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 Entered dateSiteRegionReactor typeEvent description
ENS 5532825 June 2021 15:27:00VogtleNRC Region 2W-AP1000The following is a synopsis of information received via E-mail: The individual informing the Commission is Michael J. Yox, 7825 River Road, Waynesboro, GA 30830. The activities which fail to comply include construction processes including, installation of some electrical and mechanical commodities, and control of measuring and test equipment at the Vogtle 3 and 4 construction project. The primary construction firm for the Vogtle 3 and 4 construction project is Bechtel Power Corporation (Bechtel). This report is being provided based on construction nonconformances including, installation of some electrical and mechanical commodities, and control of measuring and test equipment for Vogtle Units 3 and 4. The nonconformances affect cable separation and other raceway structural elements. The extent of condition for the measuring and test equipment issue is under evaluation and may impact additional safety-related work. The identified construction nonconformances are a small fraction of the overall structures and components. There is no specifically identified substantial safety hazard (SSH) for these nonconformances. The nonconformances identified affect some safety-related components and based on this it was conservatively judged that the issues could be related to an SSH. These issues were discovered while the facility is under construction. The identified conditions will be corrected prior to completion of the facility. The evaluation for this report was completed on June 24, 2021. As stated above, there are no specifically identified basic components that have been identified to contain a defect for Vogtle Units 3 and 4. The nonconformances identified affect some safety-related components and based on this it was conservatively judged that these conditions involve a failure to comply that could be related to an SSH. The corrective action which has been, is being, or will be taken include: Comprehensive extent-of-condition reviews and correction of identified conditions are being conducted. The actions to identify and resolve the nonconforming conditions are in process and will be completed in accordance with the site corrective action program. Bechtel, and other subcontractors as needed, will implement actions to correct the identified conditions and ensure that processes are in place to avoid future occurrences. Southern Nuclear Operating Company (SNC) is the organization responsible for ensuring Bechtel and the other subcontractors complete the required actions to correct the nonconforming conditions and ensuring that processes are in place to avoid future occurrences.
ENS 551859 April 2021 16:08:00VogtleNRC Region 2W-AP1000A contract employee supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The employee's access to the plant had been terminated.
ENS 550553 January 2021 08:33:00VogtleNRC Region 2Westinghouse PWR 4-LoopAt 1414 EST on 12/31/2020, a planned maintenance outage commenced on the Vogtle 1and 2 Seismic Monitoring System. The work was to address abnormal indications on the uninterruptable power supply, and was scheduled for an eight (8) hour duration. During the restoration activities, the system did not respond properly and has remained Non-Functional. Compensatory measures for seismic event classification were implemented in accordance with Vogtle procedures prior to removing the system from service. Based upon the troubleshooting conducted, the system is not expected to be restored within 72 hours from the start of the planned outage. This is an eight-hour, non-emergency notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the Seismic Monitoring System is the method for evaluating that an Operational Basis Earthquake (OBE) threshold has been exceeded following a seismic event in accordance with Initiating Condition 'Seismic event greater than OBE levels' and Emergency Action Level HU2. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. Compensatory measures implemented include having a phone number to call to verify if an earthquake has occurred.
ENS 5499512 November 2020 21:14:00VogtleNRC Region 2Westinghouse PWR 4-LoopAt 1732 EST on November 12, 2020, with Unit 2 in Mode 1 and 100 percent power, the reactor automatically tripped due to a turbine trip. The trip was not complex with all systems responding normally post trip. Operations responded and stabilized the plant. Decay heat is being removed by the steam generators through the steam dumps into the condenser. Unit 1 is not affected. An automatic actuation of the Auxiliary Feedwater System (AFW) also occurred. The AFW auto-start is an expected response from the reactor trip. Due to the Reactor Protection System actuation while critical, this event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B), as well as 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 5496321 October 2020 14:10:00VogtleNRC Region 2W-AP1000In accordance with 10 CFR 52.99(c)(2) as described in NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, Vogtle Units 3 and 4 Construction is making this notification to the NRC for determining that Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) 2.3.05.13a.ii (Index No. 344) for Unit 4 requires additional actions to restore the completed status. The ITAAC Closure Notifications for Unit 4 ITAAC 344 was submitted on July 22, 2020 (ML20204B029). On October 19, 2020, it was determined that maintenance activities for the Unit 4 Polar Crane auxiliary hoist holding brake used a different approach for Post Work Verification (PWV) than the original test described in the ICN (ITAAC Closure Notification) for ITAAC 344. The alternate PWV used a test method that is standard industry practice and in accordance with ASME B30.2 to demonstrate that the Acceptance Criteria was met. An ITAAC Post Closure Notification will be submitted in accordance with 10 CFR 52.99(c)(2) and NEI 08-01. The 10 CFR 52.99(c)(4) All lTAAC Complete Notification has not been submitted for VEGP (Vogtle Electric Generating Plant) 4. The NRC Resident Inspector has been notified.
ENS 5486428 August 2020 00:00:00VogtleNRC Region 2W-AP1000

