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The query [[Category:ENS Notification]] [[Reactor type::Westinghouse PWR 3-Loop]] was answered by the SMWSQLStore3 in 0.0742 seconds.


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 Entered dateSiteRegionReactor typeEvent description
ENS 533938 May 2018 10:38:00FarleyNRC Region 2Westinghouse PWR 3-LoopOn May 8, 2018 at 0139 Central Daylight Time, Farley Nuclear Plant Unit 1 declared containment inoperable due to total containment leak rate greater than technical specifications. The 1B containment cooler had seat leakage of approximately 30 gallons per minute from a service water drain valve. Though the containment cooler service water supply is not tested per the Appendix J program, a loss of the containment barrier is possible under accident conditions. The service water flow path to the 1B containment cooler has been isolated to exit the condition. The licensee will notify the NRC resident inspector.
ENS 533928 May 2018 01:39:00FarleyNRC Region 2Westinghouse PWR 3-LoopOn May 7, 2018 at 1041 CDT, Unit 1 performed an RCS (reactor coolant system) leakrate procedure that calculated an unidentified RCS leakrate of 0.202 gpm. The leak source investigation concluded at 2150 that the packing for the charging flow control valve (FCV) was the source of the RCS leakage when it was bypassed, which isolated the leakage. A second RCS leakrate calculation was performed after the charging flow control valve was isolated which calculated an acceptable leakrate of 0.00 gpm. The packing leakage from the charging flow control valve represented leakage external to containment which would result in a greater that 5 Rem dose projection to control room personnel during accident conditions which does not satisfy the GDC19 criteria described in Technical Specification Bases 3.7.10. Therefore the control room emergency filtration system would not be able to fulfill its design function resulting in an unanalyzed condition. This condition is being reported pursuant to 10CFR50.72(b)(3)(ii) for a 'condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety'. The packing leak from the charging flow control valve will remain isolated until repaired under work order SNC944374. The NRC Resident Inspector has been notified.
ENS 5336626 April 2018 20:23:00HarrisNRC Region 2Westinghouse PWR 3-LoopThis 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 planned maintenance activities were performed on April 23rd through April 25th on the seismic monitoring system without viable compensatory measures established. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5332611 April 2018 20:56:00HarrisNRC Region 2Westinghouse PWR 3-LoopOn April 11, 2018, while the Harris Nuclear Plant was shut down for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with the lnservice Inspection Program. Ultrasonic examinations identified a flaw in the head penetration nozzle number 33. The unit is in a safe and stable condition. The flaw will be repaired prior to startup from the refueling outage. The flaw and repair have no impact on the health and safety of the public or station employees. The NRC Resident Inspector has been notified.
ENS 533187 April 2018 11:59:00HarrisNRC Region 2Westinghouse PWR 3-LoopOn April 7, 2018 at 0451 EDT, with Unit 1 in Mode 3 at 0 percent power, an auto actuation of 'A' and 'B' Motor Driven Auxiliary Feedwater (MDAFW) pumps occurred during the shutdown of Unit 1 for Harris Nuclear Plant's refueling outage. Plant Operators successfully took control of the AFW flow and noted the 'B' Main Feed pump was still running with proper suction and discharge pressures of 430 lbs. and 1000 lbs. The 'A' and 'B' Motor Driven Auxiliary Feedwater (MDAFW) pumps automatically started as designed when the 'Loss of Both Main Feedwater Pumps' signal was received. The cause of the actuation is still being evaluated. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feedwater system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
ENS 5329026 March 2018 18:19:00FarleyNRC Region 2Westinghouse PWR 3-Loop

On March 25, 2018 at 1833 CDT, while at 100 percent power, Farley Unit 1 (FNP-1) conservatively declared a single Main Steam Isolation Valve (MSIV) inoperable on the 1C Steam Generator line due to indication of Steam Generator pressure rise with a corresponding reduction in flow of that loop. FNP-1 began a reactor shutdown at 0400 CDT on March 26, 2018 to establish plant conditions to support testing the affected main steam line MSIVs while in the required action time of Technical Specification 3.7.2. At 1338 CDT on March 26, 2018, testing confirmed that the single MSIV was inoperable and that valve disassembly will be required. The duration of the valve repair would exceed the required action time of Technical Specification 3.7.2. This report is being made in accordance with 10 CFR 50.72(b)(2)(i), as a plant shutdown required by technical specifications. The licensee has notified the NRC Resident Inspector.

  • * * UPDATE FROM DOUGLAS HOBSON TO KEN MOTT AT 0202 EDT ON 5/16/18 * * *

This EN (event notification) is being updated to clarify the reporting criteria as 'Voluntary'. Farley Technical Specification 3.7.2 allows continuous operation in MODE 2 with an INOPERABLE MSIV as long as the other MSIV in the affected Main Steam Line is closed. The initiation of the shutdown was performed as a prudent action to repair and restore OPERABILITY of the affected MSIV and was not a requirement of the Farley Technical Specifications. The licensee notified the NRC Resident Inspector. The R2DO (Masters) was notified.

ENS 5326818 March 2018 12:34:00North AnnaNRC Region 2Westinghouse PWR 3-LoopAt 2007 (EDT) on 3/17/18, a security Officer reported finding a container of herbal tea (Kombucha) on a platform in the Unit 1 Emergency Switchgear Room, which is located inside the Protected Area. Kombucha tea is a fermented tea containing trace amounts of alcohol, and is legally sold without restrictions. Dominion had previously notified its workforce that Kombucha tea was prohibited from being consumed or carried on-site. This is considered an alcoholic beverage and is being reported under the requirements of 10 CFR 26.719. The individual who brought the beverage on-site was identified and escorted out of the Protected Area. The NRC Resident Inspector has been notified. The licensee will also be contacting the County Administrator for Louisa County, Virginia.
ENS 5322823 February 2018 20:29:00Beaver ValleyNRC Region 1Westinghouse PWR 3-LoopAt 1750 (EST) on 2/23/2018 credible information was obtained that a non-licensed supervisory person had intentionally misused a controlled substance. Unescorted access has been withdrawn. Per 10 CFR 26.719(b)(2)(i) this is a 24 hour reportable event. The NRC Resident Inspector has been notified.
ENS 5321014 February 2018 18:04:00SurryNRC Region 2Westinghouse PWR 3-LoopA non-licensed contract supervisor had a confirmed positive for alcohol during a follow-up fitness-for-duty test. The employee's access to the plant has been terminated. The licensee notified the NRC Resident Inspector.
ENS 5317618 January 2018 17:03:00SummerNRC Region 2Westinghouse PWR 3-Loop

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 Diesel Generator.

On January 18, 2018 at 1202 EST, V.C. Summer Nuclear Station (VCSNS) lost one of its two redundant offsite power supplies. The loss of the 115kV power supply created an undervoltage condition on the normal incoming Engineered Safety Features power supply to safety related bus 1DA. The 'A' Emergency Diesel Generator started and loads sequenced as designed. The 'A' Residual Heat Removal pump started but did not inject any water into the Reactor Coolant System. The 'A' Emergency Feedwater Pump started and ran for approximately 2 minutes. Other plant equipment and systems also responded as expected.

The loss of the 115kV power supply occurred due to an issue with a component in a switchyard, external to VCSNS. The cause of the event is still under investigation.

All loads have been transferred back to the offsite 115kV power supply at 1318 EST. The diesel generator was secured at 1321 EST, reset and is ready to auto-start.

