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Issue date | Title | Topic | |
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05000244/LER-2016-001 | 7 April 2016 | Loss of Station Auxiliary Transformer 12A resulting in automatic start of Emergency Diesel Generator A due to undervoltage signals to safeguards buses 14 and 18. LER 16-001-00 for R. E. Ginna Nuclear Power Plant Regarding Loss of Station Auxiliary Transformer 12A Resulting in Automatic Start of Emergency Diesel Generator A due to Undervoltage Signals to Safeguards Buses 14 and 18 | Offsite Circuit |
05000244/LER-2017-001 | 16 June 2017 | During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction. LER 17-001-00 for R. E. Ginna re During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction | |
05000317/LER-2016-001 | 21 March 2016 | Manual Reactor Trip Due to High Secondary Side Sodium Levels Due to a Condenser Tube Leak LER 16-001-00 for Calvert Cliffs Nuclear Power Plant Unit 1, Regarding Manual Reactor Trip Due to High Secondary Side Sodium Levels Due to a Condenser Tube Leak | |
05000317/LER-2016-002 | 14 April 2016 | Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit LER 16-002-00 for Calvert Cliffs, Unit 1, Regarding Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit | Weld Overlay Nondestructive Examination Pressure Boundary Leakage Dissimilar Metal Weld DM weld |
05000317/LER-2016-003 | 29 July 2016 | Unit 1 Automatic Trip on Loss of Load due to Spurious Steam Generator High Level Turbine Trip LER 16-003-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 1 Regarding Automatic Trip on Loss of Load due to Spurious Steam Generator High Level Turbine Trip | Anticipated operational occurrence |
05000317/LER-2016-004 | 20 July 2016 | High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to be Inoperable LER 16-004-00 for Calvert Cliffs, Unit 1 Regarding High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to be Inoperable | Safe Shutdown Unanalyzed Condition |
05000318/LER-2015-001 | 27 January 2016 | Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip LER 15-001-00 for Calvert Cliffs, Unit 2, Regarding Manual Reactor Trip Due to Steam Generator Feed Pump 22 Trip | Probabilistic Risk Assessment Significance Determination Process Large early release frequency |
05000318/LER-2016-001 | 24 January 2017 | Automatic Reactor Trip Due to Main Turbine Electro-Hydraulic Control Fluid Leak LER 16-001-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 2 Regarding Automatic Reactor Trip Due to Main Turbine Electro-Hydraulic Control Fluid Leak | Anticipated operational occurrence |
05000318/LER-2017-001 | 19 April 2017 | Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due To Setpoint Drift LER 17-001-00 For Calvert Cliffs, Unit 2 re: Pressurizer Safety Valve As-Found Settings Outside Technical Specification Limits Due to Setpoint Drift | Probabilistic Risk Assessment Significance Determination Process Large early release frequency |
05000318/LER-2021-003, Forward LER 2021-003-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 2, Auxiliary Feedwater Pump Inoperable Due to Improper Reset of Trip Throttle Valve. Cover Letter Only | 23 September 2021 | Forward LER 2021-003-00 for Calvert Cliffs Nuclear Power Plant, Unit No. 2, Auxiliary Feedwater Pump Inoperable Due to Improper Reset of Trip Throttle Valve. Cover Letter Only | |
05000318/LER-2022-001, Forwards LER 2022-001-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to High Reactor Coolant System Pressure | 3 March 2022 | Forwards LER 2022-001-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip Due to High Reactor Coolant System Pressure | |
05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | 8 January 2024 | Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | |
05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip | 8 January 2024 | Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip | |
05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | 16 January 2024 | Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer | |
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 | 14 July 2011 | G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 | Fukushima Dai-Ichi Significance Determination Process Earthquake Backfit |
IR 05000220/2012008 | 1 November 2012 | Notice of Violation - Constellation Energy Nuclear Group MEMO | |
IR 05000224/2013404 | 30 September 2013 | IR 05000224/2013404; 8/19/2013 - 8/22/2013; R.E. Ginna Power Plant; Access Authorization Letter Only | Significance Determination Process Affidavit |
IR 05000244/1975013 | 1 October 1975 | R. E. Ginna - Inspection 50-244/75-13, on 09/08-12/1975, Review Licensee'S Actions on Previously Identified Unresolved Items; Review Licensee'S Corrective Actions on Previously Identified Items of Noncompliance | Boric Acid |
IR 05000244/2002001 | 1 March 2002 | 2002 Annual Assessment Letter - R. E. Ginna (Report 50-244/02-01) | |
