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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23062A5112023-03-0303 March 2023 Refueling Outage Unit 1 R33 Owner'S Activity Report for Class 1. 2, 3 and Mc Inservice Inspections L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report ML20009F3312020-01-0909 January 2020 Refueling Outage Unit 2 R31 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations ML19108A2912019-04-18018 April 2019 Submittal of 2018 Unit 1 180-Day Steam Generator Tube Inspection Report ML19018A2042019-01-18018 January 2019 Inservice Inspection Summary Report Unit 1, Interval 5, Period 2, Outage 1 Refueling Outage Dates: 9/21/2018 to 10/26/2018 L-PI-18-003, Inservice Inspection Summary Report Unit 2, Refueling Outage Dates: 10/13/2017 to 11/20/2017, Fuel Cycle 29: 12/07/2015 to 11/20/20172018-02-12012 February 2018 Inservice Inspection Summary Report Unit 2, Refueling Outage Dates: 10/13/2017 to 11/20/2017, Fuel Cycle 29: 12/07/2015 to 11/20/2017 ML17046A6592017-02-15015 February 2017 Lnservice Inspection Summary Report Unit 1, Interval 5, Period 1, Outage 1, Refueling Outage Dates: 10/15/2016 to 11/20/2016, Fuel Cycle 29: 11/23/2014 to 11/20/2016 L-PI-16-030, Transmittal of 2015 180-Day Steam Generator Tube Inspection Report2016-05-20020 May 2016 Transmittal of 2015 180-Day Steam Generator Tube Inspection Report L-PI-16-013, Inservice Inspection Summary Report Refueling Outage Dates: 10/17/2015 to 12/06/2015, Fuel Cycle 28: 01/05/2014 to 12/06/20152016-03-0202 March 2016 Inservice Inspection Summary Report Refueling Outage Dates: 10/17/2015 to 12/06/2015, Fuel Cycle 28: 01/05/2014 to 12/06/2015 L-PI-15-025, Inservice Inspection Summary Report Unit 1, Interval 4, Period 3, Outage 2 - Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/20142015-02-18018 February 2015 Inservice Inspection Summary Report Unit 1, Interval 4, Period 3, Outage 2 - Refueling Outage Dates: 10/08/2014 to 11/22/2014, Fuel Cycle 28: 01/03/2013 to 11/22/2014 L-PI-15-016, Supplement to 10 CFR 50.55a Requests (RR) 1-RR-4-9 and 2-RR-4-9 (TACs MF4795 and MF4796) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fourth Ten-Year Interval Inservice Inspection (ISI) Program2015-02-0404 February 2015 Supplement to 10 CFR 50.55a Requests (RR) 1-RR-4-9 and 2-RR-4-9 (TACs MF4795 and MF4796) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fourth Ten-Year Interval Inservice Inspection (ISI) Program L-PI-15-013, Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-5 and 2-RR-5-5 (TACs MF4839 and MF4840) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fifth Ten-Year Interval Inservice Inspection (ISI) Program2015-02-0404 February 2015 Supplement to 10 CFR 50.55a Requests (RR) 1-RR-5-5 and 2-RR-5-5 (TACs MF4839 and MF4840) Associated with Prairie Island Nuclear Generating Plant (PINGP) Fifth Ten-Year Interval Inservice Inspection (ISI) Program L-PI-14-127, Fifth Interval Inservice Inspection Plan December 21, 2014 Through December 20, 20242014-12-18018 December 2014 Fifth Interval Inservice Inspection Plan December 21, 2014 Through December 20, 2024 L-PI-14-117, Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929)2014-11-24024 November 2014 Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929) L-PI-14-096, Supplement to 10 CFR 50.55a Requests RR-01, RR-03, RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Inservice Test Program2014-09-19019 September 2014 Supplement to 10 CFR 50.55a Requests RR-01, RR-03, RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Inservice Test Program L-PI-14-095, 