The NRC Resident Inspector has been notified.

ENS 5317017 January 2018 15:08:00SurryNRC Region 2Westinghouse PWR 3-LoopAt 0952 EST on 01/17/2018 with Unit 1 and Unit 2 operating at 100 percent, the normal supply breaker to the Unit 1J Emergency Bus tripped open due to an under-voltage condition when the potential transformer fuses were inadvertently disconnected. This resulted in a loss of power to the Unit 1J Emergency Bus from its normal off-site power supply. Number 3 Emergency Diesel Generator automatically started on an under-voltage signal and loaded onto the Unit 1J Emergency Bus, as designed. All equipment performed as expected during the event and there were no unexplained occurrences. Maintenance has verified the fuses have been reconnected and at 1221 EST, off-site power was restored to Unit 1J Emergency Bus. At 1254 EST Number 3 Emergency Diesel Generator was secured in accordance with Station Operating procedures. All Electrical distribution systems have been restored to a normal alignment. There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) due to the auto start of Number 3 Emergency Diesel Generator. The licensee notified the NRC Resident Inspector.
ENS 531599 January 2018 23:38:00FarleyNRC Region 2Westinghouse PWR 3-Loop

On January 9, 2018, at 1759 CST, during review of NFPA 805 requirements and circuit analysis, it was determined that the NFPA 805 analysis and Fire Safe Shutdown Modeling did not consider all fire-induced failures. As such, a condition could possibly exist during a postulated fire where both safety related electrical trains could be impacted. This notification is to report a condition involving the fire safe shutdown analysis. The condition could result in an adverse impact on the ability of operators to respond to a postulated fire in these areas. Therefore, this notification is being made pursuant to 10 CFR 50.72(b)(3)(ii)(B), any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. Compensatory fire watches have been established in the affected areas. The licensee notified the NRC Resident Inspector.

  • * * RETRACTION FROM ANTONIO BENFORD TO HOWIE CROUCH AT 1752 EST ON 2/28/18 * * *

Following additional refinements to the NFPA 805 Fire PRA Model, the circuits which initiated the initial report of an unanalyzed condition have now been evaluated and have proven that no significant degradation to plant safety existed. Therefore, EN 53159 is being retracted. The NRC Resident Inspector has been notified. Notified R2DO (Michel).

ENS 531077 December 2017 15:03:00SurryNRC Region 2Westinghouse PWR 3-LoopThis non-emergency notification is being made in accordance with 10 CFR 50.72(b)(2)(xi), any event or situation related to the protection of the environment for which notification to other government agencies has been made. Dominion Energy is in the process of informing the Virginia Department of Health, Department of Environmental Quality, Department of Emergency Management, and the Surry County Administrator of recent groundwater monitoring results at Surry Power Station in accordance with NEI 07-07, Industry Groundwater Protection Initiative (GPI). On December 6, 2017 at 1138 EST, Surry Power Station received analysis results of recent samples from the on-site groundwater monitoring program. As part of the program, 10 new groundwater monitoring wells were recently placed in service within the Protected Area to provide early detection, to better define the site's hydrology, and if necessary, to mitigate any potential leaks. The analysis results from one of the new wells indicated tritium activity level above the GPI communication threshold. Samples were re-analyzed, resulting in different values, with the highest result of 59,300 picoCuries per liter. Since each result was above the voluntary reporting threshold, Surry stakeholder communication was implemented in accordance with the NEI GPI Voluntary Communication Protocol, Criterion 2.2. There are no known active leaks at this location; however, Dominion Energy is continuing to investigate the source of the tritium and the reason for the variability in the sample results. Tritium was not detected in the on-site monitoring locations outside of the Protected Area. No tritium has been detected in the on-site and off-site drinking water wells. Since the activity is contained within the site restricted area, the health and safety of on-site personnel and members of the public are not affected. A 30-day report will be submitted to the NRC in accordance with NEI 07-07. The NRC Senior Resident Inspector has been notified.
ENS 5308121 November 2017 11:26:00RobinsonNRC Region 2Westinghouse PWR 3-LoopA non-licensed contract employee had a confirmed positive for illegal drugs during a random fitness-for-duty test. The licensee notified the NRC Resident Inspector.
ENS 530607 November 2017 22:32:00SummerNRC Region 2Westinghouse PWR 3-Loop

On 11/7/2017 at 1957 (EST), VC Summer Nuclear Station automatically tripped due to a turbine trip. The cause of the turbine trip is under investigation at this time. All systems responded as expected. All Control Rods fully inserted and all Emergency Feedwater pumps started as required. The plant is stable in Mode 3. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The unit is currently stable in Mode 3 with decay heat removal via the Main Steam to the Main Condenser. The NRC Resident Inspector has been notified. The licensee will notify the South Carolina State Emergency Management Division, the Fairfield, Richland, Lexington and Newberry Counties.

  • * * UPDATE FROM BETH DALICK TO VINCE KLCO ON 11/8/17 AT 1409 EST * * *

All systems responded as expected, with the exception of 'B' Steam Generator Feedwater Isolation Valve XVG1611 B-FW. This valve did not appear to automatically close and was slow to indicate closed from the Main Control Board. All Control Rods fully inserted and all Emergency Feedwater pumps started as required. The plant is stable in Mode 3. Notified the R2DO (Musser).

ENS 530587 November 2017 14:19:00Beaver ValleyNRC Region 1Westinghouse PWR 3-LoopIt was determined that a licensed employee was not placed in an additional Fitness-For-Duty (FFD) testing program as directed by the MRO (Medical Review Officer). Upon discovery, the individual was subsequently tested . . . and determined Fit-For-Duty per 10 CFR 26 requirements. This event is being reported pursuant to 10 CFR 26.719(b)(4). The NRC Resident Inspector has been notified.
ENS 530567 November 2017 08:29:00Beaver ValleyNRC Region 1Westinghouse PWR 3-LoopOn November 7, at 0504 (EST), BVPS (Beaver Valley Power Station) Unit 1 experienced an automatic reactor trip due to Main Unit Generator over current. The Auxiliary Feedwater system activated and remains in service. Offsite power supply is available. Normal and Emergency busses are being supplied by Offsite power. One Source Range channel failed to energize due to its corresponding Intermediate Range instrument being under compensated. It was manually energized and is not indicating as expected. The second Source Range instrument energized but is reading erratically. Both Source Range instruments have been declared inoperable and the appropriate Technical Specification has been complied with by making the Control Rods not capable of withdrawal and isolating all dilution flow paths. Plant trip response was as expected without complications, and all control rods fully inserted in the core. The plant is currently stable in Mode 3. This event is being reported as an actuation of the Reactor Protection system 10 CFR 50.72(b)(2)(iv)(B) and a Specified System Actuation (Auxiliary Feedwater System) 10 CFR 50.72(b)(3)(iv)(A). BVPS Unit 2 is unaffected by this event and remains at 100% power in Mode 1. The NRC Resident Inspector has been notified.
ENS 5302017 October 2017 13:22:00SummerNRC Region 2Westinghouse PWR 3-LoopAt approximately 0319 EDT on 10/14/17, site personnel discovered a sanitary lift station overflowing in the protected area. The overflow entered a nearby storm drain that discharges into Outfall 12. The estimated release volume was approximately 50 gallons. At 1134 EDT on 10/17/17 an initial notification was made to South Carolina Department of Health and Environmental Control. The cause of the overflow is still under investigation. Functionality of the lift pump has been restored and cleanup is complete. The NRC Resident Inspector has been notified.
ENS 5296211 September 2017 21:48:00SummerNRC Region 2Westinghouse PWR 3-LoopThis 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 Diesel Generator. On September 11, 2017 at 1648 (EDT) the 'A' Emergency Diesel Generator (EDG) started on the low voltage signal from Bus 1DA as a result of a 115KV grid perturbation. All emergency buses remained energized from offsite power. The EDG did not tie to the 1DA bus because the offsite power voltage recovered within the designed recovery time limit. The diesel generator has been secured, reset and is ready to auto start. The NRC Senior Resident Inspector has been notified.
ENS 5296010 September 2017 22:20:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopOn 09/10/17 at 1855 (EDT), (Turkey Point) Unit 4 reactor was manually tripped from 88% RTP (Rated Thermal Power) due to a failure of 4C Steam Generator main feed regulating valve causing lowering S/G (Steam Generator) level. All other systems operated normally. Auxiliary Feed Water initiated as designed to provide S/G water level control. EOP's (Emergency Operating Procedures) have been exited and General Operating procedures (GOP'S) were entered. Unit 4 is stable in Mode 3 at NOT/NOP (Normal Operating Temperature/Normal Operating Pressure). The licensee is investigating the failure of the feed regulating valve. Offsite power is available. Decay heat is being removed via main feedwater with steam discharged to atmosphere using the ADVs (Atmospheric Dump Valves). There is no known primary-secondary steam generator tube leakage. The licensee informed the NRC Resident Inspector.
ENS 529528 September 2017 00:06:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

