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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
ML21139A31119 May 2021Independent Spent Fuel Storage Installation (ISFSI) - Revised Emergency Plan (E-Plan), Emergency Plan Implementing Procedures (EPIP) and Rec/Rpss Handbook
ML20245E56927 August 2020ES-401-9
ML20246G74027 August 2020Ile As-Administered Written Exam
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
IR 05000282/20180019 May 2018NRC Integrated Inspection Report 05000282/2018001 and 05000306/2018001
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
05000306/LER-2017-00211 December 2017Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect
LER 17-002-00 for Prairie Island, Unit 2, Regarding Reactor Coolant System Shutdown Communication Live Vent Through Wall Defect
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
ML15196A22112 August 2015Requests 1-RR-5-1 and 2-RR-5-1 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
IR 05000282/20150016 May 2015IR 05000282/2015001, 05000306/2015001; 01/01/2015 - 03/31/2015; Prairie Island Nuclear Generating Plant, Units 1 and 2; Operability Evaluations, Refueling and Outages and Event Followup
L-PI-15-001, Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-1 and 2-RR-5-1 (TACs MF4833 and MF4834) Associated with Fifth Ten-Year Lnterval Inservice Inspection (ISI) Program4 February 2015Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-1 and 2-RR-5-1 (TACs MF4833 and MF4834) Associated with Fifth Ten-Year Lnterval Inservice Inspection (ISI) Program
ML15126A57222 August 20142014 Prairie Island Nuclear Generating Plant Initial License Examination Administered Written Examination - Senior Reactor Operator
ML11252128922 January 2013Issuance of Amendments Adoption of Alternative Source Term Methodology
ML12178A37822 May 20122012 Prairie Island Nuclear Generating Plant Initial License Examination Proposed Written Examination
ML12165A12622 May 20122012 Prairie Island Nuclear Generating Plant Initial License Examination Administered Written Exam
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
L-PI-11-070, Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI9 August 2011Supplement to License Amendment Request to Exclude Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI
ML11201069622 July 2011RAI, Related to Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology
ML11172A02027 June 2011Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
L-PI-10-094, 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 - Response to RAI8 October 2010Supplement 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 - Response to RAI
L-PI-10-054, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology23 June 2010Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology
L-PI-09-114, License Amendment Request to Adopt the Alternative Source Term Methodology27 October 2009License Amendment Request to Adopt the Alternative Source Term Methodology
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
IR 05000282/200800214 May 2008IR 05000282-08-002, 05000306-08-002, on 01/01/2008 - 03/31/2008, Prairie Island Nuclear Generating Plant, Units 1 & 2, Operability Evaluations, Access Control to Radiologically Significant Areas
ML07081013120 March 2007Technical Specification Pages Re Steam Generator Tube Integrity
IR 05000282/200600314 August 2006IR 05000282/2006003, 05000306/2006003; 4/01/06 - 6/30/06; Prairie Island Nuclear Generating Plant, Units 1 and 2; Inservice Inspection Activities, Reactor Vessel Head Replacement, Radiation Protection, and Other Activities
L-HU-06-026, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity21 July 2006Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
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
ML0520901582 August 20052004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment
IR 05000282/200500421 July 2005IR 05000282-05-004, 05000306-05-004 on 04/01/2005 - 06/30/2005 for Prairie Island Nuclear Generating Plant, Units 1 and 2; Adverse Weather Protection; Fire Protection; Inservice Inspection Activities. and Other Activities
ML0517901897 July 20057/7/05, Prairie Island, Unit 1 - Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
IR 05000282/200400827 January 2005IR 05000282-04-008, 05000306-04-008; on 10/01/2004 - 12/31/2004; Prairie Island Nuclear Generating Plant, Units 1 & 2; Maintenance Effectiveness, Operability Evaluations, and Problem Identification and Resolution
L-PI-04-120, Emergency Action Levels Revision Submittal22 October 2004Emergency Action Levels Revision Submittal
ML0425803795 October 2004Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetration and Reactor Coolant Pressure Boundary Integrity.
ML04147048823 April 2004Items for Proposed Examination for Prairie Island Retake Examination - 2004
L-PI-03-089, License Amendment Request (LAR) Dated 10/31/03, Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with Unit 1 Replacement Steam Generators31 October 2003License Amendment Request (LAR) Dated 10/31/03, Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with Unit 1 Replacement Steam Generators
IR 05000282/200300529 October 2003IR 05000282-03-005 & IR 05000306-03-005, on 07/01/03 - 09/30/03, for Prairie Island Nuclear Generating Plant, Unit 1 & 2. Surveillance Testing
ML02322047618 November 2002RAI, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
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)
ML02221005426 July 2002Technical Specifications for License Amendment Nos. 158 and 149, Pages 3.4.13-1 to 5.0-4.5 (215 Pages)
ML02207065426 July 2002License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Safety Evaluation)
ML0215403013 June 2002Draft of Safety Evaluation
ML02155003730 May 2002Supplement to License Amendment Request Dated 12/11/2000, Conversion to Improved Technical Specifications (ITS)
ML02140003210 May 2002License DPR-42 and DPR-60, Supplement to License Amendment Request Dated 12/11/2000 Conversion to Improved Technical Specification (ITS)
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