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 Entered dateSiteRegionReactor typeEvent description
ENS 5400216 April 2019 02:59:00FarleyNRC Region 2At 2355 CDT on 4/15/19, life-saving activities by offsite medical personnel for a Farley employee were terminated. The coroner declared the individual deceased at the plant site at 0130 CDT. The fatality is not believed to be work-related and the individual was inside of the Radiological Controlled Area. This is a four-hour notification, non-emergency for a notification of other government agency. This event is reportable in accordance with 10 CFR 50.72(b)(2)(xi). The NRC Resident Inspector has been notified. The licensee will be notifying the Occupational Safety and Health Administration due to the on-site fatality. The licensee will perform a radiological survey of the individual prior to transportation offsite.
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 5395324 March 2019 05:23:00HatchNRC Region 2At 0159 (EDT), with Unit 2 in Mode 1 at 25 percent power, the reactor was manually tripped due to degrading condenser vacuum. After the turbine was tripped, the station service electrical buses did not transfer to alternate supply resulting in loss of the condensate feedwater system and level being controlled by the RCIC system. Operators responded and stabilized the plant. Reactor water level is being maintained via the RCIC system. Pressure is being controlled and decay heat is being removed by the HPCI system in pressure control mode. Unit 1 is not affected. Additionally, an actuation of the primary containment isolation system occurred during the reactor scram. The reason for the actuation was a group II isolation signal was received on reactor water level and a group I isolation was received on decreasing vacuum. 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). Additionally, 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 primary containment isolation system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
ENS 5394419 March 2019 07:41:00HatchNRC Region 2At 0140 (EDT) on 03/19/2019, while the unit was at approximately 1% power and 154 psig pressure in MODE 2, it was discovered that Unit 2 High Pressure Coolant Injection (HPCI) was INOPERABLE. HPCI does not have a redundant system, therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. Unit 2 entered LCO 3.5.1.c for the HPCI being inoperable. There is no effect on Unit 1.
ENS 5389323 February 2019 09:13:00HatchNRC Region 2At 0212 EST on February 23, 2019, with Unit 2 in Mode 5, an actuation signal for the 2C Emergency Diesel Generator (EDG) was received during the Loss of Coolant Accident / Loss of Offsite Power logic system functional test. The 2C EDG was running and tied onto the 2G 4160 emergency bus when the alternate supply breaker was closed as required per the test procedure. Immediately upon closing the alternate supply breaker, both the alternate supply breaker and 2C EDG output breaker tripped open. The 2C EDG output breaker reclosed once the 2G 4160 bus undervoltage relays sensed a deenergized bus. When the 2C EDG tied to the 2G 4160 bus, the bus voltage was noted as being high, and the 2C EDG was secured. Investigation is ongoing to determine the cause of the initial bus undervoltage and the subsequent bus excessive voltage. 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 AC power system. There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. This event puts Unit 1 in a 72 hour Limiting Condition for Operation for the 1C Startup Transformer being out of service.
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 5382715 January 2019 12:25:00FarleyNRC Region 2At 0800 CST on January 15, 2019, a non-licensed employee supervisor had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The employee's access to the plant has been placed on hold. The NRC Resident Inspector has been notified.
ENS 538178 January 2019 08:12:00HatchNRC Region 2On November 12, 2018, at 1331 EST, Unit 1 secondary containment isolated and Standby Gas Treatment (SBGT) systems started on Unit 1 and Unit 2 due to a blown fuse. The blown fuse was caused by a degraded refuel floor radiation monitoring relay, causing the radiation monitor to trip and resulted in an invalid actuation of the Unit 1 Group 10 and Group 11 primary containment isolation valves, all Unit 1 secondary containment isolation valves, and auto start of the Unit 1 and Unit 2 SBGT system. The Unit 1 Fission Product Monitor isolated and tripped and both Unit 1 H202 Analyzers isolated. This event is reportable per 10 CFR 50.73(a)(2)(iv)(A) since the containment isolation and auto-start of SBGT on both units was not part of a pre-planned sequence and the event resulted in the invalid actuation of general containment isolation valves in more than one system. All primary and secondary containment isolation valves, with the exception of the 2T41F003A, Refueling Floor Inboard Vent Supply Isolation valve, functioned successfully. The refuel floor inboard vent supply isolation valve failed to travel fully closed on the secondary containment isolation signal and was therefore declared inoperable. The 2T41F003B refuel floor outboard vent supply isolation valve was verified to go fully closed and therefore isolation of that associated penetration line was successful. After assistance from maintenance, the valve was verified to be fully closed. All SBGT systems functioned successfully. The associated fuse and relay were replaced, and secondary containment was returned to normal service. The licensee notified the NRC Resident Inspector."