At 2300 today, the National Weather Service issued a hurricane warning for the area including Turkey Point Nuclear Units 3 & 4. On that basis, a Notice of Unusual Event was declared at 2314 (EDT). In anticipation of severe weather, the site has completed proceduralized high wind preparations. Our plants have been specifically built to withstand natural disasters such as hurricanes, tornadoes, earthquakes, flooding and tidal surges. This approach will ensure the safety of operations and our employees and the communities surrounding our plants. Both units are currently stable at 100% power level. The NRC Resident Inspector has been informed. No safety systems are out of service. The electrical grid is stable but grid risk is high. Notified DHS, FEMA, NICC, and NSSA (e-mail).

  • * * UPDATE AT 0458 EDT ON 09/11/17 FROM TIM JONES TO JEFF HERRERA * * *

At 0400 (EDT) on 09/11/17, conditions at Turkey Point Nuclear have met established exit criteria to downgrade the Notice Of Unusual Event (NOUE). The previously reported EAL (Emergency Action Level) has been exited. The NRC Resident Inspector has been informed. Notified the R2DO (Michel) and R2OC (Miller), IRDMOC (Gott), NRREO (Miller), DHS, DOE, FEMA, HHS, USDA, EPA, FDA, DHS NICC, and NSSA (e-mail).

ENS 5293228 August 2017 10:55:00SummerNRC Region 2Westinghouse PWR 3-LoopOn 8/28/2017 at 0837 (EDT), VC Summer Nuclear Station automatically tripped due to a turbine trip. The turbine trip was caused by the Main Generator Differential Lockout due to a fault on the center phase lightning arrester on the Main Transformer (XTF-001). There were no complications with the trip. All control rods fully inserted. Balance of Plant (BOP) buses automatically transferred to their alternate power source XTF 31/32. All Emergency Feedwater pumps started as required. All systems responded as required. The plant is stable in Mode 3. Station personnel are investigating the cause of the fault on the main transformer lightning arrester. This event is reportable per 10 CFR 50. 72(b)(2)(iv)(B) and 10 CFR 50. 72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. The unit is currently stable in Mode 3 with decay heat removal via the Main Steam to the Main Condenser. The licensee will inform both State and local authorities.
ENS 528949 August 2017 17:35:00SurryNRC Region 2Westinghouse PWR 3-LoopOn 8/9/17, a Unit 1 containment entry was made in order to investigate increased Reactor Coolant System (RCS) unidentified leakage. The team noted a through-wall leak from the tubing/socket weld area of 'C' Hot Leg Sample Valve. The sample valve and RCS pressure boundary were declared inoperable, and a 6-hour action statement to place Unit 1 in Hot Shutdown was entered at 1338 (EDT) hours as required by Technical Specification 3.1.C.3. At 1606 (EDT) hours on 8/9/17, Unit 1 shutdown was commenced, and at 1637 (EDT), Unit 1 was at Hot Shutdown. This report is being submitted pursuant to 10CFR50.72(b)(2)(i) as a result of power reduction required by Technical Specifications. Further, this report is being submitted pursuant to 10CFR50.72(b)(3)(ii)(A) for any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded. The NRC Resident (Inspector) has been notified of this event and is on site. There was no radiation release associated with this event, nor were there any personnel injuries or contamination events.
ENS 5287728 July 2017 16:40:00Beaver ValleyNRC Region 1Westinghouse PWR 3-LoopOn July 20, 2017, a fire protection supply line at BVPS (Beaver Valley Power Station) Unit 1 experienced a mechanical joint separation. When the mechanical joint separated there was an unplanned flow of water from the fire protection line to the ground, which eventually re-entered the Ohio River via storm drains. The source of the water to the BVPS Unit 1 Fire Protection System is the Ohio River. The fire protection water was not treated with chemical additives. The water flow from this fire protection line was terminated on the same day. Due to the situation described above, FENOC (FirstEnergy Nuclear Operating Company) provided written documentation describing this occurrence to the Pennsylvania Department of Environmental Protection, (PADEP) on July 28, 2017. This offsite notification to PADEP requires a 4-hour report per 10 CFR 50.72 (b)(2)(xi). No press release is planned. The NRC Resident Inspector has been notified.
ENS 5283329 June 2017 12:43:00SummerNRC Region 2Westinghouse PWR 3-Loop

On 6/29/2017 at 0857 (EDT), VC Summer Nuclear Station automatically tripped due to a loss of normal feed water flow to the B Steam Generator.

There were no complications with the trip. All control rods fully inserted. All emergency feedwater pumps automatically started and recovered steam generator levels. The plant is stable in Mode 3. Station personnel are investigating the cause of the loss of normal feedwater to the B Steam Generator. This is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident Inspector has been notified. The licensee notified the State of South Carolina as well as Fairfield, Lexington, Richland and Newberry Counties regarding the event.

