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 Issue dateTitleTopic
05000263/LER-2014-00213 July 2016Torus to Drywell Vacuum Breaker Did Not Indicate Closed During Testing
LER 14-002-01 for Monticello Regarding Torus to Drywell Vacuum Breaker Did Not Indicate Closed During Testing		Unanalyzed Condition
Pressure Boundary Leakage
05000263/LER-2014-00313 July 2016Torus to Drywell Vacuum Breaker Dual Indication During Testing
LER 14-003-01 for Monticello Nuclear Generating Plant RE: Torus to Drywell Vacuum Breaker Dual Indication During Testing		Unanalyzed Condition
Pressure Boundary Leakage
05000263/LER-2015-00422 August 2017Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements
LER 15-004-01 for Monticello Regarding Past Inoperability of Turbine Stop Valve Scram Function Exceeded Technical Specification Requirements		Time of Discovery
High Radiation Area
Past operability
05000263/LER-2015-00621 January 2016- Reactor Scram due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line
LER 15-006-00 for Monticello Regarding Reactor Scram due to Group 1 Isolation from Foreign Material in the Main Steam Flow Instrument Line		Foreign Material Exclusion
05000263/LER-2015-00721 January 2016Loss of Residual Heat Removal Capability
LER 15-007-00 for Monticello Regarding Loss of Residual Heat Removal Capability
05000263/LER-2016-00125 May 2017High Pressure Coolant Injection System Cracked Pipe Nipple Caused Oil Leak
LER 16-001-02 for Monticello Regarding High Pressure Coolant Injection System Cracked Pipe Nipple Caused Oil Leak		Time of Discovery
Mission time
Past operability
Probabilistic Risk Assessment
05000263/LER-2016-00230 September 2016Inadequate Appendix R Fire Barrier Impacts Safe Shutdown Capability
LER 16-002-00 for Monticello Regarding Inadequate Appendix R Fire Barrier Impacts Safe Shutdown Capability		Safe Shutdown
Unanalyzed Condition
Fire Barrier
Exemption Request
Fire Protection Program
Hourly Fire Watch
05000263/LER-2016-00325 May 2017HPCI Declared Inoperable Due to Excessive Water Level in Turbine
LER 16-003-01 for Monticello Regarding HPCI Declared Inoperable Due to Excessive Water Level in Turbine		Temporary Modification
05000263/LER-2017-00113 June 2017Reactor Scram and Group II Isolation Due to 11 Reactor Feed Pump (RFP) Removal from Service with 12 RFP Isolated
LER 17-001-00 for Monticello Regarding Reactor Scram and Group II Isolation Due to 11 Reactor Feed Pump (RFP) Removal from Service with 12 RFP Isolated
05000263/LER-2017-00213 June 2017Main Steam Isolation Valve Closure Time Outside of Technical Specification Requirements
LER 17-002-00 for Monticello Nuclear Generating Plant Regarding Main Steam Isolation Valve Closure Time Outside of Technical Specification Requirements
05000263/LER-2017-00314 June 2017Main Steam Isolation Valve Leakage Exceeds Technical Specification Limits
LER 17-003-00 for Monticello Regarding Main Steam Isolation Valve Leakage Exceeds Technical Specification Limits		Anchor Darling
05000263/LER-2017-00416 August 2017High Pressure Coolant Injection Steam Stop Valve Failed to Open During Test
LER 17-004-00 for Monticello Regarding High Pressure Coolant Injection Steam Stop Valve Failed to Open During Test
05000263/LER-2017-00520 September 2017Diesel Generator Emergency Service Water System Automatic Transfer to Alternate Shutdown Panel
LER 17-005-00 for Monticello Nuclear Generating Plant Regarding Diesel Generator Emergency Service Water System Automatic Transfer to Alternate Shutdown Panel		Ultimate heat sink
05000263/LER-2017-00612 January 2018Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests due to Use of a Test Fixture
LER 17-006-00 for Monticello Regarding Loss of Reactor Protection System Scram Function During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Fixture		Safe Shutdown
Half scram
Fuel cladding
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 05000263/20020014 March 2002Annual Assessment Letter - Monticello Nuclear Generating Plant (Report 50-263/02-01)
IR 05000263/200200424 July 2002IR 05000263-02-004 (Drp), on 04/01-06/30/02, Nuclear Management Company, Monticello Nuclear Generating Plant; Flood Protection Measures; Event FollowupTime of Discovery
Fitness for Duty
High winds
High Radiation Area
Fire Barrier
Internal Flooding
Hydrostatic
Enforcement Discretion
Temporary Modification
Locked High Radiation Area
Significance Determination Process
Scram Discharge Volume
Operability Determination
Power-Operated Valves
Fire Watch
