ML17252A879
ML17252A879 | |
Person / Time | |
---|---|
Site: | Indian Point ![]() |
Issue date: | 12/03/1973 |
From: | Cobean W Con Edison, Consolidated Edison Co of New York |
To: | O'Leary J US Atomic Energy Commission (AEC) |
References | |
3-2-16 | |
Download: ML17252A879 (1) | |
Similar Documents at Indian Point | |
---|---|
Category:Letter
MONTHYEARIR 05000003/20240042025-02-20020 February 2025
[Table view]NRC Inspection Report Nos. 05000003/2024004, 05000247/2024004, 05000286/2024004, and Exercise of Enforcement Discretion IR 05000003/20240032024-12-11011 December 2024 NRC Inspection Report Nos. 05000003/2024003, 05000247/2024003, 05000286/2024003 L-24-017, Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2024-12-10010 December 2024 Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations ML24344A0692024-12-0909 December 2024 Proof of Financial Protection 10 CFR 140.15 IR 07200051/20244022024-11-20020 November 2024 NRC Independent Spent Fuel Storage Security Inspection Report No. 07200051/2024402 (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 And 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report IR 05000003/20230042024-02-22022 February 2024 NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage 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) 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 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 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 - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC – NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 2025-02-20 Category:Licensee Event Report (LER) MONTHYEAR05000247/LER-2018-003-01, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap2020-02-0707 February 2020
[Table view]Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap 05000247/LER-2018-003, For Indian Point Nuclear Generating Unit 2, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap2018-12-20020 December 2018 For Indian Point Nuclear Generating Unit 2, Loss of Safety Function Due to Valve SWN-6 Actuator Failure During Service Water Header Swap 05000286/LER-2018-003, Manual Reactor Trip Due to a Steam Leak on a High Pressure Feedwater Heater2018-11-19019 November 2018 Manual Reactor Trip Due to a Steam Leak on a High Pressure Feedwater Heater 05000286/LER-2018-002, Manual Reactor Shutdown Due to Weld Leak in Safety Injection System Tank2018-11-0505 November 2018 Manual Reactor Shutdown Due to Weld Leak in Safety Injection System Tank 05000247/LER-2018-002, Manual Reactor Trip Due to Trip of Both Main Boiler Feedwater Pumps2018-06-18018 June 2018 Manual Reactor Trip Due to Trip of Both Main Boiler Feedwater Pumps 05000247/LER-2018-001, Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection2018-05-21021 May 2018 Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection NL-18-039, LER 2018-001-00 for Indian Point, Unit 2 Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection2018-05-21021 May 2018 LER 2018-001-00 for Indian Point, Unit 2 Re Penetration Indications Discovered During Reactor Pressure Vessel Head Inspection 05000286/LER-2018-001, Reactor Trip Due to Main Generator Loss of Excitation2018-04-16016 April 2018 Reactor Trip Due to Main Generator Loss of Excitation 05000286/LER-1917-004, Regarding Reactor Trip Due to Main Generator Loss of Field2017-12-20020 December 2017 Regarding Reactor Trip Due to Main Generator Loss of Field 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 05000286/LER-1917-003, Regarding Condensate Storage Tank Declared Inoperable Per Technical Specification2017-08-29029 August 2017 Regarding Condensate Storage Tank Declared Inoperable Per Technical Specification 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 05000247/LER-1917-003, Regarding Technical Specification Violation of Section 3.3.1 RPS Instrumentation2017-08-23023 August 2017 Regarding Technical Specification Violation of Section 3.3.1 RPS Instrumentation 05000247/LER-1917-001, Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed Closed2017-08-22022 August 2017 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-1917-002, Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration2017-08-22022 August 2017 Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration 05000286/LER-1917-002, 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 Level2017-08-0909 August 2017 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-1917-001, Regarding Single Flow Barrier Access Point Found Unbolted2017-07-13013 July 2017 Regarding Single Flow Barrier Access Point Found Unbolted 05000247/LER-2016-010, 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 Unit2016-12-21021 December 2016 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 05000286/LER-2016-001, Regarding Safety System Functional Failure Due to an Inoperable Containment Caused by a Flaw on the 31 Fan Cooler Unit Service Water Return Coil Line Affecting Containment Integrity2016-12-21021 December 2016 Regarding Safety System Functional Failure Due to an Inoperable Containment Caused by a Flaw on the 31 Fan Cooler Unit Service Water Return Coil Line Affecting Containment Integrity 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 05000247/LER-2016-009, Regarding Automatic Reactor Trip Due to Actuation of the Trip Logic of the