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 Entered dateSiteRegionScramReactor typeEvent description
ENS 5395424 March 2019 17:40:00Indian PointNRC Region 1Automatic ScramOn March 24, 2019, at 1445 EDT, Indian Point Unit 2 automatically tripped on a turbine trip due to a loss of excitation. All control rods fully inserted and plant equipment responded normally to the unit trip. This RPS (reactor protection system) actuation is reportable under 10 CFR 50.72(b)(2)(iv)(B). The auxiliary feedwater system actuated following the automatic trip as expected. This specified system actuation is reportable under 10 CFR 50.72(b)(3)(iv)(A). During the event offsite power remained available and stable. No primary or secondary reliefs lifted. Unit 2 is in Mode 3 at normal operating temperature and pressure. Decay heat removal is via the steam generators to the atmospheric steam dumps. No radiation was released. Indian Point Unit 3 was unaffected by this event and remains defueled in a scheduled refueling outage. A post trip investigation is in progress. The licensee has notified the NRC Resident Inspector The New York State Public Service Commission, Consolidated Edison System Operator, and New York State Independent System Operator were also notified.
ENS 5393715 March 2019 13:39:00Indian PointNRC Region 1Automatic ScramOn March 15, 2019 at 1300 EDT, Indian Point Unit 2 automatically tripped offline from mode 1 - 100% power operations. Reactor Operators verified the reactor trip and the plant is currently stable in mode 3. All automatic systems functioned as required. The auxiliary feedwater system actuated following the trip, as expected. All control rods fully inserted upon the trip, as expected. This event is reportable under 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(2)(iv)(B). The unit remains on offsite power in hot standby at normal operating temperature and pressure. Decay heat is being removed from the steam generators via the auxiliary feedwater system and the condensate steam dump valves. Unit 3 remains in mode 6 for a scheduled refueling outage. The licensee notified the NRC Resident Inspector, the local transmission company, and New York State Independent System Operator. The Indian Point Unit 2 automatic trip was caused by the trip of the main generator. The cause of the generator trip is unknown at this time.
ENS 5361118 September 2018 09:06:00Indian PointNRC Region 1Manual ScramDue to a steam leak on the reheater line to 36C Feedwater Heater, operators initiated a manual trip of the reactor, verified the reactor trip, and closed all Main Steam Isolation Valves. The plant is currently stable in Mode 3 with the steam leak isolated. The Auxiliary Feedwater System actuated following the trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(2)(iv)(B). The unit remains on offsite power in Hot Standby at normal operating temperature and pressure. Decay heat is being removed from the steam generators via the Auxiliary Feedwater System and atmospheric steam dumps. Unit 2 was unaffected and remains at 100 percent power. The licensee notified the NRC Resident Inspector, the State of New York, and the local transmission company.
ENS 5334819 April 2018 23:41:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopWhile performing a turbine startup, a turbine control anomaly caused a steam generator level transient. The rise in steam generator level above the setpoint caused the turbine to automatically trip. The high steam generator level of 73 percent caused a feedwater isolation signal at 2107 EDT, which also tripped both Main Boiler Feed Pumps. The tripping of the Main Boiler Feed Pumps auto started the motor driven Aux Boiler Feed Pumps 21 and 23. The reactor was manually tripped at 2108 EDT in accordance with AOP-FW-1 Loss of Main Feedwater. All control rods inserted. Electrical power is being provided from offsite via the Station Aux Transformer. Decay heat removal is being provided via the Atmospheric Dump Valves. An investigation into the cause of the turbine control anomaly is underway. The NRC Resident Inspector has been notified. The event did not have an affect on Unit 3 and there is no primary to secondary leakage.
ENS 5321616 February 2018 04:43:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn February 16, 2018 at 02:01 EST Indian Point Unit 3 automatically tripped on a turbine trip due to a loss of main generator excitation. All control rods fully inserted and all plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). The auxiliary feedwater system actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). During the event offsite power remained available and stable. No primary or secondary reliefs lifted. The plant is stable, in Mode 3, at no load operating temperature and pressure. Decay heat removal is via the steam generators to the main condenser via the condenser steam dumps. No radiation was released. Indian Point Unit 2 was unaffected by this event and remains at 100 percent power. A post trip investigation is in progress. The licensee has notified the NRC Resident Inspector.
ENS 530523 November 2017 21:08:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-Loop

On November 3rd, 2017 at 2022 EDT, the Indian Point Unit 3 Reactor Protection system automatically actuated at 100 percent power. Annunciator first out indication was from 33 SG (Steam Generator) Low Level. This automatic reactor trip is reportable to the NRC under 10 CFR 50.72(b)(2)(iv)(B). All control rods fully inserted on the reactor trip. All safety systems responded as expected. The Auxiliary Feedwater System actuated as expected. Offsite power and plant electrical lineups are normal. All plant equipment responded normally to the unit trip. No primary or secondary code safeties lifted during the trip. The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The Unit remains on offsite power and all electrical loads are stable. Unit 3 is in Hot Standby at normal operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the condenser via the high pressure steam dumps. Unit 2 was unaffected and remains at 100 percent power. A post trip investigation is in progress. The licensee indicated that Radiation Monitor number 14 spiked twice during the transient, however, is currently not indicating any signs of radiation. The licensee will notify the NRC Resident Inspector and the NY Public Service Commission.