In accordance with 10 CFR 52.99(c)(2), as described in NEI 08-01, 'Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52,' Vogtle Units 3 and 4 Construction is making this notification to the NRC for determining that Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) 2.5.02.07a (Index No. 534) and ITAAC 2.5.02.07e (Index No. 538) for both units require additional actions to restore their completed status. The ITAAC Closure Notifications for ITAAC 534 were submitted on March 31, 2017 (Unit 3 ML17093A286, Unit 4 ML17093A535). The ITAAC Closure Notifications for ITAAC 538 were submitted on November 30, 2016 (Unit 3 ML16351A350, Unit 4 ML16351A334). On August 26, 2020, it was determined that a design change, issued for several Protection and Safety Monitoring System (PMS) isolation barrier assemblies (ISBs), materially altered the basis for determining that the ITAAC 534 and ITAAC 538 Acceptance Criteria were met. The modified ISBs will require testing per IEEE 384-1981, Standard Criteria for Independence of Class 1E Equipment and Circuits, to demonstrate that the Acceptance Criteria is met. System function is not required while the plant is under construction. ITAAC Post Closure Notifications in accordance with 10 CFR 52.99(c)(2) will be submitted following completion of corrective actions. The 10 CFR 52.99(c)(4) All ITAAC Complete Notification has not been submitted for VEGP ((Vogtle Electric Generating Plant)) 3 and 4. The NRC Resident Inspector has been notified.

  • * * UPDATE ON 9/22/21 AT 1534 EDT FROM NICK KELLENBERGER TO HOWIE CROUCH * * *

Upon successful completion of the work to correct the identified impact to ITAAC 534, it has been determined there was no material impact to ITAAC 538. Confirmation was made that the credible fault only affected PMS to PLS analog ISBs and not PMS to PLS relay isolation ISBs. It was also confirmed that the relay isolation ISB testing and qualification summary information was unaffected by the modifications made to the analog ISBs to correct the credible fault scenario condition. Resolution of the credible fault scenario did not result in modifications to the relay isolation ISBs which are the subject of ITAAC 538. Therefore, the ITAAC Closure Notifications submitted for ITAAC 538 on November 30, 2016 (Unit 3 ML16351A350, Unit 4 ML16351A334) continue to be valid and ITAAC Post Closure Notifications are not required. The licensee has notified NRC Region 2. Notified R2DO (Miller) and NRR Vogtle Project Office (via email).