ENS 527969 June 2017 10:17:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopThis 60-day telephone notification is being made in accordance with the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of several safety systems. On April 10, 2017 at 1347 hours (EDT) with Unit 3 in Mode 6 during performance of the Train B Engineered Safeguards Integrated Test, safety system actuations occurred prior to the expected point in the test procedure when a loss of continuity resulted while the seismic clips were being removed from a fuse. The actuations were supposed to occur at a subsequent step when the fuse was to be pulled to actuate the Hi Containment Pressure signal. As a result, the following equipment actuated: 3B, 4A and 4B High Head SI pumps; 3B Containment Spray pump; Containment Isolation and Containment Ventilation Isolations; 3A and 3B Emergency Diesel Generators; Emergency Containment Coolers. Because an actual high containment pressure signal did not exist at the time of the actuation, the actuation is considered invalid. All equipment responded as expected. The NRC Resident Inspector has been notified.
ENS 527916 June 2017 15:48:00Turkey PointNRC Region 2Westinghouse PWR 3-LoopThis notification is in accordance with Turkey Point Technical Specification (TS) 3.7.1.6, Action b.1 to report the inoperability of both Standby Steam Generator Feedwater Pumps (SSGFPs) for greater than 24 hours. On 6/6/17 at 1751 hours (EDT) both SSGFPs will be inoperable for greater than 24 hours in support of planned valve repairs that require isolation of the common suction and discharge piping. TS 3.7.1.6, Action b.1 requires a report within four hours if both SSGFPs have been inoperable for 24 hours providing the cause of the inoperability and restoration plans. The valve repairs are currently planned for completion on or about 2300 hours on 6/9/17 which will restore the 'A' pump to service and allow TS 3.7.1.6, Action b.1 to be exited. The diesel-driven 'B' pump will remain out of service for radiator repair which is currently planned for completion on or about 0800 hours on 6/14/17. The function of the Standby Steam Generator Feedwater System is as a backup to the Auxiliary Feedwater System and is not credited in the safety analysis. The NRC Resident Inspector has been notified. Both pumps were taken out of service at 1751 EDT on 6/5/17.
ENS 527852 June 2017 17:07:00FarleyNRC Region 2Westinghouse PWR 3-Loop

This notification is being made as required by 10 CFR 50.72(b)(3)(v) due to both trains of Penetration Room Filtration (PRF) being inoperable due to an inoperable PRF Boundary. At 0920 (CDT) on 6/2/2017, a gap was discovered between an electrical penetration room ceiling and the containment wall where seismic gap material was noted to be missing. The gap was subsequently closed and PRF testing completed sat. The condition was exited at 1345 (CDT). The licensee notified the NRC Resident Inspector.

  • * * RETRACTION ON 7/25/17 AT 1725 EDT FROM MATT STANLEY TO DONG PARK * * *

On 6/2/17 at 1707 CDT Farley Nuclear Plant notified the NRC Operations Center of an entry into Technical Specification 3.7.12 Condition B for Unit 1 loss of two trains of Penetration Room Filtration (PRF). At 0920 (CDT) on 6/2/2017, a gap had been discovered between an electrical penetration and containment where seismic gap material was noted to be missing. The report was made pursuant to 10 CFR 50.72(b)(3)(v) under Event Notification 52785. Upon further engineering review and satisfactory testing to support operability, Farley has determined that the configuration did not meet the criteria for a condition that could have prevented fulfillment of a safety function, and is retracting the notification. The NRC Resident Inspector has been notified. Notified R2DO (Blamey).

ENS 5270525 April 2017 14:53:00SummerNRC Region 2Westinghouse PWR 3-LoopOn April 25, 2017 at approximately 0900 (EDT), it was identified that power to RM-G8 Area Gamma Radiation Monitor for the Fuel Handling Building Bridge, had not been restored within 72 hours. RM-G8 was de-energized during the B train essential bus outage and was restored on April 25, 2017 at 1148. It was out of service for approximately 92 hours. Compensatory measures were in place per HPP-904 while RM-G8 was out of service. RM-G8 is identified in the emergency plan as an equipment important to emergency response. NUREG-1022, Rev. 3 Supplement 1 Event Report Guidelines 10 CFR 50.72(b)(3)(xiii), allows a 72 hour planned outage time to restore equipment important to emergency response. Since RM-G8 was not restored in 72 hours, it is reportable as an 8 hour ENS. This event should have been reported when it was known that the 72 hour outage time was not going to be met. This issue has been entered in the station's corrective action program. Fuel inspections were occurring during this time with compensatory measures in place. The licensee notified the NRC Resident Inspector.
ENS 526624 April 2017 02:33:00RobinsonNRC Region 2Westinghouse PWR 3-LoopAt 2155 hours EDT on 04/03/2017, with the unit in Mode 3 at 0 (percent) power, an automatic actuation of the Auxiliary Feedwater (AFW) System occurred during surveillance testing. The cause of the AFW system auto-start was an improperly performed procedure step to bypass the auto-start logic of the AFW pumps during performance of the surveillance test. The 'A' and 'B' AFW pumps automatically started as designed when the feedwater isolation signal was received. Due to the valid actuation of the AFW system, this event requires an 8-hour non-emergency notification under 10 CFR 50.72(b)(3)(iv)(A)(B)(6). At no time did this occurrence pose undue risk to the health and safety of the public. The NRC Resident Inspector has been notified.
ENS 5263924 March 2017 20:25:00SurryNRC Region 2Westinghouse PWR 3-LoopOn 03/24/2017 at approximately 1500 hours (EDT), a hydraulic line on vendor supplied cleaning equipment failed and leaked approximately 8 gallons of 65% glycol solution into the Surry Power Station Unit 2 D intake bay. Since the intake bay communicates with the James River, the State of Virginia Department of Environmental Quality (DEQ) was notified of the discharge at 2000 hours. The glycol solution is water soluble and dispersed quickly. All work stopped while the issue is being investigated and corrective actions implemented. No sheen was observed and no impact to state waters is expected to result from this issue. This non-emergency notification is being made in accordance with 10 CFR 50.72(b)(2)(xi), any event or situation related to the protection of the environment for which notification to other government agencies has been made. The NRC Senior Resident Inspector has been notified.
ENS 5262318 March 2017 15:07:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

On 3/18/17 at 1107 (EDT), the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. All three reactor coolant pumps (RCP) tripped and the 3B RCP was restarted for forced recirculation. The reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. In addition, Technical Specification 3.8.1.1, Action C requires a four hour report for the concurrent inoperability of the Unit 4 startup transformer to Unit 3 via the 3A 4kV bus and the Unit 3 3A diesel generator. The NRC Senior Resident Inspector will be notified.

  • * * UPDATE ON 3/18/2017 AT 1854 EDT FROM JAMES SPICHER TO BETHANY CECERE * * *

Update to previous report (EN 52623) to include additional reporting criteria. On 3/18/17 at 1107 (EDT) the Unit 3 reactor tripped as a result of the loss of the 3A 4kV bus. The 3A Emergency Diesel Generator (EDG) started on the loss of power signal but did not load, as designed, due to the bus fault. The 3A EDG was manually stopped at 1332. The Auxiliary Feedwater (AFW) System also initiated as expected. AFW was stopped at 1135. The actuations of the 3A EDG and AFW are reportable in accordance with 10 CFR 50.72(b)(3)(iv)(A). A loss of safety function affecting Units 3 and 4 occurred due to the loss of the 3A high head safety injection (HHSI) pump because it could not be powered from the faulted 3A 4kV bus with both Unit 4 HHSI pumps earlier (0624) removed from service due to planned maintenance. This caused three of the four HHSI pumps to be inoperable. The four HHSI pumps are shared by both Units 3 and 4. The safety function is achieved by two of the four HHSI pumps. Both Unit 4 HHSI pumps were restored to operable status at 1336. The loss of safety function is reportable in accordance with 10 CFR 50.72(b)(3)(v)(D). The Unit 3 reactor is stable in Mode 3. The 3A 4kV bus remains deenergized until troubleshooting and repairs are complete. Unit 4 remains operating at 100% power. The licensee will notify the NRC Resident Inspector. Notified R2DO (Ehrhardt) and NRR EO (Miller).