  • * * UPDATE AT 1523 EST ON 11/06/17 FROM RAMIREZ OVIDIO TO JEFF HERRERA * * *

The initial notification stated that Indian Point Unit 3 Reactor Tripped on 33 SG (Steam Generator) Low Level, this is incorrect. Indian Point Unit 3 Reactor Tripped on a Turbine Trip. The Turbine Trip was caused by a Generator Back-up Lockout Relay. The Turbine Trip was the 'first' annunciator first-out but was acknowledged instead of silenced during initial operator actions. The Turbine Trip first-out being acknowledged allowed a Low Steam Generator first-out to later annunciate. A Low Steam Generator Level is an expected condition post trip. This update does not change any actions taken by the operating team or required notifications under 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). A post trip investigation remains in progress. The licensee will notify the NRC Resident Inspector and the NY Public Commission. Notified the R1DO(Cook)

ENS 5282926 June 2017 18:39:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopOn June 26, 2017, at 1531 (EDT), Indian Point Unit 2 inserted a manual reactor trip prior to Steam Generator levels reaching the automatic reactor trip setpoint. Steam Generator water level perturbation resulted from a loss of 22 Main Boiler Feed Pump. All Control Rods verified inserted. The Auxiliary Feedwater System started as designed and supplied feedwater to the Steam Generators. Heat removal is via the Main Condenser through the High Pressure Steam Dumps. Offsite power is being supplied through the normal 138kV feeder 95332. The cause of the 22 Main Boiler Feed Pump loss is currently under investigation. Entergy is issuing a press release/news release on this issue. Unit 2 is stable and in Mode 3. There was no impact on Unit 3. The licensee notified the State of New York and the NRC Resident Inspector.
ENS 520676 July 2016 13:16:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn July 6, 2016 at 0938 EDT Indian Point Unit 2 experienced a trip from 100% steady state power during the performance of reactor protection testing. The cause of the trip is under investigation. All control rods fully inserted and all systems responded as expected. The auxiliary feedwater system actuated as expected on a low level in the steam generators which occurs as a result of a trip from full power. Auxiliary feedwater is maintaining steam generator levels and decay heat removal is via the steam generators to the main condenser. Offsite power and plant electrical line ups are normal with the exception of 13.8kV feeder 33332 which remains out of service during the replacement of breaker BT4-5. No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable. Indian Point Unit 3 was unaffected and remains at 100% steady state power. The NRC Resident Inspector has been notified. The licensee notified the New York Public Service Commission and the New York Independent System Operator. Indian Point indicated they have issued a press release regarding the event.
ENS 5160614 December 2015 19:49:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopAt 1906 (EST) on 12/14/2015, Indian Point Unit 3 received a Main Generator Lockout trip signal, and the reactor automatically tripped. Site personnel reported seeing arcing on a 345kV output transmission line tower. At the time of the trip, there was moderate rain and fog in the area. The site fire brigade leader investigated the reports of arcing and found no evidence of fire; fire brigade response was not required. All automatic systems functioned as designed and all control rods inserted automatically. Auxiliary Feedwater Pumps started automatically due to expected low steam generator levels following a reactor trip from 100% power. Unit 3 is being maintained in Mode 3 with decay heat removal via steam dumps to the condenser. Offsite power remains available and in service from 138kV to the 480V safeguards buses. The cause of the Main Generator Lockout signal is being investigated. Unit 2 was not impacted and continues to operate at 100% power. The NRC Resident Inspector has been notified. After the trip, operators observed high vibrations on the 33 reactor coolant pump which eventually returned to normal range. The licensee will be notifying the New York Public Service Commission and their local Independent System Operator. A press release will be issued by the Communications Department.
ENS 515865 December 2015 18:48:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopAt 1731 (EST) on December 5, 2015, Indian Point Unit 2 Control Room operators initiated a Manual Reactor Trip due to indications of multiple dropped Control Rods. The initiating event was a smoldering Motor Control Center (MCC) cubicle in the Turbine Building that supplies power to the Rod Control System. The unit is stable in Mode 3 with heat sink provided by Auxiliary Feedwater and decay heat removal is via the steam dumps to the condenser. Offsite Power remains in service. The smoldering MCC cubicle had power removed from it when 24 MCC breaker tripped on overcurrent. The affected cubicle has ceased smoldering and is being monitored by on-site Fire Brigade trained personnel. The trip of 24 MCC removed power to 22 Battery Charger, 22 DC Bus remained powered from the 22 Battery without interruption, and 22 Battery Charger was subsequently repowered. The cause of the smoldering MCC is being investigated and a post reactor trip evaluation is being conducted by the licensee. There was no impact on Unit 3, which continues to operate at 100% power. The licensee has notified the NRC Resident Inspector and appropriate State and Local authorities.
ENS 512118 July 2015 15:37:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopIndian Point Unit 3 was manually tripped at 1427 EDT due to lowering steam generator water levels. At 1425 EDT, #31 condensate pump tripped, causing the lowering water levels. There were no immediate complications on the trip and the unit is stable in Mode 3. Auxiliary feedwater actuated as expected and is in service. All rods inserted and decay heat is being rejected to the condensers. Offsite electrical power is in service. Unit 2 is stable at 100% power. The licensee plans on issuing a press release. The licensee notified the NRC Resident Inspector and New York Public Service Commission.
ENS 510609 May 2015 18:19:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-Loop

At 1750 EDT (05/09/15,) Indian Point Unit 3 experienced a fire on the 31 Main Transformer resulting in a unit trip. An Unusual Event was declared at 1801 EDT. The onsite fire brigade was mobilized. Offsite fire fighting assistance was requested. The fire was reported extinguished at 1815 EDT. The reactor was shutdown by an automatic trip. Plant response to the trip was as expected with no complications. The 31 and 33 Auxiliary Feed Pumps are operating and feeding the steam generators. Accountability is being performed. The plant is stable in mode 3, all control rods fully inserted, with normal offsite electrical power, and decay heat is being released to the main condenser. There was no impact on Unit 2 which continues to operate at 100% power. The licensee has notified the NRC Resident Inspector and state and local authorities. Notified DHS SWO, FEMA OPS Center, DHS NICC Watch Officer, and Nuclear SSA via email.

