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 Issue dateTitleTopic
ML24025A93631 January 2024Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
IR 05000263/202300431 January 2024Integrated Inspection Report 05000263/2023004
ML24024A07224 January 2024Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000263/202440122 January 2024Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401
L-MT-23-054, Subsequent License Renewal Application Supplement 811 January 2024Subsequent License Renewal Application Supplement 8Non-Destructive Examination
Coatings
Aging Management
License Renewal
L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data29 December 2023License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule DataSafe Shutdown
Shutdown Margin
Fire Barrier
Anticipated operational occurrence
Hydrostatic
Coatings
Emergency Lighting
Pressure and Temperature Limits Report
License Renewal
Subsequent License Renewal
Fire Protection Program
L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 218 December 2023Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2Offsite Dose Calculation Manual
ML23349A05715 December 2023and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota
IR 05000263/202340213 December 2023Security Baseline Inspection Report 05000263/2023402Fitness for Duty
Safeguards Contingency Plan
L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4611 December 20232023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46Power Uprate
L-MT-23-052, Subsequent License Renewal Application Supplement 730 November 2023Subsequent License Renewal Application Supplement 7Aging Management
License Renewal
L-MT-23-051, Update to the Technical Specification Bases28 November 2023Update to the Technical Specification Bases
L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 121 November 2023Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1
ML23319A31815 November 2023Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000263/202300313 November 2023Integrated Inspection Report 05000263/2023003 and 07200058/2023001Unanalyzed Condition
Packing leak
Commercial Grade Dedication
Enforcement Discretion
Functionality Assessment
Significance Determination Process
Annual Radiological Environmental Operating Report
Operability Determination
Fire Protection Program
Scaffolding
Power Uprate
L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-0913 November 202310 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09Grace period
L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.610 November 2023License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6Safe Shutdown
Surveillance Frequency Control Program
L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 19 November 2023Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1Coatings
VT-2
Aging Management
Through Wall Leak
ML23291A11023 October 2023Environmental Audit Summary and RCIs and RAIsLicense Renewal
Subsequent License Renewal
Environmental Justice
ML23285A30612 October 2023Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating PlantSafe Shutdown
Health Physics Network
Offsite Dose Calculation Manual
Earthquake
Minimum staff
Grace period
Integrated Public Alert and Warning System
Siren
L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 23 October 2023Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2Aging Management
License Renewal
Subsequent License Renewal
L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 322 September 2023Subsequent License Renewal Application Response to Request for Additional Information Set 3Coatings
Aging Management
License Renewal
Subsequent License Renewal
ML23262B03719 September 2023Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports
ML23248A20918 September 2023Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation ValveIncorporated by reference
Locked High Radiation Area
Scaffolding
ML23256A16813 September 2023Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection
IR 05000263/20230107 September 2023Commercial Grade Dedication Inspection Report 05000263/2023010Half scram
Commercial Grade Dedication
Condition Adverse to Quality
Significance Determination Process
L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 65 September 2023Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6Fire Barrier
Coatings
Aging Management
License Renewal
Subsequent License Renewal
Fire Protection Program
ML23214A24131 August 2023Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal ApplicationNon-Destructive Examination
Fire Barrier
Weld Overlay
Hydrostatic
Coatings
Operating Basis Earthquake
Nondestructive Examination
VT-2
Incorporated by reference
Aging Management
License Renewal
Subsequent License Renewal
Control of Heavy Loads
Fire Protection Program
Dissimilar Metal Weld
Power Uprate
IR 05000263/202300530 August 2023Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005)
L-MT-23-035, Subsequent License Renewal Application Supplement 528 August 2023Subsequent License Renewal Application Supplement 5Finite Element Analysis
Aging Management
Scram Discharge Volume
License Renewal
Pressure Boundary Leakage
ML23241A97321 August 2023Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263)
L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 115 August 2023Subsequent License Renewal Application Response to Request for Additional Information Set 1Hydrostatic
Operating Basis Earthquake
Incorporated by reference
Aging Management
License Renewal
Dissimilar Metal Weld
ML23222A01210 August 2023Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence
ML23215A1319 August 2023License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal ApplicationInternal Flooding
License Renewal
Subsequent License Renewal
Environmental Justice
Fatality
Power Uprate
Affidavit
IR 05000263/20230027 August 2023Plantintegrated Inspection Report 05000263/2023002High Radiation Area
Offsite Dose Calculation Manual
Enforcement Discretion
Met Tower
Nondestructive Examination
Functionality Assessment
FLEX
Aging Management
Operability Determination
Pressure Boundary Leakage
Fire Protection Program
Coast down
L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report31 July 20232023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary ReportThrough-Wall Leakage
L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-1131 July 202310 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11Locked High Radiation Area
Test box
Scaffolding
ML23198A04128 July 2023LRA Availability Letter
ML23206A23425 July 2023Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence
ML23201A03524 July 2023Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for InformationJob Performance Measure
ML23202A00321 July 2023Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1)Fitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
Fire Protection Program
L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 118 July 2023Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1Fire Barrier
Hydrostatic
Coatings
Operating Basis Earthquake
Aging Management
License Renewal
Subsequent License Renewal
Power Uprate
ML23195A17314 July 2023Revision of Standard Practice Procedures Plan
IR 05000263/202350113 July 2023Emergency Preparedness Inspection Report 05000263/2023501
L-MT-23-030, Subsequent License Renewal Application Supplement 34 July 2023Subsequent License Renewal Application Supplement 3Hydrostatic
Fire Protection Program
ML23199A2803 July 2023Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application Wright and Sherburne Counties, Minnesota
ML23181A02230 June 2023Revision to Correspondence Service List for Northern States Power - Minnesota
ML23178A24228 June 2023Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
ML24016A22827 June 2023Fws to NRC, Federal Agency Coordination Under ESA Section 7 and Concurrence That Monticello SLR Is Not Likely to Adversely Affect the Northern long-eared Bat
ML24016A22927 June 2023Fws to NRC, Monticello SLR List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project
ML24016A23027 June 2023Us Dept. of the Interior, Verification Letter for 'Monticello Subsequent License Renewal' for Specified Threatened and Endangered Species That May Occur in Proposed Project Location Consistent with the Minnesota-Wisconsin Endangered SpeciesSubsequent License Renewal
L-MT-23-025, Subsequent License Renewal Application Supplement 226 June 2023Subsequent License Renewal Application Supplement 2High Radiation Area
Fire Barrier
Coatings
Nondestructive Examination
Aging Management
Moisture barrier
License Renewal
Through-Wall Leakage
Fire Protection Program
Dissimilar Metal Weld
ML23047A1182 June 2023Notice of Intent to Conduct Scoping Process and Prepare an EISLicense Renewal
Subsequent License Renewal
ML23150A17230 May 2023Preparation and Scheduling of Operator Licensing Examinations
ML23123A42216 May 2023Request RR 001 to Use Later Edition of ASME BPV Section XI Code for Cisi ProgramNondestructive Examination
Incorporated by reference
ML23117A33815 May 2023Letter to Melanie Benjamin, Chief Executive, Mille Lacs Band of Ojibwe, from Chair Hanson Responds to Concerns Regarding the Tritium Leaks at the Monticello Nuclear Generating Plant
L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report10 May 2023Submittal of 2022 Annual Radioactive Effluent Release ReportGrab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report10 May 2023Submittal of 2022 Annual Radiological Environmental Operating ReportOffsite Dose Calculation Manual
Fukushima Dai-Ichi
Annual Radiological Environmental Operating Report
Earthquake
Chernobyl
IR 05000263/20234014 May 2023Security Baseline Inspection Report 05000263/2023401Affidavit
L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322 May 2023Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32MELLLA
ML23115A41728 April 2023Requesting for Withholding Information from Public Disclosure for Monticello Nuclear Generating Plant Core Operating Limits Report (COLR) for Cycle31, Revision 2
ML23116A26728 April 2023Request for Withholding Information from Public Disclosure for Monticello Nuclear Generating Plant Core Operating Limits Report (COLR) for Cycle 31, Revision 3
ML23111A22825 April 2023Information Meeting with Question and Answer Session to Discuss Nrc 2022 End-Of-Cycle Plant Performance Assessment of Monticello Nuclear Power StationOpen House
ML23114A12425 April 2023Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)18 April 20232022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
ML23079A07411 April 2023Request RR-003 to Use Later Edition of ASME Section XI Code for ISI Code of RecordIncorporated by reference
L-MT-23-010, Subsequent License Renewal Application Supplement 13 April 2023Subsequent License Renewal Application Supplement 1
ML22357A10031 March 2023and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations FacilitySafe Shutdown
Health Physics Network
High winds
Minimum staff
Fire Protection Program
Siren
ML23089A26730 March 2023Summary of Nuclear Property Insurance
ML23089A07629 March 2023Decommissioning Funding Status Reports
L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 328 March 2023Core Operating Limits Report (COLR) for Cycle 31, Revision 3MELLLA
ML23083B96024 March 2023Guarantee of Payment of Deferred Premiums
L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 217 March 2023Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2MELLLA
ML23069A27413 March 2023Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application
