Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing ML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program L-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) ML24164A2402024-06-10010 June 2024 Minnesota State Historic Preservation Office- Comments on Draft Monticello SLR Draft EIS ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 ML24137A2792024-06-0303 June 2024 Audit Summary for License Amendment Request to Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption 05000306/LER-2024-001-01, Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump2024-05-31031 May 2024 Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24262A1992024-05-29029 May 2024 L-PI-24-018 PINGP 75 Day Letter ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A1782024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 2024-09-27
[Table view] Category:Quality Assurance Program
MONTHYEARML24109A1002024-04-17017 April 2024 1 to the Updated Safety Analysis Report, Appendix C, Quality Assurance Program ML18213A1542018-08-0101 August 2018 Island Independent Spent Fuel Storage Installation, and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1 Revision 13 ML17213A0362017-08-0101 August 2017 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 11 ML16214A1122016-08-0101 August 2016 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 9 ML16054A4442016-01-26026 January 2016 Revision 33 to the Updated Final Safety Analysis Report, Appendix C, Quality Assurance Program ML15211A0252015-07-30030 July 2015 ISFSI and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 8 ML15020A7112015-01-20020 January 2015 Independent Spent Fuel Storage Installation and Monticello, Supplement to Request for Review and Approval of Northern States Power Company Quality Assurance Topical Report ML14316A5942014-11-12012 November 2014 Quality Assurance Topical Report, NSPM-1, Revision 8a. ML13220A0072013-08-0606 August 2013 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 6 ML12226A1782012-08-10010 August 2012 Independent Spent Fuel Storage Installation and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 5 ML1122014662011-08-0808 August 2011 Independent Spent Fuel and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1), Revision 4 L-HU-05-017, Notification of Intent to Apply the Nuclear Management Company (NMC) Quality Assurance Topical Report, NMC-1, to Independent Spent Fuel Storage Installation (Isfsi), Spent Fuel Cask and Radioactive Waste Shipment Activities at NMC Operat2005-09-13013 September 2005 Notification of Intent to Apply the Nuclear Management Company (NMC) Quality Assurance Topical Report, NMC-1, to Independent Spent Fuel Storage Installation (Isfsi), Spent Fuel Cask and Radioactive Waste Shipment Activities at NMC Operated L-HU-04-039, Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 20042004-09-22022 September 2004 Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 2004 ML0330701612003-10-31031 October 2003 List of QATR Exceptions/Alternatives to NQA-1-1994 ML0330701602003-10-31031 October 2003 Existing Site QA Programs Vs QATR Comparison Matrices ML0330701572003-10-31031 October 2003 NMC Quality Assurance Topical Report NMC-1 Revision 0a L-MT-03-025, Submittal of Revision 25 of Operational Quality Assurance Plan (Oqap)2003-03-27027 March 2003 Submittal of Revision 25 of Operational Quality Assurance Plan (Oqap) 2024-04-17
[Table view] Category:Topical Report
MONTHYEARL-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 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)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML22067A1502021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Section 6 Through Appendix B L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D2021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D ML22067A1542021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 4 ML22067A1532021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 3 ML22067A1522021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 2 ML22067A1512021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 1 ML22067A1492021-11-30030 November 2021 WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Cover Through Section 5 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 Functions2021-10-0202 October 2021 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 Functions ML19213A1602019-08-0101 August 2019 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 14 ML18213A1542018-08-0101 August 2018 Island Independent Spent Fuel Storage Installation, and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1 Revision 13 ML17213A0362017-08-0101 August 2017 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 11 ML16272A1782016-09-28028 September 2016 Xcel Energy, Northern States Power Company - Minnesota - Quality Assurance Topical Report NSPM-1, Revision 10 ML15289A0752015-10-31031 October 2015 Enclosure 6, WCAP-17549-NP, Revision 3, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using Ace. ML15327A2292015-10-31031 October 2015 Westinghouse, WCAP-17400-NP, Supplement 1, Rev. 1, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Analysis, Supplemental Analysis for the Storage of Ifba Bearing Fuel. L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report.2015-09-30030 September 2015 Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report. ML15289A0742015-09-30030 September 2015 Enclosure 5, WCAP-17252-NP, Revision 5, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project. ML15211A0252015-07-30030 July 2015 ISFSI and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 8 ML15020A7112015-01-20020 January 2015 Independent Spent Fuel Storage Installation and Monticello, Supplement to Request for Review and Approval of Northern States Power Company Quality Assurance Topical Report ML14283A1202014-07-31031 July 2014 ANP-3274NP, Revision 1, Analytical Methods for Monticello ATWS-1. ML14283A1212014-04-30030 April 2014 ANP-3284NP, Results of Analysis & Benchmarking of Methods for Monticello ATWS-1. L-MT-14-044, ANP-3135NP, Applicability of Areva BWR Methods to Extended Flow Window for Monticello.2014-04-30030 April 2014 ANP-3135NP, Applicability of Areva BWR Methods to Extended Flow Window for Monticello. ML14218A6732013-12-20020 December 2013 Enclosure 2 - Xcel Energy Northern States Power Company - Minnesota - Quality Assurance Topical Report NSPM-1, Revision 7 ML13220A0072013-08-0606 August 2013 Submittal of Quality Assurance Topical Report (NSPM-1), Revision 6 ML12226A1782012-08-10010 August 2012 Independent Spent Fuel Storage Installation and Monticello - Submittal of Quality Assurance Topical Report (NSPM-1), Revision 5 ML1122014662011-08-0808 August 2011 Independent Spent Fuel and Monticello, Submittal of Quality Assurance Topical Report (NSPM-1), Revision 4 ML11236A1342011-07-31031 July 2011 Westinghouse WCAP-17400-NP, Rev. 0, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis, Enclosure 4 ML1020104662010-06-30030 June 2010 Enclosure 16 - Westinghouse WCAP-17252-NP, (Nonproprietary) Revision 0, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project ML1020104632010-06-30030 June 2010 Enclosure 12 - Westinghouse WCAP-17085-NP, (Nonproprietary) Revision 1, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads. ML1020104652010-06-30030 June 2010 Enclosure 15 - Westinghouse WCAP-17251-NP, (Nonproprietary) Revision 0, Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report L-PI-05-110, Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage2005-12-0202 December 2005 Supplement to License Amendment Request (LAR) to Revise the Spent Fuel Pool Criticality Analyses and Technical Specifications (TS) 3.7.17, Spent Fuel Pool Storage and 4.3, Fuel Storage L-HU-04-039, Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 20042004-09-22022 September 2004 Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 2004 L-PI-04-017, Development and Qualification of a Gothic Containment Evaluation Model for the Prairie Island Nuclear Generating Plants.2004-04-30030 April 2004 Development and Qualification of a Gothic Containment Evaluation Model for the Prairie Island Nuclear Generating Plants. ML0406803962004-01-31031 January 2004 Safety Anaysis Transition Program Licensing Report. ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. ML0330701642003-10-31031 October 2003 NQA-1 Vs Non-Programmatic ANSI Standards Comparison Tables ML0330701622003-10-31031 October 2003 Table Comparing ANSI N18.7-1976 to ASME Nqa -1-1994 & NMC QATR L-PI-03-040, Praire Island, Unit 1 - Transmittal of Westinghouse Lower Row Tube Dent Root Cause Analysis2003-04-25025 April 2003 Praire Island, Unit 1 - Transmittal of Westinghouse Lower Row Tube Dent Root Cause Analysis 2023-07-04
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