  • * * UPDATE FROM LUKE HEDGES TO JOHN SHOEMAKER AT 2037 ON 5/9/15 * * *

Oil from 31 Main Transformer has spilled into the discharge canal and has made its way into the river. Plant personnel are sandbagging drains and release paths. IPEC (Indian Point Energy Center) has contacted its environmental contractor, who is expected onsite at 2100 EDT to assist with cleanup. The National Response Center was notified at 1945 EDT and issued notification number 1116011. A message was left with the Westchester County Department of Health at 1953 EDT. The NY State DEC (Department of Environment Conservation) was contacted at 1955 EDT and issued notification number 1501459. The licensee has notified the NRC Resident Inspector. Indian Point Unit 3 remains in an Unusual Event at this time. Notified R1DO (Schroeder).

  • * * UPDATE FROM LUKE HEDGES TO JOHN SHOEMAKER AT 2141 ON 5/9/15 * * *

Indian Point Unit 3 exited the Unusual Event at 2103 EDT. The basis for exiting the Unusual Event is that the fire is out and field operators report they have been successful in cooling the transformer. The licensee has notified the NRC Resident Inspector and state and local authorities. Notified R1DO (Schroeder), R1RA (Lew), NRR (Dean), NRR EO (Morris), NRR EO (Howe), and IRD (Grant). Notified DHS SWO, FEMA OPS Center, DHS NICC Watch Officer, and Nuclear SSA via email.

ENS 5036113 August 2014 13:06:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn August 13, 2014 at 1157 EDT, the Indian Point Unit 3 Reactor Protection System automatically actuated at 100% power due to Over Temperature Delta Temperature logic. At the time of the trip, pressurizer pressure Channel 1 was in test for maintenance, though testing was suspended at this time for lunch. All control rods fully inserted on the reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). The plant is stable in Mode 3 at this time. The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators, and normal heat removal through the condenser via condenser steam dumps. There was no radiation released. Indian Point Unit 2 was not affected by this event and remains at 100% power. A post trip investigation is in progress. The licensee notified the NRC Resident Inspector.
ENS 496986 January 2014 21:55:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn January 6th, 2014 at 2115 EST Indian Point Unit 3 experienced an Automatic Reactor Trip due to '33 Steam Generator Steam flow/Feed flow Mismatch.' Operators entered emergency procedure E-0, Reactor Trip or Safety Injection. All control rods fully inserted, all safety systems responded as expected, and off-site power remained in-service. No primary or secondary safety valves actuated due to the trip. This is reportable under 10CFR50.72(b)(2)(iv)(B). The main condenser is being used for heat sink. Unit 2 remains stable at 100% power. The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10CFR50.72(b)(3)(iv)(A). Investigation is underway to determine the cause of the 33 Steam Generator Mismatch condition. The licensee will inform local and other government agencies and issue a press release. The licensee has informed the State of New York and the NRC Resident Inspector.
ENS 491713 July 2013 10:46:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopOn July 3, 2013, at 0741 EST, the Indian Point Unit 2 CCR received a trip of both Main Boiler Feed Pumps (MBFP) and entered 2--1, Loss of Feedwater. The unit was manually tripped at 0741 per 2-AOP--O, Reactor Trip or Safety Injection. All control rods fully inserted. All safety systems responded as expected. The Auxiliary Feedwater (AFW) System actuated as expected. Offsite power and plant electrical lineups are normal. No primary or secondary code safety valves lifted. The 23 and 24 Main Steam Isolation Valves (MSIV) failed closed as a result of the loss of Instrument Air (IA). The 21 and 22 MSIVs remain open with the Main Condensers being used for heat sink. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power. Preliminary investigations determined a two inch copper IA line in the switchyard which is normally buried had a failed coupling causing loss of IA to the main feedwater regulating valves. The IA line traversed an excavated area of the switchyard going to the Auxiliary Boiler Feed Pump (ABFP) Building. AFW operated using the Nitrogen backup supply to ABFP control valves until Instrument Air was restored to the ABFP building. An investigation is in progress. The licensee notified the NRC Resident Inspector.
ENS 4875013 February 2013 16:41:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopAt 1352 (hrs. EST), the Unit 2 CCR (Central Control Room) noted a trip of both heater drain tank pumps and entered Abnormal Operating Procedure 2-AOP-FW-1, 'Loss of Feedwater'. Prior to the event, Instrumentation and Controls personnel were performing testing on the heater drain tank level control system. Turbine load was reduced per plant procedures, however a manual reactor trip was initiated at 1355 due to an inability to maintain steam generator water levels. The team subsequently entered E-0, 'Reactor Trip or Safety Injection'. All control rods fully inserted. All safety systems responded as expected with the exception of source range detector N-31 and intermediate range detector N-35. N-31 and N-35 were declared inoperable. The auxiliary feedwater system actuated as expected and provided feedwater to maintain steam generator water level. Decay heat removal is via the steam generators to the main condensers. Offsite power and plant electrical lineups are normal. No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power. An investigation is in progress. Unit 2 is currently at normal operating pressure and temperature. The licensee plans to issue a press release on this event. The licensee notified the State of New York Public Service Commission and the NRC Resident Inspector.
ENS 4845430 October 2012 00:30:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn October 29, 2012, at 2241EDT, the Reactor Protection System automatically actuated at 100% reactor power due to a direct electrical trip to the Unit 3 Main Turbine Generator. The generator trip resulted in a turbine/reactor trip. All control rods fully inserted on the reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). The plant is stable in Mode 3 at this time. The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal operating temperature and pressure with decay heat removal using auxiliary feedwater to the steam generators and normal heat removal through the condenser via condenser steam dumps. There was no radiation released. Indian Point Unit 2 was not affected by this event and remains at 100% power. A post trip investigation is in progress. The licensee notified the NRC Resident Inspector.
ENS 479996 June 2012 09:38:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn June 6, 2012, at approximately 0612 hours, Indian Point Unit 2 reactor automatically tripped from 100% steady state power due to a turbine-main generator electrical trip. All rods fully inserted. Investigation into the generator trip is in progress. All systems responded as expected. The Auxiliary Feedwater system actuated and responded as expected and is maintaining steam generator levels. Decay heat removal is via the steam generators to the main condenser. Offsite power and plant electrical lineups are normal. No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power. The NRC Resident Inspector has been notified, and the licensee issued a press release.
ENS 4758210 January 2012 04:49:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-Loop