ML23069A28013 March 2023Tribal - Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application
IR 05000263/20220061 March 2023Annual Assessment Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2022006)Commercial Grade Dedication
Exemption Request
COVID-19
ML23059A3521 March 2023Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000263/2023010Commercial Grade Dedication
Large early release frequency
ML23048A03728 February 2023SLRA - Portal Letter
ML23058A15227 February 2023Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2023002Non-Destructive Examination
Aging Management
Foreign Material Exclusion
Scaffolding
ML23048A02324 February 2023Subsequent License Renewal Application - Audit PlanAging Management
License Renewal
Subsequent License Renewal
ML23047A17523 February 2023SLRA Acceptance LetterSubsequent License Renewal
L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)7 February 202310CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)Incorporated by reference
ML23010A00724 January 2023SLRA Availability Letter
L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program23 January 2023CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection ProgramNon-Destructive Examination
IR 05000263/202200417 January 2023Integrated Inspection Report 05000263/2022004Temporary Modification
Functionality Assessment
Operability Determination
Fire Protection Program
ML23012A15613 January 2023Issuance of Amendment No. 210 Re Revised Methodologies for Determining the Core Operating Limits (EPID L-2021-LLA-0144) - Non-proprietaryShutdown Margin
Anticipated operational occurrence
Feedwater Controller Failure
Time Critical Operator Action
Power change
ML23009A3539 January 2023Docket No. 50-263, Renewal License Numbers DPR-22 Application for Subsequent Renewal Operating LicenseLicense Renewal
Subsequent License Renewal
L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)6 January 2023Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)Anchor Darling
ML22362A11429 December 2022Project Manager Assignment
ML22318A21527 December 2022Issuance of Amendment No. 209 Ten-Year Inspection of the Diesel Generator Fuel Oil Storage TankAnticipated operational occurrence
Temporary Modification
Cyber Security
Qualified Offsite Circuit
Aging Management
Surveillance Frequency Control Program
ML23006A13319 December 2022Submittal of Revision 40 to Updated Safety Analysis ReportSafe Shutdown
Incorporated by reference
Aging Management
Surveillance Frequency Control Program
License Renewal
Subsequent License Renewal
Fire Protection Program
IR 05000263/202201215 December 2022Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000263/2022012Scaffolding
Weak link
L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative15 December 2022L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative
L-MT-22-049, Industry Groundwater Protection Initiative Special Report15 December 2022Industry Groundwater Protection Initiative Special ReportOffsite Dose Calculation Manual
L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4613 December 20222022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-22-048, Update to the Monticello Technical Specification Bases28 November 2022Update to the Monticello Technical Specification Bases
IR 05000263/202201321 November 2022Biennial Problem Identification and Resolution Inspection Report 05000263/2022013Packing leak
Cyber Security
Condition Adverse to Quality
FLEX
Scaffolding
Inattentive
Siren
IR 05000263/202200317 November 2022Reissue - Monticello Nuclear Generating Plant - Integrated Inspection Report 05000263/2022003Ultimate heat sink
Internal Flooding
Temporary Modification
Zebra Mussel
Functionality Assessment
FLEX
Aging Management
Significance Determination Process
Operability Determination
License Renewal
Fire Protection Program
ML22314A21616 November 2022Withdrawal of Alternative Request VR-08
ML22307A18214 November 2022Integrated Inspection Report 05000263/2022003Ultimate heat sink
Internal Flooding
Temporary Modification
Zebra Mussel
Functionality Assessment
FLEX
Aging Management
Fire Protection Program
ML22308A19610 November 2022Regulatory Audit Report Regarding License Amendment Request to Transition to Atrium 11 FuelAnticipated operational occurrence
L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval10 November 2022Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-045, Letter Submitting Post-Exam Package4 November 2022Letter Submitting Post-Exam Package
ML22264A10631 October 2022Issuance of Amendment No. 208 Residual Heat Removal Drywell Spray Header and Nozzle Surveillance FrequencyUltimate heat sink
Foreign Material Exclusion
IR 05000263/202240319 October 2022Security Baseline Inspection Report 05000263/2022403 (Public)Affidavit
ML22271A9163 October 2022Operator Licensing Examination Approval
ML22258A19015 September 2022Voluntary Security Clearance Program 2022 Insider Threat Program Self-Inspection
ML22251A1717 September 202210 CFR 50 Appendix E Evacuation Time Estimate Analysis for the Monticello and Prairie Island Nuclear Generating PlantsPandemic
Coronavirus
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan6 September 2022Sixth Interval Inservice Testing (1ST) PlanSafe Shutdown
Packing leak
Stroke time
Water Inventory Control
Squib
Incorporated by reference
Locked High Radiation Area
Abnormal operational transient
Surveillance Frequency Control Program
Scram Discharge Volume
Breakaway torque
Cold shutdown justification
Earthquake
Power Operated Valves
Scaffolding
L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency29 August 2022Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency
IR 05000263/202200529 August 2022Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2022005)Commercial Grade Dedication
Operator Manual Action
Open Phase Condition
Exemption Request
Coronavirus
ML22220A2728 August 2022Response to a Request for Additional Informational Regarding the Monticello Fuel Oil Storage Tank Inspection
ML22187A2913 August 2022Request for Withholding Information from Public Disclosure Monticello Nuclear Generating Plant
ML22189A01929 July 2022Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power SystemOpen Phase Condition
IR 05000263/202200228 July 2022Integrated Inspection Report 05000263/2022002Functionality Assessment
Operability Determination
Minimum staff
Fire Protection Program
Siren
ML22206A16625 July 2022Information Request to Support Upcoming Problem Identification and Resolution Inspection at Monticello Nuclear Generating PlantTemporary Modification
Aging Management
Maintenance Rule Program
L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)22 July 2022Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
ML22201A12920 July 2022Independent Spent Fuel Storage Installation, and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1)
L-MT-22-026, Changes to the Emergency Plan19 July 2022Changes to the Emergency PlanHealth Physics Network
High Radiation Area
Met Tower
Design basis earthquake
Severe Accident Management Guideline
Earthquake
Minimum staff
ML22182A3841 July 2022Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection 05000263/2022012Probabilistic Risk Assessment
ML22161A91510 June 2022and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Response to a Request for Additional Information Xcel Energy Amendment Request to Create a Common Emergency Plan and Emergency Operations.Safe Shutdown
Health Physics Network
Offsite Dose Calculation Manual
Earthquake
Minimum staff
Fire Protection Program
Grace period
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies6 June 2022Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome MethodologiesStroke time
Anticipated operational occurrence
Safe Shutdown Earthquake
Operating Basis Earthquake
MELLLA
L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency25 May 2022Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing FrequencySurveillance Frequency Control Program
ML22139A30919 May 2022Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information Inspection Report 05000263/2022003Ultimate heat sink
Temporary Modification
Flow Induced Vibration
ML22130A52212 May 2022Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report11 May 20222021 Annual Radioactive Effluent Release ReportGrab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report11 May 20222021 Annual Radiological Environmental Operating ReportOffsite Dose Calculation Manual
Fukushima Dai-Ichi
Annual Radiological Environmental Operating Report
Earthquake
Chernobyl
IR 05000263/202200110 May 2022Generation Plant - Integrated Inspection Report 05000263/2022001Internal Flooding
Enforcement Discretion
Temporary Modification
Functionality Assessment
Operability Determination
Severe Accident Management Guideline
Fire Protection Program
Scaffolding
Power change
Unidentified leakage
IR 05000263/20224025 May 2022Security Baseline Inspection Report 05000263/2022402; Independent Spent Fuel Storage Installation Security Inspection Report 07200058/2022401Affidavit
L-MT-22-016, 2021 Annual Report of Individual Monitoring28 April 20222021 Annual Report of Individual Monitoring
ML22110A12325 April 2022Withdrawal of Relief Requests PR-09 and VR-07 (Epids: L 2021 Llr 0095 and L 2022 Llr 0021)
ML22109A07520 April 2022Information Meeting with a Question-And-Answer Session to Discuss NRC 2021 End-Of-Cycle Plant Performance Assessment of Monticello and Prairie Island Nuclear Generating Plant
L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval18 April 2022Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing IntervalIncorporated by reference
ML22088A22429 March 2022Summary of Nuclear Property Insurance
ML22088A22729 March 2022Guarantee of Payment of Deferred Premiums
IR 05000263/202240128 March 2022Generation Plant - Cyber Security Inspection Report 05000263/2022401Cyber Security
L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency18 March 2022License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance FrequencyUltimate heat sink
Foreign Material Exclusion
Power Operated Valves
ML22076A13517 March 2022Preparation and Scheduling of Operator Licensing Examinations
L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System15 March 2022Special Report for the Bypass of the Offgas Treatment Storage SystemOffsite Dose Calculation Manual
L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)7 March 202210 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)Surveillance Frequency Control Program
ML22067A0847 March 202210 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-28 (LMT-22-007)Incorporated by reference
IR 05000263/20210062 March 2022Annual Assessment Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2021006)Commercial Grade Dedication
Exemption Request
Coronavirus
ML22059A98828 February 2022Revision to Correspondence Service List
ML22056A02424 February 2022Submittal of 2021 Fitness of Duty Performance DataFitness for Duty
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)18 February 202210 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
IR 05000263/202100428 January 2022Integrated Inspection Report 05000263/2021004 and 07200058/2021001Internal Flooding
Nondestructive Examination
Temporary Modification
Functionality Assessment
FLEX
Job Performance Measure
Operability Determination
Fire Protection Program
L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report20 January 2022Technical Specification 5.6.4 Post Accident Monitoring ReportPost Accident Monitoring
