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Issue date | Title | |
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L-PI-22-001, 7 to Updated Safety Analysis Report, Enclosure 4, Bases Changes and License Amendments | 28 April 2022 | 7 to Updated Safety Analysis Report, Enclosure 4, Bases Changes and License Amendments |
ML21139A311 | 19 May 2021 | Independent Spent Fuel Storage Installation (ISFSI) - Revised Emergency Plan (E-Plan), Emergency Plan Implementing Procedures (EPIP) and Rec/Rpss Handbook |
ML20245E569 | 27 August 2020 | ES-401-9 |
ML20246G740 | 27 August 2020 | Ile As-Administered Written Exam |
ML20252A254 | 27 August 2020 | Proposed facility-developed RO-SRO Written Examination |
ML20118D318 | 27 April 2020 | Enclosure 4 - Technical Specifications (TS) Bases Control Program |
ML22179A272 | 20 September 2018 | 2018 PI Ile Administered Written Exam Reference Handouts |
IR 05000282/2018001 | 9 May 2018 | NRC 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 13 | 17 April 2018 | Enclosure 1, Form 1576 Emergency Action Level (EAL) Matrix, Revision 10 and Emergency Action Level Technical Bases, Revision 13 |
05000306/LER-2017-002 | 11 December 2017 | Reactor 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 Information | 27 September 2017 | License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information |
ML17094A576 | 29 March 2017 | License Amendment Request to Revise Emergency Action Level (EAL) Scheme |
L-PI-16-045, Revisions to Technical Specifications Bases | 20 May 2016 | Revisions to Technical Specifications Bases |
IR 05000282/2015007 | 14 October 2015 | IR 05000282/2015007, 05000306/2015007; 08/03/2015 - 09/04/2015; Prairie Island Nuclear Generating Plant, Units 1 and 2; Component Design Bases Inspection |
ML15196A221 | 12 August 2015 | Requests 1-RR-5-1 and 2-RR-5-1 Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program |
IR 05000282/2015001 | 6 May 2015 | IR 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) Program | 4 February 2015 | 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) Program |
ML15126A572 | 22 August 2014 | 2014 Prairie Island Nuclear Generating Plant Initial License Examination Administered Written Examination - Senior Reactor Operator |
ML112521289 | 22 January 2013 | Issuance of Amendments Adoption of Alternative Source Term Methodology |
ML12178A378 | 22 May 2012 | 2012 Prairie Island Nuclear Generating Plant Initial License Examination Proposed Written Examination |
ML12165A126 | 22 May 2012 | 2012 Prairie Island Nuclear Generating Plant Initial License Examination Administered Written Exam |
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-11-070, 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 RAI | 9 August 2011 | 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 RAI |
ML112010696 | 22 July 2011 | RAI, 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 |
ML11172A020 | 27 June 2011 | Technical 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 RAI | 8 October 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 - Response to RAI |
L-PI-10-054, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology | 23 June 2010 | Response 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 Methodology | 27 October 2009 | License 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 Licenses | 30 July 2009 | NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses |
IR 05000282/2008002 | 14 May 2008 | IR 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 |
ML070810131 | 20 March 2007 | Technical Specification Pages Re Steam Generator Tube Integrity |
IR 05000282/2006003 | 14 August 2006 | IR 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 Integrity | 21 July 2006 | Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity |
L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity | 16 February 2006 | Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity |
ML052090158 | 2 August 2005 | 2004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment |
IR 05000282/2005004 | 21 July 2005 | IR 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 |
ML051790189 | 7 July 2005 | 7/7/05, 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 05000282/2004008 | 27 January 2005 | IR 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 Submittal | 22 October 2004 | Emergency Action Levels Revision Submittal |
ML042580379 | 5 October 2004 | Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetration and Reactor Coolant Pressure Boundary Integrity. |
ML041470488 | 23 April 2004 | Items 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 Generators | 31 October 2003 | 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 Generators |
IR 05000282/2003005 | 29 October 2003 | IR 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 |
ML023220476 | 18 November 2002 | RAI, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity |
ML022280354 | 8 August 2002 | DAEC Emergency Planning Department Procedure Transmittal Acknowledgment Memo |
ML022210043 | 26 July 2002 | Technical Specifications for License Amendment Nos. 158 and 149, Pages 1.1-1 to 3.4.13-1 (174 Pages) |
ML022070654 | 26 July 2002 | License Amendment Nos. 158 and 149, Conversion to Improved Technical Specifications (Safety Evaluation) |
ML022210054 | 26 July 2002 | Technical Specifications for License Amendment Nos. 158 and 149, Pages 3.4.13-1 to 5.0-4.5 (215 Pages) |
ML021540301 | 3 June 2002 | Draft of Safety Evaluation |
ML021550037 | 30 May 2002 | Supplement to License Amendment Request Dated 12/11/2000, Conversion to Improved Technical Specifications (ITS) |