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	Issue date	Title	Topic
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)

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