L-MT-22-003, Submittal of Revision 1 of the Core Operating Limits Report for Cycle 3111 January 2022Submittal of Revision 1 of the Core Operating Limits Report for Cycle 31MELLLA
L-MT-21-068, 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4615 December 20212021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-21-072, License Amendment Request: Revise MNGP Technical Specifications to Support a Ten-Year Inspection of the Diesel Generator Fuel Oil Storage Tank13 December 2021License Amendment Request: Revise MNGP Technical Specifications to Support a Ten-Year Inspection of the Diesel Generator Fuel Oil Storage TankAnticipated operational occurrence
Qualified Offsite Circuit
FLEX
Aging Management
Surveillance Frequency Control Program
Offsite Circuit
Fire Protection Program
ML21347A97413 December 2021Independent Spent Fuel Storage Installation Decommissioning Funding PlansDecommissioning Funding Plan
Authorized possession limits
Aging Management
COVID-19
Fuel cladding
Fire Watch
Scaffolding
ML21342A37613 December 2021Confirmation of Initial License Examination
L-MT-21-063, Notice of Intent to Pursue Subsequent License Renewal for Plant1 December 2021Notice of Intent to Pursue Subsequent License Renewal for Plant
L-MT-21-067, Update to the Monticello Technical Specification Bases29 November 2021Update to the Monticello Technical Specification Bases
ML21322A23618 November 2021Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2022401Cyber Security
IR 05000263/202142015 November 2021Security Baseline Inspection Report Cover Letter 05000263 2021420Affidavit
ML21277A2958 November 2021Request for Withholding Information from Public Disclosure
IR 05000263/202100327 October 2021Plan, Integrated Inspection Report 05000263/2021003Internal Flooding
Cyber Security
Functionality Assessment
Locked High Radiation Area
FLEX
Aging Management
Operability Determination
Coronavirus
COVID-19
Fire Protection Program
ML21223A28015 October 2021Issuance of Amendment No. 207 Adoption of TSTF-564 Safety Limit MCPRReactor Vessel Water Level
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
IR 05000263/20210108 October 2021Design Basis Assurance Inspection (Teams) Inspection Report 05000263/2021010Internal Flooding
Probabilistic Risk Assessment
Significance Determination Process
Large early release frequency
Time Critical Operator Action
Earthquake
Coronavirus
COVID-19
ML21278A1855 October 202110 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-02 (LMT-21-049)Stroke time
Scaffolding
IR 05000263/20210051 September 2021Updated Inspection Plan for Monticello Nuclear Generating Plant 2 (Report 05000263/2021005)Cyber Security
Open Phase Condition
Exemption Request
Coronavirus
IR 05000263/20215011 September 2021Emergency Preparedness Biennial Exercise Inspection Report 05000263/2021501Coronavirus
COVID-19
L-MT-21-038, 2021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report17 August 20212021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
ML21215A2173 August 2021Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for InformationJob Performance Measure
IR 05000263/20210023 August 2021Integrated Inspection Report 05000263/2021002High Radiation Area
Nondestructive Examination
Temporary Modification
VT-2
Functionality Assessment
Locked High Radiation Area
FLEX
Aging Management
Scram Discharge Volume
Operability Determination
Coronavirus
COVID-19
Pressure Boundary Leakage
Fire Protection Program
Coast down
L-MT-21-044, License Amendment Request: Application to Adopt Advanced Framatome Methodologies29 July 2021License Amendment Request: Application to Adopt Advanced Framatome MethodologiesShutdown Margin
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Finite Element Analysis
Feedwater Controller Failure
MELLLA
Fuel cladding
Power change
ML21148A27412 July 2021Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4bSafe Shutdown
High winds
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Tornado Missile
Water Inventory Control
Internal Flooding
Probabilistic Risk Assessment
Squib
Qualified Offsite Circuit
Emergency Lighting
FLEX
Tornado-Generated Missile
Fukushima Dai-Ichi
Seismically rugged
Surveillance Frequency Control Program
Scram Discharge Volume
Large early release frequency
MELLLA
Flooding Focused Evaluation
Maintenance Rule Program
Offsite Circuit
L-MT-21-043, Supplement to License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b30 June 2021Supplement to License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4bProbabilistic Risk Assessment
Large early release frequency
ML21160A1049 June 2021Submittal of Changes to the Emergency Plan
ML21147A5083 June 2021Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML21146A19025 May 2021Notice of Information Meeting with a Question and Answer Session to Discuss NRC 2020 End-Of-Cycle Plant Performance Assessment of Monticello Nuclear Generating Plant
ML21134A10013 May 2021Submittal of Core Operating Limits Report for Cycle 31
ML21133A49513 May 20212020 Annual Radiological Environmental Operating ReportOffsite Dose Calculation Manual
Fukushima Dai-Ichi
Annual Radiological Environmental Operating Report
Earthquake
Chernobyl
L-MT-21-033, 2020 Annual Radioactive Effluent Release Report13 May 20212020 Annual Radioactive Effluent Release ReportOffsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
L-MT-21-035, Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System7 May 2021Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System
ML21130A3027 May 2021Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System
IR 05000263/202100130 April 2021Integrated Inspection Report 05000263/2021001Packing leak
Enforcement Discretion
Functionality Assessment
Operability Determination
Coronavirus
COVID-19
Offsite Circuit
Fire Protection Program
Power change
Coast down
Weak link
L-MT-21-028, 2020 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)28 April 20212020 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-21-031, Preparation and Scheduling of Operator Licensing Examinations20 April 2021Preparation and Scheduling of Operator Licensing Examinations
L-MT-21-017, Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 220 April 2021Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 2Mission time
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
ML21106A21814 April 2021NRC Letter Re NRC Office of Investigations Report No. 3-2020-006
ML21099A0908 April 2021Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000263/2021011Operator Manual Action
Open Phase Condition
ML21067A0387 April 2021U.S. NRC Analysis of Northern States Power Company'S Initial and Updated Decommissioning Funding Plans for the Prairie Island Nuclear Generating Plant, Units 1 and 2, and Monticello Nuclear Generating Plant Independent Spent Fuel Storage inDecommissioning Funding Plan
Authorized possession limits
ML21088A18029 March 2021Decommissioning Funding Status Reports
ML21085A85826 March 2021Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000263/2021010Stroke time
Temporary Modification
Aging Management
Job Performance Measure
Large early release frequency
Coronavirus
ML21084A26125 March 2021Summary of Nuclear Property Insurance
ML21084A26625 March 2021Guarantee of Payment of Deferred Premiums
L-MT-21-016, Nuclear Material Transaction Report25 March 2021Nuclear Material Transaction Report
L-MT-21-015, Nuclear Material Transaction Report22 March 2021Nuclear Material Transaction Report
L-MT-21-002, Northern States Power Company - Nuclear Material Transaction Report5 March 2021Northern States Power Company - Nuclear Material Transaction Report
IR 05000263/20200064 March 2021Annual Assessment Letter for the Monticello Nuclear Generating Plant (Report 05000263/2020006)Open Phase Condition
Exemption Request
Coronavirus
IR 05000263/20200102 March 2021Reissue - Monticello Nuclear Generating Plant - Biennial Problem Identification and Resolution Inspection Report 05000263/2020010Stroke time
Internal Flooding
Past operability
Condition Adverse to Quality
Foreign Material Exclusion
Scram Discharge Volume
Pandemic
Coronavirus
COVID-19
Flow Induced Vibration
Operability Assessment
Power Uprate
ML21057A05026 February 2021Submittal of Fitness for Duty Performance Data for 2020Fitness for Duty
ML21070A10411 February 20218 to the Updated Safety Analysis ReportSafe Shutdown
Fire Protection Program
ML21029A29829 January 2021Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2021002Nondestructive Examination
Aging Management
Foreign Material Exclusion
Scaffolding
L-MT-21-003, Submission of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)27 January 2021Submission of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)
ML21013A45421 January 2021Request for Withholding Information from Public Disclosure
IR 05000263/202000420 January 2021Integrated Inspection Report 05000263/2020004High winds
Internal Flooding
Enforcement Discretion
Functionality Assessment
Foreign Material Exclusion
Operability Determination
Time Critical Operator Action
Coronavirus
COVID-19
Fire Protection Program
Coast down
ML21013A42213 January 2021Biennial Problem Identification and Resolution Inspection Report 05000263/2020010Stroke time
Internal Flooding
Past operability
Condition Adverse to Quality
Foreign Material Exclusion
Scram Discharge Volume
Pandemic
Coronavirus
COVID-19
Flow Induced Vibration
ML20328A0388 January 2021Regulatory Audit Summary License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times RITSTF Initiative 4B
ML20352A3498 January 2021Issuance of Amendment No. 205, Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-582, RPV WIC Enhancements, and TSTF-583-T, TSTF-582 Diesel Generator VariationHigh Radiation Area
Water Inventory Control
Surveillance Frequency Control Program
Fuel cladding
Offsite Circuit
ML20317A13622 December 2020Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0174 (COVID-19))Exemption Request
Pandemic
Coronavirus
COVID-19
ML20346A09721 December 2020Request for Alternative for Examination of Reactor Pressure Vessel Threads in Flange
L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times21 December 2020Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion TimesSafe Shutdown
Reactor Vessel Water Level
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Multiple Spurious Operation
FLEX
Fukushima Dai-Ichi
Thermoset
Scram Discharge Volume
Large early release frequency
Earthquake
Fuel cladding
Offsite Circuit
Very Early Warning Fire Detection
L-MT-20-045, 2020 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4616 December 20202020 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML20336A1609 December 2020Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XIIncorporated by reference
IR 05000263/20203019 December 2020NRC Initial License Examination Report 05000263/2020301Job Performance Measure
IR 05000263/20204023 December 2020Security Baseline Inspection Report 05000263/2020402 (Cover Letter Only)Affidavit
L-MT-20-031, 10 CFR 50.55a Request No. RR-018, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI30 November 202010 CFR 50.55a Request No. RR-018, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XIIncorporated by reference
ML20324A63125 November 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi AccidentUnanalyzed Condition
Ultimate heat sink
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Earthquake
Backfit
L-MT-20-043, Update to the Monticello Technical Specification Bases24 November 2020Update to the Monticello Technical Specification Bases
IR 05000263/20200039 November 2020Integrated Inspection Report 05000263/2020003Packing leak