Plant shutdown from 100% due to increased leakage from 21 RCP (Reactor Coolant Pump) seal return was commenced at 0100 EST. A manual reactor trip was actuated in accordance with plant procedures at 25% power. Auxiliary feedwater pump was placed in service prior to the reactor trip, per plant procedures. Decay heat is being removed via the condenser steam dumps. All offsite power sources are available. All equipment operated as expected. The licensee has notified the NRC Resident Inspector and other government agencies.

  • * * RETRACTION FROM CHARLES ROKES TO HOWIE CROUCH AT 0940 EST ON 2/15/12 * * *

Subsequent review concluded the condition did not meet reporting criteria. A normal plant shutdown was initiated in accordance with plant procedures for a known problem with the 21 RCP # 1 seal whose seal leakoff rate had reached an administrative alarm limit. Shutdown was not required by the Technical Specifications. On January 10, 2012, at 0100 hours (EST) a plant shutdown commenced per plant operating procedure 2-POP-2.1. At 0436 hours, the reactor was manually tripped in accordance with procedure 2-POP-3.1. This event is not reportable as the reactor trip was part of a normal shutdown for corrective maintenance. The licensee has notified the NRC Resident Inspector. Notified R1DO (Powell).

ENS 464007 November 2010 19:07:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-Loop

At 1849 EST, the licensee declared an Alert due to an explosion in the 21 Main Transformer. As a result of the loss of the transformer, Unit 2 experienced a reactor trip. Plant response to the trip was normal and the plant is stable in Mode 3. At 1839 hrs., the licensee activated their Emergency Response Organization. Additionally, there was a report of smoke issuing from a metering station at the site boundary. Offsite assistance has been requested to investigate the metering station. No injuries were reported and the licensee is investigating whether any other equipment damage occurred as a result of the transformer failure.

  • * * UPDATE FROM NICK LIZZO TO HOWIE CROUCH AT 2200 EST ON 11/07/10 * * *

On November 7, 2010, at 1839 hours, the Reactor Protection System automatically actuated at 100% Reactor Power when the 21 Main Transformer failed. The failure resulted in a turbine / reactor trip. All plant equipment responded normally to the unit trip. This is reportable under 10 CFR 50.72(b)(2)(iv). The transformer failure was characterized as an explosion that meets the IPEC (Indian Point Energy Center) EAL criteria 8.2.3. An Alert was declared at 1849 hours. The plant is stable in Mode 3 at this time. The Auxiliary Feedwater System actuated following the manual trip, as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). The Emergency Diesel Generators did not start as offsite power remained available and stable. The Station Auxiliary Transformer tap changer has remained at the maximum tap changer position and is inoperable, however the unit remains on offsite power and all electrical loads are stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal temperature and pressure with residual heat removal using auxiliary feedwater and normal heat removal through the condenser via steam dumps. There was no radiation released. Indian Point Unit Three was not affected by this event and remains at 100% power. A post trip investigation is in progress. A one hour notification of the Alert Declaration was made to the NRC Emergency Operations Duty Center officer Howie Crouch at 1907 (hrs. EST). The licensee has notified the NRC Resident Inspector, the New York State Public Service Commission, New York State EMA and local county officials. Notified R1DO (White).

  • * * UPDATE FROM CHARLES LAVERDE TO HOWIE CROUCH AT 2230 EST ON 11/07/10 * * *

At 2218 EST, the licensee exited the Alert emergency declaration. The exit criteria was that: 1) The plant was in or was proceeding to cold shutdown, 2) No radiation release was in progress or anticipated 3) All radiation levels in the plant were stable or decreasing, and 4) No limitation on access to all plant areas. The licensee has notified the NRC Resident Inspector. Notified IRD (Gott), R1DO (White), NRR EO (Bahadur), FEMA (Heyman), DHS (Doyle), HHS (Gruenspecht), USDA (John) and DOE (Turner).