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 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 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 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 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 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 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 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 5281822 June 2017 09:32:00HatchNRC Region 2GE-4On April 27, 2017 at 0029 EDT, Unit 2 received an invalid partial Group 2 isolation due to a failed relay (2D11-K80) on the auxiliary trip unit. Both of the U1 and U2 Standby Gas Treatment (SGT) trains started and the U2 Group II primary containment and all secondary containment inboard isolation valves closed. Also, the refuel floor isolation dampers closed, the reactor building supply and exhaust fans tripped, and the refueling floor supply and exhaust fans tripped. This event is reportable per 10 CFR 50.73(a)(2)(iv)(A) since the containment isolation and auto-start of SGT on both units was not part of a pre-planned sequence and the event resulted in the invalid actuation of general containment isolation valves in more than one system. All primary and secondary containment inboard isolation valves and SGT systems functioned successfully. The failed relay was replaced and the systems were restored to normal alignment. The licensee will notify the NRC Resident Inspector.
ENS 5280314 June 2017 08:42:00HatchNRC Region 2GE-4On April 17, 2017 at 1120 EDT, following scheduled maintenance, the Reactor Protection System (RPS) 'A' bus was returned to its normal supply, the RPS 'A' motor generator (MG) set. The RPS MG set had been running loaded for 1 hour when the RPS 'A' bus tripped. Maintenance personnel had connected probes of a grounded oscilloscope to check for proper operation of the MG set, resulting in the RPS 'A' bus trip. The controlling procedure did not contain a caution about using only an ungrounded oscilloscope. The trip of the RPS 'A' MG set resulted in a half scram and an invalid isolation signal causing primary containment isolation valves in multiple systems to isolate. This event is reportable per 10 CFR 50.73 (a)(2)(iv)(A) since the containment isolation was not part of a pre-planned sequence and the event resulted in the invalid actuation of general containment isolation valves in more than one system. Corrective actions include revising the governing procedure with the proper precaution and limitation to require the use of an ungrounded oscilloscope. A training needs analysis will also be performed to cover the lessons learned from this event. The licensee notified the NRC Resident Inspector.
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 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 5270021 April 2017 05:41:00HatchNRC Region 2GE-4At 2345 (EDT) on 04/20/2017, the Unit 1 Reactor Mode Switch was taken to the Shutdown position to comply with Technical Specification 3.10.4 due to having no operable IRM's (Intermediate Range Monitors) in one quadrant of the reactor vessel as a result of maintenance activities. Placing the mode switch to Shutdown inserts a valid scram signal into the Reactor Protection System (RPS). All control rods had been previously inserted and no rod movement occurred when the mode switch was positioned to Shutdown. Due to this valid RPS scram, and not being a part of a preplanned evolution, this condition is reportable under criteria 50.72(b)(3)(iv)(A) as an event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. The licensee notified the NRC Resident Inspector.
ENS 5269620 April 2017 05:57:00HatchNRC Region 2GE-4On 04/20/2017 at 0302 EST during a reactor startup, a reactor scram resulted from upscale spike on two Intermediate Range Monitors (IRMs), 1C51K601A and 1C51K601B. IRM A, 1C51K601A is in Reactor Protection System Channel A and IRM B, 1C51K601B is in Reactor Protection System Channel B. All control rods fully inserted. No PCIS (Primary Containment Isolation System) actuations occurred and none were expected to occur based upon plant condition following the reactor scram. Investigation is in progress. Condition was not due to a true flux event. This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) as an event or condition that resulted in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. CR 10356172 The NRC Resident has been notified. The reactor was at 0.5% (percent) power at the time of the event and will remain in Hot Shutdown pending the results of the root cause investigation.
