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L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2 January 2024Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report20 December 2023Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits ReportHydrostatic
Nondestructive Examination
Pressure and Temperature Limits Report
L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 35 December 2023Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3Safe Shutdown
Surveillance Frequency Control Program
Offsite Circuit
L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 328 September 2023License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3Safe Shutdown
Surveillance Frequency Control Program
Offsite Circuit
L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy11 September 2023Baffle Former Bolts Alternate Aging Management StrategyAging Management
L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT14 July 2023License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HTNon-Destructive Examination
Hydrostatic
Liquid penetrant
L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions22 June 2023License Amendment Request to Revise Technical Specification 3.7.8 Required ActionsSafe Shutdown
Probabilistic Risk Assessment
L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report14 June 20232022 10 CFR 50.46 LOCA Annual Report
L-PI-23-010, Annual Report of Individual Monitoring27 April 2023Annual Report of Individual Monitoring
L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)28 March 2023Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)Hydrostatic
Pressure and Temperature Limits Report
L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)3 March 2023CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)Incorporated by reference
L-PI-23-001, Day Steam Generator Tube Inspection Report30 January 2023Day Steam Generator Tube Inspection Report
L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report21 December 2022Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection ReportNondestructive Examination
L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2 December 2022Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)Stroke time
Hydrostatic
Nondestructive Examination
Incorporated by reference
Pressure and Temperature Limits Report
Exemption Request
L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections6 October 2022Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube InspectionsNondestructive Examination
L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts20 September 2022Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former BoltsAging Management
L-PI-22-032, CFR 50.46 LOCA Annual Report16 June 2022CFR 50.46 LOCA Annual Report
L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles10 June 2022Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles
L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections7 June 2022Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube InspectionsNondestructive Examination
L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle7 March 2022Supplement to Application for License Amendment to Implement 24-Month Operating Cycle
L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 27 December 2021Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2Fire Protection Program
L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request4 November 2021Response to Request for Additional Information Cooling Water System License Amendment Request
L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.17 October 2021Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1Safe Shutdown
Ultimate heat sink
Non-Destructive Examination
L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2 October 2021License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS FunctionsSafe Shutdown Earthquake
Operating Basis Earthquake
Surveillance Frequency Control Program
Earthquake
L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island30 September 2021Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie IslandShutdown Margin
Recently irradiated fuel
L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle6 August 2021Application for License Amendment to Implement 24-Month Operating CycleSafe Shutdown
Reactor Vessel Water Level
Offsite Dose Calculation Manual
Anticipated operational occurrence
Surveillance Frequency Control Program
Maintenance Rule Program
Fuel cladding
L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report28 June 20212020 10 CFR 50.46 LOCA Annual Report
L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report14 May 2021Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program ReportGrab sample
Offsite Dose Calculation Manual
FLEX
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes19 April 2021Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and NotesBoric Acid
Shutdown Margin
High Radiation Area
Offsite Dose Calculation Manual
Hydrostatic
Nondestructive Examination
Pressure and Temperature Limits Report
Surveillance Frequency Control Program
Deep Dose Equivalent
Power Uprate
L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic7 October 2020Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 PandemicExemption Request
Pandemic
Coronavirus
COVID-19
L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements28 September 2020Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position RequirementsShutdown Margin
Surveillance Frequency Control Program
L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ1 September 2020Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4Safe Shutdown
High Radiation Area
Mission time
Fire Barrier
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Surveillance Frequency Control Program
Large early release frequency
L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule28 July 2020= Request for Revision to Reactor Vessel Material Surveillance Capsule Removal SchedulePressure and Temperature Limits Report
L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)10 June 2020Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)Tornado Missile
Safe Shutdown Earthquake
Finite Element Analysis
FLEX
Aging Management
Earthquake
Fuel cladding
L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI29 April 2020Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI
L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.1330 March 2020License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13Stroke time
Pressure and Temperature Limits Report
Surveillance Frequency Control Program
L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-129 January 2020License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1Anticipated operational occurrence
Surveillance Frequency Control Program
Power change
L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements23 December 2019Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position RequirementsShutdown Margin
Anticipated operational occurrence
Surveillance Frequency Control Program
B.5.b Mitigating Strategies
Fuel cladding
L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b16 December 2019License 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
High Radiation Area
Ultimate heat sink
Fire Barrier
Anticipated operational occurrence
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Surveillance Frequency Control Program
Large early release frequency
Earthquake
Turbine Missile
Offsite Circuit
Fire Protection Program
L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency7 October 2019License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test FrequencyInternal Flooding
Probabilistic Risk Assessment
Coatings
Operating Basis Earthquake
Aging Management
Surveillance Frequency Control Program
Large early release frequency
Moisture barrier
Maintenance Rule Program
Fuel cladding
Grace period
L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report19 September 2019Submittal of Revised Pressure and Temperature Limits ReportPressure and Temperature Limits Report
L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals16 September 2019Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals
L-PI-19-025, Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)27 August 2019Request to Approve Site-Specific Probabilistic Risk Assessment (PRA) Model for Flowserve N-Seal Abeyance Seal and Dynamic Testing for the Prairie Island Nuclear Generating Plant (PINGP)Safe Shutdown
Probabilistic Risk Assessment
Coatings
L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...5 August 2019Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...High winds
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 213 June 201910 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2Probabilistic Risk Assessment
L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors29 April 2019Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power ReactorsHigh winds
Internal Flooding
Probabilistic Risk Assessment
FLEX
Large early release frequency
L-PI-19-003, Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)4 February 2019Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule for Prairie Island Nuclear Generating Plant (PINGP)Pressure and Temperature Limits Report
L-PI-19-006, Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time Requirements29 January 2019Emergency License Amendment Request Regarding One-Time Extension for Technical Specification Completion Time RequirementsSafe Shutdown
Enforcement Discretion
Probabilistic Risk Assessment
FLEX
L-PI-19-005, Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.6915 January 2019Online Reference Portal for NRC Review of License Amendment Request to Implement 10 CFR 50.69
L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8056 December 2018Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805Safe Shutdown
Mission time
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