Internal Flooding
Temporary Modification
Functionality Assessment
Scram Discharge Volume
Operability Determination
Coronavirus
COVID-19
Fire Protection Program
IR 05000263/20200159 November 2020NRC Inspection Report 05000263/2020015Safe Shutdown
Past operability
Probabilistic Risk Assessment
Significance Determination Process
Large early release frequency
Fire Protection Program
L-MT-20-023, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR3 November 2020License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPRReactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Offsite Dose Calculation Manual
Anticipated operational occurrence
Surveillance Frequency Control Program
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding
ML20307A0172 November 2020Request for Alternative for Core Support Structure Weld ExaminationIncorporated by reference
ML20293A25616 October 2020Operator Licensing Examination Approval
IR 05000263/202001313 October 2020Design Basis Assurance Inspection (Programs) Inspection Report 05000263/2020013Stroke time
Anchor Darling
Squib
Operability Determination
Power-Operated Valves
Coronavirus
COVID-19
Weak link
ML20275A3941 October 2020Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at the Monticello Nuclear Generating PlantTemporary Modification
Aging Management
Maintenance Rule Program
Coronavirus
IR 05000263/202040122 September 2020Security Baseline Inspection Report 05000263/2020401 (Cover Letter Only)Affidavit
L-MT-20-018, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements22 September 2020License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) EnhancementsReactor Vessel Water Level
High Radiation Area
Stroke time
Water Inventory Control
Operating Basis Earthquake
Qualified Offsite Circuit
Surveillance Frequency Control Program
Control of Heavy Loads
Fuel cladding
Recently irradiated fuel
Offsite Circuit
Scaffolding
ML20210M0148 September 2020and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application RulesTime of Discovery
IR 05000263/20200051 September 2020Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2020005)Fitness for Duty
Operator Manual Action
Cyber Security
Open Phase Condition
Exemption Request
Power-Operated Valves
COVID-19
IR 05000263/20200023 August 2020Integrated Inspection Report 05000263/2020002Packing leak
Past operability
Anchor Darling
Temporary Modification
Functionality Assessment
Scram Discharge Volume
Operability Determination
Coronavirus
COVID-19
Fire Protection Program
Downpower
Weak link
Unidentified leakage
Siren
Exclusive Use
ML20213C71431 July 2020Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant - Submittal of Quality Assurance Topical Report (NSPM-1)
ML20153A80431 July 2020Co. - Issuance of Amendments Revising Emergency Action RA3
ML20184A01322 July 2020Units 1 and 2 and Prairie Island ISFSI - Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Sections I, II, IV, and VI (EPID L-2020-LLE-0108 (COVID-19))Exemption Request
Pandemic
Coronavirus
L-MT-20-024, Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval20 July 2020Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval
ML20174A54515 July 2020Request for Alternative for Pressure Isolation Valve TestingIncorporated by reference
ML20183A17630 June 2020Public Webinar to Discuss NRC 2019 End-of-Cycle Plant Performance Assessment of Prairie Island Nuclear Generating Plant and Monticello Nuclear Generating Plant
ML20183A16530 June 2020Public Webinar to Discuss NRC 2019 End-Of-Cycle Plant Performance Assessment of Prairie Island Nuclear Generating Plant and Monticello Nuclear Generating Plant
IR 05000263/202001430 June 2020License Renewal Phase IV Report 05000263/2020014Coatings
Aging Management
License Renewal
Subsequent License Renewal
Coronavirus
COVID-19
L-MT-20-015, Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan8 June 2020Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan
ML20153A4011 June 2020and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME CodeLiquid penetrant
ML20134H95829 May 2020and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME CodeWeld Overlay
Liquid penetrant
ML20135G99229 May 2020and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME CodeLiquid penetrant
IR 05000263/202001226 May 2020Inspection of the Implementation of EA-13-09: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Report 05000263/2020012FLEX
B.5.b
Coronavirus
COVID-19
ML20133K05314 May 2020Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
L-MT-20-014, 2019 Annual Radioactive Effluent Release Report14 May 20202019 Annual Radioactive Effluent Release ReportGrab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
L-MT-20-013, 2019 Annual Radiological Environmental Operating Report14 May 20202019 Annual Radiological Environmental Operating ReportOffsite Dose Calculation Manual
Fukushima Dai-Ichi
Annual Radiological Environmental Operating Report
Earthquake
Chernobyl
ML20134H92812 May 2020Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000263/2020013Commercial Grade Dedication
Squib
Power-Operated Valves
Weak link
IR 05000263/20200014 May 2020Integrated Inspection Report 05000263/2020001Internal Flooding
Enforcement Discretion
Temporary Modification
Functionality Assessment
Operability Determination
Coronavirus
COVID-19
Fire Protection Program
Power change
L-MT-20-008, 2019 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)24 April 20202019 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
ML20098F9897 April 2020Confirmation of Initial License Examination
ML20099F3626 April 2020Lr Phase 4 Request for InformationAging Management
Coronavirus
IR 05000263/202001131 March 2020Triennial Fire Protection Inspection Report 05000263/2020011Hot Short
Safe Shutdown
Time Critical Operator Action
Fire Protection Program
L-MT-20-003, License Amendment Request: Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4b30 March 2020License Amendment Request: Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4bSafe Shutdown
High winds
Shutdown Margin
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Tornado Missile
Water Inventory Control
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Surveillance Frequency Control Program
Scram Discharge Volume
Feedwater Controller Failure
Large early release frequency
B.5.b Mitigating Strategies
Earthquake
Turbine Missile
Offsite Circuit
Fire Protection Program
IR 05000263/201500726 March 2020RE-Issued - Monticello Nuclear Generating Plant - NRC Component Design Bases Inspection (Inspection Report 05000263/2015007)Safe Shutdown
Mission time
Internal Flooding
Probabilistic Risk Assessment
Significance Determination Process
Job Performance Measure
Large early release frequency
Time Critical Operator Action
Battery sizing
Weak link
Power Uprate
ML20083G90320 March 2020Revised Non-Cited Violation - Monticello Nuclear Generating Plant NRC Component Design Bases Inspection Report 05000263/2015007
ML20077G73117 March 2020Summary of Nuclear Property Insurance
ML20076F97916 March 2020Revision to Correspondence Service List for Northern States Power - Minnesota
ML20076G01016 March 2020Guarantee of Payment of Deferred Premiums
ML20076F94916 March 2020Revision to Correspondence Service List for Northern States Power -Minnesota
IR 05000263/20190063 March 2020Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2019006 and 07200058/2019006)Open Phase Condition
ML20058F94327 February 2020and Prairie Island Nuclear Generating Plant, Units 1 and 2 - License Amendment Request: Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules Revision 4Time of Discovery
Incorporated by reference
Missed surveillance
ML20056C76925 February 2020Submittal of 2019 Fitness for Duty Performance Data ReportFitness for Duty
ML20055F36724 February 2020Information Request to Support Upcoming Temporary Instruction 2515/193 Inspection at Monticello Nuclear Generating PlantFLEX
ML20045E89414 February 2020Response to a Request for Additional Information for Proposed 10 CFR 50.55a(z)(2) Alternatives to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, and AS
L-MT-20-004, 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval14 February 202010 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) IntervalNon-Destructive Examination
Water Inventory Control
Flow Induced Vibration
L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange31 January 202010 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in FlangeFinite Element Analysis
Weak link
IR 05000263/201900424 January 2020Integrated Inspection Re 05000263/2019004Shutdown Margin
High Radiation Area
Hydrostatic
Temporary Modification
Functionality Assessment
Condition Adverse to Quality
Fire Protection Program
Power change
L-MT-20-005, Submission of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)23 January 2020Submission of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)
L-MT-20-001, 10 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve Testing16 January 202010 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve TestingPower-Operated Valves
L-MT-19-053, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4616 December 2019Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-19-058, Revision 37 to Updated Safety Analysis Report9 December 2019Revision 37 to Updated Safety Analysis ReportSafe Shutdown
Fire Barrier
Fire Protection Program
IR 05000263/201901227 November 2019Follow-Up Inspection Regarding the Assessment and Management of Shutdown Risk During the Refueling Outage Report 05000263/2019012Water Inventory Control
Time to boil
Enforcement Discretion
Functionality Assessment
Significance Determination Process
Large early release frequency
Operability Determination
ML19324F85120 November 2019Long-Term Replacement Steam Dryer Inspection Plan
ML19322C05114 November 2019Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report Number 05000263/2020011Safe Shutdown
Fire Barrier
Probabilistic Risk Assessment
Fire impairment
Job Performance Measure
Fire Protection Program
ML19305A80112 November 2019Correction Letter for Amendment No. 203 to Renewed Operating License No. DPR-22High winds
Internal Flooding
Probabilistic Risk Assessment
L-MT-19-050, Submittal of Notification of Changes to the Emergency Response Data System (ERDS)1 November 2019Submittal of Notification of Changes to the Emergency Response Data System (ERDS)
IR 05000263/201941129 October 2019NRC Security Baseline Inspection Report 05000263/2019411; Independent Spent Fuel Storage Security Inspection Report; 07200058/2019401 (Letter Only)Affidavit
L-MT-19-046, Changes to the Monticello Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan. and Independent Spent Fuel Storage Installation Security Program24 October 2019Changes to the Monticello Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan. and Independent Spent Fuel Storage Installation Security Program
ML19288A17817 October 2019Exelon Fleet: Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
IR 05000263/201901116 October 2019Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000263/2019011Internal Flooding
Significance Determination Process
Power Uprate
IR 05000263/20195012 October 2019Emergency Preparedness Biennial Exercise Inspection Report 05000263/2019501 (DRS-G.Hansen)
ML19255F5821 October 2019Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4376; EPID No. L-2014-JLD-0052)Ultimate heat sink
Tornado Missile
FLEX
Fukushima Dai-Ichi
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Battery sizing
Earthquake
Hardened vent
GOTHIC
