ML14203A383
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| ML14203A383 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/27/2014 |
| From: | Davison K Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14203A384 | List: |
| References | |
| L-PI-14-058 | |
| Download: ML14203A383 (4) | |
Similar Documents at Prairie Island | |
|---|---|
Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024
[Table view]Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) 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,2024-01-0202 January 2024 Response 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 Report2023-12-20020 December 2023 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 Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan 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-40HT2023-07-14014 July 2023 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-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01 Category:Updated Final Safety Analysis Report (UFSAR) MONTHYEARL-PI-22-001, 7 to Updated Safety Analysis Report, Enclosure 4, Bases Changes and License Amendments2022-04-28028 April 2022
[Table view]7 to Updated Safety Analysis Report, Enclosure 4, Bases Changes and License Amendments ML22124A0452022-04-28028 April 2022 Submittal of Revision 37 to Updated Safety Analysis Report, Cover Letter and Information on Enclosures ML20118D3672020-04-27027 April 2020 Enclosure 2 - Updated Safety Analysis Report (Usar), Revision 36 L-PI-20-016, Enclosure 2 - Prairie Island Updated Safety Analysis Report, Revision 36, Section 8 - Section 112020-04-27027 April 2020 Enclosure 2 - Prairie Island Updated Safety Analysis Report, Revision 36, Section 8 - Section 11 ML20118D1772020-04-27027 April 2020 Updated Safety Analysis Report (USAR) Revision 36 ML20118D3202020-04-27027 April 2020 Enclosure 5 - Report of Changes, Tests, and Experiments ML20118D1802020-04-27027 April 2020 Enclosure 1 - Information Regarding Changes to the UFSAR ML18155A4572018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 13, Plant Operations ML18166A2092018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix G, Containment System Evaluation ML18155A4652018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix J, Pre-Operational and Startup Tests ML18155A4662018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix K, Containment Pressure Response to LOCA ML18155A4672018-05-18018 May 2018 Updated Safety Analysis Report (UFSAR) Revision 35, Appendix L, Requirements of Renewed Operating Licenses ML18166A2042018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 14, Safety Analysis ML18166A2052018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix D, Radioactive Source Bases ML18166A2062018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix E, Report of Environmental Studies Geology, Hydrology and Seismology ML18166A2082018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix F, Probable Maximum Flood Study L-PI-18-018, Updated Safety Analysis Report (USAR) Revision 35, Appendix I, Postulated Pipe Failure Analysis Outside of Containment2018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix I, Postulated Pipe Failure Analysis Outside of Containment ML18155A4562018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 12, Plant Structures and Shielding - Redacted ML18155A4552018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 11, Plant Power Conversion System ML18155A4542018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 10, Plant Auxiliary Systems ML18155A4532018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 9, Plant Radioactive Waste Control Systems ML18155A4522018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 8, Plant Electrical Systems ML18155A4512018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 7, Plant Instrumentation and Control Systems ML18155A4502018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 6, Engineered Safety Features ML18155A4492018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 5, Containment System ML18155A4482018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 4, Reactor Coolant System ML18155A4472018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 3, Reactor ML18155A4462018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 2, Site and Environs ML18155A4452018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Section 1, Introduction and Summary Description ML18155A4402018-05-18018 May 2018 Submittal of Updated Safety Analysis Report (Usar), Revision 35 ML18166A2102018-05-18018 May 2018 Updated Safety Analysis Report (USAR) Revision 35, Appendix H, Annual Report, the Meteorological Program ML16278A0432016-10-0404 October 2016 Revision 34 to Updated Safety Analysis Report, Section 1, Introduction and Summary Description Public Version ML16168A3442016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 2, Site and Environs ML16168A3622016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 13, Plant Operations ML16168A3642016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Appendix D, Radioactive Source Bases L-PI-16-049, Revision 34 to Updated Safety Analysis Report, Appendix L, Requirement of Renewed Operating Licenses2016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Appendix L, Requirement of Renewed Operating Licenses ML16168A3422016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, List of Effective Pages and Table of Contents ML16168A3782016-06-0303 June 2016 Revision 4 to Updated Safety Analysis Report, Appendix J, Pre-Operational and Startup Tests ML16168A3792016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Appendix K, Containment Pressure Response to LOCA ML16168A3762016-06-0303 June 2016 Revision 30 to Updated Safety Analysis Report, Appendix H, Annual Report - the Meteorological Program ML16168A3452016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 3, Reactor ML16168A3502016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 8, Plant Electrical Systems ML16168A3742016-06-0303 June 2016 Revision 4 to Updated Safety Analysis Report, Appendix F, Probable Maximum Flood Study Mississippi River at Prairie Island, Minnesota ML16168A3492016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 7, Plant Instrumentation and Control Systems ML16168A3472016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 5, Containment System ML16168A3752016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Appendix G, Containment System Evaluation ML16168A3462016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 4, Reactor Coolant System ML16168A3512016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 9, Plant Radioactive Waste Control Systems ML16168A3482016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 6, Engineered Safety Features ML16168A3632016-06-0303 June 2016 Revision 34 to Updated Safety Analysis Report, Section 14, Safety Analysis 2022-04-28 |
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