IR 05000263/200200518 March 2003IR 05000263-02-005, on 08/19 - 23/2002, Nuclear Management Company, LLC, Monticello Nuclear Generating Plant. Routine Baseline Inspection Report. No Violations NotedSignificance Determination Process
IR 05000263/200200627 January 2003IR 05000263-02-006, on 10/01/2002 - 12/28/2002, Nuclear Management Company, LLC; Monticello. Routine Baseline Inspection ReportSafe Shutdown
High Radiation Area
Ultimate heat sink
Internal Flooding
Temporary Modification
Locked High Radiation Area
Significance Determination Process
Foreign Material Exclusion
Operability Determination
Exemption Request
Maintenance Rule Program
Failure to Scram
IR 05000263/200201129 July 2002IR 05000263-02-011, on 06/03-21/2002, Monticello Nuclear Generating Plant, Fire Protection TriennialFire Protection Program
IR 05000263/200230121 November 2002Er 05000263-02-301(DRS); Nuclear Management Company, LLC; on 10/14-18/02; Monticello Nuclear Generating Plant. Initial License Examination Report
IR 05000263/20030014 March 2003Annual Assessment Letter - Monticello Nuclear Power Plant (Report 05000263-03-001)
IR 05000263/200300231 March 2003IR 05000263-03-002(DRS), on 02/03/2003 Thru 02/21/2003, for Nuclear Management Company, LLC, Monticello, Mn; Monticello Nuclear Generating Plant Safety System Design and Performance Capability Inspection
IR 05000263/200300321 April 2003IR 05000263-03-003, on 12/29/02 - 03/31/03, Monticello Nuclear Generating Plant, Maintenance Effectiveness, Maintenance Risk Assessments and Emergenct Work Control, Personnel Performance During Non-Routine Plant Evolutions and EventsStroke time
Internal Flooding
Probabilistic Risk Assessment
Temporary Modification
Condition Adverse to Quality
Significance Determination Process
Job Performance Measure
Operability Determination
Maintenance Rule Program
IR 05000263/200300425 July 2003IR 05000263-03-004, on 04/01/03 - 06/30/03, Nuclear Management Co., Llc. Routine Integrated ReportHigh winds
High Radiation Area
Nondestructive Examination
Temporary Modification
Significance Determination Process
Liquid penetrant
Pressure Boundary Leakage
Fire Protection Program
Scaffolding
Power change
IR 05000263/200300523 October 2003IR 05000263-03-005, on 07/01/2003 Through 09/30/2003, for Monticello Nuclear Generating Plant, Monticello, Mn; Routine Integrated ReportSafe Shutdown
Shutdown Margin
High Radiation Area
Offsite Dose Calculation Manual
Fire Barrier
Temporary Modification
Significance Determination Process
Annual Radiological Environmental Operating Report
Fire Protection Program
Fire Watch
Failure to Scram
IR 05000263/200300622 January 2004IR 05000263-03-006; 10/01/2003-12/31/2003; Monticello Nuclear Generating Plant; Routine Integrated Inspection ReportMission time
Temporary Modification
Significance Determination Process
Maintenance Rule Program
Fire Protection Program
IR 05000263/200300716 December 2003IR 05000263-03-007(DRS); on 11/17/03 - 11/21/03; for Monticello Nuclear Generating Plant; Emergency Preparedness Specialist Report
IR 05000263/200300829 December 2003IR 05000263-03-008(DRS); on 10/06/03 - 10/10/03; for Monticello Nuclear Generating Plant; Ti 2515/148, Revision 2, Verification of Compliance with Interim Compensatory Measures Order
IR 05000263/200300914 January 2004IR 05000263-03-009; 11/3/2003 -12/05/2003; Nuclear Management Company, LLC; Monticello Nuclear Generating Plant; Identification and Resolution of ProblemsHigh Radiation Area
Locked High Radiation Area
Condition Adverse to Quality
Foreign Material Exclusion
IR 05000263/200400127 August 2003IR 05000263-04-001- Monticello, Mid-Cycle Assessment Letter
IR 05000263/200400231 March 2004IR 05000263-04-002, on 01/01/2004 - 03/31/2004; Monticello Nuclear Generating Plant; Fire Protection and Operability EvaluationsSafe Shutdown
Fire Barrier
Probabilistic Risk Assessment
Temporary Modification
Condition Adverse to Quality
Significance Determination Process
Fire Protection Program
Power change
Failure to Scram
IR 05000263/200400321 July 2004IR 05000263-04-003 on 04/01/2004-06/30/2004 for Monticello Nuclear Generating Plant. Adverse Weather, Operability Evaluation, Post Maintenance Testing, Access Control to Radiologically Significant AreasHigh Radiation Area
Hydrostatic
Probabilistic Risk Assessment
Temporary Modification
Condition Adverse to Quality
Significance Determination Process
Process Control Program
Earthquake
Fire Protection Program
Scaffolding
Unidentified leakage
Unidentified leak
IR 05000263/200400425 October 2004IR 05000263-04-004, on 07/01/2004 - 09/30/2004; Monticello Nuclear Generating Plant; Surveillance TestingHigh Radiation Area
Hydrostatic
Temporary Modification
