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{{Adams | |||
| number = ML17003A008 | |||
| issue date = 12/21/2016 | |||
| title = LER 16-010-00 for Indian Point, Unit 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 | |||
| author name = Vitale A J | |||
| author affiliation = Entergy Nuclear Operations, Inc, Indian Point Energy Center | |||
| addressee name = | |||
| addressee affiliation = NRC/Document Control Desk, NRC/NRR | |||
| docket = 05000247 | |||
| license number = DPR-026 | |||
| contact person = | |||
| case reference number = NL-16-140 | |||
| document report number = LER 16-010-00 | |||
| document type = Letter, Licensee Event Report (LER) | |||
| page count = 7 | |||
| revision = 0 | |||
}} | |||
Revision as of 12:34, 25 February 2018
| ML17003A008 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Docket Number ,  |
| Issue date: | 12/21/2016 |
| Revision: | 0 |
| From: | Vitale A J Entergy Nuclear Operations, Indian Point |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-16-140 LER 16-010-00 | |
| Download: ML17003A008 (7) | |
Similar Documents at Indian Point, Docket Number , | |
|---|---|
Category:Letter
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Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - 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[Table view]Some use of "" in your query was not closed by a matching "".LER 2018-001-00 for Indian Point, Unit 2 Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection 05000286/LER-2017-0042017-12-20020 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 05000458/LER-2017-0092017-11-13013 November 2017 Potential Loss of Safety Function of Secondary Containment due to Unsecured Personnel Door, LER 17-009-00 for River Bend, Unit 1 Regarding Potential Loss of Safety Function of Secondary Containment due to Unsecured Personnel Door ML17252A8662017-09-0909 September 2017 Letter Regarding a 04/26/1977 Occurrence Concerning Failure of Number 22 Main Steam Line Isolation Valve to Close to a Manual Signal Initiated by the Control Room Operator - Indian Point Unit No. 2 05000247/LER-2015-0012017-08-29029 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 NL-17-107, 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 fo2017-08-29029 August 2017 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 05000286/LER-2017-0032017-08-29029 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 05000247/LER-2017-0032017-08-23023 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 05000247/LER-2017-0012017-08-22022 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 05000247/LER-2017-0022017-08-22022 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 05000483/LER-2017-0012017-08-15015 August 2017 Violation of Technical Specification 3.7.9 Due to Ultimate Heat Sink (UHS) Cooling Tower Train Inoperability, LER 17-001-00 for Callaway, Unit 1, Regarding Violation of Technical Specification 3.7.9 Due to Ultimate Heat Sink (UHS) Cooling Tower Train Inoperability 05000286/LER-2017-0022017-08-0909 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 05000286/LER-2017-0012017-07-13013 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 05000247/LER-2016-0102017-02-28028 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 05000247/LER-2016-0022017-02-28028 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 NL-16-108, LER 15-001-01 for Indian Point 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 Conta2016-09-29029 September 2016 LER 15-001-01 for Indian Point 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 Contai 05000286/LER-2015-0042016-09-14014 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 05000286/LER-2015-0052016-09-14014 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-2015-0072016-09-0606 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-2015-0062016-08-0808 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-2014-0042016-08-0101 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 05000336/LER-2016-0012016-06-27027 June 2016 Turbine Driven Auxiliary Feedwater Putnp Room HELB Door Left Open, LER 16-001-00 for Millstone Power Station Unit 2 RE: Turbine Driven Auxiliary Feedwater Pump Room HELB Door Left Open 05000423/LER-2016-0032016-06-0808 June 2016 Loss of Safety Function- Supplementary Leak Collection and Release System, LER 16-003-00 for Millstone Power Station, Unit 3, Regarding Loss of Safety Function-Supplementary Leak Collection and Release System 05000247/LER-2016-0042016-05-31031 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 05000247/LER-2016-0052016-05-25025 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 05000247/LER-2016-0012016-05-0202 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 05000247/LER-2015-0042016-02-18018 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 