  • * * UPDATE ON 11/8/2010 AT 1228 FROM MICHAEL McCARTHY TO MARK ABRAMOVITZ * * *

Approximately 50-100 gallons of oil from the transformer reached the Hudson River. The licensee notified the National Response Center and the New York State Department of Environmental Conservation. The licensee notified the NRC Resident Inspector. Notified the R1DO (White).

ENS 4624110 September 2010 00:29:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopOn September 9, 2010, at approximately 2129 hours (EDT), Indian Point 3 manually tripped the reactor from the control room following indications of a service water leak in the Main Generator Exciter housing. Unit 3 is currently stable in mode 3. All automatic actions occurred as required. All control rods fully inserted. No primary or steam generator safety relief valves lifted. The motor driven auxiliary feedwater pumps automatically started on low steam generator level as designed. Decay heat removal is via the steam generators to the main condenser. Offsite power is available and supplying all safeguards busses. Unit 2 is unaffected and remains in Mode 5 in a forced outage for 21 RCP (Reactor Coolant Pump) repair. During the Fast Bus Transfer (the) 34 Reactor Coolant Pump tripped. The cause is being investigated. There was an inadvertent release of CO2 to 31 Main Boiler Feed Pump. The cause was due to the suction relief valve lifting which has subsequently reseated. The NRC Sr. Resident Inspector and New York State Public Service Commission have been notified. The reactor is currently being maintained at normal operating temperature and pressure.
ENS 462293 September 2010 13:11:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-Loop

UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP DUE TO HIGH STEAM GENERATOR LEVEL

On September 3, 2010, at approximately 1058 hrs., Indian Point Unit 2 automatically tripped from 41% power due to High Steam Generator Level. At the time of the trip, Unit 2 was performing a power reduction to take the unit offline for a planned maintenance outage. Unit 2 is currently stable in Mode 3. All automatic actions occurred as required. All control rods fully inserted with the exception of rod H-8 - which indicates 26 inches withdrawn. No primary or steam generator safety or relief valves lifted. The motor driven auxiliary feedwater pumps automatically started on low steam generator level as designed. Decay heat removal is via the steam generators to the main condenser. Offsite power is available and supplying all safeguards busses.

The cause of the trip and rod H-8 position indication are under investigation.

Unit 3 is unaffected and remains in Mode 1 at 100% power.

The NRC Resident Inspector has been notified.

Offsite notification was made to the State of New York.

No press releases are planned.