ML19270E86527 September 2019Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information (Rbaker)Job Performance Measure
L-MT-19-036, Update to 2018 Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4616 September 2019Update to 2018 Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML19246A3513 September 2019Independent Spent Fuel Storage Installation, and Monticello - Offsite Nuclear Emergency Plan Revision
ML19176A42129 August 2019Issuance of Amendment No. 203 Adoption of 10 CFR 50.69Safe Shutdown
High winds
Tornado Missile
Internal Flooding
Probabilistic Risk Assessment
FLEX
Large early release frequency
Earthquake
IR 05000263/201900528 August 2019Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2019005)Cyber Security
ML19231A22416 August 2019Proposed Alternative to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping & ASME Code Case N-789-3, Alternative Requirement
L-MT-19-028, 2019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection Summary9 August 20192019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection SummaryHydrostatic
VT-2
Earthquake
IR 05000263/20190022 August 2019Integrated Inspection Report 05000263/2019002Unanalyzed Condition
High Radiation Area
Internal Flooding
Past operability
Enforcement Discretion
Nondestructive Examination
Temporary Modification
Functionality Assessment
FLEX
Significance Determination Process
Large early release frequency
Operability Determination
Fuel cladding
Pressure Boundary Leakage
Fire Protection Program
ML19213A1601 August 2019Submittal of Quality Assurance Topical Report (NSPM-1), Revision 14Fitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
Fire Protection Program
ML19162A09330 July 2019Issuance of Amendment No, 202 Regarding Deletion of the Note Associated with Technical Specification 3.5.1., Erccs - OperatingWater Inventory Control
ML19148A69412 June 2019Request for Relief for Coverage of Nozzle-To-Vessel Weld ExaminationsNondestructive Examination
VT-2
Incorporated by reference
Aging Management
Pressure Boundary Leakage
L-MT-19-033, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.467 June 2019Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML19143A26729 May 2019Assignment of Lisa M. Regner as Acting Branch Chief Effective May 26, 2019
ML19144A25723 May 2019Public Open House to Discuss the 2018 End-Of-Cycle Performance Assessment of the Monticello Nuclear Generating PlantOpen House
IR 05000263/201941020 May 2019NRC Security Baseline Inspection Report 05000263/2019410 (Cover Letter Only) (DRS-M.Ziolkowski)Affidavit
L-MT-19-030, Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors.15 May 2019Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors.High winds
Internal Flooding
Probabilistic Risk Assessment
ML19136A02015 May 2019Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza)
IR 05000263/20190017 May 2019NRC Integrated Inspection Report 05000263/2019001Internal Flooding
Enforcement Discretion
Functionality Assessment
Operability Determination
Fire Protection Program
Power change
Downpower
ML14224A3563 May 2019Letter to All Holders of Licenses for Operating Power Reactors - Rescission of Certain Power Reactor Security Orders Applicable to Nuclear Power Plants
L-MT-19-026, Submittal of 2018 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)26 April 2019Submittal of 2018 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..25 April 2019Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..High winds
Tornado Missile
FLEX
Design basis earthquake
Severe Accident Management Guideline
Hardened vent
L-MT-19-021, Submittal of Changes to Emergency Plan24 April 2019Submittal of Changes to Emergency Plan
ML19074A26922 April 2019Non-Proprietary - Issuance of Amendment Revision to Technical Specifications 2.1.2 Safety Limit Minimum Critical Power RatioReactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Fuel cladding
L-MT-19-024, Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.118 April 2019Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.1
ML19106A01715 April 2019GFE Results, March 2019
ML19088A04929 March 2019Decommissioning Funding Status Reports
ML19085A47726 March 2019Confirmatory Order, EA-14-193, Closure LetterExemption Request
ML19081A21622 March 2019Summary of Nuclear Property Insurance
ML19080A28821 March 2019Guarantee of Payment of Deferred Premiums
ML19074A30415 March 2019Ltr. 03/15/19 Monticello Nuclear Generating Plant - Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000263/2019011 (DRS-D.Szwarc)
L-MT-19-018, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors13 March 2019Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power ReactorsHigh winds
Tornado Missile
Internal Flooding
Probabilistic Risk Assessment
FLEX
Large early release frequency
TORMIS
IR 05000263/201901012 March 2019Ltr. 03/12/19 Monticello Nuclear Generating Plant - Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000263/2019010 (DRS-A.Dahbur)Open Phase Condition
ML19065A20011 March 2019Correction to License Amendment No. 200 Related to Adoption of TSTF-425, Relocated Surveillance Frequencies to Licensee Control - RITSTF Initiative 5BSafe Shutdown
High winds
Reactor Vessel Water Level
High Radiation Area
Water Inventory Control
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Squib
Surveillance Frequency Control Program
Scram Discharge Volume
Large early release frequency
Overtravel
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
ML19052A14211 March 2019Correction to License Amendment No. 198 Related to Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory ControlReactor Vessel Water Level
Water Inventory Control
ML19070A1308 March 2019Ltr. 03/08/19 Monticello Nuclear Generating Plant - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000263/2019003 (DRS-V.Petrella)Temporary Modification
Aging Management
Flow Induced Vibration
ML19065A0835 March 2019Ltr. 03/05/19 Monticello Nuclear Generating Plant - Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2019002 (DRS-E.Fernandez)Nondestructive Examination
Foreign Material Exclusion
Scaffolding
IR 05000263/20180064 March 2019Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2018006 and 07200058/2018006)
ML19058A39627 February 2019Submittal of Fitness for Duty Performance Data Report, Including Annual Fatigue Reporting Form and Single Positive Test Forms for 2018. (Cover Letter)Fitness for Duty
ML18289A73514 February 2019Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section Iii.G.2.AHot Short
Safe Shutdown
Fire Barrier
Probabilistic Risk Assessment
Exemption Request
Fire Protection Program
ML19045A37212 February 2019March 2019 GFE Cover Letter Riii
IR 05000263/20180046 February 2019NRC Integrated Inspection Report 05000263/2018004 and 07200058/2018002Temporary Modification
Functionality Assessment
Scram Discharge Volume
Operability Determination
Exemption Request
Maintenance Rule Program
Fire Protection Program
Downpower
Unidentified leakage
L-MT-19-003, Thirty Day Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4628 January 2019Thirty Day Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML19007A09028 January 2019Issuance of Amendment Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5BSafe Shutdown
High winds
Reactor Vessel Water Level
High Radiation Area
Water Inventory Control
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Squib
Surveillance Frequency Control Program
Scram Discharge Volume
Large early release frequency
Overtravel
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
Backfit
ML19014A03914 January 2019Independent Spent Fuel Storage Installation, and Monticello, Offsite Nuclear Emergency Plan Revision
IR 05000263/201841114 January 2019NRC Security Baseline Inspection Report 05000263/2018411 (Cover Letter Only) (DRS-M.Ziolkowski)Affidavit
ML19009A2508 January 2019GFE Annual Registration Letter - 2019 Examinations, Region III
IR 05000263/201830127 December 2018NRC Initial License Examination Report 05000263/2018301Stroke time
Job Performance Measure
L-MT-18-079, Ninth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ...17 December 2018Ninth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ...Tornado Missile
FLEX
Hardened vent
ML18333A31513 December 2018Request for Withholding Information from Public Disclosure
L-MT-18-071, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4612 December 2018Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-18-076, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel10 December 2018Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
L-MT-18-022, 2018 Monticello Outline Submittal Letter6 December 20182018 Monticello Outline Submittal Letter
ML18291B21426 November 2018Issuance of Amendment Adoption of TSTF-551 Revise Secondary Containment Surveillance Requirements
L-MT-18-074, Independent Spent Fuel Storage Installation - Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel20 November 2018Independent Spent Fuel Storage Installation - Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
L-MT-18-073, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee...20 November 2018Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee...Stroke time
Water Inventory Control
Operating Basis Earthquake
Surveillance Frequency Control Program
Scaffolding
ML18324A67916 November 2018Update to the Monticello Technical Specification Bases
L-MT-18-009, License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO Note12 November 2018License Amendment Request: Revise Limiting Condition for Operation (LCO) of Specification 3.5.1, Emergency Core Cooling System - Operating, to Remove the LCO NoteWater Inventory Control
L-MT-18-060, License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.112 November 2018License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.1Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
MELLLA
Fuel cladding
L-MT-18-067, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel9 November 2018Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
L-MT-18-059, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel31 October 2018Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
IR 05000263/201800331 October 2018NRC Integrated Inspection Report 05000263/2018003 and 07200058/2018001High winds
Packing leak
Internal Flooding
Functionality Assessment
Design basis earthquake
Annual Radiological Environmental Operating Report
Operability Determination
Exemption Request
Maintenance Rule Program
Liquid penetrant
Fire Protection Program
Siren
IR 05000263/201801030 October 2018NRC Biennial Problem Identification and Resolution Inspection Report 05000263/2018010Coatings
Condition Adverse to Quality
Maintenance Rule Program
Fire Protection Program
Unidentified leak
ML18250A07529 October 2018Issuance of Amendment Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory ControlShutdown Margin
Reactor Vessel Water Level
High Radiation Area
Water Inventory Control
Hydrostatic
Probabilistic Risk Assessment
Fuel cladding
Pressure Boundary Leakage
Recently irradiated fuel
ML18299A08426 October 2018Submittal of Offsite Nuclear Emergency Plan Revision
IR 05000263/201801224 October 2018NRC Design Bases Assurance Inspection (Teams); Inspection Report 05000263/2018012 (DRS-J.Benjamin)Safe Shutdown
Stroke time
Tornado Missile
Internal Flooding
Condition Adverse to Quality
FLEX
Tornado Generated Missile
Significance Determination Process
Tornado Missile Protection
Fuel cladding
L-MT-18-058, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ...23 October 2018Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ...