Significance Determination Process
Fire Protection Program
GOTHIC
Overexposure
IR 05000263/200400524 January 2005IR 05000263-04-005, on 10/01/2004 - 12/31/2004, Monticello Nuclear Generating Plant, Routine Integrated Inspection ReportHigh Radiation Area
Stroke time
Internal Flooding
Probabilistic Risk Assessment
Temporary Modification
Significance Determination Process
Fire Protection Program
Substantial potential for an overexposure
Overexposure
IR 05000263/200400611 August 2004IR 05000263-04-006, on 04/06/2004 - 07/01/2004, Nuclear Management Company Corporate Office; Monticello Nuclear Generating Plant; Security Review of Access Authorization, Access Control, FFD, Work Hours, and Performance IndicatorsSignificance Determination Process
Affidavit
IR 05000263/20040073 December 2004IR 05000263-04-007 (Drs), on 10/18/2004 - 11/05/2004; Monticello Nuclear Generating Plant; Safety System Design and Performance CapabilityCondition Adverse to Quality
Aging Management
Significance Determination Process
Grace period
Power Uprate
Failure to Scram
IR 05000263/200500229 April 2005IR 05000263-05-002 on 01/01/2005 - 03/31/2005 for Monticello Nuclear Generating Plant. Maintenance EffectivenessHigh Radiation Area
Non-Destructive Examination
Stroke time
Probabilistic Risk Assessment
Nondestructive Examination
Temporary Modification
VT-2
Significance Determination Process
Job Performance Measure
Foreign Material Exclusion
Liquid penetrant
Pressure Boundary Leakage
Fire Protection Program
Scaffolding
IR 05000263/200500417 October 2005IR 05000263-05-004 on 07/01/2005 - 09/30/2005 for Monticello Nuclear Generating Plant; Problem Identification and ResolutionInternal Flooding
Temporary Modification
Significance Determination Process
Maintenance Rule Program
Fire Protection Program
IR 05000263/200500524 January 2006IR 05000263-05-005 on 10/01/2005 - 12/31/2005 for Monticello Nuclear Generating Plant. Routine Integrated ReportTemporary Modification
Significance Determination Process
Biofouling
Fire Protection Program
Substantial potential for an overexposure
Overexposure
IR 05000263/200500617 March 2005IR 05000263-05-006, on 01/31/2005 - 02/17/2005, Monticello Nuclear Generating Plant; Identification and Resolution of ProblemsHigh Radiation Area
Significance Determination Process
Operability Determination
IR 05000263/200500723 February 2005IR 05000263-05-007 (DRS) on 01/10/2005 - 01/12/2005 for Monticello Nuclear Generating Plant; Safety System Design and Performance CapabilitySignificance Determination Process
Siren
IR 05000263/200501113 October 2005IR 05000263-05-011(DRS); on 09/12/2005 - 09/16/2005; Monticello Nuclear Generating Plant; Evaluation of Changes, Tests, or Experiments (10 CFR 50.59)Fire Barrier
Internal Flooding
Significance Determination Process
Foreign Material Exclusion
IR 05000263/200501211 October 2005IR 05000263-05-012(DRS), on 08/29/2005 - 09/02/2005; Monticello Nuclear Generating Plant, Emergency Preparedness Specialist ReportSignificance Determination Process
Siren
IR 05000263/200501319 December 2005IR 05000263-05-013, on 10/17/2005 - 11/04/2005, Monticello Nuclear Generating Plant Fire Protection Triennial Baseline InspectionHot Short
Safe Shutdown
Fire Barrier
Emergency Lighting
Significance Determination Process
Fire Protection Program
IR 05000263/200530116 June 2005Er 05000263-05-301(DRS); 05/03/2005 - 05/12/2005; Monticello Nuclear Generating Plant; Initial License Examination Report
IR 05000263/20060012 March 2006(EOC) Annual Assessment Letter (Report 05000263/2006-001)
IR 05000263/200600226 April 2006IR 05000263-06-002, on 01/01/2006 - 03/31/2006, Monticello Nuclear Generating Plant, Post-Maintenance Testing and Surveillance TestingInternal Flooding
Temporary Modification
Aging Management
Significance Determination Process
Job Performance Measure
Scram Discharge Volume
Fire Protection Program
Scaffolding
Power change
IR 05000263/200600317 July 2006Inspection Report 05000263-06-003; 05000263-06-010; 04/01/2006 - 06/30/2006; Monticello Nuclear Generating Plant. Fire Protection and Surveillance TestingHigh winds
Temporary Modification
Significance Determination Process
Fire Protection Program
Downpower
IR 05000263/200600413 October 2006IR 05000263-06-004, 05000263-06-013; Nuclear Management Company LLC; 07/01/2006 - 09/30/2006; Monticello Nuclear Generating Plant. Routine Integrated Resident Inspection ReportUltimate heat sink
Stroke time
Internal Flooding
Temporary Modification
Significance Determination Process
Scram Discharge Volume
Fire Protection Program
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