ENS 5262118 March 2017 12:09:00Turkey PointNRC Region 2Westinghouse PWR 3-Loop

Alert declared at 1119 EDT 3/18/17 based on EAL H.A.2 - Fire or Explosion affecting plant safety systems. Fire alarms in the Unit 3 4kV switchgear rooms resulting in a loss of the 3A 4kV bus and trip of all three Reactor Coolant Pumps. The reactor tripped and was stabilized in Mode 3. No actual fire was observed. The 3A 4kV is deenergized. The 3B Reactor Coolant Pump was restarted for forced circulation. All other safety systems functioned as required. A refueling outage was scheduled to begin on 3/20/17. All control rods fully inserted on the reactor trip. Decay heat is being removed using feedwater and steam generator atmospheric steam dumps. One person was injured with a minor burn and possible sprained ankle and was taken to a local hospital. The licensee notified the NRC Resident Inspector. Notified DHS SWO, DOE, FEMA, HHS, NICC, USDA, EPA, FDA (e-mail), NWC (e-mail), NNSA (e-mail), and NRCC SASC (e-mail).

  • * * UPDATE AT 1426 EDT ON 3/18/2017 FROM DAN HAGARDY TO BETHANY CECERE * * *

Unit 3 was determined by the Emergency Coordinator to be in a safe and stable condition, the Emergency Plan personnel at the Technical Support Center and Emergency Operations Facility were no longer required for support, the Operations Support Center was staffed for recovery efforts, and plant personnel were sufficient and capable for continuing mitigation efforts. Investigation of the fault on the 3A 4kV bus is ongoing. Based on the above conditions, the Alert was exited at 1420 hours (on 3/18/2017). The injured electrician was taken to an offsite hospital to treat minor burns and possible sprained ankle. The licensee notified the NRC Resident Inspector. Notified the R2DO (Ehrhardt), NRR EO (Miller and King), IRD MOC (Stapleton), DHS SWO, DOE, FEMA, HHS, NICC, USDA, EPA, FDA (e-mail), NWC (e-mail), NNSA (e-mail), and NRCC SASC (e-mail).

ENS 5257123 February 2017 13:02:00Beaver ValleyNRC Region 1Westinghouse PWR 3-LoopIn order to address the concerns outlined in RIS (Regulatory Information Summary) 2015-06 'TORNADO MISSILE PROTECTION', an evaluation of tornado missile vulnerabilities and their potential impact on Technical Specification (TS) plant equipment was conducted. This evaluation concluded that the following Structures, Systems, and Components (SSCs) are potentially vulnerable to tornado generated missiles: The BVPS Unit 1 (BV-1) and BVPS Unit 2 (BV-2) Main Steam Safety Valve (MSSVs) discharge flow paths to atmosphere (reference TS 3.7.1) are potentially vulnerable to tornado generated missiles. A tornado could generate missiles capable of striking the exhaust piping of the MSSVs potentially crimping the piping and resulting in reduced flow capacity. In the worst case, all MSSV's could be rendered inoperable. This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B), and 10 CFR 50.72(b)(3)(v)(A). The BV-1 and BV-2 Atmospheric Steam Dumps (ADVs) discharge flow paths to atmosphere (reference TS 3.7.4) are potentially vulnerable to tornado generated missiles. A tornado could generate missiles capable of striking the exhaust piping of the ADVs potentially crimping the piping and resulting in reduced flow capacity. In the worst case, all ADVs could be rendered inoperable. This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B), and 10 CFR 50.72(b)(3)(v)(A). The BV-2 Auxiliary Building tornado missile shield door (A-35-5A), credited for tornado missile protection of the Primary Component Cooling Water (PCCW) system, was found to not be fully closed and latched. A tornado could generate missiles capable of striking the PCCW system with the missile door open rendering both trains of the PCCW system inoperable. This door is now maintained closed and latched except when opened under administrative controls. This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B). The BV-2 Spent Fuel Building tornado missile shield door (F-66-3), credited for tornado missile protection of the irradiated fuel assemblies in the Spent Fuel Pool including the Cask Pit, was found to not be fully closed and latched. This door is now maintained closed and latched except when opened under administrative controls. This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B). The potential tornado missile vulnerabilities for the MSSVs and ADVs (discussed above) are being addressed in accordance with EGM-15-002 Rev 1 and DSS-ISG-2016-01 (NRC enforcement discretion and interim guidance documents). Immediate compensatory measures were taken to reduce the likelihood and mitigate the potential consequences of an onsite tornado generated missiles. The NRC Resident inspector has been notified.
ENS 5251327 January 2017 07:25:00Beaver ValleyNRC Region 1Westinghouse PWR 3-Loop

An Unusual Event (HU.4) was declared at BVPS (Beaver Valley Power Station) Unit 1 at 0641 EST due to a fire alarm in Containment which was unable to be verified extinguished within 15 minutes. Current Containment parameters do not indicate an actual fire. The Fire Alarm has subsequently been reset (at 0648 EST). The Licensee notified the NRC Resident Inspector." The Licensee has notified State and local government agencies. A containment entry is planned for 1000 EST to verify that there is no fire. Unit 1 continues at 100 percent power. Unit 2 was unaffected. Notified DHS SWO, FEMA Ops Center, and NICC Watch Officer. E-mailed FEMA NWC and Nuclear SSA.

  • * * UPDATE FROM MICHAEL SMITH TO STEVEN VITTO ON 1/27/2017 AT 0952 EST * * *

The time of the fire alarm reset was at 0648 EST on 1/27/2017. The Unusual Event has been terminated at 0934 EST on 1/27/2017 after a containment entry and visual inspection determined no fire or indications of a fire exist. The following notifications were made: Commonwealth of Pennsylvania Emergency Management Agency, Beaver County in Pennsylvania, The State of Ohio Emergency Management Agency, Columbia County in Ohio, The State of West Virginia Emergency Management Agency and Hancock County in West Virginia. The Licensee notified the NRC Resident Inspector. Notified R1DO (Welling), NRR EO (Miller), and IRD MOC (Gott). Notified DHS SWO, FEMA Ops Center, and NICC Watch Officer. E-mailed FEMA NWC and Nuclear SSA.

ENS 5243815 December 2016 13:50:00North AnnaNRC Region 2Westinghouse PWR 3-Loop

On 12/14/16 at 1206 (EST), 0-PT-89.9K (underground fuel-oil piping pressure test), was performed UNSAT after a failed attempt to maintain pressure in the supply line to the Unit 2 'H' Emergency Diesel Generator (EDG) Day Tank. The exact source of the leakage is unknown at this time but is reasonable to believe some fuel oil was released underground. The associated Fuel Oil line is currently tagged out and isolated. This condition is reportable to the Virginia Department of Environmental Quality (VA DEQ) as part of the Underground Storage Tank Program. Pressure tasting of the other EDG fuel oil supply lines has been previously completed satisfactorily. The 2H EDG remains Operable as the redundant fuel oil transfer pump and its fuel oil piping are Operable and capable of maintaining adequate day tank level. The VA DEQ was notified of this condition at 1130 (EST) on 12/15/16. This event is reportable in accordance with 10CFR50.72(b)(2)(xi) for 'Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.' The licensee has notified the NRC Resident Inspector and will notify Louisa County.

