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 Issue dateTitle
ML23130A38718 May 2023Request 1-RR-5-15 and 2-RR-5-15 to Use Later Edition of ASME Section XI Code for Performance of Repair/Replacement Activities
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)
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)
ML22270A32530 September 2022(Prairie Island), Unit 2 - Authorization and Safety Evaluation for Alternative Request No. RR-08
IR 05000282/202100411 February 2022Integrated Inspection Report 05000282/2021004 and 05000306/2021004
ML20276A0032 October 2020Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
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 4
ML18270A01519 October 2018and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Relief from the Requirements of the ASME OM Code
ML18173A1797 August 2018OEDO-17-00070 - Notice of Issuance of Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan C
ML18173A1752 August 2018OEDO-17-00070/SRM-DD-18-03 - Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan Casting
ML18107A4026 June 2018OEDO-17-00070 - Letter to Petitioner on Areva Forgings 2.206
ML18107A4046 June 2018OEDO-17-00070 - Proposed Director'S Decision on Areva Forgings 2.206
IR 05000282/201700128 April 2017Prairie Island Nuclear Generating Plant, Units 1 and 2 - NRC Integrated Inspection Report 05000282/2017001 and 05000306/2017001
ML16246A2004 October 2016Request for Relief 1RR-4-11 and 2-RR-4-11 Associated with Certain Inservice Inspection of Component Welds for the Fourth 10-Year Interval
L-PI-16-056, Response to Request for Additional Information on the Fourth Ten-Year Lnservice Inspection Interval Relief Request Nos. 1-RR-4-11 and 2-RR-4-1113 July 2016Response to Request for Additional Information on the Fourth Ten-Year Lnservice Inspection Interval Relief Request Nos. 1-RR-4-11 and 2-RR-4-11
NRC-2011-0088, Comment (23) from Thomas Conboy of Prairie Island Nuclear Plant on the Proposed Rule for 10 CFR Part 50 - Incorporation by Reference of American Society of Mechanical Engineers Codes and Code Cases15 December 2015Comment (23) from Thomas Conboy of Prairie Island Nuclear Plant on the Proposed Rule for 10 CFR Part 50 - Incorporation by Reference of American Society of Mechanical Engineers Codes and Code Cases
ML15196A22712 August 2015Requests 1-RR-5-3 and 2-RR-5-3 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
ML15196A4326 August 2015Requests 1-RR-4-11 and 2-RR-4-11 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program
ML15196A1956 August 2015Request 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program
L-PI-15-011, 10 CFR 50.55a Request for Approval to Use a Portion of a Subsequent Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI, for the Inservice Inspection Program Fourth Ten-Year Interval17 February 201510 CFR 50.55a Request for Approval to Use a Portion of a Subsequent Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI, for the Inservice Inspection Program Fourth Ten-Year Interval
L-PI-14-127, Fifth Interval Inservice Inspection Plan December 21, 2014 Through December 20, 202418 December 2014Fifth Interval Inservice Inspection Plan December 21, 2014 Through December 20, 2024
ML14357A2105 December 2014Fifth Ten-Year Interval Inservice Testing Program for Prairie Island Nuclear Generating Plant Units 1 and 2, Enclosure 1 - Prairie Island Nuclear Generating Plant ASME Inservice Testing Program. H10.1, Revision 35 502 Pages
L-PI-14-085, 10CFR 50.55a Requests Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program15 September 201410CFR 50.55a Requests Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
ML14198A32816 July 2014Task Order No. NRC-HQ-20-14-T-0017 Under Interagency Agreement No. NRC-HQ-20-14-D-0014
ML13205A1207 November 2013Draft Environmental Assessment for the Proposed Renewal of the Prairie Island Independent Spent Fuel Storage Installation
ML13113A4002 July 2013License Amendments TSTF-510
L-PI-11-098, Submittal of 50.59 Evaluation Summary Report12 December 2011Submittal of 50.59 Evaluation Summary Report