10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 Associated with the Fifth Ten-Year Interval for the Lnservice Inspection Program2014-09-15015 September 2014 10 CFR 50.55a Requests 1-RR-5-7 and 2-RR-5-7 Associated with the Fifth Ten-Year Interval for the Lnservice Inspection Program L-PI-14-085, 10CFR 50.55a Requests Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program2014-09-15015 September 2014 10CFR 50.55a Requests Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program L-PI-14-080, 10 CFR 50.55a Requests 1-RR-4-9, 2-RR-4-9 and 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program2014-09-0303 September 2014 10 CFR 50.55a Requests 1-RR-4-9, 2-RR-4-9 and 2-RR-4-10 Associated with the Fourth Ten-Year Interval for the Inservice Inspection Program L-PI-14-015, 10 CFR 50.55a Requests RR-01, RR-03. RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Lnservice Test Program2014-04-0909 April 2014 10 CFR 50.55a Requests RR-01, RR-03. RR-05, RR-06 and RR-07 Associated with the Fifth Ten-Year Interval for the Lnservice Test Program L-PI-14-029, Lnservice Inspection Summary Report Unit 2. Interval 4, Period 3, Outage 2, Refueling Outage Dates: 09/21/2013 to 01/04/2014, Fuel Cycle 27: 05/29/2012 to 01/04/20142014-04-0303 April 2014 Lnservice Inspection Summary Report Unit 2. Interval 4, Period 3, Outage 2, Refueling Outage Dates: 09/21/2013 to 01/04/2014, Fuel Cycle 27: 05/29/2012 to 01/04/2014 L-PI-13-089, Supplement to Aging Management Program Submittals2013-10-0808 October 2013 Supplement to Aging Management Program Submittals L-PI-13-027, Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 10-23-2012 to 01-02-2013 Unit 1, Fuel Cycle 27: 06-12-2011 to 01-02-20132013-03-29029 March 2013 Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 10-23-2012 to 01-02-2013 Unit 1, Fuel Cycle 27: 06-12-2011 to 01-02-2013 L-PI-12-077, Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 02-21-2012 to 05-29-2012 U2, Fuel Cycle 26: 05-26-2010 to 05-29-20122012-08-23023 August 2012 Inservice Inspection Summary Report, Interval 4, Period 3, Outage 1, Refueling Outage Dates: 02-21-2012 to 05-29-2012 U2, Fuel Cycle 26: 05-26-2010 to 05-29-2012 L-PI-11-087, Lnservice Inspection Summary Report, Interval 4, Period 2, Outage 2 Refueling Outage Dates: 04-29-2011 to 06-11-2011 Unit 1, Fuel Cycle 26: 11-23-2009 to 06-11-20112011-09-0808 September 2011 Lnservice Inspection Summary Report, Interval 4, Period 2, Outage 2 Refueling Outage Dates: 04-29-2011 to 06-11-2011 Unit 1, Fuel Cycle 26: 11-23-2009 to 06-11-2011 L-PI-10-099, Unit 2 180-Day Steam Generator Tube Inspection Report2010-11-12012 November 2010 Unit 2 180-Day Steam Generator Tube Inspection Report L-PI-10-083, Inservice Inspection Summary Report, Interval 4, Period 2, Outage 2, Refueling Outage Dates: 04-16-2010 to 05-24-2010 Unit 2, Fuel Cycle 25: 11-02-2008 to 05-24-20102010-08-20020 August 2010 Inservice Inspection Summary Report, Interval 4, Period 2, Outage 2, Refueling Outage Dates: 04-16-2010 to 05-24-2010 Unit 2, Fuel Cycle 25: 11-02-2008 to 05-24-2010 L-PI-10-051, Revision to Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006 Fuel Cycle 23: 11-23-2004 to 06-06-2006 and Revision to 2008 Unit 1 180-Day Steam Generator Tube Inspection Report2010-06-0101 June 2010 Revision to Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006 Fuel Cycle 23: 11-23-2004 to 06-06-2006 and Revision to 2008 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-10-013, Inservice Inspection Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage Dates: 09-12-2009 to 11-23-2009, Unit 1, Fuel Cycle 25: 