. This condition is reportable as an 8 hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant. The NRC Resident Inspector has been notified.
ENS 500937 May 2014 15:19:00OconeeNRC Region 2B&W-L-LPA leak containing a low level tritium concentration assumed to be greater than 100 gallons of water, with the potential to reach groundwater, occurred at Oconee Nuclear Station. A water sample indicated that the tritium level was 3150 picocuries per liter; which is less than a quarter of the US Environmental Protection Agency drinking water standard of 20,000 picocuries per liter for tritium. While conducting a transfer from one chemical treatment pond to another, water was observed seeping from the ground at a location near the transfer piping between the ponds. The transfer was terminated and the ground seepage subsided. Actions have been taken to prevent further use of the chemical treatment pond discharge path at this time. Based upon the on-site location and low tritium levels, there is no health or safety impact to the public or employees. Voluntary notification of state and local agencies is being made via the industry groundwater protection initiative; measured tritium levels were below any required notification threshold. Agencies notified: South Carolina Department of Health and Environmental Control, South Carolina Emergency Management, City of Seneca, City of Anderson, Greenville Water System, Oconee County Administration, Pickens County Administration, Anderson County Administration, Oconee County Emergency Management, Pickens County Emergency Management, Greenville County Emergency Management, and Clemson University Utility Services. The licensee notified the NRC Resident Inspector.
ENS 5005925 April 2014 16:29:00Three Mile IslandNRC Region 1B&W-L-LPA review of industry Operating Experience identified that there were unprotected DC control circuits for non safety-related DC motors which are routed from the turbine building to other separate fire areas. Fuses used to protect the motor power conductors appear to be inadequate to protect the control conductors. The concern is that under fire safe shutdown conditions, it is postulated that a fire in one area can cause short circuits potentially resulting in secondary fires or cable failures in other fire areas where the cables are routed. The secondary fires or cable failures are outside the assumptions of the 10 CFR 50 Appendix R Safe Shutdown Analysis. This condition is reportable as an 8-hour ENS report in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition. Compensatory measures (fire watches) have been implemented for affected areas of the plant. The NRC Resident Inspector has been notified.
ENS 4996828 March 2014 16:21:00OconeeNRC Region 2B&W-L-LPEvent: In an NRC Component Design Basis Inspection (CDBI) debrief held at 1300 EDT on March 28, 2014, it was stated that a potential non-compliance and unanalyzed condition exists with respect to the design and installation of the Keowee emergency power system 13.8kV power cables associated with the underground power path. The NRC stated that Duke does not have sufficient documentation to support the station's position that the cables comply with the station's licensing basis. In particular, there are questions related to the station's compliance with IEEE-279-1971. This issue has been documented in Duke's corrective action program. Duke has reviewed the design associated with the subject 13.8kV cables and considers the design to be robust. Pending further analysis and/or testing, Duke has made a decision to report this event in accordance with 10 CFR 50.72(b)(3)(ii) as an 'Unanalyzed Condition.' The Oconee NRC Senior Resident Inspector has been notified of the event. Initial Safety Significance: An Immediate Determination of Operability has been performed and concluded the existing system design is adequately robust to address circuit faults. The health and safety of the public and station personnel is not impacted by this event. Corrective Action(s): Corrective actions are being implemented in accordance with Duke's Corrective Action Program.
ENS 495127 November 2013 13:02:00Three Mile IslandNRC Region 1B&W-L-LPOn Thursday, November 7, 2013, while performing planned inspections on a 2 inch reactor coolant system drain line, TMI technicians identified an indication of a flaw on the weld internal diameter of an elbow to pipe weld on the line. This flaw is determined to not meet acceptable criteria and a repair is being developed. This condition is reportable under 10CFR50.72(b)(3)(ii). No actual impact occurred during plant operations. The NRC Senior Resident Inspector has been notified.
ENS 495117 November 2013 11:41:00OconeeNRC Region 2B&W-L-LPTechnical Support Center (TSC) out of service due to planned maintenance. This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility. Planned maintenance activities during the Unit 2 outage on 11/7/2013 will render TSC out of service for approximately 48 hours. The unit 2 work is on electrical equipment that will impact the power supply to the TSC. If an emergency is declared requiring TSC activation during this period, the alternate TSC will be used per existing emergency planning procedures. The NRC Resident Inspector has been notified. This event poses no threat to the public or station employees.
ENS 4947124 October 2013 09:45:00OconeeNRC Region 2B&W-L-LP