ML18296A71523 October 2018Operator Licensing Examination Approval (Jxd)
ML18270A01519 October 2018and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM CodeIncorporated by reference
Through-Wall Leak
Through-Wall Leakage
L-MT-18-057, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel18 October 2018Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
L-MT-18-055, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel28 September 2018Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
L-MT-18-053, Thirty Day Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4628 September 2018Thirty Day Report of Changes in the Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML18267A18924 September 2018Independent Spent Fuel, Monticello, Submit Changes in Foreign Ownership, Control or Influence
ML18262A37820 September 2018Letter to T.O'Connor Exemption from Certain Provisions of 10 CFR 72.212 and 72.214 - Storage Standardized Nuhoms Dry Shielded Canisters 11-15 at Monticello Nuclear Generating Plant Isfsi(Cac No.001028, Dockets 72-58 and 50-263, EPID L-2017-Exemption Request
L-MT-18-039, Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel17 September 2018Thirty (30) Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
L-MT-18-051, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control,11 September 2018Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control,Water Inventory Control
L-MT-18-044, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan28 August 2018Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency PlanHealth Physics Network
High Radiation Area
Design basis earthquake
Severe Accident Management Guideline
Earthquake
Minimum staff
IR 05000263/201800528 August 2018Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2018005)Fitness for Duty
ML18218A5386 August 2018Information Request to Support Upcoming Problem Identification and Resolution Inspection at the Monticello Nuclear Generating PlantTemporary Modification
Maintenance Rule Program
ML18213A1541 August 2018Island Independent Spent Fuel Storage Installation, and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1 Revision 13Fitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Coatings
Nondestructive Examination
Temporary Modification
Cyber Security
Condition Adverse to Quality
Process Control Program
Fire Protection Program
L-MT-18-043, Online Reference Portal for NRC Review of License Amendment Requests to Adopt TSTF-425 and 10 CFR 50.6931 July 2018Online Reference Portal for NRC Review of License Amendment Requests to Adopt TSTF-425 and 10 CFR 50.69
IR 05000263/201800227 July 2018NRC Integrated Inspection Report 05000263/2018002Packing leak
Internal Flooding
Enforcement Discretion
Functionality Assessment
Aging Management
Significance Determination Process
Operability Determination
Fire Protection Program
Downpower
Unidentified leakage
ML18206A42025 July 2018Clarification of Discrepancies in Safety Evaluations for Revision to Emergency Plan Staff Augmentation Response Times Amendments
L-MT-18-041, Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel20 July 2018Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural SteelFire Barrier
Fire Protection Program
L-MT-18-040, Follow-up to Interim Report of a Deviation or Failure to Comply17 July 2018Follow-up to Interim Report of a Deviation or Failure to Comply
L-MT-18-006, Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements3 July 2018Application to Revise Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance RequirementsRecently irradiated fuel
IR 05000263/201820127 June 2018NRC Inspection Report 05000263/2018201Affidavit
L-MT-18-031, Project Plan Progress Update Toward Restoring 10 CFR 72 Compliance to Dry Shielded Canisters Designated 11 Through 161 June 2018Project Plan Progress Update Toward Restoring 10 CFR 72 Compliance to Dry Shielded Canisters Designated 11 Through 16Exemption Request
L-MT-18-032, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-03601 June 2018Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-0360Water Inventory Control
L-MT-18-034, Supplement to Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 (CAC No. 001028, EPID L-2017-LLE-002931 May 2018Supplement to Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 (CAC No. 001028, EPID L-2017-LLE-0029Nondestructive Examination
Exemption Request
IR 05000263/201841024 May 2018NRC Security Baseline Inspection Report 05000263/2018410 - Cover Letter (DRS-M.Ziolkowski)Affidavit
ML18142B05722 May 2018Ltr. 05/22/18 Monticello Nuclear Generating Plant - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (DRS-J.Kutlesa)
ML18138A46117 May 2018Ltr. 05/17/18 Monticello Nuclear Generating Plant - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000263/2018012 (DRS-J.Benjamin)Stroke time
Commercial Grade Dedication
Temporary Modification
Job Performance Measure
ML18130A92114 May 2018Correction to the Report for the Audit of Lic. Responses to Interim Staff Eval. Open Items Related to U.S. Nuclear Regulatory Commission Order EA-13-109 to Modify Lic. with Regard to Reliable.....Supersedes ML18094A804Mission time
Tornado Missile
FLEX
Tornado Generated Missile
Battery sizing
L-MT-18-023, 10 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year Interval11 May 201810 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year IntervalNondestructive Examination
VT-2
Aging Management
Pressure Boundary Leakage
ML18131A22311 May 2018Prairie and Monticello - Response to Request for Additional Information Regarding Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Di
L-MT-18-029, 2017 Annual Radiological Environmental Operating Report10 May 20182017 Annual Radiological Environmental Operating ReportOffsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
L-MT-18-027, 2017 Annual Radioactive Effluent Release Report10 May 20182017 Annual Radioactive Effluent Release ReportGrab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
ML18122A0018 May 2018Letter to Power Reactor Licensees - U.S. Nuclear Regulatory Commission Analysis of Licensees' 2017 Decommissioning Funding Status Reports
L-MT-18-028, Changes to the Monticello Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program. (Cover Letter Only)2 May 2018Changes to the Monticello Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program. (Cover Letter Only)
ML18093A1081 May 2018Exemption from the Requirements of 10 CFR Part 50, Appendix R, Section III.G.2Hot Short
Safe Shutdown
Fire Barrier
Probabilistic Risk Assessment
Multiple Spurious Operation
Large early release frequency
Exemption Request
Maintenance Rule Program
Fire Protection Program
ML18122A0881 May 2018Public Open House to Discuss NRC Activities, and 2017 End-of Cycle Performance Assessment of the Monticello Nuclear PlantOpen House
L-MT-18-026, NRC Regulatory Issue Summary 2018-02 - Preparation and Scheduling of Operator Licensing Examinations27 April 2018NRC Regulatory Issue Summary 2018-02 - Preparation and Scheduling of Operator Licensing Examinations
L-MT-18-021, 2017 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)26 April 20182017 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
IR 05000263/201801125 April 2018NRC Temporary Instruction 2515/191, Mitigation Strategies, Spent Fuel Pool Instrumentation and Emergency Preparedness Inspection Report 05000263/2018011FLEX
B.5.b
Spent Fuel Pool Instrumentation
L-MT-18-024, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan24 April 2018Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency PlanSafe Shutdown
Health Physics Network
High winds
Reactor Vessel Water Level
High Radiation Area
Operating Basis Earthquake
Design basis earthquake
Severe Accident Management Guideline
Earthquake
Pressure Boundary Leakage
Minimum staff
L-MT-18-020, Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Control24 April 2018Supplement to License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee ControlProbabilistic Risk Assessment
IR 05000263/201800118 April 2018NRC Integrated Inspection Report 05000263/2018001High Radiation Area
Internal Flooding
Enforcement Discretion
Temporary Modification
Functionality Assessment
Locked High Radiation Area
FLEX
Significance Determination Process
Operability Determination
Fire Protection Program
Scaffolding
Power change
Downpower
Unidentified leakage
L-MT-18-013, Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 155 April 2018Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15Probabilistic Risk Assessment
Exemption Request
Earthquake
Fuel cladding
Fatality
ML18089A11130 March 2018Xcel Energy - Summary of Nuclear Property Insurance
ML18089A11330 March 2018Guarantee of Payment of Deferred Premiums
L-MT-18-010, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors28 March 2018Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power ReactorsSafe Shutdown
Ultimate heat sink
Internal Flooding
Probabilistic Risk Assessment
Tornado Generated Missile
Large early release frequency
Turbine Missile
ML18088A38327 March 2018Confirmation of Initial License Examination (DRS-D.Reeser)
L-MT-18-001, Request for Permanent Exemption from 10 CFR 50 Appendix R III.G.2.a Requirements for Exposed Structural Steel21 March 2018Request for Permanent Exemption from 10 CFR 50 Appendix R III.G.2.a Requirements for Exposed Structural SteelHot Short
Safe Shutdown
Fire Barrier
Probabilistic Risk Assessment
Exemption Request
Fire Protection Program
ML18065A5466 March 2018Letter to T. J. O'Connor First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15 (CAC No. 001028, Docket No. 72-58, EPID L-2017-LLE-0029)Exemption Request
ML17345A0466 March 2018Issuance of Amendment No. 197 to Adopt Changes to the Emergency Plan (CAC No. MF9560; EPID L-2017-LLA-0184)High winds
Ultimate heat sink
Operating Basis Earthquake
Spent Fuel Pool Instrumentation
Earthquake
Fuel cladding
IR 05000263/20170062 March 2018Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2017006)
ML18059A17628 February 2018Submittal of Fitness for Duty Performance Data Report, Including Annual Fatigue Reporting Form and Single Positive Test Forms, for 12-Month Period Ending December 31, 2017Fitness for Duty
L-MT-18-012, Interim Report of a Deviation or Failure to Comply12 February 2018Interim Report of a Deviation or Failure to Comply