ENS 5268517 April 2017 13:35:00HatchNRC Region 2GE-4On February 17, 2017 at 1021 EST, secondary containment isolated and Standby Gas Treatment (SBGT) systems started on Unit 1 and Unit 2 during a maintenance activity to replace a relay in the Unit 2 primary containment isolation system. The work was being conducted as part of planned maintenance during the Unit 2 refueling outage. Poor work instruction led to a jumper not being installed as required, thus causing relays to de-energize, resulting in an invalid actuation of the Unit 1 and Unit 2 outboard primary and secondary containment isolation valves and auto-start of the Unit 1 and Unit 2 SBGT system. This event is reportable per 10 CFR 50.73(a)(2)(iv)(A) since the containment isolation and auto-start of SBGT on both units was not part of a pre-planned sequence and the event resulted in the invalid actuation of general containment isolation valves in more than one system. All primary and secondary containment isolation valves and SBGT systems functioned successfully. The associated wires were re-landed and secondary containment was returned to normal service. The licensee notified the NRC Resident Inspector.
ENS 5265030 March 2017 12:58:00HatchNRC Region 2GE-4During the evaluation of tornado missile vulnerabilities and the potential impacts to safety-related plant equipment, it was concluded that the following structures are vulnerable to tornado generated missiles: All five of the Unit 1 and Unit 2 Emergency Diesel Generator (EDG) fuel oil storage tanks have ventilation pipe extending approximately 5 feet above grade. In the event that a tornado missile impact occurs on the aforementioned ventilation piping, there is a possibility that the vent lines could crimp. This could prevent the tanks from venting and inhibit the transfer of fuel oil from the main fuel oil storage tanks to the day tank. Ultimately, this causes the emergency diesels to be inoperable. These conditions are reportable per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(D) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety and also an event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequence of an accident. This issue is being addressed in accordance with EGM-15-002, Revision 1, Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance. The NRC Resident Inspector has also been notified.
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 5256720 February 2017 01:14:00HatchNRC Region 2GE-4On 2/19/2017 at 2323 EST, during LLRT (local leak rate test) testing per 42SV-TET-001-2, 2T48F320 exceeded the maximum allowable leakage limit. The companion isolation valve in the same line (2T48F319) had previously failed LLRT. The failure of the 2T48F320 represents a failure of the 2T23X26 penetration to maintain primary containment integrity. This event is reportable per 10CFR50.72(b)(3)(ii)(A) since the failure of the 2T23X26 penetration caused primary containment leakage to exceed La (allowable leakage) and thus represents a degraded principle safety barrier. CR (condition report) 10333178. NRC Resident Inspector has been notified. 2T48F319 and 2T48F320 are 18 inch dampers. This event places the licensee in a Technical Specification limit that requires the dampers to be repaired and pass LLRT prior to the plant entering Mode 3.
ENS 5256317 February 2017 17:46:00HatchNRC Region 2GE-4On 2/17/2017 at 1414 EST, secondary containment was declared inoperable due to the discovery of an 18-inch open pipe penetration in the secondary containment boundary. During walkdown activities, it was discovered that a blind flange installed to support removal of a Unit 2 secondary containment isolation valve had been installed on the wrong flange to provide isolation for secondary containment. At 1503 EST, the blind flange was moved to the correct side of the flange and secondary containment was declared operable. This event is reportable per 10 CFR 50.72(b)(3)(v)(C) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system needed to control the release of radioactive material. In conjunction with operation of the Standby Gas Treatment (SGT) subsystems, secondary containment is designed to reduce the activity level of the fission products prior to release to the environment and to isolate and contain fission products that are released during certain operations. Therefore, the lack of a qualified isolation device to limit the release of radioactive material constitutes a loss of safety function due to a loss of secondary containment integrity. CR 10332592 The NRC Resident has been notified.