At 0553 EDT on 10/24/2013, Oconee Unit 3 was manually tripped due to oscillations in the feedwater system in anticipation of an automatic reactor trip. At 0549 EDT, Unit 3 began experiencing small feedwater oscillations. The feedwater control system was placed in manual in an attempt to stabilize feedwater flows. Feedwater oscillations continued to grow in magnitude and at 0553 EDT, a manual trip was directed to prevent an automatic reactor trip. Due to an RPS actuation, this event is being reported as a 4 and 8 hour Non-Emergency per 10 CFR 50.72 (b)(2)(iv)(B) and 10 CFR 50.72 (b)(3) Following the reactor trip, four main steam relief valves failed to reseat. Procedure guidance was utilized to reduce main steam system pressure by approximately 30 psig to reseat the main steam relief valves. All main stream relief valves are now reseated. All other post trip conditions were normal and all other systems performed as expected. Unit 3 is currently in Mode 3 and stable. Operations have been stabilized on Unit 3. A post-trip investigation is in progress, per site procedures and directives. The licensee has notified the NRC Resident Inspector.

  • * * UPDATE FROM BOB MEIXELL TO DONALD NORWOOD AT 1439 ON 9/10/14 * * *

Duke Energy reviewed NRC Event Number 49471 against NUREG 1022, Rev 3, section 3.2.6, "System Actuation" and determined this event should have been reported only per 10 CFR 50.72 (b)(2)(iv)(B), RPS Actuation (while critical). Thus, Duke Energy is revising NRC Event Number 49471 to remove the 8-hour report criteria 10 CFR 50.72 (b)(2)(iv)(A). The NRC Resident Inspector was notified of this revised report. This update has no effect on safety significance. Notified R2DO (Shaeffer).

ENS 4929120 August 2013 11:49:00OconeeNRC Region 2B&W-L-LPA non-licensed contract supervisor had a confirmed positive fitness for duty test. Plant access for the individual has been terminated. The licensee has notified the NRC Resident Inspector.
ENS 4914926 June 2013 18:33:00OconeeNRC Region 2B&W-L-LPAt 1040 (EDT), on June 26, 2013, with the Unit 1B Low Pressure Injection (LPI) and Reactor Building Spray (RBS) trains inoperable for planned maintenance, a motor operated isolation valve (1LP-21) was inadvertently closed, rendering the 1A LPI and RBS trains inoperable. The intended action was to close 1LP-22 in the Unit 1B train. 1LP-21 was closed due to a human error. Unit 1 entered Tech Spec 3.0.3 for both trains of LPI and RBS being inoperable. At 1053, on June 26, 2013, the Unit 1A train of LPI and RBS were restored to operable by opening 1LP-21, and Tech Spec 3.0.3 was exited. Units 1, 2 and 3 were stable at 100% power during and after this event. No other safety or non-safety systems were degraded or lost as a result of this event. The event was determined to be reportable under 10 CFR 50.72(b)(3)(v) A, B, C and D "Event or Condition that Could Have Prevented Fulfillment of a Safety Function. Initial Safety Significance: None. There was no event on-going at the time of discovery that required the Unit 1 LPI and RBS systems to function, and the safety function was restored when the 1A LPI and RBS trains were restored to operability. Although declared inoperable, the Unit 1B LPI and RBS trains were available during the time 1LP-21 was closed. Corrective Actions: The Unit 1A LPI and RBS trains were restored to operable, an event investigation was commenced and the event was entered into the Oconee Corrective Action Program. The licensee notified the NRC Resident Inspector.
ENS 490862 June 2013 04:38:00Crystal RiverNRC Region 2B&W-L-LPOn June 1, 2013 at 2129 (EDT), a valid actuation of the 'B' Emergency Diesel Generator occurred when power was lost to the 'B' 4160V engineered safeguards bus due to failure of the 'B' Unit 6900 V bus feeder breaker 3104. There were no interruptions of spent fuel pool cooling during this event. This event is reportable as an 8-hour notification per 10 CFR 50.72(b)(3)(iv)(B)(8). This condition has no adverse affect on the public's or employees' health and safety. NRC Region II has been notified.
ENS 4906824 May 2013 14:47:00OconeeNRC Region 2B&W-L-LPThere is no current event in progress at Oconee Nuclear Station (ONS). This notification is (being made) to complete a required 10 CFR 50.72 report that was not made at the time of discovery. During a review of the guidance in NUREG 1022, Rev. 2, ONS recognized conditions that were reported to the NRC in LER 269/2013-001-00 on April 8, 2013, (ADAMS Accession ML13101A307), which met the 8-hour reporting requirements of 10 CFR 50.72(b)(3)(ii)(B) -- 'Unanalyzed Condition,' and 10 CFR 50.72(b)(3)(v)(A,B,C&D) -- 'Event or Condition That Could Have Prevented Fulfillment of a Safety Function,' but were not previously reported per 10 CFR 50.72(b)(3). LER 269/2013-001-00 previously documented Duke Energy's conclusion that emergency power equipment could be adversely impacted by a licensee identified, original design issue involving inadequate analysis of electrical equipment heat loads and weaknesses in the Heating Ventilation and Air Conditioning (HVAC) system design. Nothing in this notification modifies or supplements the information provided in LER 269/2013-001-00. This legacy event notification completes the action required by 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(A,B,C&D). The need to perform a 10 CFR 50.72 notification was not recognized during the reportability evaluation. Initial Safety Significance: None. This is a legacy event notification. Oconee's emergency power equipment is currently operable, but nonconforming with Oconee's license. Corrective Action(s): Compensatory measures are in place, and modifications are in progress to address the legacy design issue. The issue of not reporting as required under 10 CFR 50.72(b)(3) is entered into Duke Energy's corrective action program. The Oconee NRC Resident Inspector has been notified.
ENS 4895522 April 2013 23:23:00Arkansas NuclearNRC Region 4CE
B&W-L-LP