  • * * UPDATE ON 12/28/16 AT 1659 EST FROM JAY LEBERSTIEN TO DONG PARK * * *

This is a follow-up report to Event Number 52438, made on 12/15/2016, regarding offsite notification to the Virginia Department of Environmental Quality for potential fuel oil leakage from the supply line to the Unit 2H Emergency Diesel Generator (EDG) Day Tank. During investigation of the potential fuel oil leak from the 2HB EDG Day Tank supply line (as previously reported in EN 52438), the 2HA fuel oil line, which runs close to the 2HB line, was disturbed and began to leak a mist of fuel oil. The fuel oil was contained in the area and was being cleaned via vacuum truck as it was leaking. Personnel at the scene noted the soil was not contaminated with fuel oil initially and saw the leak start on 2HA line. It has been estimated that less than one gallon of fuel oil was released to the surrounding soil during troubleshooting of the leak. The fuel oil was immediately vacuumed. The 2HA line was isolated and the leakage was stopped. The 2HA line is to be repaired and tested. The 2H EDG remains available, however, it is considered inoperable at this time. Investigation of the 2HB fuel oil line continues. The condition of the 2HA fuel oil line was reported to the Virginia Department of Environmental Quality (VA DEQ) as part of the Underground Storage Tank Program on 12/28/16. Therefore, this event is reportable in accordance with 10CFR50.72(b)(2)(xi) for 'Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.' The licensee has notified the NRC Resident Inspector and will notify Louisa County. Notified R2DO (Rose).

ENS 524188 December 2016 21:05:00HarrisNRC Region 2Westinghouse PWR 3-LoopThis 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) as the discovered condition affects the functionality of an emergency response facility. A condition impacting functionality of the Technical Support Center (TSC) Ventilation System was discovered on December 8, 2016, at 1330 (EST). The issue involved a loss of the ability to maintain habitability of the TSC due to a failed outside air intake fan. The repair of the equipment failure is currently being planned. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures. The secondary TSC has been notified that relocation may be necessary upon facility activation. This condition does not affect the health and safety of the public or station employees. The NRC Resident Inspector has been notified.
ENS 524147 December 2016 17:24:00FarleyNRC Region 2Westinghouse PWR 3-LoopDuring the evaluation of tornado missile vulnerabilities and the potential impacts to Technical Specification (TS) plant equipment, it was concluded that the following SSCs (systems, structures, and components) were vulnerable to tornado generated missiles. The Service Water Intake Structure (SWIS) intake and exhaust ventilation hoods, located on the roof of the SWIS, are not adequately protected from missiles generated by a tornado. Should a tornado-generated missile strike the SWIS intake and exhaust ventilation hoods, the hoods could crimp thus reducing air flow and challenging the performance of their heating and cooling safety functions. If the intake hoods were damaged or removed due to a missile strike, entry of rainwater could occur due to severe weather high wind velocity, and could affect safety related electrical equipment in the rooms directly below the hoods. These potential conditions could render Service Water trains inoperable on either or both units. 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 EGM-15-002 and DSS-ISG-2016-01 (enforcement discretion and interim guidance documents). Required actions have been taken. Corrective actions will be documented in a follow up licensee event report. The NRC Resident Inspector will be notified. The licensee is evaluating the operability of the service water system. Should one train be declared inoperable, the licensee would be in a 72 hr. LCO action statement. If both trains are inoperable, then the licensee would enter T.S. 3.0.3.
ENS 5239527 November 2016 03:08:00FarleyNRC Region 2Westinghouse PWR 3-LoopAt 0026 (CST) on November 27, 2016, Farley Unit 1 was manually tripped from 100% reactor power due to voltage swings suspected to be caused by the Auto Voltage Regulator. All control rods fully inserted and Auxiliary Feedwater (AFW) auto-started as expected. All systems responded as expected. The plant is currently stable in Mode 3 (Hot Standby). The cause of the main generator voltage oscillations is under investigation. The NRC Resident Inspector has been notified. The trip was uncomplicated. Decay heat is being removed via the steam dumps to condenser. The plant is at normal operating pressure and temperature with auxiliary feedwater supplying the steam generators. The electrical grid is stable and supplying plant loads. All safety equipment is available, if needed. Unit 2 was unaffected by the event and remains at 100% power.
ENS 5239022 November 2016 18:44:00Beaver ValleyNRC Region 1Westinghouse PWR 3-LoopDuring routine floor cleaning activities inside of the BVPS (Beaver Valley Power Station) Main River Water Intake Structure, approximately one and one half cups (approximately 12 oz.) of Simple Green cleaning solution diluted in three gallons of mop cleaning water was inadvertently released into the Ohio River. Subsequent to confirmation of the inadvertent release to the Ohio river, a notification was made to the Pennsylvania Department of Environmental Protection, (PADEP). This offsite notification to PADEP requires a 4-hour report per 10 CFR 50.72(b)(2)(xi). Actions were taken to preclude any further liquid cleaning solution to be released, and no detectable impact to the Ohio River was observed. The amount of cleaning solution does not exceed any Reportable Quantity limit that would be hazardous to the environment or personal health. No press release is planned. The NRC Resident Inspector has been notified.
ENS 5237417 November 2016 20:51:00FarleyNRC Region 2Westinghouse PWR 3-LoopAt 1859 CST on November 17, 2016, Farley Nuclear Plant Unit 1 initiated a shutdown from approximately 99 percent reactor power. The shutdown was initiated per Technical Specification LCO 3.0.3. This LCO entry was based on having no operable steam flow channels on the C loop for Farley Nuclear Plant Unit 1. Unit 2 as not affected. The NRC Resident Inspector has been notified.
ENS 523579 November 2016 14:58:00SummerNRC Region 2Westinghouse PWR 3-LoopAt approximately 1008 (EST) on 11/9/16, site personnel discovered a sanitary lift station overflowing in the protected area. The overflow entered a nearby storm drain that discharges into Outfall 13. The estimated release volume is approximately 10 gallons. The release has been stopped. At 1339 an initial notification was made to SCDHEC (South Carolina Department of Health and Environmental Control). The cause of the overflow is still under investigation. Functionality of the lift pump has been restored and cleanup is complete. The NRC Senior Resident has been notified.
ENS 523568 November 2016 17:36:00FarleyNRC Region 2Westinghouse PWR 3-LoopAt 1331 (CST) on November 8, 2016, Farley Nuclear Plant Unit 1 manually tripped from 32% reactor power. The plant was ramping down to remove the main generator from service due to an unrelated issue. 1A SGFP did not respond to control Steam Generator (SG) level as expected when the miniflow was opened per procedure. SG levels lowered due to lower feed flow and the reactor was manually tripped in accordance with plant procedures. All control rods fully inserted and Auxiliary feedwater (AFW) auto started as expected. The Main Steam Isolation Valves were closed to minimize the cool-down. Decay heat is being removed through the Atmospheric Relief Valves. All other systems responded as expected. The plant is currently stable in Mode 3 (Hot Standby). The failure of the 1A SGFP control is under investigation. Unit 2 was not affected. The NRC Resident Inspector has been notified. There is no primary to secondary leakage.
ENS 523401 November 2016 19:01:00FarleyNRC Region 2Westinghouse PWR 3-Loop

At 1743 CDT on 11/1/16, readings were obtained that indicated ammonia above IDLH (Immediately Dangerous to Life and Health) values in the Unit 1 Auxiliary Building and an Alert was declared by the Emergency Director. The plant is stable with Unit 1 at 2% power. Unit 2 is at 100% power (and stable). The site is currently investigating to determine the source and ventilate the area." The licensee has informed the NRC Resident Inspector. Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, FEMA National Watch Center (email), FDA EOC (email), Nuclear SSA (email).

