Semantic search

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)

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.

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).

At 1143 on 4/6/07 the licensee declared an Unusual Event due to a main transformer explosion in the protected area. The event was declared in accordance with EAL 8.2.2. Unit 3 automatically tripped due to a load reject at the main generator. The Unit is currently stable at normal operating temperature and pressure. Decay heat is being removed via the steam dumps to the main condenser. All emergency diesel generators are available if needed but safety buses are currently supplied with offsite power. At the transformer site the deluge system actuated and the fire brigade responded. The fire was out at the time of the report The licensee informed the NRC Resident Inspector.

* * * UPDATE AT 1232 ON 4/6/07 FROM LAUGHLIN TO HUFFMAN * * *

The offsite local fire department was called by the licensee but their support was not needed and they were released.

* * * UPDATE AT 1259 ON 4/6/07 FROM LAUGHLIN TO HUFFMAN * * * 

The licensee exited Unusual Event at 1247 based on the fact that the fire was confirmed to be extinguished, there was no damage to safety equipment and the plant was in a safe and stable condition.

* * * UPDATE AT 1440 ON 4/6/07 FROM PRUSSMAN TO KNOKE * * * 

On April 6 at 1143 hours, an unusual event was declared based on Emergency Action Level 8.2.2, an explosion in the 'B' phase of the 31 main transformer. This is a one hour reportable event to the NRC made at 1159 hours. This is an update of EN 43285. The NUE was terminated at 1247 hours. The State and County were also notified of the unusual event. A press release was made. Although no one was injured as a result of this event, a four hour report is being made since this is related to on-site personnel safety. The main generator tripped and this resulted in a consequential reactor trip. The Reactor Protection System shut down the reactor at 1109 hours, a four hour report. The plant operated as designed and the Auxiliary Feedwater System actuated, an eight hour report. The fire was reported to the Control Room at 1111 hours. The fire was put out in less than 15 minutes. The event is currently under investigation. The header information in this event was revised as a result of this update to indicate 'Offsite Notification.'

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).

Indian Point Unit 3 tripped on Generator Differential (Direct Generator Trip). Current conditions are stable, mode 3 operation with all automatic actions occurring properly. Steam Generators levels are stable on aux. feed water. Unit 2 was unaffected by the trip. All control rods inserted fully and decay heat is being removed via steam dump to the condenser. All required safety related systems are working properly and the electrical buses and diesel generators are in their normal alignment. The licensee will notify the NRC Resident Inspector.

• * * UPDATE AT 0938 ON 07/06/08 B. ROKES TO W. GOTT * * *

The Auxiliary Feedwater System actuated and the Auxiliary Feedwater Pump started as designed due to the reactor trip. The actuation of the Auxiliary Feedwater System was the result of Steam Generator shrink/swell effect due to the reactor trip at full power. The actuation of the Auxiliary Feedwater System is an eight-hour non-emergency event reportable under 10 CFR 50.72(b)(3)(iv). The licensee will notify the NRC Resident Inspector. Notified R1DO (P. Henderson)