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Issue date | Title | Topic | |
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05000247/LER-2015-001 | 29 August 2017 | Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size that Results in Exceeding the Allowed Leakage Rate for Containment LER 15-001-02 for Indian Point, Unit 2, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Containment Caused by a Service Water Pipe Leak with a Flaw Size that Results in Exceeding the Allowed Leakage Rate for Containment | Time of Discovery Through-Wall Leak Through Wall Leak |
05000247/LER-2015-003 | 3 February 2016 | Manual Reactor Trip Due to Indications of Multiple Dropped Control Rods Caused by Loss of Control Rod Power Due to a Power Supply Failure LER 15-003-00 for Indian Point, Unit 2, Regarding Manual Reactor Trip Due to Indications of Multiple Dropped Control Rods Caused by Loss of Control Rod Power Due to a Power Supply Failure | Boric Acid |
05000247/LER-2015-004 | 18 February 2016 | Safety System Functional Failure Due to an Inoperable Containment Caused by a Flawed Elbow on the 21 Fan Cooler Unit Service Water Motor Cooling Return Pipe LER 15-004-00 for Indian Point 2 Regarding Safety System Functional Failure Due to an Inoperable Containment Caused by a Flawed Elbow on the 21 Fan Cooler Unit Service Water Motor Cooling Return Pipe | Time of Discovery Through Wall Leak |
05000247/LER-2016-001 | 2 May 2016 | Technical Specification Prohibited Condition Caused by One Main Steam Safety Valve Outside Its As-Found Lift Set Point Test Acceptance Criteria LER 16-001-00 for Indian Point 2 RE: Technical Specification Prohibited Condition Caused by One Main Steam Safety Valve Outside Its As-Found Lift Set Point Test Acceptance Criteria | Anticipated operational occurrence |
05000247/LER-2016-002 | 28 February 2017 | Automatic Actuation of Emergency Diesel Generators (EDGs) Due to 480 VAC Bus Undervoltage Condition and Loss of Residual Heat Removal (RHR) While in Cold Shutdown LER 16-002-01 for Indian Point, Unit 2 Regarding Automatic Actuation of Emergency Diesel Generators (EDGs) Due to 480 VAC Bus Undervoltage Condition and Loss of Residual Heat Removal (RHR) While in Cold Shutdown | Boric Acid Past operability |
05000247/LER-2016-004 | 31 May 2016 | Unanalyzed Condition due to Degraded Reactor Baffle-Former Bolts LER 16-004-00 for Indian Point 2 re Unanalyzed Condition Due to Degraded Reactor Baffle-Former Bolts | Safe Shutdown Unanalyzed Condition Time of Discovery |
05000247/LER-2016-005 | 25 May 2016 | Technical Specification (TS) Prohibited Condition Due to a Surveillance Requirement Never Performed for Testing the Trip of the Main Boiler Feedwater Pumps LER 16-005-00 for Indian Point, Unit 2, Regarding Technical Specification (TS) Prohibited Condition Due to a Surveillance Requirement Never Performed for Testing the Trip of the Main Boiler Feedwater Pumps | Missed surveillance |
05000247/LER-2016-010 | 28 February 2017 | Safety System Functional Failure Due to an Inoperable Containment Caused by a Through Wall Defect in a Service Water Supply Pipe Elbow to the 24, Fan Cooler Unit LER 16-010-01 for Indian Point 2 Regarding Safety System Functional Failure Due to an Inoperable Containment Caused by a Through Wall Defect in a Service Water Supply Pipe Elbow to the 24 Fan Cooler Unit | Coatings Through-Wall Leak Through Wall Leak |
05000247/LER-2017-001 | 22 August 2017 | Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused By Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed Closed LER 17-001-00 for Indian Point, Unit 2 Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused By Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed Closed | Power change Loctite |