  • * * UPDATE FROM BLAKE MITCHELL TO STEVEN VITTO ON 11/02/2016 AT 0443 EDT * * *

The following is the Emergency Preparedness 8-hour report for the Plant Farley ALERT declaration. An ALERT was declared at 1743 CDT on November 1, 2016, based on Emergency Action Level (EAL) HA3 (Release of toxic, asphyxiant, or flammable gases within vital areas which jeopardizes operation of systems required to maintain safe operations or establish or maintain safe shutdown) due to an ammonia discharge into the Auxiliary Building. Farley Unit 1 was in Mode 2 at 2 percent power and Unit 2 was in Mode 1 at 100 percent power throughout the event. Actions completed during and leading up to termination from the event included walkdown of the area to locate the ammonia source, and isolating the ammonia source while atmospheric monitoring was performed in all affected and adjacent areas. Installation of additional ventilation fans was completed. This event has been entered into the Farley Corrective Action Program under Condition Report 10293519 (Ammonia levels in 100 Feet Radside). A review of the Alert classification has determined that the classification was timely and accurate. All required notifications were completed accurately and in a timely manner. The ERO (Emergency Response Organization) notification system functioned as expected and all emergency response facilities were activated in a timely manner. There were no missing or injured personnel during the event. There is no evidence of tampering or sabotage of plant equipment leading to this event. At 2202 CDT on 11/1/2016, the ammonia source was identified as Valve N1P20V913. At 2228 CDT, the ammonia source was isolated. Final assessment of the Auxiliary Building showed that the ammonia levels were less than 5 ppm. It was determined that a deficiency in the valve component was the cause of the ammonia leak. The Alert was terminated on 11/1/2016 at 2340 CDT. The Licensee has notified the NRC Resident Inspector. Notified R2DO(Ernstes), IRD (Stapleton), NRR EO (Miller). Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, FEMA National Watch Center (email), FDA EOC (email), Nuclear SSA (email).

ENS 5233531 October 2016 16:39:00HarrisNRC Region 2Westinghouse PWR 3-LoopOn October 26, 2016, the Harris Nuclear Plant was in Mode 6 with core reload complete, the reactor head removed, and reactor cavity water level greater than 23 feet. The refueling water storage tank (RWST) was less than 23.4% level as expected for the refueling conditions. During surveillance testing to adjust the eductor flow throttle position, the containment spray pump was started in recirculation mode with the discharge valve shut. With RWST level less than 23.4%, logic was satisfied to actuate Engineered Safety Features Actuation System (ESFAS) Functional Unit 8, containment spray switchover to containment sump. The containment sump suction valve opened in accordance with the design, however the action was unexpected by the operators. Therefore, operators secured the containment spray pump and shut the containment sump suction valve. ESFAS Functional Unit 2, Containment Spray, was not actuated and water did not flow through the containment spray nozzles. This event is reported as a specified system actuation in accordance with 10 CFR 50.72(b)(3)(iv)(A) due to the opening of the containment sump suction valve. This event did not impact the health and safety of the public. The licensee has notified the NRC Resident Inspector.
ENS 5233229 October 2016 15:31:00RobinsonNRC Region 2Westinghouse PWR 3-LoopThis 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) as the discovered condition affects the functionality of an emergency response facility. A deficiency with the TSC and EOF ventilation system was discovered on October 29, 2016 at 1032 (EDT). The deficiency involved a fire alarm unable to be reset impeding the ability to place the TSC and EOF in recirculation mode in the event of a radiological release. The fire alarm was reset at 1204 (EDT) on October 29, 2016, restoring capability to perform full emergency assessment to the TSC and EOF. If an emergency had been declared while the fire alarm was unable to be reset requiring TSC or EOF activation during this period, the TSC and EOF would be staffed and activated using existing emergency planning procedures unless the TSC or EOF became uninhabitable due to ambient temperature. radiological, or other conditions. If relocation of the TSC or EOF became necessary, the Emergency Response Manager would relocate the TSC and/or EOF staff to an alternate location in accordance with applicable site procedures. This condition had no impact on the health and safety of the public. The NRC Resident Inspector has been notified. A malfunctioning smoke detector was removed from the system. Compensatory measures are being employed.
ENS 5229715 October 2016 15:46:00HarrisNRC Region 2Westinghouse PWR 3-Loop

On October 15, 2016, while the Harris Nuclear Plant was shut down for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with the lnservice Inspection Program. Ultrasonic examinations identified a flaw in a head penetration nozzle. The unit is in a safe and stable condition. The flaw will be repaired prior to startup from the refueling outage. The flaw and repair have no impact on the health and safety of the public or station employees. The NRC Resident Inspector has been notified. The flaw is located on the J groove weld of Nozzle 40. No boric acid deposits were located near the nozzle.

  • * * UPDATE FROM JOHN CAVES TO STEVEN VITTO ON 10/16/2016 AT 1549 EDT * * *

Subsequent inspections identified an additional nozzle that will require repairs (Nozzle 51) prior to startup. Inspections continue and are expected to be completed by October 18. The additional inspection indication and repair have no impact on the health and safety of the public or station employees. The NRC Resident Inspector has been notified. The flaw is located on the J groove weld. No boric acid deposits were located near the nozzle. Notified R2DO(Ehrhardt).

  • * * UPDATE FROM JOHN CAVES TO STEVEN VITTO ON 10/16/2016 AT 1844 EDT * * *

Subsequent inspections identified an additional nozzle that will require repairs (Nozzle 30) prior to startup. Inspections continue and are expected to be completed by October 18. The additional inspection indication and repair have no impact on the health and safety of the public or station employees. The NRC Resident Inspector has been notified. Notified R2DO(Ehrhardt).

ENS 522929 October 2016 06:09:00SurryNRC Region 2Westinghouse PWR 3-LoopSurry Unit 2 reactor automatically tripped at 0254 hours on 10/09/2016, due to a Main Generator Differential Lockout Turbine Trip. The cause of the generator differential lockout is under investigation at this time. Reactor Coolant System temperature is currently being maintained at 547 degrees Fahrenheit on the main steam dump valves. All three Auxiliary Feedwater Pumps automatically started as designed on Low-Low Steam Generator Water Level following the trip. Auxiliary feedwater pumps have since been secured and Main Feedwater is in use. All systems operated as required. The source range nuclear instruments had to be manually reinstated following the reactor trip due to indications of undercompensation on Intermediate Range Nuclear Instrument channel N-36. Off site power remains available. There is no impact on Surry Unit 1. This notification is being made pursuant to 10CFR50.72(b)(2)(iv)(B) for 4-hour notification of Reactor Protection System activation and 10CFR50.72(b)(3)(iv)(A) for 8-hour notification of automatic actuation of the Auxiliary Feedwater System. The NRC Resident Inspector has been notified and is responding to the site. There were no radiation releases, personnel injuries, or contamination events due to this event. All control rods fully inserted. Secondary reliefs lifted and reseated as expected following a reactor trip from 100% power.
ENS 522918 October 2016 14:23:00HarrisNRC Region 2Westinghouse PWR 3-Loop

Loss of all offsite power capability, Table S-5, to 6.9kV emergency buses 1A-SA and 1B-SB for greater than or equal to 15 minutes. At 1328 EDT, while shutdown in Mode 4 (Hot Shutdown), Harris declared an Unusual Event due to a loss of offsite power. Following the loss of offsite power (LOOP), the Emergency Diesel Generators started and loaded onto their respective emergency buses. The reactor remains stable and shutdown in Mode 4. The licensee is currently investigating the cause of the LOOP and the emergency buses will continue to be powered by the EDGs until the licensee has determined the cause for the LOOP. Offsite power is currently available into the switchyard. The licensee notified the state government, the local government, and the NRC Resident Inspector. Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).