03-23-2008 to 11-23-20092010-02-22022 February 2010 Inservice Inspection Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage Dates: 09-12-2009 to 11-23-2009, Unit 1, Fuel Cycle 25: 03-23-2008 to 11-23-2009 L-PI-09-015, Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-20082009-01-28028 January 2009 Submittal of Inservice Inspection Examination Summary Report, Interval 4, Period 2, Outage 1, Refueling Outage, Dates: 09-19-2008 to 11-01-2008 Unit 2, Fuel Cycle 24:12-15-2006 to 11-01-2008 L-PI-08-082, Amendment to Unit 2 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-20062008-10-0707 October 2008 Amendment to Unit 2 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006 L-PI-08-055, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2 Refueling Outage Dates: 02-13-2008 to 03-23-2008, Fuel Cycle 24: 06-06-2006 to 03-23-20082008-06-19019 June 2008 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2 Refueling Outage Dates: 02-13-2008 to 03-23-2008, Fuel Cycle 24: 06-06-2006 to 03-23-2008 ML0727800262007-10-31031 October 2007 Relief Request from ASME Code, Section X1, Inservice Inspection Program Relief Requests Nos. 1-RR-4-7 and 2-RR-4-7 L-PI-07-037, 10 CFR 50.55a Request 1-RR-4-6 for the Prairie Island, Unit 1, Fourth Ten-year Interval Inservice Inspection Program2007-05-11011 May 2007 10 CFR 50.55a Request 1-RR-4-6 for the Prairie Island, Unit 1, Fourth Ten-year Interval Inservice Inspection Program L-PI-07-023, Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-20062007-03-14014 March 2007 Inservice Inspection Summary Report, Interval 4, Period 1, Outage 2, Refueling Outage Dates: 11-15-2006 to 12-15-2006, Fuel Cycle 23: 06-11-2005 to 12-15-2006 L-PI-06-102, Unit 2 Steam Generator Inspection Results - 15 Day Report2006-12-18018 December 2006 Unit 2 Steam Generator Inspection Results - 15 Day Report L-PI-06-096, CFR 50.55a Requests 1-RR-4-7 and 2-RR-4-7 for the Units 1 and 2 Fourth 10-Year Interval Inservice Inspection Program2006-12-14014 December 2006 CFR 50.55a Requests 1-RR-4-7 and 2-RR-4-7 for the Units 1 and 2 Fourth 10-Year Interval Inservice Inspection Program ML0627701952006-10-0202 October 2006 Notification of NRC Inspection and Request for Information L-PI-06-072, Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006, Fuel Cycle 23: 11-23-2004 to 06-06-20062006-09-0101 September 2006 Inservice Inspection Summary Report, Interval 4, Period 1, Refueling Outage Dates: 04-28-2006 to 06-06-2006, Fuel Cycle 23: 11-23-2004 to 06-06-2006 L-PI-05-082, Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program2005-09-0808 September 2005 Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program L-PI-04-135, Inservice Inspection Summary Report, Interval 3, Period 3, Interval 4, Period 1 Refueling Outage Dates: April 16, 2005 - June 10, 2005, Fuel Cycle 22: October 11, 2003 - June 10, 20052005-09-0808 September 2005 Inservice Inspection Summary Report, Interval 3, Period 3, Interval 4, Period 1 Refueling Outage Dates: April 16, 2005 - June 10, 2005, Fuel Cycle 22: October 11, 2003 - June 10, 2005 L-PI-05-074, Response to Request for Additional Information Regarding the Unit 1 Lnservice Lnspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-10-2004 to 11-23-2004 Fuel Cycle 22..2005-08-22022 August 2005 Response to Request for Additional Information Regarding the Unit 1 Lnservice Lnspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-10-2004 to 11-23-2004 Fuel Cycle 22.. L-PI-05-013, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-042005-02-22022 February 2005 Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates 09-10-04 Fuel Cycle 22: 12-7-2002 to 11-23-04 L-PI-05-012, Request for Relief No. 17, Revision 0, for the Plant 3rd 10-year Interval Inservice Inspection Program2005-02-22022 February 2005 Request for Relief No. 17, Revision 0, for the Plant 3rd 10-year Interval Inservice Inspection Program L-PI-05-002, 60-Day Report Pursuant to NRC Bulletin 2003-02 for 2004 Prairie Island Unit 1 Lower Head Penetration Inspection2005-01-24024 January 2005 60-Day Report Pursuant to NRC Bulletin 2003-02 for 2004 Prairie Island Unit 1 Lower Head Penetration Inspection L-PI-04-009, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-13-2003 to 10-10-2003 Fuel Cycle 21: 3-3-2002 to 10-10-20032004-01-0707 January 2004 Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates: 9-13-2003 to 10-10-2003 Fuel Cycle 21: 3-3-2002 to 10-10-2003 L-PI-04-005, Request for Relief No. 16, Revision 0 for the Third 10-Year Interval Inservice Inspection Program2004-01-0707 January 2004 Request for Relief No. 16, Revision 0 for the Third 10-Year Interval Inservice Inspection Program L-PI-03-035, Relief Request to Perform a Visual Examination in Lieu of Volumetric Examination of Reactor Vessel Nozzle Inner Radius Sections Per Code Case N-648-12003-04-0303 April 2003 Relief Request to Perform a Visual Examination in Lieu of Volumetric Examination of Reactor Vessel Nozzle Inner Radius Sections Per Code Case N-648-1 L-PI-03-025, Relief Request to Use VT-1 Visual Examination in Lieu of Surface Examination of Reactor Vessel Head Closure Nuts2003-03-14014 March 2003 Relief Request to Use VT-1 Visual Examination in Lieu of Surface Examination of Reactor Vessel Head Closure Nuts ML0309003422003-03-0606 March 2003 Request for Relief No.14 for Unit 1 3rd 10-Year Interval Inservice Inspection Program L-PI-03-029, Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates:11-15-2002 to 12-6-2002 Fuel Cycle 21: 2-25-2001 to 12-6-02, Items 1-18-010 - I-19-10062003-03-0606 March 2003 Inservice Inspection Summary Report, Interval 3, Period 3, Refueling Outage Dates:11-15-2002 to 12-6-2002 Fuel Cycle 21: 2-25-2001 to 12-6-02, Items 1-18-010 - I-19-1006 2023-03-03
[Table view] Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
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1717 Wakonade Drive Welch, MN 55089 800.895.4999 xcelenergy.com FEC \ 5 2017 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Unit 1 Docket 50-282 Renewed License No. DPR-42 Xcel Energy@ R E S P 0 N SIBLE BY NAT U R E L -PI-17 -009 10 CFR 50.55a lnservice Inspection Summary Report Unit 1. Interval 5. Period 1, Outage 1. Refueling Outage Dates: 10/15/2016 to 11/20/2016, Fuel Cycle 29: 11/23/2014 to 11/20/2016 During the 2016 Prairie Island Nuclear Generating Plant (PINGP) Unit 1 refueling outage, an inservice inspection (lSI) examination for the first period of the fifth interval was conducted.
Form OAR-1 Owner's Activity Report (Enclosure
- 1) is being submitted for this time period as required by the American Society of Mechanical Engineers (ASME) Code Section XI, in accordance with the provisions of Code Case N-532-5, and is intended to satisfy the inspection reporting requirements.
The form includes a listing of items with flaws or relevant conditions that required evaluation for continued service (Table 1) and an abstract of repair/replacement activities required for continued service (Table 2). Also attached is an evaluation of the acceptability of inaccessible areas of the Unit 1 Containment Vessel (Enclosure
- 2) in accordance with the requirements of 1 OCFR 50.55a(b )(2)(ix)(A).