ENS 5477613 July 2020 17:10:00VogtleNRC Region 2On July 13, 2020 at 0831 (EDT), Southern Nuclear Operating Company (SNC) determined an SNC supervisory personnel failed their fitness for duty test. The employee has been removed from the site and their access has been terminated. The NRC Resident Inspector has been notified.
ENS 546508 April 2020 17:03:00VogtleNRC Region 2A 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 NRC Resident Inspector has been notified.
ENS 5459621 March 2020 23:46:00VogtleNRC Region 2At 1644 EDT with Unit 1 in Mode 6 at 0 percent power, an actuation of the Unit 1 Bravo Train Emergency Diesel Generator system (EDG) occurred during Engineered Safety Feature Actuation System (ESFAS) testing. The reason for the EDG auto-start signal was a loss of voltage on the Bravo train safety related electrical bus due to the EDG output breaker opening. The EDG was already running at the time of the loss of voltage on the bus. 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 EDG system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. There was no impact to Unit 2.
ENS 5435929 October 2019 13:25:00VogtleNRC Region 2A contract employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's badge has been confiscated. The NRC Resident Inspector has been notified.
ENS 543189 October 2019 12:48:00VogtleNRC Region 2At 1023 EDT, on October 9, 2019, with Unit 2 in Mode 1 and 100 percent power, an actuation of the Emergency Diesel Generator and Auxiliary Feedwater Systems occurred. The reason for the Emergency Diesel Generator auto-start was the loss of power to the 4160V 1E electrical bus 2AA02 due to a fault at an offsite electrical switchyard. The Emergency Diesel Generator started and energized the 4160V safety bus, and Auxiliary Feedwater Systems automatically started as designed when the undervoltage condition on the safety bus was detected. 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 Emergency Diesel Generator and Auxiliary Feedwater Systems. There was no impact on the health and safety of the public or plant personnel. The NRC resident has been notified.
ENS 5417519 July 2019 13:05:00VogtleNRC Region 2At 0945 (EDT) on July 19, 2019, with Unit 2 in Mode 1 and 100 percent power, the reactor automatically tripped due to Loop 2 'B' Main Steam Isolation Valve failing shut. The Auxiliary Feedwater system (AFW) started automatically as a result of the automatic reactor trip. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Due to the valid AFW actuation from the reactor trip, this event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A). Unit 1 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified. All control rods fully inserted.
ENS 5401722 April 2019 16:16:00VogtleNRC Region 2A contract supervisor tested positive for drugs on a follow-up fitness-for-duty test. The contractor's access to the facility has been revoked and his badge was confiscated. Additionally, the supervisor failed a random test administered the next day (see EN #54018). The licensee notified the NRC Resident Inspector.
ENS 5401822 April 2019 16:16:00VogtleNRC Region 2

EN Revision Text: CONTRACT SUPERVISOR TESTED POSITIVE ON A RANDOM FITNESS-FOR-DUTY TEST A contract supervisor tested positive for drugs on a random fitness-for-duty test. The contractor's access to the facility has been revoked and his badge was confiscated. Additionally, the supervisor failed a follow-up test administered the previous day (see EN #54017).

  • * * RETRACTION ON 4/30/2019 AT 1642 EDT FROM KELLI ROBERTS TO BRIAN LIN * * *

On April 16, 2019, an individual was selected for a follow-up drug test. The same individual was selected again on April 17, 2019 for a random drug test. The results for both tests were ruled by the Medical Review Officer (MRO) on the same day and ruled positive for the same drug on April 22, 2019. These FFD violations were reported to the NRC on April 22, 2019, as EN #54017 and EN #54018, respectively. As allowed by 10 CFR 26.185(o), the MRO further reviewed the quantitation of the drug in both tests and determined that no further drug use had occurred since the first positive test. Therefore, the MRO concluded that this should be considered one FFD violation, and EN #54018 is being retracted. No changes are needed to EN #54017. The NRC Resident Inspector has been notified of this retraction. Notified R2DO (Heisserer) and FFD Group (email).

ENS 5396731 March 2019 00:17:00VogtleNRC Region 2At 2130 (EDT) on March 30, 2019, with Unit 2 in Mode 1 at 30 percent reactor power, the reactor was manually tripped due to a main steam isolation valve failing closed. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser. The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A). Unit 1 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified.
ENS 5383217 January 2019 16:00:00VogtleNRC Region 2A non-licensed contractor supervisor had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The contractor's access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 5378913 December 2018 14:37:00VogtleNRC Region 2At 1700 EST on December 12, 2018, a contractor supervisor violated the licensee's Fitness-for-Duty (FFD) program by subverting a follow-up Fitness for Duty Test. The contractor's site access has been terminated. The NRC Resident Inspector was notified. No work was performed on safety related equipment. The licensee has made a PADs entry.
ENS 536434 October 2018 07:57:00VogtleNRC Region 2

EN Revision Text: MANUAL REACTOR TRIP DURING LOW POWER PHYSICS TESTING At 0544 EDT on October 4, 2018, with Unit 1 in Mode 2 with reactor power in the intermediate range performing low power physics testing, the reactor was manually tripped due to a rod control urgent failure alarm. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam system. Unit 2 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified. All control rods inserted as expected. The cause of the rod control urgent failure is being investigated.