05000286/LER-2015-0082016-02-11011 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 05000247/LER-2015-0032016-02-0303 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 NL-15-124, LER 15-001-00 for Indian Point 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 Cont2015-10-0909 October 2015 LER 15-001-00 for Indian Point 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 Conta NL-13-166, Report on Inoperable Gross Failed Fuel Detector2013-12-20020 December 2013 Report on Inoperable Gross Failed Fuel Detector NL-13-038, Event Report for Discovery of a Condition That Prevented Immediate Protective Actions to Avoid Exposures to Radiation from Byproduct Material2013-02-19019 February 2013 Event Report for Discovery of a Condition That Prevented Immediate Protective Actions to Avoid Exposures to Radiation from Byproduct Material NL-12-060, Submittal of Report on Inoperable Gross Failed Fuel Detector2012-04-26026 April 2012 Submittal of Report on Inoperable Gross Failed Fuel Detector ML1101906402010-11-0909 November 2010 Event Notification Report; Subject: Power Reactor Indian Point Unit 2 NL-09-108, Submittal of Report on Inoperable Core Exit Thermocouples2009-08-10010 August 2009 Submittal of Report on Inoperable Core Exit Thermocouples ML0509600412004-12-17017 December 2004 Final Precursor Analysis - IP-2 Grid Loop ML0509600512004-12-17017 December 2004 Final Precursor Analysis - IP-3 Grid Loop NL-03-136, LER 03-03-00 for Indian Point Unit 3 Regarding Automatic Turbine Trip/Reactor Trip Due to Fault in 345kV Generator Output Breaker 32003-08-21021 August 2003 LER 03-03-00 for Indian Point Unit 3 Regarding Automatic Turbine Trip/Reactor Trip Due to Fault in 345kV Generator Output Breaker 3 ML0209104352002-03-19019 March 2002 LER 98-001-01 for Indian Point Unit 3 Re Potential Failure or Inadvertent Operation of Fire Protection Systems, Caused by Personnel Error in Design ML17252A8951979-05-25025 May 1979 Letter Reporting a 05/18/1973 Occurrence of a Pressure Transient within the Reactor Coolant System Due to the Closure of Certain Air Operated Valves in the Reactor Coolant Letdown System - Indian Point Unit 2 ML17252A8481974-02-19019 February 1974 Letter Regarding a February 1, 1974 Occurrence Where Both Door of the 80 Foot Elevation Personnel Air Lock to the Containment Building Were Inadvertently Open at the Same Time for a Period of About Thirty Seconds - Indian Point Unit. 2 ML17252A8461974-02-19019 February 1974 Letter Regarding Performance of a Surveillance Test PT-M2 Reactor Coolant Temperature Analog Channel Functional Test - Delta T Overtemperature and T Overpower - Indian Point Unit No. 2 ML17252A8471974-02-0808 February 1974 Letter Regarding an Occurrence on 1/25/1974 at the Indian Point Unit No. 2 Reactor Was Brought Critical in Preparation for Placing the Plant Back in Service Following Completion of Repairs Associated with No. 22 Steam Generator Feedwater Li ML17252A8491974-02-0606 February 1974 Letter Regarding an Occurrence Where Both Doors of the 80 Foot Elevation Personnel Air Lock to the Containment Building Were Inadvertently Opened at the Same Time for About Thirty Seconds - Indian Point Unit 2 ML17252A8501974-02-0505 February 1974 Letter Regarding an Occurrence Where a Slight Reactor Coolant System Pressure Transient Was Experienced in the Course of Placing a Reactor Coolant Pump in Service - Indian Point Unit No. 2 ML17252A8511974-02-0101 February 1974 Letter Regarding an Inspection of All Bergen-Paterson Hydraulic Shock and Sway Arrestors (Snubbers) Located in the Vapor Containment Was Performed and Two Did Not Meet the Established Criterion for Operability - Indian Point Unit No. 2 ML17252A8521974-01-31031 January 1974 Letter Regarding an Occurrence Where the Reactor Was Brought Critical Preparatory to Placing the Plant Back in Service Following Completion of Repairs Associated with the 11/13/1973 Feedwater Line Break Incident - Indian Point Unit No. 2 ML17252A8591974-01-28028 January 1974 Letter Regarding an Occurrence 01/23/1974 Where a Slight Reactor Coolant System Pressure Transient Above the Technical Specifications Limit Was Experienced in the Course of Placing a Reactor Coolant Pump in Service - Indian Point Unit No. 2 ML17252A8721974-01-18018 January 1974 Letter Regarding Analysis of Results of Monthly Periodic Surveillance Test PT-M11 (Steam Line Pressure Analog Channel Function Test) Indicated That One of the Low Steam Line Pressure Bistables Associated with High Steam - Indian Point Unit ML17252A8761973-12-28028 December 1973 Letter Regarding 12/17/1973 Analysis of the Results of Periodic Tests and Calibration Checks Relating to Pressurizer Level Indicated a Setpoint Drift - Indian Point Unit 2 2018-05-21 |
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