Reactor Protection System During Preparation for Testing2016-09-0606 September 2016 Regarding Automatic Reactor Trip Due to Actuation of the Trip Logic of the Reactor Protection System During Preparation for Testing 05000247/LER-2016-008, Regarding Technical Specification Required Shutdown Due to Not Completing Weld Repairs to Defect in Service Water Pipe Elbow to Inlet Nozzle of Component Cooling Water Heat Exchanger within TS AOT2016-08-23023 August 2016 Regarding Technical Specification Required Shutdown Due to Not Completing Weld Repairs to Defect in Service Water Pipe Elbow to Inlet Nozzle of Component Cooling Water Heat Exchanger within TS AOT 05000247/LER-2016-007, Safety System Functional Failure and Common Cause Inoperability of the Emergency Core Cooling System Due to Violation of Containment Sump Debris Barrier Integrity2016-08-0909 August 2016 Safety System Functional Failure and Common Cause Inoperability of the Emergency Core Cooling System Due to Violation of Containment Sump Debris Barrier Integrity 05000286/LER-2014-004-01, Regarding Automatic Reactor Trip as a Result of Meeting the Trip Logic for Over Temperature Delta Temperature During Reactor Protection System Pressurizer Pressure Calibration2016-08-0101 August 2016 Regarding Automatic Reactor Trip as a Result of Meeting the Trip Logic for Over Temperature Delta Temperature During Reactor Protection System Pressurizer Pressure Calibration 05000247/LER-2016-004, Re Unanalyzed Condition Due to Degraded Reactor Baffle-Former Bolts2016-05-31031 May 2016 Re Unanalyzed Condition Due to Degraded Reactor Baffle-Former Bolts 05000247/LER-2016-006, Regarding Technical Specification Prohibited Condition Due to Inoperable 138 Kv Offsite Circuits Caused by a Disconnected Safety Injection Signal to the Station Auxiliary Transformer Load Tap Changer2016-05-27027 May 2016 Regarding Technical Specification Prohibited Condition Due to Inoperable 138 Kv Offsite Circuits Caused by a Disconnected Safety Injection Signal to the Station Auxiliary Transformer Load Tap Changer 05000247/LER-2016-005, Regarding Technical Specification (TS) Prohibited Condition Due to a Surveillance Requirement Never Performed for Testing the Trip of the Main Boiler Feedwater Pumps2016-05-25025 May 2016 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-2016-003, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable 21 Main Boiler Feedwater Pump Discharge Valve for Greater than the TS Allowed Outage Time2016-05-0606 May 2016 Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable 21 Main Boiler Feedwater Pump Discharge Valve for Greater than the TS Allowed Outage Time 05000247/LER-2016-002, 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 Shutdown2016-05-0505 May 2016 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 05000247/LER-2016-001, Technical Specification Prohibited Condition Caused by One Main Steam Safety Valve Outside Its As-Found Lift Set Point Test Acceptance Criteria2016-05-0202 May 2016 Technical Specification Prohibited Condition Caused by One Main Steam Safety Valve Outside Its As-Found Lift Set Point Test Acceptance Criteria 05000247/LER-2015-004, 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 Pipe2016-02-18018 February 2016 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-2015-008, 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 Streaming2016-02-11011 February 2016 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-2015-003, Regarding Manual Reactor Trip Due to Indications of Multiple Dropped Control Rods Caused by Loss of Control Rod Power Due to a Power Supply Failure2016-02-0303 February 2016 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 05000247/LER-2015-002, Regarding Safety System Functional Failure Due to Fuses for Residual Heat Removal Heat Exchanger Outlet Valves That Would Not Remain Operable Under Degraded Voltage Conditions2015-10-19019 October 2015 Regarding Safety System Functional Failure Due to Fuses for Residual Heat Removal Heat Exchanger Outlet Valves That Would Not Remain Operable Under Degraded Voltage Conditions 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 05000247/LER-2015-001, 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 Containment2015-10-0909 October 2015 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 05000286/LER-2015-007, Regarding Manual Reactor Trip Due to Decreasing Steam Generator Water Levels Caused by a Miss-Wired Circuit Board in the Main Feedwater Pump Speed Control System2015-09-0808 September 2015 Regarding 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 05000286/LER-2015-006, Regarding Technical Specification Prohibited Condition Due to Two Pressurizer Code Safety Valves Discovered Outside Their As-Found Lift Setpoint Test Acceptance Criteria2015-08-28028 August 2015 Regarding Technical Specification Prohibited Condition Due to Two Pressurizer Code Safety Valves Discovered Outside Their As-Found Lift Setpoint Test Acceptance Criteria 05000286/LER-2015-005, Regarding 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 52015-08-14014 August 2015 Regarding 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-2015-004, Regarding Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by a Failure of the 31 Main Transformer2015-07-0707 July 2015 