IR 05000244/2002002 | 3 May 2002 | IR 05000244/2002-002, R.E. Ginna Nuclear Power Plant, Inspection on 02/17-03/30/2002 Related to Maintenance Risk, Refueling and Outage, and Other. Violation Noted | |
IR 05000244/2002003 | 7 June 2002 | IR 05000244-02-03, on 03/31-05/18/2002, Rochester Gas & Electric, R. E. Ginna Nuclear Power Plant. Fire Protection | |
IR 05000244/2002004 | 25 July 2002 | IR 05000244-02-004, on 05/19-06/29/2002, Rochester Gas & Electric; R. E. Ginna Nuclear Power Plant. Alert Notification System (ANS) | Significance Determination Process Siren |
IR 05000244/2002005 | 28 October 2002 | IR 05000244-02-005, on 06/30 - 09/28/2002, R. E. Ginna Nuclear Power Plant, Fire Protection, Surveillance Testing and Identification and Resolution of Problems. Non-Cited Violations Noted | |
IR 05000244/2002006 | 22 January 2003 | IR 05000244-02-006, Rochester Gas & Electric; 09/29-12/28/2002; R. E. Ginna Nuclear Power Plant. Flood Protection, Other Activities | |
IR 05000244/2002010 | 18 November 2002 | IR 05000244-02-010, on 10/07/2002 - 10/25/2002, R. E. Ginna Nuclear Power Plant; Biennial Baseline Inspection of the Identification and Resolution of Problems | Boric Acid High Radiation Area Offsite Dose Calculation Manual Temporary Modification Condition Adverse to Quality Significance Determination Process Operability Determination Siren |
IR 05000244/2003002 | 28 May 2003 | IR 05000244-03-002; on 03/31 - 04/17/2003; R. E. Ginna Nuclear Power Plant; Safety System Design and Performance Capability | Boric Acid Significance Determination Process Operability Determination |
IR 05000244/2003003 | 29 April 2003 | IR 05000244-03-003, on 12/29/2002 - 03/29/2003; Rochester Gas & Electric; R. E. Ginna Nuclear Power Plant. Equipment Alignment, Fire Protection, Licensed Operator Requalification Program, Other Activities | Fire Barrier Temporary Modification Significance Determination Process Operability Determination License Renewal Fire Protection Program Power change |
IR 05000244/2003005 | 16 July 2003 | IR 05000244-03-005, on 03/30/2003 - 06/28/2003, R.E. Ginna Nuclear Power Plant; Routine Integrated Report. No Violations Were Noted | Offsite Dose Calculation Manual Fire Barrier Past operability Temporary Modification Operability Determination Siren |
IR 05000244/2003006 | 6 November 2003 | IR 05000244-03-006, on 06/29/2003 - 09/27/2003; R. E. Ginna Nuclear Power Plant; Maintenance Risk Assessment and Emergent Work, Personnel Performance During Non-routine Plant Evolutions, Post Maintenance Testing, Other Activities | Boric Acid High Radiation Area Fire Barrier Contraband Enforcement Discretion Nondestructive Examination Temporary Modification Locked High Radiation Area Significance Determination Process Foreign Material Exclusion Liquid penetrant Pressure Boundary Leakage Fire Watch Scaffolding |
IR 05000244/2003007 | 22 January 2004 | IR 05000244-03-007, on 09/28/2003 - 12/31/2003; R. E. Ginna Nuclear Power Plant; Adverse Weather, Post Maintenance Testing, Risk Assessment and Emergent Work, Event Follow-up | Boric Acid High winds High Radiation Area Fire Barrier Probabilistic Risk Assessment Temporary Modification Locked High Radiation Area Significance Determination Process Job Performance Measure Foreign Material Exclusion Operability Determination License Renewal Earthquake Pressure Boundary Leakage Fire Protection Program |
IR 05000244/2003008 | 12 May 2004 | IR 05000244-03-008, R. E. Ginna - Supplemental Information Letter | Aging Management |
IR 05000244/2003009 | 21 May 2003 | IR 05000244-03-009, on 04/21/2003 Through 04/24/2003, for Rochester Gas & Electric Corp., Rochester, Ny; Supplemental Inspection Report - Violation - White Significance | Significance Determination Process Preliminary White Finding Siren |
IR 05000244/2003011 | 18 September 2003 | IR 05000244-03-011, on 08/04/03-08/07/03; Ginna Nuclear Power Plant; Temporary Instruction 2515/148, Inspection of Nuclear Reactor Safeguards Interim Compensatory Measures | |
IR 05000244/2003012 | 11 December 2003 | IR 05000244-03-012; on 10/07/03 - 10/28/03; R. E. Ginna Nuclear Power Plant; Special Inspection of a Containment Sump Screen Bypass Issue; Event Follow-up | Boric Acid Past operability Temporary Modification Condition Adverse to Quality Significance Determination Process Foreign Material Exclusion Operability Determination |
IR 05000244/2003013 | 14 January 2004 | IR 05000244-03-013; on 11/3/2003 - 11/21/2003; R. E. Ginna Nuclear Power Plant; Triennial Fire Protection Inspection Report | Significance Determination Process |
IR 05000244/2004002 | 23 April 2004 | IR 05000244-04-002, on 01/01/2004 - 03/31/2004; R. E. Ginna Nuclear Power Plant; Operator Performance During Non Routine Events, Post-Maintenance Testing | Boric Acid High winds Packing leak High Radiation Area Fire Barrier Stroke time Temporary Modification Locked High Radiation Area Significance Determination Process Operability Determination Fire Protection Program Scaffolding Power change |