ENS 5255816 February 2017 17:28:00HatchNRC Region 2GE-4On February 16, 2017 at 1320 EST, the 2A Emergency Diesel Generator (EDG) started in response to a valid actuation signal due to the momentary loss of the 2C Startup Transformer (SAT). While performing maintenance activities on the 2D SAT, the alternate supply breaker tripped and reclosed, allowing the 4160 2E Emergency Bus to be momentarily de-energized. When the 4160 2E Emergency Bus de-energized, the 2A EDG received a valid autostart signal due to emergency bus low voltage. Although, the 2A EDG did autostart, it did not tie to the 4160 2E Emergency Bus as the 4160 2E Emergency Bus was re-energized from the 2C SAT. This event is reportable per 10 CFR 50.72(b)(3)(iv)(A) since the autostart of the 2A EDG was not part of a pre-planned sequence and the event resulted in the valid actuation of an emergency ac electrical power system. CR 10332134 The NRC Resident has been notified.
ENS 525438 February 2017 17:31:00HatchNRC Region 2GE-4During a control room panel walk down by an on-shift Reactor Operator at approximately 1151 (EST) on 2/8/2017, Unit 1 High Pressure Coolant Injection (HPCI) suction and discharge pressure indicators were noted to be downscale. I & C investigated and found the output of 1E41K603, DC to AC inverter, degraded. This inverter also powers the HPCI flow controller. Without the flow controller HPCI would not auto-start to mitigate the consequences of an accident, thus HPCI was declared inoperable. All other emergency core cooling systems and the Reactor Core Isolation Cooling (RCIC) system remain operable. HPCI is a single train system with no redundant equipment in the same system, thus this failure is reportable as an event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident, 10CFR50.72(b)(3)(v)(D). Inverter 1E41K603 was replaced and functionally tested satisfactorily at 1630 on 2/8/2017, restoring HPCI to operable status. The NRC Resident Inspector was 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 525313 February 2017 16:33:00HatchNRC Region 2GE-4In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10CFR50.48(b) (Appendix R) to 10CFR50.48(c) (NFPA 805), a weak-link and operator manual action (OMA) analysis for Information Notice (IN) 92-18 type hot shorts on motor-operated valves (MOVs) was performed to support the Plant Hatch Appendix R Safe Shutdown Analysis. As a result of the analysis, it was identified that cable impacts can bypass valve limit and torque switches, resulting in physical damage to valves required for Safe Shutdown. This would prevent the valves from being operated locally or being operated from the remote shutdown panel. These cable failures could also cause the valve motors to fail. This updated analysis has identified circuit configuration deficiencies in Fire Areas 0024 A & C (Main Control Room & Cable Spread Room), 1203F (U1 Reactor Building SE), 1205F (U1 Reactor Building NE), and 2203F (U2 Reactor Building NE). Therefore, due to the identified deficient conditions, it was determined that in the event of a postulated fire in the affected fire areas, the paths of safe shutdown on the affected unit(s) could be compromised and impact the ability to achieve safe shutdown conditions. Compensatory measures were already in place in accordance with the plant's Fire Hazard Analysis (FHA) as a result of previous conditions in these same fire areas. The presence of the compensatory measures in addition to automatic fire detection in these fire areas ensure that the safe shutdown paths are preserved until the degraded conditions can be repaired. CRs 10326399, 10326401, 10326402, 10326404 and 10326405 The licensee notified the NRC Resident Inspector. The unanalyzed condition is applicable to 10CFR50.48(b) Appendix R and not to 10CFR50.48(c) (NFPA 805).
ENS 525261 February 2017 16:46:00HatchNRC Region 2GE-4

Plant Hatch declared a notification of unusual event. Subsequent investigation determined the paraphernalia was related to plant drills. The Unusual Event was terminated at 1727 EST. The licensee notified the NRC Resident Inspector. Notified the DHS SWO, FEMA, NICC, and NNSA (via e-mail).

  • * * RETRACTION FROM KENNETH HUNTER TO MARK ABRAMOVITZ AT 1829 EST ON 2/1/2017 * * *

The event was retracted. The licensee notified the NRC Resident Inspector. Notified the R2DO (Shakur), NSIR (Holian), IRD MOC (Gott), DHS SWO, FEMA, NICC, and NNSA (via e-mail).