L-MT-18-008, Initial and Final Part 21.21(d)(4) Report Notification of Failure to Comply or Existence of a Defect Regarding Westinghouse Breaker Cubicle1 February 2018Initial and Final Part 21.21(d)(4) Report Notification of Failure to Comply or Existence of a Defect Regarding Westinghouse Breaker CubicleTime of Discovery
IR 05000263/201700430 January 2018NRC Integrated Inspection Report 05000263/2017004 and Emergency Preparedness Annual Inspection Report 05000263/2017501Safe Shutdown
Ultimate heat sink
Fire Barrier
Temporary Modification
Significance Determination Process
Job Performance Measure
Operability Determination
Fire Protection Program
Hourly Fire Watch
Downpower
ML18029A27129 January 2018Corrected Decommissioning Funding Status Reports
IR 05000263/201740625 January 2018NRC Security Baseline Inspection Report 05000263/2017406; Independent Spent Fuel Storage Security Inspection Report 05000263/2017403; 07200058/2017401 - Cover Letter Only (DRS-M.Ziolkowski)Affidavit
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
ML18005A7895 January 2018Submittal of Revised Fitness for Duty Performance Data Report for 2016Fitness for Duty
L-MT-17-081, Seventh Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order ...21 December 2017Seventh Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order ...Mission time
Tornado Missile
FLEX
Hardened vent
L-MT-17-083, License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program19 December 2017License Amendment Request: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled ProgramSafe Shutdown
High winds
Shutdown Margin
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Stroke time
Post Accident Monitoring
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Squib
Multiple Spurious Operation
Incorporated by reference
Fukushima Dai-Ichi
Surveillance Frequency Control Program
Scram Discharge Volume
Feedwater Controller Failure
Large early release frequency
Battery sizing
Overtravel
Power Operated Valves
Fuel cladding
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
ML17352A67318 December 2017Submittal of Anchor Darling Double Disc Gate Valve Information and StatusAnchor Darling
IR 05000263/201740915 December 2017Inspection of the Cyber Security Full Implementation; Inspection Report 05000263/2017409 - Cover Letter Only (DRS-G.Hausman)Cyber Security
Affidavit
L-MT-17-086, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4615 December 2017Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
IR 05000263/201740815 December 2017NRC Material Control and Accounting Program Inspection Report 05000263/2017408 (Cover Letter Only)Affidavit
ML17345A84011 December 2017Information Request to Support Upcoming Temporary Instruction 2515/191 Inspection at Monticello Nuclear Generating PlantFLEX
Spent Fuel Pool Instrumentation
ML17319A59110 December 2017Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051Safe Shutdown
High winds
Shutdown Margin
High Radiation Area
Ultimate heat sink
Tornado Missile
Time to boil
Safe Shutdown Earthquake
Anchor Darling
Emergency Lighting
Locked High Radiation Area
FLEX
Tornado Generated Missile
Fukushima Dai-Ichi
Design basis earthquake
Spent Fuel Pool Instrumentation
Flood Hazard Mitigation Strategies Assessment
Earthquake
Fire Protection Program
L-MT-17-080, Submittal of Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan6 December 2017Submittal of Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
ML17341A09929 November 2017FEMA - Submittal of After Action Report/Improvement Plan for Monticello Nuclear Generating Plant Radiological Emergency Preparedness, Partial Participation Plume Exposure Pathway Exercise Conducted on Tuesday, August 29, 2017
ML17333A77529 November 2017Proposed Alternative to Utilize Code Case N-513-4. Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1.Functionality Assessment
Through-Wall Leak
ML17310B23928 November 2017and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Unit Staff Qualifications (CAC Nos. MF9545, MF9546, and MF9547; EPID L-2017-LLA-0195)
L-MT-17-071, Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves20 November 2017Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated ValvesHot Short
Probabilistic Risk Assessment
Multiple Spurious Operation
Exemption Request
Fire Protection Program
IR 05000263/20170036 November 2017NRC Integrated Inspection Report 05000263/2017003Offsite Dose Calculation Manual
Internal Flooding
Probabilistic Risk Assessment
Temporary Modification
VT-2
Annual Radiological Environmental Operating Report
Operability Determination
Annual Radiological Effluent Release Report
Fire Protection Program
Downpower
IR 05000263/20170111 November 2017NRC Design Bases Assurance Inspection (Programs): Inspection Report 05000263/2017011 (DRS-B.Jose)Probabilistic Risk Assessment
Significance Determination Process
L-MT-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control20 October 2017Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory ControlShutdown Margin
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Stroke time
Water Inventory Control
Post Accident Monitoring
Hydrostatic
Operating Basis Earthquake
Qualified Offsite Circuit
Scram Discharge Volume
Power-Operated Valves
Fuel cladding
Recently irradiated fuel
Offsite Circuit
Scaffolding
L-MT-17-053, Redacted - Monticello and Independent Spent Fuel Storage Installation - Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 1518 October 2017Redacted - Monticello and Independent Spent Fuel Storage Installation - Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15Time of Discovery
High winds
Non-Destructive Examination
Tornado Missile
Hydrostatic
Probabilistic Risk Assessment
Nondestructive Examination
Finite Element Analysis
Tornado-Generated Missile
Aging Management
Design basis earthquake
License Renewal
Exemption Request
Earthquake
Fuel cladding
Liquid penetrant
Fatality
Power Uprate
Affidavit
ML17277B00710 October 2017Staff Review of Mitigating Strategies Assessment Report of the Impact of the Re-evaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(F) LetterSafe Shutdown Earthquake
FLEX
Fukushima Dai-Ichi
L-MT-17-066, Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events28 September 2017Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External EventsHigh winds
Safe Shutdown Earthquake
Anchor Darling
FLEX
Tornado Generated Missile
Fukushima Dai-Ichi
Design basis earthquake
Spent Fuel Pool Instrumentation
Earthquake
IR 05000263/201750227 September 2017Baseline Emergency Preparedness Biennial Exercise Inspection Report 05000263/2017502
L-MT-17-065, License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information25 September 2017License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional InformationSafe Shutdown
Time of Discovery
High winds
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Safe Shutdown Earthquake
Post Accident Monitoring
Hydrostatic
Probabilistic Risk Assessment
Operating Basis Earthquake
Operator Manual Action
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Safeguards Contingency Plan
Battery sizing
Earthquake
Fuel cladding
Pressure Boundary Leakage
Fire Protection Program
Grace period
Backfit
Unidentified leakage
Failure to Scram
ML17265A28722 September 2017Revision to Correspondence Service Lists for Northern States Power Company - Minnesota/Xcel Energy
ML17264A04821 September 2017Response to Xcel Energy Letter Regarding Non-Cited Violation and Significant Condition Adverse to QualityCondition Adverse to Quality
L-MT-17-063, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times20 September 2017Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response TimesHigh Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Probabilistic Risk Assessment
Locked High Radiation Area
Job Performance Measure
Minimum staff
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
ML17261A70518 September 2017Requal Notification and RFI (Meb)Job Performance Measure
ML17156A21418 September 2017Transmittal Letter Requesting Licensee Comments on OPC 2.206 Proposed DDSafe Shutdown
Anticipated operational occurrence
Enforcement Discretion
Probabilistic Risk Assessment
Open Phase Condition
ML17258A07714 September 201717 U.S. Nuclear Regulatory Commission Region III 2017 Operator Licensing Workshop (Public Meeting) for Monticello Nuclear Generating Plant (CMS)
IR 05000263/201740514 September 2017NRC Security Baseline Inspection Report 05000263/2017405 (Cover Letter Only) (Mez)Affidavit
IR 05000263/20170077 September 2017Reissue - Monticello Nuclear Generating Plant - Triennial Fire Protection Inspection Report 05000263/2017007 (AAS)Hot Short
Safe Shutdown
Fire Barrier
Operator Manual Action
Emergency Lighting
B.5.b
Significance Determination Process
B.5.b Mitigating Strategies
Continuous fire watch
Fire Protection Program
IR 05000263/201700528 August 2017Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2017005)Spent Fuel Pool Instrumentation
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
ML17234A73021 August 2017Triennial Fire Protection Inspection Report 05000263/2017007 (AAS)Hot Short
Safe Shutdown
Fire Barrier
Hydrostatic
Operator Manual Action
Emergency Lighting
Significance Determination Process
Time Critical Operator Action
B.5.b Mitigating Strategies
Continuous fire watch
Fire Protection Program
Fire Watch
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
IR 05000263/201700211 August 2017NRC Integrated Inspection Report 05000263/2017002High Radiation Area
Non-Destructive Examination
Water Inventory Control
Hydrostatic
Enforcement Discretion
Anchor Darling
Temporary Modification
Significance Determination Process
Operability Determination
Maintenance Rule Program
Pressure Boundary Leakage
Fire Protection Program
ML17220A32810 August 2017Nuclear Regulatory Commission Audits of Licensee Responses to Phase 2 of Order EA-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
L-MT-17-060, Steam Dryer Visual Inspection Report10 August 2017Steam Dryer Visual Inspection ReportEarthquake
L-MT-17-059, 2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report9 August 20172017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary ReportNondestructive Examination
Pressure Boundary Leakage
Through-Wall Leak
ML17213A0361 August 2017Submittal of Quality Assurance Topical Report (NSPM-1), Revision 11Fitness for Duty
Shutdown Margin
Offsite Dose Calculation Manual
Commercial Grade Dedication
Coatings
Nondestructive Examination
Temporary Modification
Condition Adverse to Quality
Process Control Program
Fire Protection Program