  • * * UPDATE FROM KEVIN LOWE TO DONALD NORWOOD AT 1408 EDT ON 10/19/2018 * * *

This Event Notification is being updated to clarify that the reactor was not critical when this event occurred. Therefore, the reporting requirement is changed from 10 CFR 50.72(b)(2)(iv)(B) to 10 CFR 50.72 (b)(3)(iv)(A). During Dynamic Rod Worth Measurement testing, Control Bank Charlie was inserted approximately 153 steps when the urgent failure occurred (CBC positioned at 75 steps out). Following the scram, additional analysis concluded that the reactor was subcritical when the Reactor Protection System was actuated." The licensee notified the NRC Resident Inspector. Notified the R2DO (McCoy).

ENS 5362827 September 2018 14:42:00VogtleNRC Region 2At 1000 EDT on September 27, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for drugs during a random Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified.
ENS 5361018 September 2018 08:28:00VogtleNRC Region 2At 1610 (EDT) on September 17, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for drugs during a Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified.
ENS 5359912 September 2018 14:14:00VogtleNRC Region 2At 1115 EDT on September 12, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for drugs during a Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The Resident Inspector has been notified.
ENS 5359511 September 2018 17:53:00VogtleNRC Region 2At 1430 EDT on September 11, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for drugs during a Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified.
ENS 5356324 August 2018 15:14:00VogtleNRC Region 2At 1034 (EDT) on August 24, 2018, a contractor supervisor violated the licensee's Fitness-for-Duty (FFD) program by subverting a follow-up Fitness for Duty Test. The contractor's site access has been terminated. The NRC Resident Inspector was notified.
ENS 535387 August 2018 14:45:00VogtleNRC Region 2At 0909 (EDT) on August 7, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for alcohol during a random Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified.
ENS 5352827 July 2018 13:41:00VogtleNRC Region 2A non-licensed contractor supervisor had a confirmed positive for alcohol during a random fitness-for-duty (FFD) test. The employee's unescorted access to the plant has been suspended. The licensee notified the NRC Resident Inspector.
ENS 5352626 July 2018 17:51:00VogtleNRC Region 2At 1040 (EDT) on July 26, 2018, a contractor supervisor violated the licensee's Fitness-for-Duty (FFD) program by subverting the Fitness for Duty program. The contractor's site access has been terminated. The licensee notified the NRC Resident Inspector.
ENS 5351719 July 2018 12:36:00VogtleNRC Region 2At 1300 (EDT) on July 18, 2018, a contractor supervisor violated the licensee's Fitness-for-Duty (FFD) program by subverting the Fitness for Duty process. The contractor's site access has been terminated. The NRC Resident Inspector was notified.
ENS 5351518 July 2018 19:27:00VogtleNRC Region 2A contractor supervisor tested positive for alcohol during an access upgrade fitness-for-duty test. The employee's access to the facility has been suspended. The licensee has notified the NRC Resident Inspector.
ENS 5351117 July 2018 17:01:00VogtleNRC Region 2At 1338 (EDT) on July 17, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for a controlled substance during a random Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The Resident Inspector has been notified.
ENS 534999 July 2018 20:05:00VogtleNRC Region 2At 1515 (EDT) on July 9, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for a controlled substance during a for cause Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified.
ENS 534843 July 2018 12:00:00VogtleNRC Region 2At 0954 (EDT) on July 3, 2018, with Unit 1 in Mode 1 at 100 percent power, the reactor was manually tripped due to high steam generator water level. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser. The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A). Unit 2 was not affected. There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspectors have been notified. All control rods inserted and Unit 1 is in an electrical shutdown lineup. The cause of the high steam generator water level transient is being investigated.
ENS 5347928 June 2018 13:05:00VogtleNRC Region 2At 0902 EDT on June 28, 2018, 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 NRC Resident Inspector has been notified.
ENS 5346922 June 2018 15:12:00VogtleNRC Region 2At 0900 (EDT) on June 22, 2018, a non-licensed supervisory contractor subverted a random Fitness for Duty test. The contractor's site access has been terminated. The NRC Resident Inspector was notified.