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments. . Scott Northard Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota Enclosure (2) cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, SNRC ENCLOSURE 1 FORM OAR-1 OWNER'S ACTIVITY REPORT for Unit 1, Interval 5, Period 1, Outage 1, Refueling Outage Dates: 10/15/2016 to 11/20/2016, Fuel Cycle 29: 11/23/2014 to 11/20/2016 3 pages follow Report Number FORM OAR-1 OWNER'S ACTIVITY REPORT Prairie Island Nuclear Generating Plant As required by the provisions of ASME Code Case N-532-5 1R30 Plant Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East. Welch, Minnesota, 55089 Unit No. _ __,1 __ _ Commercial service date -----'1'""2"-/1_,_,6'-'-/1.!..:9"-'7_,3,__
__ _ Refueling outage no. -----'1'-'-R-'-"3""0'---
Current inspection interval_5 1 h lSI Inspection Interval for class 1 I 2, and 3. 2nd IWE Inspection Interval for class MC Current inspection period_ 1st lSI Inspection Period for class 1, 2, and 3. 3rct IWE Inspection period for class MC Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition -2008 Addenda for class 1, 2. and 3. 2001 Edition -2003 Addenda for class MC __ _ Date and revision of inspection plans __ _,6'-'-'/2"'"'2"'-/-'-'16"--'-'R,_,e"'"v
_,_1_,__, =.2 .
9"'--'-'fo"-'-r__,c""la.,s""s-"M'""C"'----
Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as Inspection Plan for class 1.2. and 3. 2007 Edition -2008 Addenda for class MC Code Cases used for inspection and evaluation;
__ _,_N_,__-""'5,32,_-_,5..__, '--'N_,-6,_,6'--'1__,-2=-<,_,_N_,__-_,__7-'-'16"---'-1.._, N'-!-!-7_,_7-"6"--,
__ CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this Owner's Activity Report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section XI: and (c) the repair/replacement activities and evaluations supporting the completion of refueling outage number 1 R30 conform to the requirements of Section XI. Date I 2.4. -'ZO I CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
{) 2, 2.011 TABLE 1 *'* ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and lteni Description
' Evaluation Description Item Number B-L-2, B12.20 12 RCP Pump *Internals Two indications of minor gouges determined to be non-relevant AR 1539956. B-P, B15.80 Reactor Vessel Bottom Head per Non-relevant indications of light translucent Code Case N-722-1 streaks AR 1541635. B-P, B15.10 SP 1168.1 RCS Pressure Test Non-relevant p1;1cking and fitting indications ARs: 1542388, 1542377. B-P, B15.10. SP 1392 Bolted Connections Borated Dry White boric acid indications at bolted conn. C-H, 07.10 Pressure Test accepted by evaluation AR 1538861. C-H, 07.10 SP 1168.12 Sl Accumulator Pressure Non-relevant packing indication AR 1542409. test . C-H, 07.10 SP 1168.13 Safety Injection Pressure Non-relevant packing and fitting indications test ARs: 1540887, 1540890, 1540893, 1540891. C-H, 07.10 .SP 1168.13 Safety Injection Pressure Dry white boric acid indication at bolted conn. test accepted by evaluation AR 1541116. C-H, 07.10 SP 1168.14 Containment Spray Dry white boric acid indication at packing. Non-Pressure Test releva11t packing indication AR 1514520. C-H, 07.10 SP 1168.16 CVCS Pressure Test Non-relevant packinQ indication AR 1447393. C-H, 07.10 SP 1168.17 Feedwater Pressure Test Non-relevant indication outside code boundary AR 1542651. C-H, 07.10 SP 1168.6 Aux Feed Pressure test Non-relevant packing indication AR 1542522. D-B, D2.10 D-B, D2.10 SP 1168.4 Component Cooling Non-relevant bolted connection and fitting Pressure Test indications AR 1538737..
