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Issue date | Title | |
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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 Functions | 2 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 |
ML20237F368 | 29 October 2020 | Amendment No. 11 to Materials License No. SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation Safety Evaluation Report |
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 Initiativ | 1 September 2020 | 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 Initiative 4 |
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 2020 | 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) |
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 4b | 16 December 2019 | License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b |
ML19268A042 | 26 September 2019 | Pre-Application Meeting License Amendment Request Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b |
IR 05000282/2018011 | 1 August 2018 | NRC Design Bases Assurance Inspection (Teams); Inspection Report 05000282/2018011 and 05000306/2018011 (DRS-A.Dunlop) |
ML17303B162 | 21 December 2017 | Documentation of the Completion of Required Actions Taken in Response to Fukushima Lessons Learned |
L-PI-17-035, License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information | 27 September 2017 | License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information |
ML17110A275 | 4 May 2017 | Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 |
ML17094A576 | 29 March 2017 | License Amendment Request to Revise Emergency Action Level (EAL) Scheme |
L-PI-16-096, Notification of Full Compliance with NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. | 13 December 2016 | Notification of Full Compliance with NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. |
L-PI-16-082, NEI 12-06, Appendix H, Revision 2, H.4.1 Path 1: GMRS Less than or Equal to SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information | 26 October 2016 | NEI 12-06, Appendix H, Revision 2, H.4.1 Path 1: GMRS Less than or Equal to SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information |
L-PI-16-063, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events | 17 August 2016 | Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
L-PI-16-001, Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report | 14 January 2016 | Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report |
ML15341A162 | 15 December 2015 | Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations |
L-PI-15-064, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation | 25 August 2015 | Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation |
ML15148A376 | 1 June 2015 | Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015 |
ML17297A323 | 14 November 2014 | Enclosure 2 (Redacted): Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal for Prairie Island Unit 1 |
ML14245A386 | 29 August 2014 | NRDC V. NRC Et. Al., No. 13-1311 (Scheduled Oral Argument November. 21, 2014) |
ML14111A147 | 9 May 2014 | Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights |
ML14120A162 | 9 May 2014 | Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident |
ML14120A208 | 9 May 2014 | Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident |
L-PI-14-028, PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident | 27 March 2014 | PINGP Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident |
L-PI-14-020, Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted) | 4 March 2014 | Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted) |
ML14030A540 | 27 February 2014 | Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) |
ML14041A204 | 26 February 2014 | Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2, TAC Nos.: MF0834 and MF0835 |
ML112521289 | 22 January 2013 | Issuance of Amendments Adoption of Alternative Source Term Methodology |
L-PI-12-108, Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 26 November 2012 | Final Response to NRC Request for Information, Per 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident |
ML12056A049 | 12 March 2012 | Enclosure 3 - Recommendation 2.3: Seismic |
ML12053A340 | 12 March 2012 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident |
ML12056A047 | 12 March 2012 | Enclosure 1 - Recommendation 2.1: Seismic |
ML11349A005 | 15 December 2011 | Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 |
NRC-2011-0290, Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 | 15 December 2011 | Biweekly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations: Fr Publication Date December 27, 2011 |
ML112200856 | 27 October 2011 | Operating Plant, Units 1 and 2 - Issuance of Amendments Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology |
L-PI-11-074, Redacted- Volume 2 to Prairie Island Independent Spent Fuel Storage Installation Safety Analysis Report, Rev. 14 | 20 October 2011 | Redacted- Volume 2 to Prairie Island Independent Spent Fuel Storage Installation Safety Analysis Report, Rev. 14 |
L-PI-10-085, Clarification of Responses to Requests for Additional Information Regarding a License Amendment Request for Certain Applications of Leak-Before-Break Methodology | 20 August 2010 | Clarification of Responses to Requests for Additional Information Regarding a License Amendment Request for Certain Applications of Leak-Before-Break Methodology |
L-PI-10-077, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Additional ... | 23 July 2010 | Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology Additional ... |
ML102100259 | 30 June 2010 | Seismic Fragilities for Unit #1 and Unit #2 Turbine Building Piping and Equipment |
ML101550668 | 10 June 2010 | Request for Additional Information Related to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-before-Break |
L-PI-10-041, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology | 29 April 2010 | Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology |
L-PI-09-134, License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology | 22 December 2009 | License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology |
ML100200131 | 21 December 2009 | Report No. 0900634.401, Revision 2, Updated Leak-Before-Break Evaluation for Several RCS Piping at Prairie Island Nuclear Generating Plant, Units 1 & 2. |
ML100200132 | 18 December 2009 | Report 0900634.402, Revision 2, Updated Leak-Before-Break Report for Prairie Island Nuclear Generating Plant Unit 2 Pressurizer Surge Line Nozzle. |
ML091460809 | 1 July 2009 | Issuance of Amendments Technical Specifications Changes to Allow Use of Westinghouse 0.422-Inch OD 14X14 Vantage + Fuel |
L-PI-08-047, License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel | 26 June 2008 | License Amendment Request for Technical Specifications Changes to Allow Use of Westinghouse 0.422-inch OD 14x14 Vantage+ Fuel |
L-PI-07-093, Request for Extension of Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. | 5 December 2007 | Request for Extension of Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. |
L-PI-05-036, License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time | 21 November 2005 | License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time |
L-PI-04-120, Emergency Action Levels Revision Submittal | 22 October 2004 | Emergency Action Levels Revision Submittal |
ML040680396 | 31 January 2004 | Safety Anaysis Transition Program Licensing Report. |