05000247/LER-2017-002 | 22 August 2017 | Auxiliary Feedwater Flow Indication Inoperable for Longer Than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration LER 17-002-00 for Indian Point, Unit 2 Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer Than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration | |
05000247/LER-2017-003 | 23 August 2017 | Technical Specification Violation of Section 3.3.1 RPS Instrumentation LER 17-003-00 for Indian Point Unit 2, Regarding Technical Specification Violation of Section 3.3.1 RPS Instrumentation | Safe Shutdown |
05000286/LER-2014-004 | 1 August 2016 | Automatic Reactor Trip as a Result of Meeting the Trip Logic for Over Temperature Delta Temperature during Reactor Protection System Pressurizer Pressure Calibration LER 14-004-01 for Indian Point Unit 3, Regarding Automatic Reactor Trip as a Result of Meeting the Trip Logic for Over Temperature Delta Temperature During Reactor Protection System Pressurizer Pressure Calibration | |
05000286/LER-2015-004 | 14 September 2016 | Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by a Failure of the 31 Main Transformer LER 15-004-01 for Indian Point Unit No. 3 Regarding Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by a Failure of the 31 Main Transformer | Main transformer failure |
05000286/LER-2015-005 | 14 September 2016 | Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by the Trip of 345kV Main Generator Output Breaker 3 due to a Failure of South Ring Bus 345kV Breaker 5 LER 15-005-01 for Indian Point 3 RE: Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by the Trip of 345kV Main Generator output Breaker 3 due to a Failure of South Ring Bus 345kV Breaker 5 | |
05000286/LER-2015-006 | 8 August 2016 | Technical SpecificatiOn Prohibited Condition Due to Two Pressurizer Code Safety Valves Discovered Outside their As-Found Lift Setpoint Test Acceptance Criteria LER 15-006-01 for Indian Point Unit No. 3 Regarding Technical Specification Prohibited Condition Due to Two Pressurizer Code Safety Valves Discovered Outside Their As-Found Lift Setpoint Test Acceptance Criteria | |
05000286/LER-2015-007 | 6 September 2016 | Manual Reactor Trip Due to Decreasing Steam Generator Water Levels Caused by a Miss- Wired Circuit Board in the Main Feedwater Pump Speed Control System LER 2015-007-01 for Indian Point, Unit 3 Regarding Manual Reactor Trip Due to Decreasing Steam Generator Water Level Caused by a Miss-Wired Circuit Board in the Main Feedwater Pump Speed Control System | |
05000286/LER-2015-008 | 11 February 2016 | Automatic Reactor Trip Due to a Turbine-Generator Trip as a Result of a Fault on 345 kV Feeder W96 Tower Lines Caused by Pre-Existing Degraded Insulator LER 15-008-00 for Indian Point, Unit 3, Regarding Automatic Reactor Trip Due to a Turbine-Generator Trip as a Result of a Fault on 345 kV Feeder W96 Tower Lines Caused by Bird Streaming | |
05000286/LER-2017-001 | 13 July 2017 | Single Flow Barrier Access Point Found Unbolted LER 17-001-00 for Indian Point, Unit 3 Regarding Single Flow Barrier Access Point Found Unbolted | Locked High Radiation Area Scaffolding |
05000286/LER-2017-002 | 9 August 2017 | Manual Isolation of Chemical and Volume Control System Normal Letdown to Stop a Valve Leak Resulted in an Exceedance of Technical Specification 3.4.9 Condition A Limit for Pressurizer Level LER 17-002-00 for Indian Point, Unit 3 re Manual Isolation of Chemical and Volume Control System Normal letdown to Stop a Valve Leak Resulted in an Exceedance of Technical Specification 3.4.9 Condition A Limit for Pressurizer Level | Safe Shutdown |