- D-8, 02.10 SP 1168.8 Cooling Water Pressure Non-relevant mechanical connection Test indications AR 1518348. E*A, E1.11 Containment Accessible Areas 3 indications of gouges accepted by evaluation AR 1540848. E-A, E1.30 Moisture Barrier 3 indications of la13k of adhesion and 1 tear accepted by corrective measures AR 1541212 and WO 478898. F-A, F1.10b Rupture Restraint 9-RHR-3A Residual Heat Removal Restraint with indication oflack otthreact engagement.
Accepted by evaluation EO 27137 and AR 1539806. . F-A, F1.20a Rod/Clamp 1-SIRH-15 Safety Injection hanger with indication of misalignment.
Accepted by evaluation EC 27737 and AR 1539778. F-A, F1.20a Rod/Clamp 1-RSH-3 Safety Injection small bore support rod has slight bend non-relevant EC 27737 and AR 1538986. F-A, F1.20b Constant Support 1-MSDH-24 Main Steam large bore support missing scale and rod in contact With condu.it non-relevant EC 27737 and AR 1538356. F-A 1 FL30a Rod/Clamp Cooling Water hanger with indication of bent rod at top of hanger top. Accepted by evaluation EC 27137 and AR *-1539147. F-A, F1.30b Pipe Rack Support 1-CWH-261 Cooling Water multiple support assernbly with indications cif bolt not fully engaged and bent column. Accepted by evaluation EC 27737 and AR 1539153. F-A, F1.30c Spring Hanger 1-CWH-218 Cooling Water hanger with indication of skewed anchor bolt in baseplate.
Accepted by evaluation EC 27737 and AR 1539844. F-A, F1.40 12 RCP Support Column H-2 Hairline crack in grout. Non-relevant indication outside the scope of ASME XI AR 1540224. ...
TABLE2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Plant ID Item Description of Work Completed Date RIR Class # Description Completed Plan# D2 DSLGEN 035-072 Lube Oil Cooler Performed weld build of eroded areas of 3 D2 DSL GEN the channel ends and covers as needed to 3/13/2015 1-29-002 035-062 Jacket Water restore sealing surfaces.
Cooler 035-052 D2DSL GEN Air Cooler Cooling 3 3-CL-88 Water Pipe Replaced segment of pipe due to MIC. 3/9/2016 1-29-003 Segment 2 174-011 11 FCU Coils Replaced the containment fan coil unit 1/4/2017 1-29-026 coils. Cooling Replaced a section of Cooling Water pipe 3 4-CL-11 Water system 4/12/2016 1-29-012 pipe spool due to MIC. 2 162-393 13 CHG PMP Replaced Cap Screw on Desurger.
8/3/2016 1-29-032 Hyd Desurger 2 174-014 14 FCU Coils Replaced the containment fan coil unit 1/4/2017 1-29-034 coils. 2 174-012 12 FCU Coils Replaced the containment fan coil unit 1/4/2017 1-29-035 coils. 2 174-013 13 FCU Coils Replaced the containment fan coil unit 1/4/2017 1-29-036 coils. 3 035-052 D2 Air Cooler Replaced the D2 Diesel Generator air cooler 1/3/2017 1-29-043 tube bundle. ZX Piping 3 10-ZX-75 Segment Installed Code Case N-661-2 weld overlay 12/16/2016 1-29-060 (located in on area of thinning due to MIC. the E1 elbow)
ENCLOSURE 2 Evaluation of the Acceptability of the Inaccessible Areas of the Unit 1 Containment Vessel in Accordance with the requirements of 10CFR 50.55a(b)(2)(ix)(A) 5 pages follows Condition Evaluation NUMBER: 01538143-03 SHEET NO: 1 OF 5 TITLE: EVALUATION OF INACCESSIBLE CONTAINMENT AREAS DATE: 10/22/2016 COMP. BY: TRD 1.0 Purpose and Summary Result The purpose of this evaluation is to evaluate the acceptability of inaccessible areas of the Unit 1 Containment vessel in accordance with the requirements of 1 OCFR 50.55a(b )(2)(ix)(A).
