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 Issue dateTitle
L-PI-22-001, 7 to Updated Safety Analysis Report, Enclosure 4, Bases Changes and License Amendments28 April 20227 to Updated Safety Analysis Report, Enclosure 4, Bases Changes and License Amendments
L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle6 August 2021Application for License Amendment to Implement 24-Month Operating Cycle
ML21139A31119 May 2021Independent Spent Fuel Storage Installation (ISFSI) - Revised Emergency Plan (E-Plan), Emergency Plan Implementing Procedures (EPIP) and Rec/Rpss Handbook
ML20252A25427 August 2020Proposed facility-developed RO-SRO Written Examination
ML20118D31827 April 2020Enclosure 4 - Technical Specifications (TS) Bases Control Program
ML22179A27220 September 20182018 PI Ile Administered Written Exam Reference Handouts
L-PI-18-016, Enclosure 1, Form 1576 Emergency Action Level (EAL) Matrix, Revision 10 and Emergency Action Level Technical Bases, Revision 1317 April 2018Enclosure 1, Form 1576 Emergency Action Level (EAL) Matrix, Revision 10 and Emergency Action Level Technical Bases, Revision 13
L-PI-17-035, License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information27 September 2017License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information
ML17094A57629 March 2017License Amendment Request to Revise Emergency Action Level (EAL) Scheme
L-PI-16-045, Revisions to Technical Specifications Bases20 May 2016Revisions to Technical Specifications Bases
ML15264A20930 November 2015Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License
L-PI-14-034, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation11 December 2014License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation
L-PI-12-110, License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA1.2 and Fuel Clad Barrier Loss Criteria13 December 2012License Amendment Request (LAR) to Revise Emergency Plan (EP) Emergency Action Levels (Eals): RA1.2 and Fuel Clad Barrier Loss Criteria
L-PI-11-098, Submittal of 50.59 Evaluation Summary Report12 December 2011Submittal of 50.59 Evaluation Summary Report
ML11172A02027 June 2011Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
ML10169050518 June 2010Northern States Power Company'S Initial Disclosures Regarding Safety Culture Contention
ML0806704197 March 2008CDBI Findings
L-PI-08-009, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.28 February 2008Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
ML05227007318 April 2005Event Notification Report for April 18, 2005
L-PI-04-120, Emergency Action Levels Revision Submittal22 October 2004Emergency Action Levels Revision Submittal
ML0416102968 June 2004Technical Specifications, Eliminate Requirements for Hydrogen Recombiners and Relocate the Requirements for Hydrogen Monitors to the Technical Requirements Manual
ML1025100356 May 2004PIC000004-Appendix H, Containment Integrity Significance Determination Process
ML1021607756 May 2004Intervenor-Exhibit 5-Inspection Manual Chapter 0609, Containment Integrity Significance Determination Process, Appendix H, U.S. NRC
ML04042042430 January 2004Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process
ML04021000419 November 2003Additional Post Examination Comments for the Prairie Island Initial Examination - September 2003
L-PI-03-014, Emergency Plan Implementing Procedures18 February 2003Emergency Plan Implementing Procedures
ML02304035612 August 2002Final as - Administered Administrative Jpms for the Prairie Island Initial Examination - August 2002
ML0222803548 August 2002DAEC Emergency Planning Department Procedure Transmittal Acknowledgment Memo
ML02221004326 July 2002Technical Specifications for License Amendment Nos. 158 and 149, Pages 1.1-1 to 3.4.13-1 (174 Pages)
ML02214037026 July 2002Technical Specification Bases for License Amendment Nos. 158 and 149, Pages B.3.3.2-1 to B3.4.13-13 (185 Pages)
ML02155003730 May 2002Supplement to License Amendment Request Dated 12/11/2000, Conversion to Improved Technical Specifications (ITS)
ML02119053617 April 2002Emergency Plan Implementing Procedures - F3
ML02056057531 January 2002Supplement to License Amendment Request for Conversion to Improved Technical Specifications (ITS) for Prairie Island Nuclear Generating Plant
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
ML20206G51530 April 1999Summary of 990421 Meeting with Util Re Error Involving Recent ATWS Analyses Using GE Odyn Code.List of Attendees Encl
ML20207C0978 February 1999Forwards Rev 16 to Prairie Island Nuclear Generating Plant Usar,Per 10CFR50.71(e).Rev 12 to Fire Hazards Analysis,Encl, Which Satisfies Commitment Made in Licensee to Nrc.Fire Hazards Analysis Sent Under Separate Cover
ML20207C0708 February 1999Forwards Rev 16 to Prairie Island Nuclear Generating Plan Usar,Per 10CFR50.71(e).Rev 12 of Fire Hazards Analysis,Encl, Which Satisfies Commitment Made in Licensee to Nrc.Revised USAR Sent Under Separate Cover
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
IR 05000282/19980041 April 1998Insp Repts 50-282/98-04 & 50-306/98-04 on 980210-13 & 0316-20.No Violations Noted.Major Areas Inspected:Rp Performance During Unit 1 Refueling Outage & Unit 2 Forced Outage,Calibration of Radiation Monitoring Sys
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
ML20087F3579 August 1995Proposed Tech Specs Table TS 3.15-1,Pages 1 & 2 & Bases Page B.3.15-1 Marked Up to Implement License Amend Request
ML20077R52210 January 1995Proposed Tech Specs Re Post Accident Monitoring
ML20077R51510 January 1995Application for Amends to Licenses DPR-42 & DPR-60,revising Event Monitoring Instrumentation TS to Conform to Std TS for Post Accident Monitoring
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
ML20069M79615 June 1994Rev to 940129 LAR to Licenses DPR-42 & DPR-60,adding Specific Action Statements to Section 3.15.A of TS for Core Exit Thermocouples
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