05000286/LER-2017-003 | 29 August 2017 | Condensate Storage Tank Declared Inoperable Per Technical Specification LER 17-003-00 for Indian Point, Unit 3, Regarding Condensate Storage Tank Declared Inoperable Per Technical Specification | Time of Discovery Non-Destructive Examination Through Wall Leak |
05000286/LER-2017-004 | 20 December 2017 | Reactor Trip Due to Main Generator Loss of Field LER 17-004-00 for Indian Point Unit 3, Regarding Reactor Trip Due to Main Generator Loss of Field | Temporary Modification |
05000293/LER-2016-001 | 9 June 2016 | Both Emergency Diesel Generators Inoperable LER 16-001-00 for Pilgrim Nuclear Power Station Regarding Both Emergency Diesel Generators Inoperable | Safe Shutdown Abnormal operational transient Pressure boundary leak |
05000293/LER-2016-002 | 20 June 2016 | Online Maintenance Test Configuration Prohibited By Technical Specifications LER 16-002-00 for Pilgrim Nuclear Power Station Regarding Online Maintenance Test Configuration Prohibited By Technical Specifications | Safe Shutdown Abnormal operational transient |
05000293/LER-2016-003 | 11 July 2016 | Spent Fuel Storage Design Feature Exceeded LER 16-003-00 for Pilgrim Nuclear Power Station Regarding Spent Fuel Storage Design Feature Exceeded | Unanalyzed Condition |
05000293/LER-2016-004 | 11 July 2016 | Salt Service Water Pump B Past Operability - Operation or Condition Prohibited by Technical Specifications LER 16-004-00 for Pilgrim Nuclear Power Station Regarding Salt Service Water Pump B Past Operability - Operation or Condition Prohibited by Technical Specifications | Past operability |
05000293/LER-2016-007 | 4 November 2016 | Manual Reactor Scram Due To Feedwater Regulating Valve Malfunction LER 16-007-00 for Pilgrim Nuclear Power Station Regarding Manual Reactor Scram Due To Feedwater Regulating Valve Malfunction | Reactor Vessel Water Level Packing leak Power change |
05000293/LER-2016-008 | 9 December 2016 | Emergency Diesel Generator 'A' Past Inoperability LER 16-008-00 for Pilgrim Nuclear Power Station Regarding Emergency Diesel Generator 'A' Past Inoperability | Safe Shutdown Time of Discovery Mission time Abnormal operational transient |
05000293/LER-2016-010 | 14 June 2017 | MSIV Inoperability Led to a Condition Prohibited by the Plant s Technical Specifications LER 16-010-01 for Pilgrim Nuclear Power Station re MSIV Inoperability | Packing leak |
05000293/LER-2017-001 | 17 July 2017 | Reactor Building Isolation Dampers Failed to Isolate LER 17-001-01 for Pilgrim Nuclear Power Station Regarding Reactor Building Isolation Dampers Failed to Isolate | |
05000293/LER-2017-002 | 25 May 2017 | Isolation of HPCI LER 17-002-00 for Pilgrim Regarding Isolation of HPCI | |
05000293/LER-2017-003 | 25 May 2017 | Supplement to Suppression Pool Declared Inoperable Due to High Water Level LER 17-003-00 for Pilgrim Nuclear Power Station Regarding Pressure Suppression Pool Declared Inoperable Due to High Water Level | Time of Discovery |
05000293/LER-2017-004 | 2 June 2017 | Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System LER 17-004-00 for Pilgrim Nuclear Power Station Regarding Secondary Containment Testing Led to Loss of Safety Function to Both Trains of Standby Gas Treatment System | Mission time |
05000293/LER-2017-005 | 7 June 2017 | 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded LER 17-005-00 for Pilgrim Regarding 10 CFR 50, Appendix J, Option B, Leak Rate Criteria Exceeded | Fuel cladding |
05000293/LER-2017-006 | 13 June 2017 | Source Range Monitor Inoperable During Fuel Movement LER 17-006-00 for Pilgrim Nuclear Power Station Regarding Source Range Monitor Inoperable During Fuel Movement | |
05000293/LER-2017-007 | 22 June 2017 | Supplement to Potential Inoperability of Safety Relief Valve 3A LER 17-007-00 for Pilgrim Regarding Potential Inoperability of Safety Relief Valve 3A | |