The containment vessel is determined to be acceptable for continued service with no corrective actions. 2.0 Background AR 01538143 "identified that there was numerous excessive deposits of boric acid around the 695 elevation of containment that were due to water migration through the concrete originating from the flooded Sump B." The flooding was the result of leaking RHR suction valves which allowed water from the Refueling Water Storage Tank to leak into the containment RHR sump and overflow into the surrounding areas. Increasing sump level was identified in June of 2015 with potential exposure of the containment vessel to borated water conservatively estimated at 18 months [4.1]. Migration of borated water through the containment concrete (as identified in the AR) indicates borated water may have come in contact with the containment vessel. Borated water in contact with the containment vessel is a condition that could indicate the presence of or could result in degradation of inaccessible areas. As required by 1 OCFR 50.55a(b)(2)(ix)(A): (A) Metal containment examinations:
First provision.
For Class MC applications, the following apply to inaccessible areas. (1) The applicant or licensee must evaluate the acceptability of inaccessible areas when conditions exist in accessible areas that could indicate the presence of or could result in degradation to such inaccessible areas. (2) For each inaccessible area identified for evaluation, the applicant or licensee must provide the following in the lSI Summary Report as required by IWA-6000: (i) A description of the type and estimated extent of degradation, and the conditions that led to the degradation; (ii) An evaluation of each area, and the result of the evaluation; and (iii) A description of necessary corrective actions.
Condition Evaluation NUMBER: 01538143-03 SHEET NO: 2 OF 5 TITLE: EVALUATION OF INACCESSIBLE CONTAINMENT AREAS DATE: 10/22/2016 COMP. BY: TRD 3.0 Evaluation 3.1 A description of the type and estimated extent of degradation, and the conditions that led to the degradation; Based on a long history of borated water exposure with no measureable degradation and evaluation of potential corrosion rates, there is a high level of confidence there is no significant degradation of the containment vessel. Refueling cavity leakage has been experienced in various areas of containment of both units dating back to approximately 1988. The most prominent a,nd consistent leakage was through the grout in Sump B [4.2]. Cavity leakage has been mitigated in recent years after cavity liner modifications were performed in 1 R27 (2011) and 2R27 (2012) [4.3]. In order to access the potential degradation to the containment vessels, the site performed several excavations of areas known and suspected of repeated or long term exposure to borated water as summarized in the below table. Excavation When/Reference Results Location Unit 2 1998 (2R 19) [4.2] During the 1998 Unit 2 refueling outage Containment (2R19) water was found entering sump 8 RHR Sump B from the area outside the RHR suction penetration sleeve. Leakage was measured at 0.5 gph. The water was sampled and determined to be at refueling water boron concentration, approximately 2700 ppm. The water also contained short lived nuclides.
The pH of the water was 7.8, slightly alkaline.
The grout around the penetration was partially removed to determine the condition of the containment vessel wall. The vessel showed no signs of degradation.
Unit 1 2002 (1 R22) [4.2] Removed grout unit 1 sump 8 for visual Containment inspection of containment vessel. RHR Sump B Unit 2 2008 (2R25) [4.2] The grout was removed from sump B to Containment allow visual and UT inspection of the RHR Sump 8 containment vessel. There was no indication of degradation.
The leakage in sump 8 was reported to well up from the bottom of the removed grout at a rate of Condition Evaluation NUMBER: 01538143-03 SHEET NO: 3 OF 5 TITLE: EVALUATION OF INACCESSIBLE CONTAINMENT AREAS DATE: 1 0/22/2016 COMP. BY: TRD approximately 1gph. Unit 1 2009(1R26)
Removed grout and took UT readings Containment W0372531 (BOP-UT-09-012).
All readings above RHR Sump B 3.56" thickness.
No degradation.
Unit 1 RV 2011 (1 R27) [4.3] Concrete was removed from sump C. VT Sump C examination of exposed rebar and containment vessel, and UT thickness readings of containment vessel showed no indication of degradation (reference VT report BOP-VT-11-032 and BOP-UT 01 0). The containment vessel showed no rust, pitting or other degradation.