ENS 5340316 May 2018 16:51:00VogtleNRC Region 2At 1133 EDT on May 16, 2018, Southern Nuclear Operating Company determined a non-licensed contractor supervisor had a confirmed positive for a controlled substance during a random Fitness-for-Duty test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified.
ENS 533092 April 2018 18:33:00VogtleNRC Region 2W-AP1000A contractor employee supervisor had a confirmed positive for illegal drugs during a fitness for duty test. The employee's access to the site has been terminated. The NRC Resident Inspector has been notified.
ENS 5327722 March 2018 09:31:00VogtleNRC Region 2W-AP1000A non-licensed contract supervisor attempted to subvert a random Fitness For Duty test using a subversion kit on their person. The employee's access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 5322120 February 2018 15:36:00VogtleNRC Region 2W-AP1000At 0925 (EST) on February 20, 2018, a non-licensed supervisory contractor subverted a random Fitness for Duty test. The contractor's site access has been terminated. The NRC Resident Inspector was notified.
ENS 5301816 October 2017 17:59:00VogtleNRC Region 2W-AP1000A non-licensed supervisory contractor subverted a random Fitness for Duty (FFD) test. At 0851 (EDT) on October 16, 2017, a contractor supervisor was notified to report for a random FFD test and (the individual) did not report to the testing facility and left the premises. The contractor's site access has been terminated. The NRC Resident Inspector was notified.
ENS 5299226 September 2017 11:03:00VogtleNRC Region 2Westinghouse PWR 4-LoopAt approximately 0543 (EDT), while (recovering from the performance of) 2B Emergency Diesel Generator and ESFAS testing, a (subsequent) valid undervoltage actuation signal was sent to the 2B Emergency Diesel Generator (EDG). The 2B AC emergency bus (2BA03) was load shed, the 2B EDG automatically started, and tied to 2BA03. The 2BA03 bus was loaded by the automatic load sequencer. The actuation was identified by the Control Room operators and the 2B EDG was locally monitored while in service. This actuation is reportable due to the automatic actuation of a system listed in 10 CFR 50.72(b)(3)(iv)(B). The reactor was not critical at the time of the event and not challenged throughout the event. Decay heat removal and spent fuel pool cooling were not challenged throughout the event. The NRC Resident Inspector has been notified. The cause of the undervoltage condition is under investigation.
ENS 5296814 September 2017 09:10:00VogtleNRC Region 2W-AP1000On September 13, 2017, Southern Nuclear Operating Company (SNC) determined a Contractor Manager confirmed positive for alcohol during a for cause fitness-for-duty test. The employee's unescorted access to the plant has been terminated. The NRC Resident Inspector has been notified.
ENS 5276318 May 2017 15:14:00VogtleNRC Region 2W-AP1000On May 17, 2017, at 1852 (EDT), Southern Nuclear Operating Company (SNC) contractor informed SNC that a contractor Fitness-for-Duty (FFD) collector failed to follow the process defined in both NRC Regulation 10 CFR 26.105(b) and contractor FFD procedures. The collector was fully trained, qualified, and knowledgeable of the process requirements. This determination was made based on initial department investigations and corroborated via independent investigations performed by the contractor. SNC has determined that this is reportable under 10 CFR 26.719(b)(3). The licensee informed the NRC Resident Inspector and NRC Region II.
ENS 5264127 March 2017 16:02:00VogtleNRC Region 2W-AP1000A non-licensed contractor employee had a confirmed positive for a controlled substance during a random fitness-for-duty test. The employee's access to the site has been terminated. The licensee notified the NRC Resident Inspector.
ENS 5261917 March 2017 17:12:00VogtleNRC Region 2Westinghouse PWR 4-LoopAt approximately 1517 (EDT), while restoring protective relay power to the 1B Reserve Auxiliary Transformer, a valid undervoltage actuation signal was sent to the 1B Emergency Diesel Generator (EDG). The 1B EDG automatically started and tied to the safety bus (1BA03). The 1BA03 bus was loaded by the automatic load sequencer. This actuation was identified by the Control Room Operators and the 1B EDG was locally monitored while in service. This actuation is reportable due to the automatic actuation of a system listed in 10 CFR 50.72(b)(3)(iv)(B). The reactor was not critical at the time of the event and not challenged throughout the event. Containment Cooler Number 8 did not automatically start in 'Fast Speed' as expected. Containment Cooler Number 8 was successfully started in 'Fast Speed' manually by the Control Room Operators. The NRC Resident Inspector has been notified.