  • * * UPDATE FROM RALPH DOWNEY TO DONALD NORWOOD AT 1658 EDT ON 10/8/16 * * *

The cause (of the LOOP) is not known. Duke Energy Control Center has evaluated the grid and is comfortable with Harris connecting emergency buses back to the grid. Harris Plant is evaluating restoration. Faults were validated on the 115kV Cape Fear North and South supply lines into the Harris switchyard. This notification also addresses various valid actuations of safety systems, including the Emergency Diesel Generators, as well as, potential loss of Emergency Assessment Capabilities due to the LOOP impacting Emergency Planning equipment. The licensee notified the NRC Resident Inspector. Notified R2DO (Bonser), IRD (Grant), and NRR EO (King).

  • * * UPDATE FROM RALPH DOWNEY TO DONALD NORWOOD AT 1755 EDT ON 10/8/16 * * *

The cause of the LOOP has been determined to be a momentary electricity loss on the 115kV Cape Fear North and South supply lines into the Harris switchyard. This event notification also addresses the loss of safety function of the offsite power system which occurred as a result of grid perturbations. The licensee notified the NRC Resident Inspector. Notified R2DO (Bonser), IRD (Grant), and NRR EO (King).

  • * * UPDATE FROM DUSTIN MARTIN TO DONALD NORWOOD AT 2055 EDT ON 10/8/16 * * *

Based on the grid being stable and the 115kV Cape Fear North and South lines being available, the licensee terminated the Unusual Event at 2049 EDT on 10/8/16. The licensee notified the NRC Resident Inspector. Notified R2DO (Bonser), IRD (Grant), and NRR EO (King). Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).

  • * * UPDATE FROM SARAH McDANIEL TO DONALD NORWOOD AT 1330 EDT ON 10/9/16 * * *

10 CFR 50.72(b)(2)(XI) - OFFSITE NOTIFICATION At approximately 1305 EDT on October 9, 2016, Duke Energy personnel notified the North Carolina Department of Environment and Natural Resources of a spill of untreated sanitary wastewater. During a significant rainfall event associated with Hurricane Matthew, wastewater was released from the overflow of a lift station that did not function as a result of a power outage. The untreated sanitary wastewater entered the plant's storm drain system. The release has been stopped and the lift station power is restored. An investigation is in progress to further determine the cause and additional corrective actions. There is no impact to public health and safety or the environment due to this incident. This event is reportable per 10 CFR 50.72(b)(2)(xi), an event related to protection of the environment for which a notification to other government agencies has been made. The NRC Resident Inspector has been notified. Notified R2DO (Bonser).

ENS 522908 October 2016 13:44:00RobinsonNRC Region 2Westinghouse PWR 3-Loop

UE SU1.1 declared due to momentary loss of power from the qualified off-site source. Both Emergency Diesel Generators started and loaded to supply power to both of the Emergency Buses. 'A' Service Water Pump did not start on Blackout sequencer. Sufficient Service Water flow is available from the other three operating pumps. All other systems operated as designed." At 1304 EDT Robinson Unit 2 experienced a momentary grid voltage drop that lowered the 4kV bus voltage and initiated an automatic reactor trip. All rods inserted and decay heat is being removed by steam generator PORVs. In response to the reduced bus voltage, the Emergency Diesel Generators (EDGs) automatically started and loaded onto the emergency busses. At 1317 EDT, the licensee declared an Unusual Event (EAL SU1.1) due to the loss of offsite power. The licensee is currently investigating the cause of the grid voltage instability. The emergency busses will continue to be powered by the EDGs until the licensee has determined the cause for the voltage drop. All offsite power sources and all equipment is available. The licensee has notified the state government and Darlington County. The NRC Resident Inspector has been notified. Notified DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).

  • * * UPDATE FROM ALEX CURLINGTON TO DANIEL MILLS AT 1658 EDT on 10/08/16 * * *

At 1303 EDT on 10/08/2016, a reactor trip occurred. The cause was under voltage to the plant 4kV buses due to an offsite grid disturbance. The cause of the disturbance is under investigation. Following the reactor trip, the Auxiliary Feedwater System actuated as expected on low steam generator level. At the time of the trip, the plant was in Mode 1. Currently, the Plant is in Mode 3. The current RCS Temperature is 550 degrees F (Average), and the Steam Generator Levels are in the range of 42 to 53% (normal range) with levels controlled by the Auxiliary Feedwater System. Decay heat removal is being controlled by the steam generator PORVs. 'A' Service Water Pump did not start on Blackout sequencer. Sufficient Service Water flow is available from the other three operating service water pumps 'B', 'C', and 'D'. All other systems operated as designed. Due to the Automatic Actuation of the Reactor Protection System, this event is being reported as a 4-hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B). Due to the valid actuation of Auxiliary Feedwater System, this event is also being reported as an 8-hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A)(B)(6). At no time during this occurrence was the public or plant staff at risk as a result of this event. The Resident Inspector has been notified.

  • * * UPDATE FROM BOBBY STUCKEY TO DANIEL MILLS AT 2347 EDT on 10/08/16 * * *

At 2323 (EDT) Emergency Bus E-2 powered from off-site power." The NRC Resident Inspector will be notified. Notified R2DO (Bonser), IRD (Grant), NRR EO (Miller).

  • * * UPDATE FROM BOBBY STUCKEY TO JOHN SHOEMAKER AT 0028 EDT ON 10/09/16 * * *

At 0011 (EDT) Robinson Nuclear Plant has terminated the Unusual Event. Basis for the Unusual Event termination was restoration of power to Emergency Bus E-2 from off-site power. The licensee has notified the NRC Resident Inspector. Notified R2DO (Bonser), NRR EO (Miller), IRD (Grant), DHS SWO, FEMA OPS Center, FEMA National Watch (email only), DHS NICC, Nuclear SSA (email only).

  • * * UPDATE FROM GEORGE CURTIS TO JOHN SHOEMAKER AT 0253 EDT ON 10/09/16 * * *

At approximately 2323 EDT on 10/08/2016, an auto-start of the Auxiliary Feedwater (AFW) Motor-Driven pumps occurred during the transfer of Emergency Bus power from the 'B' Emergency Diesel Generator (EDG) to offsite power. AFW system auto-start logic associated with Main Feed Pump (MFP) breakers being open is defeated when the EDG output breaker is closed. As such, when the EDG output breaker was opened during the power transfer while the MFP breakers were open, the auto-start logic was thereby met causing the AFW auto-start.

Due to the valid actuation of the AFW System, this event is being reported as an 8-hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A). At no time did this occurrence pose undue risk to the health and safety of the public. The NRC Senior Resident Inspector has been notified of this event. H.B. Robinson Unit 2 was in Mode 3 during this event. Notified R2DO (Bonser).