Ten thickness readings were taken with a lowest reading of 1.561 inch as compared to the nominal/design shell thickness of 1.5 inch. Unit 2 RV 2012 (2R27) [4.3] Concrete was excavated from the unit 2 Sump C reactor vessel sump C in 2R27 (spring 2012) to allow for direct visual examination and UT thickness measurement of the containment vessel. Water seeped into the excavation at approximately 8 cubic inches in 15 minutes (AR01337188).
The pH of the water was not tested. Boron concentration was less than 1 0 ppm and reactivity was 2.0 1 E-05 uCi/ml Co-58. The containment vessel was found to be in good condition with no degradation.
UT thickness readings were above 1.6" as compared to a design thickness of 1.5" (NDE report BOP-VT-12-055).
The exposed rebar was also in good condition with no significant degradation The above summary shows six excavations performed over a period of approximately 14 years. The excavations included areas known to be periodically wetted (RHR Sumps) and areas thought to be continually wetted (RV Sumps as they are near the low point of the containment vessel). None of the excavations showed detectable degradation either visually or with ultrasonic thickness measurement.
Condition Evaluation NUMBER: 01538143-03 SHEET NO: 4 OF 5 TITLE: EVALUATION OF INACCESSIBLE CONTAINMENT AREAS DATE: 10/22/2016 COMP. BY: TRD A Root Cause Evaluation (RCE) of refueling cavity leakage assessed potential corrosion rates of the containment vessels with the following results [4.2]: Tests at ambient temperature indicate that the rates of corrosion of steel in aerated concentrated boric acid solutions range between 0.002 to 0.007 inches (Section 4.4.1 of the Boric Acid Corrosion Guidebook, Rev. 1 [29]). These rates are probably conservative for the current application since the pH of solution in contact with the steel containment vessel will be buffered by alkalinity from the cement in the concrete.
A test in 1998 of leaking water at the RHR penetration in Sump B where grout had been removed indicated that the pH was 7.8 [30]. Another test in 1998 of water collected on the floor of the RCDT room indicated a pH of 7.0 [30]. The water had high concentrations of boron which, if it had not been buffered, would have resulted in pH values of 5 or less. This indicates that the boric acid had been buffered by alkalinity from the cement in the concrete.
Corrosion rates in near neutral water at ambient temperatures are about 0.2 mm/year (0.008 in./year) (Figure 3 on Page 536 of [28]). A long term test was performed by Florida Power and Light to determine the corrosion rate of carbon steel rebar in contact with concentrated boron solution (2370 ppm) at pH 7.4 at ambient temperature
[31]. This test measured a corrosion rate after 8 years of test of 0.005 inches/year.
Research performed as part of the RCE indicates potential corrosion rates of approximately 0.008 in I year. A potential exposure of 18 months would not result in significant degradation of the containment vessel. Based on six excavations over a period of 14 years with no degradation and an expected corrosion rate of approximately 0.008 in./year, there is a high level of confidence that the potential borated water exposure during Unit 1 cycle 29 did not result in any significant degradation.
3.2 An evaluation of each area, and the result of the evaluation.
All areas of potential degradation as a result of RHR Sump B flooding are discussed above. The evaluation has determined a high level of confidence there is no significant degradation of the containment vessel.
Condition Evaluation NUMBER: 01538143-03 SHEET NO: 5 OF 5 TITLE: EVALUATION OF INACCESSIBLE CONTAINMENT AREAS DATE: 10/22/2016 COMP. BY: TRD 3.3 A description of necessary corrective actions. As there is no indication of degradation, no corrective actions are necessary.
4.0 References
4.1 AR 01484218 Unit 1 Sump B level increasing.
4.2 RCE 01160372-01 Refueling Cavity Leakage Event Date: 1988-2008.
4.3 AR 01160372 Refueling Cavity Leakage Corrective Actions and the LRA 5.0 Attachments None.