ENS 4562411 January 2010 18:31:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopAt 1559 on January 11, 2010, Indian Point Unit 2 tripped from 100% power due to a main generator electrical trip. The investigation into the generator trip is ongoing. All systems responded as expected. The auxiliary feedwater system responded as expected and is maintaining steam generator water levels. Decay heat removal is via the steam generators to the main condenser. Offsite power and plant electrical lineups are normal. No primary or secondary side relief valves lifted. The reactor plant is in mode 3 and stable. Indian Point Unit 3 was not affected and remains at 100% power. The licensee notified the NRC Resident Inspector and the N.Y. State Public Service Commission. The licensee intends to notify the Mayor's Office and issue a press release.
ENS 4530627 August 2009 21:40:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopAt 1945 on 8/27/09 Indian Point Unit #3 automatically tripped due to a turbine trip signal. The cause for this automatic trip is under investigation. All auxiliary feedwater pumps started as expected. All control rods inserted as expected. Currently, Indian Point #3 is in Mode 3. The reactor coolant system is at Normal Operating Temperature, Pressure and Level. Offsite power is available and supplying all safeguards busses. Heat removal is to the main condenser via the steam dumps. Indian Point Unit 2 is unaffected and remains in Mode 1 at 100% power. The (NRC) Resident Inspector has been notified.
ENS 4509828 May 2009 07:12:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopAt 0530 EDT a power reduction commenced due to elevated vibrations on 32 MBFP (Main Boiler Feedwater Pump). When reactor power reached 60% the team was attempting to stabilize reactor power when a level excursion occurred in 32 steam generator. When level reached its high level turbine trip set point an automatic reactor trip occurred and all systems responded as expected. Auxiliary feedwater actuated as expected. The Unit is currently in mode 3 and stable with auxiliary feed water in service and reactor temperature maintained with the steam dumps to the main condenser. Investigation into the cause of the steam generator level excursion is in progress. Offsite power is available and supplying safeguard busses. Unit 2 was unaffected and remains at 100% power. The (NRC) Resident Inspector has been notified. No safety or relief valves lifted during this event.
ENS 4506915 May 2009 03:58:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopOn May 15, 2009 Indian Point Unit 3 initiated a manual Reactor Trip at 0153 in response to a failure of 33 Main Feed Regulating Valve. 33 Main Feed Regulating Valve failed open causing 33 Steam Generator Level to rise. A manual Reactor Trip signal was inserted when it was determined that the level rise in 33 Steam Generator could not be corrected. As a result of the reactor trip, the Auxiliary Feedwater System automatically actuated per plant design. Unit 3 is currently in Mode 3. This results in a condition that resulted in an actuation of the Reactor Protection System which is reportable under 10 CFR 50.72(b)(2)(iv)(B). The valid actuation of the Auxiliary Feedwater System is reportable under 10 CFR 50.72(b)(3)(iv)(A). All rods inserted during the trip. There were no relief or safety valves that lifted during the transient. The electrical grid is stable and is in the normal shutdown electrical lineup. The plant is being maintained at normal operating temperature and pressure using steam dumps to condenser to remove decay heat. Unit 2 was not affected by the trip. The licensee notified the New York Public Service Commission and the NRC Resident Inspector.
ENS 449673 April 2009 13:40:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopAt 1136 hours on April 3, 2009 with the plant in mode 1, Indian Point Energy Center Unit 2 experienced a 21 Main Boiler Feed Pump (MBFP) trip. Following the MBFP trip the turbine runback circuit did not actuate as expected. The plant operators attempted to perform a manual main turbine runback and inserted a manual reactor trip based on the impending trip signal of Steam Generator low level. Auxiliary feedwater automatically started as expected. Troubleshooting of the cause of the transient is in progress. Unit 2 is stable in mode 3 with AFW in service. Heat removal is to the main condenser via the steam dumps. Offsite power is available and supplying all safeguards busses. Unit 3 is not affected and remains in mode 6 for 3R15. The (NRC) Resident Inspector has been notified.
ENS 4415321 April 2008 14:24:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopOn April 21 2008, at approximately 1123 hours, during power ascension from a scheduled refueling outage, Unit 2 experienced an inadvertent main turbine runback. The runback initiated for unknown reasons from an initial reactor power of approximately 37%. As a result of the runback, operators observed decreasing steam generator levels and initiated a manual reactor trip at 1125 hours. As a result of the reactor trip, the auxiliary feedwater pumps actuated on a low steam generator level as designed. Prior to the runback, one of two main feedwater pumps was operating. The unit is stable and in Mode 3. Operators closed the main steam isolation valves as a result of indications of lowering RCS temperature. A 4-hour non-emergency notification is provided for a reactor trip while critical and 8 hour non-emergency notification is provided for a valid actuation of the auxiliary feedwater system. All rods inserted as expected. Decay heat is being removed by AFW through the atmospheric steam dumps. Offsite power is in a normal configuration. The licensee notified the NRC Resident Inspector.
ENS 4408924 March 2008 01:56:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopThe Indian Point Unit 2 reactor was manually tripped from 94% power at 2216 on 3/23/08 due to a loss of speed on 22 main boiler feed pump (MBFP). Indian Point Unit 2 is currently in mode 3 with all automatic actions for a manual reactor trip occurring as required. Indian Point Unit 2 was in a coast down in advance of a scheduled refueling outage. The reactor was manually tripped as required by abnormal operating procedure 2-AOP-FW-001. All control rods inserted on the trip. No safety or relief valves lifted due to the trip. The motor driven aux feedwater pumps automatically started on low steam generator level and are being used to maintain steam generator level. Condenser steam dumps are maintaining reactor temperature. The Unit 2 electrical lineup is the normal shutdown electrical lineup. The licensee has notified the state Public Service Commission. Unit 3 was unaffected and remains in mode 1 at 100% power. The licensee has notified the NRC Resident Inspector. The licensee expects to issue a media release.
ENS 432723 April 2007 05:07:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopThe Indian Point Unit 3 reactor was manually tripped at 04:16 on 4/3/2007 due to low steam generator levels that occurred while the 31 MBFP (main boiler feed pump) speed control was being isolated for maintenance. Indian Point Unit 3 is currently in mode 3 with all automatic actions for a manual reactor trip occurring as required. Unit 2 was unaffected and remains in mode 1 at 100% power. The reactor was manually tripped when steam generator levels reduced to 18% in all four steam generators. All rods inserted on the trip. No safety or relief valves lifted due to the trip. The motor driven aux feedwater pumps automatically started on low steam generator level and are being used to maintain steam generator level. Atmospheric steam dumps are maintaining reactor temperature. The Unit 3 electrical lineup is the normal shutdown electrical lineup. The licensee has notified the state Public Service Commission. The licensee will notify the NRC Resident Inspector.
ENS 4319928 February 2007 10:01:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopAt approximately 0633 AM on February 28, 2007, control room operators manually initiated a reactor trip after observing decreasing steam generator levels as a result of low feed water flow. Control room alarms indicated low main feed water pump suction pressure which was subsequently, attributed to a malfunction of the main feed water pump low suction pressure cutback pressure transmitter (PT-408B) on the common main feed pump water supply header. The malfunction of the main feed pump water low suction cutback pressure transmitter resulted in a cutback of both main feed water pumps reducing main feed water flow to the steam generators and causing decreasing steam generator levels. All control rods fully inserted and all safety systems responded as expected. The auxiliary feedwater system actuated as expected from low steam generator levels which occurs as a result of a full power reactor trip. The emergency diesel generators (EDGs) did not start as offsite power remained available. The plant was stabilized in hot shutdown with the (Auxiliary Feedwater System) providing decay heat removal via the main condenser. The main feed water pumps are shutoff and secured. The event is under investigation and a post trip review is being conducted. A courtesy call to stakeholders will be made. All EDGs remain available in standby. No steam generator Power Operated Relief Valves or Main Steam Safety Valves lifted. The licensee notified state and will notify local authorities. The licensee plans to issue a press release. The licensee notified the NRC Resident Inspector.
ENS 4299315 November 2006 16:26:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn November 15, 2006, at 14:00 hours, an automatic reactor trip occurred during troubleshooting of the Main Generator Exciter Generrex power supply, when an electrical spike resulted in a turbine trip which caused a reactor trip. All control rods fully inserted and safety equipment operated as expected. The Auxiliary Feedwater (AFW) System actuated as expected as a result of a low steam generator level from the reactor trip and started the motor driven AFW pumps. The Emergency Diesel Generators did not start as offsite power remained available. The plant was stabilized in hot standby with decay heat being removed by the main condenser. There were no radiation releases. The condition is under investigation and a post trip review is being conducted. No PORVs or SG safety valves lifted during the event. The electrical plant is in a normal shutdown lineup and the EDGs are operable in standby. There was no affect on Unit 3 operation due to this event. The licensee notified the NRC Resident Inspector, and stated that IPEC communications has transmitted an IPEC Status Report which provides a status to local, state, and federal agencies.
ENS 4279723 August 2006 13:19:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-Loop