IR 05000244/2004003 | 21 July 2004 | IR 05000244-04-003, on 04/01/2004 - 06/30/2004; R. E. Ginna Nuclear Power Plant; Evaluation of Changes, Tests, or Experiments and Post Maintenance Testing | Boric Acid Fire Barrier Temporary Modification Locked High Radiation Area Significance Determination Process Process Control Program Operability Determination Fire Protection Program Operability Assessment Siren |
IR 05000244/2004004 | 9 November 2004 | IR 05000244-04-004, on 07/01/2004 - 09/30/2004; R. E. Ginna Nuclear Power Plant; Post Maintenance Testing, Identification and Resolution of Problems, Event Followup, Other Activities | Safe Shutdown High Radiation Area Fire Barrier Locked High Radiation Area Main transformer failure Significance Determination Process Annual Radiological Environmental Operating Report Large early release frequency Operability Determination Pressure boundary leak Fire Protection Program Power Uprate |
IR 05000244/2004005 | 20 January 2005 | IR 05000244-04-005, on 10/01/2004 - 12/31/2004; R. E. Ginna Nuclear Power Plant; Other Activities | Boric Acid High Radiation Area Fire Barrier Temporary Modification Locked High Radiation Area Significance Determination Process Job Performance Measure Operability Determination Fire Protection Program |
IR 05000244/2004006 | 16 April 2004 | IR 05000244-04-006, on 03/26/2004, R. E. Ginna Nuclear Power Plant - NRC Physical Security Baseline Inspection Report. Cover Letter | |
IR 05000244/2004007 | 13 December 2004 | IR 05000244-04-007; 10/18/04 - 10/22/04 and 11/1/04 - 11/5/04; R. E. Ginna Nuclear Power Plant; Biennial Baseline Inspection of the Identification and Resolution of Problems | |
IR 05000244/2004301 | 11 May 2004 | IR 05000244-04-301, on April 5 Through 7, 2004, for Ginna Nuclear Power Plant; Initial Operator Licensing Examination | |
IR 05000244/2005001 | 2 March 2005 | Annual Assessment Letter - R.E. Ginna Nuclear Power Plant (Report 05000244/2005001) | |
IR 05000244/2005002 | 4 May 2005 | IR 05000244-05-002; on 01/01/2005 - 03/31/2005; R. E. Ginna Nuclear Power Plant | Boric Acid High Radiation Area Ultimate heat sink Fire Barrier Locked High Radiation Area Significance Determination Process Job Performance Measure Foreign Material Exclusion Operability Determination Frazil ice Moisture barrier Fire Protection Program Scaffolding Substantial potential for an overexposure Power change Operability Assessment Overexposure |
IR 05000244/2005003 | 21 July 2005 | IR 05000244-05-003; on 04/01/2005 - 06/30/2005; for R. E. Ginna Nuclear Power Plant; Post Maintenance Testing, Refueling and Other Outage Activities, Public Radiation Safety', Other Activities | Boric Acid High Radiation Area Grab sample Offsite Dose Calculation Manual Fire Barrier Nondestructive Examination Temporary Modification Significance Determination Process Operability Determination Annual Radiological Effluent Release Report License Renewal Liquid penetrant Pressure Boundary Leakage Fire Protection Program |
IR 05000244/2005004 | 1 November 2005 | IR 05000244-05-004, on 07/01/2005 - 09/30/2005, R. E. Ginna Nuclear Power Plant; Equipment Alignment, Operator Performance During Non-Routine Evolutions and Events | High Radiation Area Fire Barrier Internal Flooding Hydrostatic Significance Determination Process Operability Determination Biofouling Fire Protection Program Downpower |
IR 05000244/2005005 | 25 January 2006 | IR 05000244-05-005; 10/01/2005 - 12/31/2005; R. E. Ginna Nuclear Power Plant; Fire Protection | Boric Acid Fire Barrier Temporary Modification Significance Determination Process Operability Determination Earthquake Fire Protection Program |
IR 05000244/2005006 | 21 November 2005 | IR 05000244-05-006; 09/19/2005 - 10/07/2005; R.E. Ginna Nuclear Power Plant; Safety System Design and Performance Capability | Significance Determination Process Operability Determination Flow Induced Vibration |
IR 05000244/2005007 | 23 January 2008 | IR 05000244-05-007; 10/01/2007 Through 12/31/2007; R.E. Ginna Nuclear Power Plant; Routine Integrated Inspection Report | High Radiation Area Fire Barrier Internal Flooding Functionality Assessment Locked High Radiation Area Aging Management Operability Determination |
IR 05000244/2006002 | 5 May 2006 | IR 05000244-06-002 on 01/01/2003 - 03/31/2006 for Constellation Energy; R.E. Ginna Nuclear Power Plant; Fire Protection, Licensed Operator Requalification Program, and Program Identification and Resolution, Cross-Cutting Areas | High winds High Radiation Area Fire Barrier Temporary Modification Locked High Radiation Area Significance Determination Process Operability Determination Fire Protection Program Scaffolding Power change Siren Power Uprate Overexposure |