ML17192A4681 August 2017Flood Hazard Mitigation Strategies AssessmentUltimate heat sink
Hydrostatic
FLEX
Fukushima Dai-Ichi
Flood Hazard Mitigation Strategies Assessment
L-MT-17-050, Follow-up to Interim Report of a Deviation or Failure to Comply31 July 2017Follow-up to Interim Report of a Deviation or Failure to Comply
L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 426 July 2017Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4Tornado Missile
Safe Shutdown Earthquake
Operator Manual Action
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
B.5.b Mitigating Strategies
ML17212A62824 July 2017Lake Engineering Co. - Potentially Degraded Snubber SF1154 Hydraulic Fluid Second - Interim Notification Per 10 CFR Part 21
IR 05000263/201701021 July 2017NRC Supplemental Inspection Report 05000263/2017010 and Assessment Follow-Up LetterMission time
Probabilistic Risk Assessment
Condition Adverse to Quality
Significance Determination Process
ML17192A45218 July 2017Generic Audit Plan for 50.54(f) Flooding Focused Evaluation ResponsesFukushima Dai-Ichi
Flooding Focused Evaluation
L-MT-17-054, Changes to the Monticello Nuclear Generating Plant Security Plan, Training and Qualification Plan. Safeguards Contingency Plan. and Independent Spent Fuel Storage Installation Security Program13 July 2017Changes to the Monticello Nuclear Generating Plant Security Plan, Training and Qualification Plan. Safeguards Contingency Plan. and Independent Spent Fuel Storage Installation Security Program
ML17180A0316 July 2017Staff Review of High Frequency Confirmation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1Safe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
ML17177A4466 July 2017Audit Plan for Licensee Responses Concerning Seismic Hazard Reevaluations Related to Request for Information -(50.54(F) Letter) Regarding Recommendation 2.1 of the Near-Term Task ForceProbabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
L-MT-17-047, Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Event6 July 2017Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External EventSafe Shutdown
High winds
Ultimate heat sink
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Emergency Lighting
FLEX
Fukushima Dai-Ichi
Seismically rugged
Design basis earthquake
Spent Fuel Pool Instrumentation
Earthquake
L-MT-17-051, Submittal of Core Operating Limits Report (NAD-MN-042, Revision 2) for Cycle 2929 June 2017Submittal of Core Operating Limits Report (NAD-MN-042, Revision 2) for Cycle 29Shutdown Margin
MELLLA
L-MT-17-052, Submittal of Monticello Nuclear Generating Plant (MNGP) Emergency Plan (EP) 2017 Exercise Scenario28 June 2017Submittal of Monticello Nuclear Generating Plant (MNGP) Emergency Plan (EP) 2017 Exercise Scenario
ML17172A43123 June 2017Correction of Amendment No. 194, Issuance of Amendment to Adopt F Tstf 545, Revision 3, Ts Inservice Testing Program Removal & Clarify Sr Usage Rule Application to Section 5.5 Testing
L-MT-17-045, June 2017, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.4622 June 2017June 2017, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
ML17171A30420 June 201717 Monticello Nuclear Generating Plant - Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program Inspection Report 05000263/2017009 (Bxj)High Radiation Area
IR 05000263/201700920 June 2017Ltr 06/20/2017 Monticello Nuclear Generating Plant - Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program Inspection Report 05000263/2017009 (BXJ)
ML17123A32116 June 2017Issuance of Amendment Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 TestingIncorporated by reference
Missed surveillance
Pressure Boundary Leakage
L-MT-17-048, Submittal of Change to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan15 June 2017Submittal of Change to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
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
L-MT-17-043, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Commitment Completion14 June 2017Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Commitment CompletionFukushima Dai-Ichi
L-MT-17-042, Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions14 June 2017Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident ConditionsFLEX
Tornado Generated Missile
Containment Hardened Vent
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
ML17159A6998 June 2017Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2017409
ML17160A1437 June 2017Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg)
L-MT-17-041, Independent Spent Fuel Storage Installation - Project Plan Progress Toward Restoring 10 CFR 72 Compliance to Dry Shielded Canisters Designated 11 Through 166 June 2017Independent Spent Fuel Storage Installation - Project Plan Progress Toward Restoring 10 CFR 72 Compliance to Dry Shielded Canisters Designated 11 Through 16Enforcement Discretion
Probabilistic Risk Assessment
Exemption Request
ML17153A12831 May 2017Public Open House to Discuss NRC Activities, and 2016 End-Of-Cycle Performance Assessment of Monticello Nuclear Generating PlantOpen House
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-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
L-MT-17-038, Submittal of Core Operating Limits Report (NAD-MN-042, Revision 1) for Cycle 2925 May 2017Submittal of Core Operating Limits Report (NAD-MN-042, Revision 1) for Cycle 29
ML17122A15715 May 2017Request for Alternative to Use Code Case OMN-20 for the Fifth 10-Year Inservice Testing IntervalGrace period
L-MT-17-040, Changes to Inspection Intervals for ASME Code, Subsection IWE Examinations and Supplemental Examinations of Torus Coatings Associated with License Amendment No. 193 for the Integrated Leak Rate Interval Extension12 May 2017Changes to Inspection Intervals for ASME Code, Subsection IWE Examinations and Supplemental Examinations of Torus Coatings Associated with License Amendment No. 193 for the Integrated Leak Rate Interval ExtensionCoatings
L-MT-17-039, 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual(Enclosure 2)10 May 20172016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual(Enclosure 2)Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
L-MT-17-037, 2016 Annual Radiological Environmental Operating Report10 May 20172016 Annual Radiological Environmental Operating ReportOffsite Dose Calculation Manual
Annual Radiological Environmental Operating Report
ML17123A2733 May 2017NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing ExaminationsGeneric Fundamentals Examination
ML17103A23525 April 2017Issuance of Amendment Technical Specification 5.5.11 Primary Containment Leakage Rate Testing ProgramHigh winds
Probabilistic Risk Assessment
Coatings
FLEX
Aging Management
Large early release frequency
Moisture barrier
ML17104A31024 April 2017Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism ReevaluationUltimate heat sink
Hydrostatic
FLEX
Fukushima Dai-Ichi
Earthquake
L-MT-17-031, Interim Report of a Deviation or Failure to Comply Regarding New Relay Coil GE Part Number 6306774G120 April 2017Interim Report of a Deviation or Failure to Comply Regarding New Relay Coil GE Part Number 6306774G1
L-MT-17-029, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan18 April 2017Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency PlanHealth Physics Network
High Radiation Area
Design basis earthquake
Severe Accident Management Guideline
Earthquake
Fuel cladding
Pressure Boundary Leakage
Integrated Public Alert and Warning System
Siren
ML17096A44318 April 2017Audit Report Relating to the Flood Hazard Reevaluation ReportFukushima Dai-Ichi
L-MT-17-014, 2016 Annual Report of Individual Monitoring for the Plant12 April 20172016 Annual Report of Individual Monitoring for the Plant
ML17103A56012 April 2017Gfes Results, March 2017, MonticelloGeneric Fundamentals Examination
L-MT-17-025, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accid11 April 2017High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi AccidentUltimate heat sink
Safe Shutdown Earthquake
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Seismically rugged
Earthquake
L-MT-17-028, Submittal of Areva Cycle 29 Reload Safety Analysis Report7 April 2017Submittal of Areva Cycle 29 Reload Safety Analysis Report
L-MT-17-016, Risk-Informed Request for Exemption from 10 CFR 50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves6 April 2017Risk-Informed Request for Exemption from 10 CFR 50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated ValvesHot Short
Safe Shutdown
Ultimate heat sink
Mission time
Fire Barrier
Internal Flooding
Probabilistic Risk Assessment
Fire impairment
Operator Manual Action
Multiple Spurious Operation
Job Performance Measure
Thermoset
Scram Discharge Volume
Large early release frequency
Exemption Request
Earthquake
Maintenance Rule Program
Fire Protection Program
ML17094A4353 April 2017Monticello - Notification of NRC Supplemental Inspection (95001) and Request for Information
L-MT-17-024, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Focused Evaluation3 April 2017Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Focused EvaluationHigh winds
Internal Flooding
FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
ML17090A20131 March 2017License Amendment Request to Revise Technical Specification for Plant/Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators
ML17090A38731 March 2017Summary of Nuclear Property Insurance
ML17090A39231 March 2017Guarantee of Payment of Deferred Premiums
ML17095A11231 March 2017License Amendment Request to Revise Emergency Action Level Scheme: Attach. 1, EAL Comparison Matrix Document (Deviations & Differences) and Attachments 2 & 3, Red-Line & Clean Versions of EAL Technical Bases DocumentSafe Shutdown
Time of Discovery
High winds
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Safe Shutdown Earthquake
Post Accident Monitoring
Hydrostatic
Probabilistic Risk Assessment
Operating Basis Earthquake
Operator Manual Action
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Safeguards Contingency Plan
Battery sizing
Earthquake
Fuel cladding
Pressure Boundary Leakage
Fire Protection Program
Grace period
Backfit
Unidentified leakage
Failure to Scram
L-MT-17-022, Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval29 March 2017Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test IntervalHigh winds
Ultimate heat sink
Probabilistic Risk Assessment
FLEX
Large early release frequency