ENS 525343 February 2017 18:56:00VogtleNRC Region 2Westinghouse PWR 4-LoopAt 1545 EST on 2/3/17, Vogtle Unit 1 was manually tripped from 100% power when loop 1 Main Steam Isolation Valve (MSIV) started to fail closed. Non-Safety Related 4160V bus 1NA01 failed to transfer to alternate incoming power supply automatically and was successfully manually energized. All control rods fully inserted and AFW (Auxiliary Feedwater) and FWI (Feedwater Isolation) actuated as expected. Unit 1 is in Mode 3 and stable with decay heat being removed by AFW. The licensee informed the NRC Resident Inspector.
ENS 5251830 January 2017 14:38:00VogtleNRC Region 2Westinghouse PWR 4-LoopAt approximately 1049 EST, an individual was discovered to be unresponsive at a site training facility outside of the Protected Area. The individual was transported via ambulance to the Burke County Hospital and was declared deceased at 1143 EST. The licensee has notified the NRC Resident Inspector. The licensee notified the State of Georgia Department of Labor - OSHA at 1414 EST.
ENS 5248211 January 2017 13:52:00VogtleNRC Region 2W-AP1000A non-licensed supervisor tested positive for alcohol during a for-cause test. The individual's access to the site has been terminated pending the results of an investigation. The licensee notified RII (Patterson) and the NRC Resident Inspector.
ENS 524239 December 2016 23:46:00VogtleNRC Region 2Westinghouse PWR 4-LoopOn December 09, 2016 at 1734 EST, U2 Train-A NSCW (Nuclear Service Cooling Water) Transfer Pump #8 tripped during Return To Service Surveillance testing for Train-B NSCW Transfer pump #7. Technical Spec 3.7.9 Condition E entered at 1734 with Required Actions to be in M3 (mode 3, Hot Standby) in 6 hours AND M4 (mode 4, Hot Shutdown) in 12 hours. A unit shutdown was commenced at 2042 EST (as a conservative measure) to comply with TS 3.7.9 Condition E. At 1937, U2 B-train NSCW Transfer Pump #7 was declared operable and TS 3.7.9 Condition E was exited. The plant is currently raising power to 100%. The licensee notified the NRC Resident Inspector.
ENS 524127 December 2016 13:12:00VogtleNRC Region 2W-AP1000In accordance with 10 CFR 52.99(c)(2), Vogtle Units 3 and 4 Construction is making this notification to NRC for determining that Inspection, Test, Analysis, and Acceptance Criteria (ITAAC) 2.6.01.02.ii (ECS System Seismic Category I Equipment Design Basis Loads) for both units requires additional actions to restore its completed status. The Closure Notification for this ITAAC (NRC Index No. 580) was originally submitted on May 17, 2016 (reference ML 16138A080 and ML 16166A030). On November 1, 2016, it was determined by the Vogtle 3&4 Contractor that modifications to the Reactor Coolant Pump (RCP) breaker (i.e., switchgear) cabinet design were required to ensure compliance with the applicable portions of IEEE 384, 'Standard Criteria for Independence of Class 1E Equipment and Circuits.' The modification involves an engineering change which adds different equipment to the RCP Breaker cabinet that function to trip the RCP. The new components were not previously qualified for use in the RCP breaker cabinet assembly. Additional seismic qualification type testing and analysis of components are being performed for the added components in the RCP breaker. Update of the Equipment Qualification Data Package and Equipment Qualification Summary Report for the RCP breaker to confirm the breaker withstands seismic design basis loads and Licensee's acceptance is in progress. The revised ITAAC Completion Notice will be submitted to the NRC once all related ITAAC activities have been completed. The licensee has notified the NRC Resident Inspector.
ENS 5231926 October 2016 16:35:00VogtleNRC Region 2Westinghouse PWR 4-LoopDuring the evaluation of tornado missile vulnerabilities and the potential impacts to Technical Specification (TS) plant equipment, it was concluded that the following SSCs (Structures, Systems, and Components) were vulnerable to tornado generated missiles: The Turbine Driving Auxiliary Feedwater (TDAFW) pump exhaust vent is not adequately protected from tornado generated missiles. A tornado could generate missiles capable of striking the exhaust piping on the Turbine Driven Auxiliary Feedwater Pump, crimping the piping resulting in reduced flow capacity and rendering the TDAFW pump inoperable. The Condensate Storage Tank (CST) vents are not adequately protected from tornado generated missiles. A tornado generated missile could strike the vent piping rendering it unable to relieve vacuum on the top of the CST and allow adequate water flow to the Auxiliary Feedwater Pumps and rendering the CST inoperable. These conditions are 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). The NRC Resident lnspector has been notified.
ENS 5220830 August 2016 16:05:00VogtleNRC Region 2W-AP1000A 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.