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 Entered dateEvent description
ENS 466491 March 2011 12:54:00At 1100 EST, Indian Point Unit 2 experienced a loss of offsite power from the 138 Kv circuit. All three Emergency Diesel Generators automatically started as required. All other plant systems functioned as required. Restoration of offsite power from the 13.8 Kv offsite circuit is in progress. Investigation into the loss of the 138 Kv circuit is ongoing. Indian Point, Unit 2 continues in Mode 1 at 100 % power. Indian Point, Unit 2 is in a 72 hour LCO due to a loss of 1 of 2 offsite circuits. Unit 3 was not affected. The licensee has notified the NRC Resident Inspector and will be notifying the Public Service Commission of the State of New York.
ENS 4576513 March 2010 21:38:00At 1825 EST service water to '22' and '23' EDGs was isolated while applying a protective tagout to the service water '1-2-3' header. Previously, the supply from the other service water header '4-5-6' was also isolated. '21' EDG was out of service on a tagout. This resulted in a condition where no service water flow to the Emergency Diesel Generators was available for approximately three minutes. Service water flow was restored by opening the supply from the '1-2-3' service water header. During this condition, LCO 3.8.2 was not met. All required actions for LCO 3.8.2 were performed. LCO 3.8.2 was met when service water flow was restored to the Emergency Diesel Generators. The Emergency Diesel Generators were required to support residual heat removal in the event of a loss of offsite power. At no time was residual heat removal lost. The licensee will inform the NRC Resident Inspector.
ENS 4401729 February 2008 11:05:00At approximately 1040 EST, a spill of approximately 4.5 gallons of hydraulic fluid from a small dry cask storage utility vehicle occurred. Approximately half the fluid spilled onto the asphalt roadway and half onto the soil. This is not a de-minimis spill and New York State Department of Environmental Conservation and the Westchester County Department of Health will be contacted. Clean-up of the spilled fluid is in progress and the leaking vehicle has a containment device under the leak. There is no impact to sewers or waterways. No operating equipment on Unit 2 or Unit 3 is affected. The licensee notified the NRC Resident Inspector.
ENS 432723 April 2007 05:07:00The 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 426876 July 2006 04:25:00

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)

ENS 4140311 February 2005 19:54:00Notified by Barnwell Waste Management Facility that the filter liner sent to the Facility had arrived and that they found 'waste outside the liner.' This is a violation of the Barnwell license. This notification is made in accordance with the New York State PSC (Public Service Commission) requirements per corporate procedure. Ref: CR-IP2-2005-00613 The licensee will inform the State of New York and had informed the NRC Resident Inspector.
ENS 4104115 September 2004 03:13:00

Unit 2 was taken offline for repairs to "21" Main Feed Discharge Check Valve. The licensee will maintain Unit 2 in mode 2 at approximately 2% power for the duration of repairs. The licensee informed the NY State Public Services Commission and the NRC Resident Inspector.

  • * * UPDATE 1045 EDT ON 9/15/04 FROM JOHN BAKER TO ARLON COSTA * * *

The above report was corrected to remove inaccurate information. Notified R1DO( Doerflein) and NRR EO (Haney).

ENS 4016617 September 2003 17:44:00The Indian Point Unit 2 Technical Specification 3.14.A requires prompt notification of the NRC when hurricane force winds are within 500 nautical miles of the plant. Indian Point will continue to monitor the situation and update as necessary. The licensee has notified the NRC Resident Inspector.