05000293/LER-2017-008 | 30 June 2017 | Supplement to 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure LER 17-008-00 for Pilgrim re 480V Bus B6 Auto Transfer Function Degraded Due to Time Delay Relay Failure | |
05000293/LER-2017-009 | 17 July 2017 | Supplement to Potential Primary Containment System Inoperability Due to Relay Concerns LER 17-009-00 for Pilgrim Nuclear Power Station Regarding Potential Primary Containment System lnoperability Due to Relay Concerns | Fuel cladding |
05000293/LER-2017-010 | 7 August 2017 | Air Accumulation Creates Small Void in Core Spray Discharge Piping LER 17-010-00 for Pilgrim re Air Accumulation Creates Small Void in Core Spray Discharge Piping | Time of Discovery |
05000293/LER-2017-011 | 15 August 2017 | Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment LER 17-011-00 for Pilgrim Nuclear Power Station Regarding Simultaneously Opened Reactor Building Airlock Doors Caused Loss of Secondary Containment | Recently irradiated fuel |
05000293/LER-2017-012 | 13 November 2017 | Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit LER 17-012-00 for Pilgrim Nuclear Power Station Regarding Start-Up Transformer Degraded Voltage Relay Found Outside Technical Specification Limit | |
05000293/LER-2017-013 | 25 January 2018 | 1 OF 4 LER 17-013-00 for Pilgrim Nuclear Power Station Regarding Reportable Conditions Involving Standby Gas Treatment System and Secondary Containment lnoperability Not Reported During the Previous Three Years | Mission time Recently irradiated fuel |
BVY 02-078, Proof of Financial Protection (10 CFR.140.15) and Guarantee Payment of Deferred Premiums (10 CFR 140.21) | 9 October 2002 | Proof of Financial Protection (10 CFR.140.15) and Guarantee Payment of Deferred Premiums (10 CFR 140.21) | |
BVY 03-016, Entergy Nuclear Northeast - Proof of Financial Protection (10 CFR 140.15) & Guarantee of Payment of Deferred Premiums (10 CFR 140.21) for Pilgrim Station, Indian Point Units 2 & 3, James A. Fitzpatrick Nuclear Power Plant & Vermont Yankee | 26 March 2003 | Entergy Nuclear Northeast - Proof of Financial Protection (10 CFR 140.15) & Guarantee of Payment of Deferred Premiums (10 CFR 140.21) for Pilgrim Station, Indian Point Units 2 & 3, James A. Fitzpatrick Nuclear Power Plant & Vermont Yankee S | |
BVY 03-026, Sources and Levels of Insurance Required by 10 CFR 50.54(w) | 28 March 2003 | Sources and Levels of Insurance Required by 10 CFR 50.54(w) | |
BVY 03-044, 2002 Annual Report, and Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants | 28 May 2003 | 2002 Annual Report, and Securities and Exchange Commission Form 10-K Submittal for All Entergy Nuclear Operations, Inc. Plants | |
BVY 03-069, Fitness-for-Duty Program Performance Report for Period January - June 2003 | 18 August 2003 | Fitness-for-Duty Program Performance Report for Period January - June 2003 | Fitness for Duty Stolen |
BVY 04-018, Fitness-for-Duty Program Performance Report for the Period of July - December 2003 | 23 February 2004 | Fitness-for-Duty Program Performance Report for the Period of July - December 2003 | Fitness for Duty |
BVY 04-022, Response to RAI on Relief Requests to Use ASME Code Case N-600 | 4 March 2004 | Response to RAI on Relief Requests to Use ASME Code Case N-600 | |
BVY 04-027, Response to RAI on Relief Requests to Use ASME Code Case N-600, Supplement 1 | 18 March 2004 | Response to RAI on Relief Requests to Use ASME Code Case N-600, Supplement 1 | |
BVY 04-028, Proof of Financial Protection (10CFR140.15) and Guarantee of Payment of Deferred Premiums (10CFR140.21) | 25 March 2004 | Proof of Financial Protection (10CFR140.15) and Guarantee of Payment of Deferred Premiums (10CFR140.21) |