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 Issue dateTitleTopic
05000244/LER-2016-0017 April 2016Loss 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-2017-00116 June 2017During 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-2016-00121 March 2016Manual 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-2016-00214 April 2016Pressurizer 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-2016-00329 July 2016Unit 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-2016-00420 July 2016High 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-2015-00127 January 2016Manual 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-2016-00124 January 2017Automatic 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-2017-00119 April 2017Pressurizer 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 Only23 September 2021Forward 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 Pressure3 March 2022Forwards 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 Transformer8 January 2024Forward 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 Trip8 January 2024Forward 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 Transformer16 January 2024Submittal 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 197114 July 2011G20110523/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 1971Fukushima Dai-Ichi
Significance Determination Process
Earthquake
Backfit
IR 05000220/20120081 November 2012Notice of Violation - Constellation Energy Nuclear Group MEMO
IR 05000224/201340430 September 2013IR 05000224/2013404; 8/19/2013 - 8/22/2013; R.E. Ginna Power Plant; Access Authorization Letter OnlySignificance Determination Process
Affidavit
IR 05000244/19750131 October 1975R. 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 NoncomplianceBoric Acid
IR 05000244/20020011 March 20022002 Annual Assessment Letter - R. E. Ginna (Report 50-244/02-01)
IR 05000244/20020023 May 2002IR 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 05000244/20020037 June 2002IR 05000244-02-03, on 03/31-05/18/2002, Rochester Gas & Electric, R. E. Ginna Nuclear Power Plant. Fire Protection
IR 05000244/200200425 July 2002IR 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 05000244/200200528 October 2002IR 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 05000244/200200622 January 2003IR 05000244-02-006, Rochester Gas & Electric; 09/29-12/28/2002; R. E. Ginna Nuclear Power Plant. Flood Protection, Other Activities
IR 05000244/200201018 November 2002IR 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 ProblemsBoric Acid
High Radiation Area
Offsite Dose Calculation Manual
Temporary Modification
Condition Adverse to Quality
Significance Determination Process
Operability Determination
Siren
IR 05000244/200300228 May 2003IR 05000244-03-002; on 03/31 - 04/17/2003; R. E. Ginna Nuclear Power Plant; Safety System Design and Performance CapabilityBoric Acid
Significance Determination Process
Operability Determination
IR 05000244/200300329 April 2003IR 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 ActivitiesFire Barrier
Temporary Modification
Significance Determination Process
Operability Determination
License Renewal
Fire Protection Program
Power change
IR 05000244/200300516 July 2003IR 05000244-03-005, on 03/30/2003 - 06/28/2003, R.E. Ginna Nuclear Power Plant; Routine Integrated Report. No Violations Were NotedOffsite Dose Calculation Manual
Fire Barrier
Past operability
Temporary Modification
Operability Determination
Siren
IR 05000244/20030066 November 2003IR 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 ActivitiesBoric 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 05000244/200300722 January 2004IR 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-upBoric 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 05000244/200300812 May 2004IR 05000244-03-008, R. E. Ginna - Supplemental Information LetterAging Management
IR 05000244/200300921 May 2003IR 05000244-03-009, on 04/21/2003 Through 04/24/2003, for Rochester Gas & Electric Corp., Rochester, Ny; Supplemental Inspection Report - Violation - White SignificanceSignificance Determination Process
Preliminary White Finding
Siren
IR 05000244/200301118 September 2003IR 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 05000244/200301211 December 2003IR 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-upBoric Acid
Past operability
Temporary Modification
Condition Adverse to Quality
Significance Determination Process
Foreign Material Exclusion
Operability Determination
IR 05000244/200301314 January 2004IR 05000244-03-013; on 11/3/2003 - 11/21/2003; R. E. Ginna Nuclear Power Plant; Triennial Fire Protection Inspection ReportSignificance Determination Process
IR 05000244/200400223 April 2004IR 05000244-04-002, on 01/01/2004 - 03/31/2004; R. E. Ginna Nuclear Power Plant; Operator Performance During Non Routine Events, Post-Maintenance TestingBoric 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 05000244/200400321 July 2004IR 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 TestingBoric Acid
Fire Barrier
Temporary Modification
Locked High Radiation Area
Significance Determination Process
Process Control Program
Operability Determination
Fire Protection Program
Operability Assessment
Siren
IR 05000244/20040049 November 2004IR 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 ActivitiesSafe 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 05000244/200400520 January 2005IR 05000244-04-005, on 10/01/2004 - 12/31/2004; R. E. Ginna Nuclear Power Plant; Other ActivitiesBoric Acid
High Radiation Area
Fire Barrier
Temporary Modification
Locked High Radiation Area
Significance Determination Process
Job Performance Measure
Operability Determination
Fire Protection Program
IR 05000244/200400616 April 2004IR 05000244-04-006, on 03/26/2004, R. E. Ginna Nuclear Power Plant - NRC Physical Security Baseline Inspection Report. Cover Letter
IR 05000244/200400713 December 2004IR 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 05000244/200430111 May 2004IR 05000244-04-301, on April 5 Through 7, 2004, for Ginna Nuclear Power Plant; Initial Operator Licensing Examination
IR 05000244/20050012 March 2005Annual Assessment Letter - R.E. Ginna Nuclear Power Plant (Report 05000244/2005001)
IR 05000244/20050024 May 2005IR 05000244-05-002; on 01/01/2005 - 03/31/2005; R. E. Ginna Nuclear Power PlantBoric 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 05000244/200500321 July 2005IR 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 ActivitiesBoric 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 05000244/20050041 November 2005IR 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 EventsHigh Radiation Area
Fire Barrier
Internal Flooding
Hydrostatic
Significance Determination Process
Operability Determination
Biofouling
Fire Protection Program
Downpower
IR 05000244/200500525 January 2006IR 05000244-05-005; 10/01/2005 - 12/31/2005; R. E. Ginna Nuclear Power Plant; Fire ProtectionBoric Acid
Fire Barrier
Temporary Modification
Significance Determination Process
Operability Determination
Earthquake
Fire Protection Program
IR 05000244/200500621 November 2005IR 05000244-05-006; 09/19/2005 - 10/07/2005; R.E. Ginna Nuclear Power Plant; Safety System Design and Performance CapabilitySignificance Determination Process
Operability Determination
Flow Induced Vibration
IR 05000244/200500723 January 2008IR 05000244-05-007; 10/01/2007 Through 12/31/2007; R.E. Ginna Nuclear Power Plant; Routine Integrated Inspection ReportHigh Radiation Area
Fire Barrier
Internal Flooding
Functionality Assessment
Locked High Radiation Area
Aging Management
Operability Determination
IR 05000244/20060025 May 2006IR 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 AreasHigh 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