On August 23, 2006, at 1035 hours, the Reactor Protection System was manually actuated while at reduced load of approximately 68 percent reactor power upon indication of an apparent disparity in net electric load. It was determined that the cyclic operation of the condenser steam dumps varied steam to the turbine resulting in the indicated drop in electrical output power from about 500 Mwe to 150 Mwe. The manual trip is reportable under 10 CFR 50.72(b)(2)(iv). The event started when heater drain tank pumps 21 and 22 tripped, apparently due to a failure of the automatic heater drain level control valves that could not be manually corrected from the single controller. Reactor operators reduced load in accordance with station procedures to respond to the trip of the heater drain tank pumps and stabilized reactor power at 77%. As a result of the required load reduction delta flux was outside of the operational limit envelope specified at 77% reactor power. This required a further load reduction to less than 50 percent as per Technical Specification 3.2.3. At approximately 68% percent power the reactor was manually tripped due to the mismatch of primary power and secondary load indications. The Auxiliary Feedwater System actuated following the manual trip as expected. This is reportable under 10 CFR 50.72(b)(3)(iv)(A). A high-high water level signal was received on the 22 Steam Generator. This was due to a feedwater regulating valve that did not fully close. The feedwater isolation valves closed. All other safety systems actuated as required and safety equipment operated as expected. The Emergency Diesel Generators did not start as offsite power remained available and stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal temperature and pressure with residual heat removal using auxiliary feedwater and normal heat removal through the condenser via steam dumps. There was no radiation released. A post trip investigation will be performed prior to restart. The licensee notified the NRC Resident Inspector.

      • UPDATE FROM GEORGE DAHL TO JOHN KNOKE AT 1830 EDT ON 08/23/06 ***

This is an update of non-emergency Event Notification 42797 that was previously made on August 23, 2006. Clarification is provided to include reporting of the Event Classification for actuation of a second system (automatic feedwater isolation) as an 8-Hr. Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A). This update revises the wording as follows: The feedwater isolation valve was manually closed. After receipt of the high-high level trip signal, 21, 23, and 24 feedwater isolation valves automatically closed. This is also reportable under 10 CFR 50.72(b)(3)(iv)(A). The licensee notified the NRC Resident Inspector. Notified R1DO (Conte).

ENS 4272021 July 2006 11:06:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-Loop

At 1031 hours on July 21, 2006, the reactor operator manually tripped the reactor from 100% power resulting in turbine trip and actuation of auxiliary feedwater. This is reportable under 10 CFR 50.72(b)(2)(iv)(B). 31 Reactor Coolant Pump tripped after the reactor trip. All other systems operated as expected. Steam is being condensed by the condenser. The reactor was tripped due to an abnormal condition under the main generator; electrical arcing/sparking was observed. The reactor will remain shutdown until the cause of the arcing/sparking is identified and corrected. There was no indication of fire but the fire brigade was called out. The observed arcing and sparking from underneath the main generator secured after the turbine trip. All control rods fully inserted on the reactor trip. The electric plant is in a normal shutdown lineup and the EDGs are operable. The unit is stable and Unit 2 was not affected. The licensee notified the NRC Resident Inspector and the New York Public Service Commission.

  • * * UPDATE PROVIDED BY DON CROULET TO JEFF ROTTON AT 1416 EDT ON 07/21/06 * * *

Licensee reported the AFW actuation as a Specified System Actuation per 10 CFR 50.72(b)(3)(iv)(A). The licensee notified the NRC Resident Inspector. Notified the R1DO (Kinneman)

