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| Entered date | Event description | |
|---|---|---|
| ENS 45474 | 2 November 2009 23:55:00 | At 2242 on November 2, 2009 Indian Point Unit 2 reactor tripped from 100% due to a turbine trip. The turbine tripped due to a generator lockout relay actuation. The investigation into the relay actuation is ongoing. All systems responded as expected. Auxiliary feed water is providing steam generator feed and levels are being maintained. No steam safeties opened and no coolant system relief or safety valves actuated. The reactor plant is in mode 3 and stable. Unit 3 was unaffected and remains at 100%. The trip was characterized as uncomplicated. All rods fully inserted and stabilized at the normal mode 3 no-load Tave and pressure. The shutdown electrical lineup is normal and the unit was not in any significant LCOs at the time of the trip. The licensee stated that they were not performing any maintenance or surveillances at the time of the trip. Initial investigation has not revealed any obvious generator electrical system issues but a detailed investigation is ongoing. The licensee has notified State and local authorities and the NRC Resident Inspector. |
| ENS 45432 | 14 October 2009 17:09:00 | At 1500 hours on October 14, 2009, the power supply for neutron source range detector N-38 was determined to be unable to provide reliable power to detector N-38 and the detector was declared inoperable. Technical Specification (TS) 3.3.4 (Remote Shutdown) Basis Table 3.3.4-1, Function 1.a requires one channel. Technical Requirements Manual (TRM) 3.3.D (Appendix R Alternate Safe Shutdown Instrumentation) requires entry into the condition referenced in TRM Table 3.3.0-1 and entry into the applicable related TS referenced in TRM Table 3.3.D-1 when one or more required functions with one or more required instruments in Table 3.3.D-1 (are) inoperable. TRM Table 3.3.D-1, TRO 3.3.D1, neutron flux (source range only) lists and specifies detector N-38 only and references TS 3.3.4 Basis Table 3.3.4-1, Item 1a. Although there is an operable redundant source range neutron detector N-39, the only source range detector which has indication remote from the control room is N-38. Therefore, the safety function for safe shutdown remote from the control room for reactivity control in accordance with TS Basis Table 3.3.4-1, Function 1a can not be met with N-38 inoperable. The inability to meet the TS condition is a safety system functional failure. Actions are in progress to provide a reliable power supply for N-38. Unit 2 is at 100% and is not affected by the condition. The licensee notified the NRC Resident Inspector. |
| ENS 45098 | 28 May 2009 07:12:00 | At 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 44096 | 26 March 2008 13:54:00 | On March 26, 2008, at approximately 11:07 hours, an oil sheen was discovered outside the Indian Point cooling water discharge canal in the Hudson River. In accordance with the Indian Point Spill/Release plan, a spill or leak causing a visible sheen in the river as a result of the release of a petroleum product requires a notification to the New York State Department of Environmental Conservation (NYS DEC) and the National Response Center (U.S. Coast Guard). The National Response Center was notified at 11:16 hours and the NYS DEC was notified at 11:38 hours. The source and cause of the petroleum product spill/leak is under investigation. An environmental cleanup vendor was contacted and is scheduled to be on site the afternoon of March 26, 2008, for assessment and cleanup. The licensee notified the site resident inspector. R1DO notified. |
| ENS 44091 | 25 March 2008 14:38:00 | On March 25, 2008, during scheduled monthly testing per surveillance procedure M628, '480 Volt Undervoltage Degraded Grid Protection System Bus 5A Functional', an Instrumentation & Control technician conducting the test inadvertently caused an undervoltage condition on 480 volt AC safeguards Bus 5A, resulting in the automatic actuation of the associated Emergency Diesel Generator (EDG)-33. In accordance with design EDG-33 started and loads on Bus 5A were stripped and required loads were sequenced back onto Bus 5A. All equipment performed as designed. Normal power for Bus 5A has been restored and all equipment returned to pre-event condition. Investigation into the cause of the event is in progress. Unit 2 is currently in a refueling outage and was unaffected. Licensee has notified the NRC Resident Inspector and the State Public Service Commission. |
| ENS 43199 | 28 February 2007 10:01:00 | At 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 41227 | 26 November 2004 14:29:00 | At 1322 EST on 11/26/04, the Indian Point Unit 2 Reactor automatically shutdown due to a turbine generator trip resulting from a loss of stator cooling water. All systems responded as expected, no PORV's opened. The reactor is currently shutdown with all control rods inserted. Temperature is being maintained in Mode 3 with the steam dumps. AFW was initiated and is being used to maintain SG levels. Investigation into the loss of stator cooling water is ongoing. The licensee has notified the NRC Resident Inspector. |
| ENS 41174 | 5 November 2004 12:03:00 | Indian Point Emergency Center (IPEC) Units 2 & 3 are making an eight-hour non-emergency notification in accordance with 10CFR50.72(b)(3)(xiii). On November 5, 2004, at 0705 hours during a routine daily check it was discovered that 88 of 156 sirens were in communication failure due to equipment malfunction that occurred at approximately 1950 hours on November 4, 2004. At 0710 hours on November 5, 2004 the equipment malfunction was corrected and all but one siren was returned to service. The one siren out of service is unrelated to the event." State and Local counties were notified of the loss of the emergency sirens. The licensee has been notified the NRC Resident Inspector. |
| ENS 41066 | 24 September 2004 13:29:00 | On 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. |