Regarding Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by a Failure of the 31 Main Transformer 05000286/LER-2015-003, Regarding Technical Specification Prohibited Condition Caused by Failure to Meet Containment Fan Cooler Unit Service Water (SW) Flow Rate Due to Improper SW Surveillance Test Configuration2015-06-0808 June 2015 Regarding Technical Specification Prohibited Condition Caused by Failure to Meet Containment Fan Cooler Unit Service Water (SW) Flow Rate Due to Improper SW Surveillance Test Configuration 05000286/LER-2015-002, Regarding Technical Specification Prohibited Condition Caused by Three Main Steam Safety Valves Outside Their As-Found Lift Set Point Test Acceptance Criteria2015-04-27027 April 2015 Regarding Technical Specification Prohibited Condition Caused by Three Main Steam Safety Valves Outside Their As-Found Lift Set Point Test Acceptance Criteria 05000286/LER-2015-001, Regarding Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Level Alarms Due to Freezing of the Level Instrument Sensing Lines Caused by a Failed Strip Heater2015-03-0303 March 2015 Regarding Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Level Alarms Due to Freezing of the Level Instrument Sensing Lines Caused by a Failed Strip Heater 05000247/LER-2014-003, Regarding Technical Specification (TS) Prohibited Condition Due to a Mode Change with an Inoperable 22 Auxiliary Feedwater Pump2014-05-19019 May 2014 Regarding Technical Specification (TS) Prohibited Condition Due to a Mode Change with an Inoperable 22 Auxiliary Feedwater Pump 05000247/LER-2014-002, Regarding Technical Specification Prohibited Condition Due to an Inoperable 23 Steam Generator (SG) Caused by a Through Wall Defect in 23 SG Drain Line Valve MS-682014-04-23023 April 2014 Regarding Technical Specification Prohibited Condition Due to an Inoperable 23 Steam Generator (SG) Caused by a Through Wall Defect in 23 SG Drain Line Valve MS-68 05000247/LER-2014-001, Regarding Technical Specification (TS) Prohibited Condition Due to Failure to Comply with TS 3.4.3 Reactor Coolant System Pressure-Temperature Limits During Vacuum Refill2014-04-0707 April 2014 Regarding Technical Specification (TS) Prohibited Condition Due to Failure to Comply with TS 3.4.3 Reactor Coolant System Pressure-Temperature Limits During Vacuum Refill 05000286/LER-2014-003, Automatic Actuation of the Turbine Driven Auxiliary Feedwater Pump Following Testing of the 31 Emergency Diesel Generator Due to Non-SI Blackout Logic Defeated Reset2014-04-0707 April 2014 Automatic Actuation of the Turbine Driven Auxiliary Feedwater Pump Following Testing of the 31 Emergency Diesel Generator Due to Non-SI Blackout Logic Defeated Reset 05000286/LER-2014-002, Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Essential Service Water (SW) Header as a Result of a Socket Weld Leak in Code Class 3 SW Piping2014-03-10010 March 2014 Regarding Technical Specification (TS) Prohibited Condition Due to an Inoperable Essential Service Water (SW) Header as a Result of a Socket Weld Leak in Code Class 3 SW Piping 05000286/LER-2014-001, Regarding Automatic Reactor Trip as a Result of Steam Flow/Feedwater Flow Mismatch with Low 33 Steam Generator (SG) Water Level Due to the Failure of the 33 SG Feedwater Flow Controller2014-03-0404 March 2014 Regarding Automatic Reactor Trip as a Result of Steam Flow/Feedwater Flow Mismatch with Low 33 Steam Generator (SG) Water Level Due to the Failure of the 33 SG Feedwater Flow Controller NL-13-166, Report on Inoperable Gross Failed Fuel Detector2013-12-20020 December 2013 Report on Inoperable Gross Failed Fuel Detector 2020-02-07 |
Text
- .-d> \.A.II I/ Edison-. Consolidated Edison Company of New York, Inc.
- 4 Irving Place, New York, NY 10003 Mr. John F. O'Leary Directorate of Licensing Off ice of Regulation
- u. S. Atomic Energy Commission Washington, ,D. C.* 20545
Dear Mr. O'Leary:
Re: December 3, 1973 Indian Point Unit No. 2 Facility Operating License DPR-26 A.O. 3-2-16 50-247 The following report is provided pursuant to the requirements of Section 6.12.2(a) of the Technical Specifications of Facility Operating License DPR-26. On November 18, 1973, following an analysis of the results of periodic tests and calibration checks relating to pressurizer pressure it was found that the setting for one of the three stables associated with low pressurizer pressure safety tion was below that required by Item 3 in Table 3-1 of the nical Specifications.
At the time of these periodic tests and calibration checks, the reactor was in the cold shutdown dition for maintenance work. File **cy. The bistable that had an erroneous setting is part of a of-three logic system which provides for a safety injection nal on coincident low pressurizer pressure and low pressurizer level. The other two bistables were operating correctly.
The channel associated with this device was .recalibrated and retested satisfactorily.
Safety implications of this occurrence are considered to be slight since the remaining two channels of the two-of-three actuation ic were properly set and would have functioned if required. vestigations into the reason for the low setting have not as yet yielded a te cause and are being contimJed.
DOCK mo USAEC Very truly yours, Warren R. Cobean, Jr., Manager, Nuclear Power Generation 8700