ML11220085627 October 2011Operating 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
ML10202016420 July 2010License Amendment Request for Approval of the Northern States Power Company - Minnesota Cyber Security Plan
L-PI-09-086, NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses30 July 2009NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses
ML09211081229 July 2009Request for Approval to Use a Subsequent ASME Code Edition and Addenda for the Second IWE Interval
L-PI-09-076, License Amendment Request (LAR) to Revise Technical Specifications in Accordance with TSTF-448, Revision 3 - Control Room Habitability24 June 2009License Amendment Request (LAR) to Revise Technical Specifications in Accordance with TSTF-448, Revision 3 - Control Room Habitability
IR 05000282/200900728 May 2009IR 05000282-09-007, 05000306-09-007, on 04/06/2009 - 04/24/2009, Prairie Island Nuclear Generating Plant, Units 1 and 2, Routine Triennial Fire Protection Baseline Inspection
ML0834004995 December 2008LB Memorandum and Order (Ruling on Petition to Intervene, Request for Hearing, and Motion to Strike). (LBP-08-26)
ML0831202268 September 2008License Renewal Environmental Report Additional Information, Documents Requested During NRC Environmental Review, Socioeconomics, Binder 1 of 1
L-PI-08-046, Application for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater (AFW) Pump Inoperable Using Consolidated Line Item Improvement Process11 July 2008Application for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater (AFW) Pump Inoperable Using Consolidated Line Item Improvement Process
ML08165027227 June 2008Prairie, Units 1 and 2, License Amendments 185 and 175 Regarding Incorporation of TS Task Force Travelers TSTF-479, TSTF-485 and TSTF-497
ML0807905639 May 2008Relief Request 1-RR-4-6 for Piping Weld Examination Coverage for the Fourth Inservice Inspection Interval
ML07278002631 October 2007Relief Request from ASME Code, Section X1, Inservice Inspection Program Relief Requests Nos. 1-RR-4-7 and 2-RR-4-7
L-PI-07-048, License Amendment Request (LAR) Incorporating Technical Specification Task Force (TSTF) Industry Travelers TSTF-479, TSTF-485, and TSTF-4973 July 2007License Amendment Request (LAR) Incorporating Technical Specification Task Force (TSTF) Industry Travelers TSTF-479, TSTF-485, and TSTF-497
L-HU-07-018, Comment (10) Submitted by Nuclear Management Company, LLC, Edward J. Weinkam on Proposed Rule Pr 50 Regarding Industry Codes and Standards; Amended Requirements19 June 2007Comment (10) Submitted by Nuclear Management Company, LLC, Edward J. Weinkam on Proposed Rule Pr 50 Regarding Industry Codes and Standards; Amended Requirements
L-PI-07-028, Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item Improvement..10 May 2007Application for Technical Specification Change TSTF-491, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Technical Specifications Using Consolidated Line Item Improvement..
ML06207003529 August 2006Letter, Request for Relief No. 21
ML0617200153 July 2006Relief, Evaluation of Relief Request 2-RR-4-6 for Reduced Examination Volume for Class 2 RHR Heat Exchanger Shell- to-Flange Weld
ML0617103643 July 2006Monticello Nuclear Generating Plant, Palisades Nuclear Plant, Point Beach Nuclear Plant Units 1 and 2, Prairie Island Nuclear Generating Plant, Units 1 and 2 - Use of ASME Code Case N-513-2
L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity16 February 2006Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
ML0532700795 January 2006Issuance of Relief Request for the Risk-Informed Inservice Inspection Program
ML0525200063 October 2005Evaluation of Third 10-Year Interval Inservice Inspection Request for Relief RR-17
ML05179025825 July 2005Issuance of Safety Evaluation for the Fourth 10-Year IST Program Interval at Prairie Island Nuclear Generating Plant, Units 1 and 2
ML05096018727 April 2005Evaluation of Relief Request Nos. 1-RR-4-2, 1-RR-4-3, 2-RR-4-3, 1-RR-4-4, and 2-RR-4-4 for the Fourth 10-Year Inservice Inspection Interval
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