ENS 423781 March 2006 18:13:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopOn March 1, 2006, at 1435 hours, the Reactor Protection System was manually actuated while at 100 percent power upon indication of 12 dropped rods. All safety systems actuated as required and safety equipment operated as expected. There were eight control rods that did not indicate full insertion. One control rod had a bad rod bottom light bulb and the other seven control rods require calibration to indicate full insertion. Auxiliary Feedwater started as expected. The Emergency Diesel Generators did not start as offsite power remained available and stable. No primary or secondary relief valves lifted. The plant is in Hot Standby at normal temperature and pressure with residual heat removal using auxiliary feedwater and normal heat removal through the condenser via steam dumps. There was no radiation released. An investigation revealed that a manual disconnect switch for power control cabinet 1AC was open and scaffold work was being performed in the area. Cabinet 1AC is the power supply for the 12 dropped rods. The event is still under investigation and a post trip review is being conducted. The licensee notified the State and the NRC Resident Inspector.
ENS 4176210 June 2005 09:55:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopAt 0924 on 06/10/05, Indian Point 3 was manually tripped due to a service water leak in the main generator exciter. All control rods fully inserted. Plant response was as designed. Unit 3 is stable in Mode 3. Investigation is ongoing. Unit 2 (was not affected and) remains at 100% power. The steam generators are discharging steam to the main condenser to remove decay heat. The licensee notified the NRC resident inspector.
ENS 416736 May 2005 13:10:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-LoopOn May 6, 2005, at 10:32 hours, an automatic reactor trip occurred due to a Main Steam Flow/Feedwater Flow mismatch on the 32 Steam Generator (SG). All control rods fully inserted and safety equipment operated as expected. Auxiliary Feedwater started as expected. The Emergency Diesel Generators did not start as offsite power remained available. The plant is in Hot Shutdown at Normal Temperature and Pressure and there was no radiation release. The condition is under investigation and a post trip review is being conducted. No primary or secondary relief valves lifted during the reactor trip. Decay heat is being discharged to the main condenser via the high pressure steam dumps. Auxiliary feedwater is being used to maintain SG level. The electrical grid is stable. There was no affect on Unit 2. The licensee notified the NRC Resident Inspector and the State of New York.
ENS 4106624 September 2004 13:29:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-LoopOn September 24, 2004, at 11:53 hours, operations noticed the 23 Main Feedwater (FW) regulating valve operating erratically and FW flow and 23 Steam Generator (SG) level decreasing. At 11:55 hours operations initiated a manual trip of the reactor based on the degrading condition with FW flow and SG level. All control rods fully inserted and safety equipment operated as expected. Auxiliary Feedwater started as expected, the Emergency Diesel Generators did not start as offsite power remained available. The plant is in Hot (Standby) at Normal Temperature and Pressure and there was no radiation releases. The condition is under investigation and a post trip review is being conducted." State was notified of this event by the licensee. The NRC Resident Inspector was notified of this event by the licensee.
ENS 410031 September 2004 07:46:00Indian PointNRC Region 1Manual ScramWestinghouse PWR 4-Loop

On September 1, 2004, at 00:01 hours, operations noticed the 22 Main Feedwater (FW) regulating valve operating erratically and FW and 22 Steam Generator (SG) level oscillating. Operators placed the 22 Main FW regulating valve in manual and attempted to control FW flow and SG level but were unsuccessful. A Nuclear Plant Operator (NPO) in the plant reported water hammer in the Auxiliary Building that contains the FW regulating valves. At 00:05 hours operations initiated a manual trip of the reactor based on the degrading condition with FW flow and SG level. All control rods fully inserted and safety equipment operated as expected. Auxiliary Feedwater started as expected, the Emergency Diesel Generators did not start and offsite power remained available. The plant is in Hot (Standby) at Normal Temperature and Pressure and there was no radiation release. The 22 Main FW regulating valve was discovered to be partially stuck open. At 00:19 hours operations isolated the 22 FW flow path by closing the 22 FW line motor operated valve (MOV) BFD 5-1. The condition is under investigation and a post trip review is being conducted." State of NY was notified of this event by the licensee. The NRC Resident Inspector was notified of this event by the licensee.

  • * * UPDATE AT 1113 ON 9/1/04 FROM B. ROKES TO W. GOTT * * *

After further review of the reporting guidelines and discussion with the NRC R1, Licensing concluded the event notification should be reported under 10CFR50.72 (b)(1)(iv)(B) for a 4-hour report. A Condition Report was initiated for the late notification. Notified NRR (Reis) and R1DO (Henderson).

ENS 4006914 August 2003 21:50:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-Loop

Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All systems operating properly. NRC Resident Inspector was notified of the event by the licensee.

  • * * UPDATE 2340EDT ON 8/14/03 FROM ANDY MIHALIK TO S.SANDIN * * *

The following information was provided as an update: RPS Actuation (loss of flow) due to loss of offsite power. Auto actuation of AFW in response to the unit trips. Auto start & load of Emergency Diesel Generators in response to the loss of offsite power. Unit 3 also experienced a second AFW auto start during the event. Unit 3 also entered Tech Spec LCO 3.0.3 for loss of two offsite circuits and one EDG inoperable. #31 EDG was declared inoperable when its associated Fuel oil storage tank inventory decreased below required. The licensee informed the state/local authorities and the NRC resident inspector. Notified R1IRC.

          • UPDATE ON 8/15/03 AT 0226 FROM CELENTANO TO GOTT*****

The licensee exited the Unusual Event at 0210 upon confirmation of a stable off-site power. Notified R1 IRC and FEMA(Heyman).

ENS 4006714 August 2003 21:39:00Indian PointNRC Region 1Automatic ScramWestinghouse PWR 4-Loop

Automatic reactor scram due to a loss of offsite power. All rods fully inserted. Supplying power to vital buses via emergency diesel generators. All systems operating properly. NRC Resident Inspector was notified of the event by the licensee.

  • * * UPDATE 2340EDT ON 8/14/03 FROM ANDY MIHALIK TO S.SANDIN * * *

The following information was provided as an update: RPS Actuation (loss of flow) due to loss of offsite power. Auto actuation of AFW in response to the unit trips. Auto start & load of Emergency Diesel Generators in response to the loss of offsite power. The licensee informed the state/local authorities and the NRC resident inspector. Notified R1IRC.

          • UPDATE ON 8/15/03 AT 0226 FROM CELENTANO TO GOTT*****

The licensee exited the Unusual Event at 0210 upon confirmation of a stable off-site power. Notified R1 IRC and FEMA(Heyman).