On 4-22-13, at 1623 (CDT), the ANO Unit 2 control room was notified of a loss of ventilation capability to the Emergency Operations Facility (EOF). The main control boards associated with the variable speed drives on both air handling units at the EOF have failed. Therefore, there are no means to filter air for the EOF. If the EOF is staffed, the EOF will be required to relocate to the Alternate EOF in the event of a release that causes the EOF evacuation criteria to be exceeded, as directed by approved emergency response procedures. The on-site Operations Support Center, on-site Technical Support Center and off-site Alternate EOF remain fully functional to perform emergency assessment activities. Efforts are underway to expedite repairs. This notification is required by 10CFR50.72(b)(3)(xiii). The licensee has notified the NRC Resident Inspector.

  • * * UPDATE ON 4/24/13 AT 1003 EDT FROM STEVE COFFMAN TO DONG PARK * * *

At 1637 EDT on 4/23/13, the EOF ventilation has been restored and the EOF has full functionality. The licensee has notified the NRC Resident Inspector. Notified R4DO (Whitten).

ENS 4885527 March 2013 09:14:00Three Mile IslandNRC Region 1B&W-L-LP

This is a non-emergency eight hour notification for a loss of emergency assessment capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of a emergency response facility. Planned maintenance activities are being performed today (March 27, 2013) to the Technical Support Center (TSC) HVAC. The work includes both corrective and preventive maintenance to the TSC HVAC system. This work activity is planned to be performed and completed expeditiously within about 14 hours. If an emergency condition occurs that requires activation of the TSC, plans are to utilize the TSC concurrent with this work activity as long as habitability conditions allow. Additionally, plans are in place to expedite the return of the system should an emergency condition occur. The emergency response organization duty team members will be relocated to an alternate location if required by habitability conditions in accordance with emergency implementing procedures. The licensee notified the NRC Resident Inspector.

  • * * UPDATE FROM DAVE LEWIS TO HOWIE CROUCH AT 1511 EDT ON 3/27/13 * * *

The Technical Support Center has been returned to service. The licensee has notified the NRC Resident Inspector. Notified R1DO (Krohn).

ENS 4878927 February 2013 14:47:00OconeeNRC Region 2B&W-L-LPOn 2/26/13 at 2030 hrs (EST), a four (4) inch sewage line in the Oconee Nuclear Station turbine building failed. This failure allowed sanitary wastewater to spill into the turbine building basement. An estimated 750 gallons entered into trench drains and traveled to the station sump which discharges into the conventional wastewater system. This conventional wastewater system is discharged to the Keowee River from NPDES (National Pollutant Discharge Elimination System) outfall 002. The discharge of outfall 002 is into the Keowee River below the Keowee Hydro Station. The normal discharge path for sanitary wastewater is to the City of Seneca, South Carolina (SC). South Carolina Department of Health and Environmental Control (SCDHEC) and the Oconee Joint Regional Sewer Authority (OJRSA) were notified of the spill on 2/27/13 at approximately 1358 hrs (EST). Note: SCDHEC requires the reporting of any overflow that reaches waters of the state, for overflows that exceed an estimated 500 gallons that don't reach water, and for any overflow that may cause a public health or environment concern. This event was determined to be reportable pursuant to 10CFR50.72(b)(2)(xi) due to notification of the SCDHEC and OJRSA. Initial Safety Significance: The sewage leak did not contain any plant produced radiological material and due to dilution, this event posed no safety risk with respect with respect to the health and safety of the public. Corrective Actions: The affected portions of the sanitary sewage system has been isolated and an investigation is underway to determine the cause. There was no impact on plant operations, and the cleanup has been completed. The event was entered into the correction action program. The licensee notified the NRC Resident Inspector.
ENS 4877019 February 2013 17:45:00OconeeNRC Region 2B&W-L-LP

Event: At 1400 EST on 2/19/2013, Oconee Nuclear Station (ONS) Emergency Preparedness (EP) was notified that the 65 Oconee Alert and Notification System sirens (65 is the total number of sirens within the ONS 10 mile Emergency Planning Zone) were found to be non-functional at 1054 EST during weekly testing on 2/19/2013. Oconee and Pickens County Emergency Management have been notified and will conduct 'Route Alerting' should ONS experience an emergency event that would normally require siren activation for notifying the public. Route Alerting, a method of backup alerting, is an approved FEMA process and is documented in the Emergency-Plan of both counties. Initial Safety Significance: None. A pre-planned alternate process for notifying the public was put in place immediately and will remain in place until siren repair and testing are completed. Corrective Action(s): An investigation is in progress to determine the cause of the siren system failure. Appropriate repairs will be made and testing conducted once the cause is determined. ONS will notify the NRC when the sirens are returned to service. The ONS NRC Resident Inspector has been notified of this issue." The licensee has also notified state authorities and the appropriate county authorities as indicated in the event description.

  • * * UPDATE AT 1522 EST ON 2/20/12 FROM MEIXELL TO HUFFMAN * * *

The ONS Siren control systems were recovered and the ONS Alert and Notification System was retested and fully returned to service as of 1040 EST on 2/20/2013. Oconee and Pickens County Emergency Management Division (EMD), South Carolina EMD, and the ONS NRC Senior Resident Inspector were notified of the return of the systems to service. The systems were restored after correcting issues associated with the computer system for the sirens. An investigation is in progress to determine the cause of the event. R2DO (McCoy) notified.

ENS 487165 February 2013 10:57:00Crystal RiverNRC Region 2B&W-L-LPAt 0800 Eastern Standard Time (EST) on 02/05/2013, Progress Energy Florida, Inc., a subsidiary of Duke Energy, announced its plan to permanently shutdown and decommission the Crystal River Unit 3 (CR3) Nuclear Plant. A media release was issued at 0800 EST on 02/05/2013. CR3 Security personnel are stationed at the Emergency Operations Facility/Training Facility located outside the Owner Controlled Area to monitor potential media coverage and public assembly. At this time, Security reports no security issues. No other media releases are planned at this time. This event is being reported under 10 CFR 50.72(b)(2)(xi) for offsite notifications based on the media release of the planned shutdown and decommissioning of CR3. The NRC Resident Inspector has been notified.
ENS 487145 February 2013 08:19:00Three Mile IslandNRC Region 1B&W-L-LP

This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility. Planned maintenance activities are being performed today (February 5, 2013) to the Technical Support Center (TSC) HVAC. The work entails performance of DOP (dioctyplthalate oil smoke test) and Halide testing. This work activity is planned to be performed and completed expeditiously within about 12 hours including establishing and removing the clearance and performing post maintenance testing. If an emergency condition occurs that requires activation of the TSC, plans are to utilize the TSC concurrent with this work activity as long as habitability conditions allow. Additionally, plans are in place to expedite the return of the system should an emergency condition occur. The Emergency Response Organization duty team members will be relocated to alternate location if required by habitability conditions in accordance with emergency implementing procedures. The licensee notified the NRC Resident Inspector.

  • * * UPDATE AT 1433 EST ON 2/5/2013 FROM JASON HARNER TO MARK ABRAMOVITZ * * *

TSC ventilation has been returned to service. Notified the R1DO (Powell) via e-mail.

ENS 4862526 December 2012 04:13:00Three Mile IslandNRC Region 1B&W-L-LPThis is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility. Planned maintenance activities are being performed today (December 26, 2012) to the Technical Support Center (TSC) HVAC. The work entails removing power to the system fan and dampers to perform required preventative maintenance (PM) rendering the TSC HVAC non-functional during the performance of this work activity. This work activity is planned to be performed and completed expeditiously within about 16 hours including establishing and removing the clearance and performing post maintenance testing. If an emergency condition occurs that requires activation of the TSC, plans are to utilize the TSC concurrent with this work activity as long as habitability conditions allow. Additionally, plans are in place to expedite the return of the system should an emergency condition occur. The Emergency Response Organization duty team members will be relocated to alternate locations if required by habitability conditions in accordance with emergency implementing procedures. The licensee notified the NRC Resident Inspector.