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MONTHYEARML0727800262007-10-31031 October 2007 Relief Request from ASME Code, Section X1, Inservice Inspection Program Relief Requests Nos. 1-RR-4-7 and 2-RR-4-7 Project stage: Other 2007-10-31
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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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October 31, 2007 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - RELIEF REQUEST FROM ASME CODE, SECTION XI, INSERVICE INSPECTION PROGRAM RELIEF REQUESTS NOS. 1-RR-4-7 AND 2-RR-4-7 (TAC NOS. MD3809 AND MD3810)
Dear Mr. Wadley:
By letter dated December 14, 2006 (Agencywide Documents Access and Management System Accession No. ML063480521), Nuclear Management Company, LLC, (the licensee),
requested Nuclear Regulatory Commission (NRC) approval, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(ii), for relief from a section of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section XI, 1998 Edition, with 2000 Addenda. In Relief Request (RR) Nos. 1-RR-4-7 and 2-RR-4-7, the licensee requested relief from performing the ASME Code-required pressure test of the buried portion of cooling water piping by proposing the alternative method of measuring rate of pressure loss or change in flow between the ends of the buried components. Alternatively, the licensee proposed a test that will confirm that flow during operation is not impaired.
Based on the information provided in RR Nos. 1-RR-4-7 and 2-RR-4-7, the NRC staff concluded, in the enclosed safety evaluation, that the licensees compliance with the Inservice Inspection (ISI) Code of Record would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety and, further, that the licensees proposed alternative provides reasonable assurance of operational readiness. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the NRC staff authorizes the ISI program alternative proposed in RR Nos. 1-RR-4-7 and 2-RR-4-7, for the fourth 10-year ISI interval of the Prairie Island Nuclear Generating Plant, Units 1 and 2.
Sincerely,
/RA/
Cliff G. Munson, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Safety Evaluation cc w/encl: See next page
October 31, 2007 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - RELIEF REQUEST FROM ASME CODE, SECTION XI, INSERVICE INSPECTION PROGRAM RELIEF REQUESTS NOS. 1-RR-4-7 AND 2-RR-4-7 (TAC NOS. MD3809 AND MD3810)
Dear Mr. Wadley:
By letter dated December 14, 2006 (Agencywide Documents Access and Management System Accession No. ML063480521), Nuclear Management Company, LLC, (the licensee),
requested Nuclear Regulatory Commission (NRC) approval, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(ii), for relief from a section of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section XI, 1998 Edition, with 2000 Addenda. In Relief Request (RR) Nos. 1-RR-4-7 and 2-RR-4-7, the licensee requested relief from performing the ASME Code-required pressure test of the buried portion of cooling water piping by proposing the alternative method of measuring rate of pressure loss or change in flow between the ends of the buried components. Alternatively, the licensee proposed a test that will confirm that flow during operation is not impaired.
Based on the information provided in RR Nos. 1-RR-4-7 and 2-RR-4-7, the NRC staff concluded, in the enclosed safety evaluation, that the licensees compliance with the Inservice Inspection (ISI) Code of Record would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety and, further, that the licensees proposed alternative provides reasonable assurance of operational readiness. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the NRC staff authorizes the ISI program alternative proposed in RR Nos. 1-RR-4-7 and 2-RR-4-7, for the fourth 10-year ISI interval of the Prairie Island Nuclear Generating Plant, Units 1 and 2.
Sincerely, Cliff G. Munson, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282, and 50-306
Enclosure:
Safety Evaluation cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrPMMChawla RidsNrrLATHarris RidsNrrDorlLpl3-1 RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDciCsgb Jpoole CLipa, RGN-III RidsRgn3MailCenter TBloomer, EDO, Rgn III ADAMS Accession Number: ML072780026 *per Memo dated September 10, 2007 OFFICE LPL3-1 LPL3-1/PM LPL3-1/LA DCI/CSGB/BC OGC LPL3-1/(A)BC NAME JPoole MChawla THarris AHiser* Bklukan (NLO) CMunson DATE 10/ 30 /07 10/ 30 /07 10/ 30 /07 9/10/07 10/17/07 10 / 31 /07 OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INSERVICE INSPECTION PROGRAM RELIEF REQUESTS 1-RR-4-7 AND 2-RR-4-7 NUCLEAR MANAGEMENT COMPANY, LLC PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP), UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306
1.0 INTRODUCTION
By letter dated December 14, 2006 (Agencywide Documents Access and Management System Accession No. ML063480521), Nuclear Management Company, LLC, (NMC, the licensee), requested Nuclear Regulatory Commission (NRC) approval, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(a)(3)(ii), for relief from a section of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 1998 Edition, with 2000 Addenda. In Relief Request (RR) Nos. 1-RR-4-7 and 2-RR-4-7, the licensee requested relief from performing the ASME Code-required pressure test of the buried portion of cooling water piping by proposing the alternative method of measuring rate of pressure loss or change in flow between the ends of the buried components. Alternatively, the licensee proposed a test that will confirm that flow during operation is not impaired.
The licensee proposed that the integrity of the buried piping will be verified during quarterly pump testing under the inservice testing (IST) program for pumps and valves. The NRC staff has reviewed the licensees proposed alternative pursuant to 10 CFR 50.55a(a)(3)(ii) since compliance to the ASME Code requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
2.0 REGULATORY REQUIREMENTS The inservice inspection (ISI) of the ASME Code Class 1, 2, and 3 components is to be performed in accordance with the ASME Code,Section XI, and applicable edition and addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). According to 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph 50.55a(g) may be used, when authorized by the NRC, if an applicant demonstrates that the proposed alternatives would provide an acceptable level of quality and safety or if the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components.
ENCLOSURE
The regulations require that ISI of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
The ISI Code of Record for the fourth 10-year inspection interval of the PINGP, Units 1 and 2, is the 1998 Edition with the 2000 Addenda of the ASME Code,Section XI.
3.0 TECHNICAL EVALUATION
System/Component(s) for Which Relief is Requested Buried Class 3 Cooling Water Supply Lines 30-CL-20 and 30-CL-23 ASME Code Requirements As applicable to PINGP, Units 1 and 2, the 1998 Edition with the 2000 Addenda of the ASME Code,Section XI, Table IWD-2500-1, Examination Category D-B, Item No. D2.10 requires a system leakage test and a VT-2 visual examination. Subsection IWA-5244(b) states that for buried components where a VT-2 visual examination cannot be performed, the examination requirement is satisfied by the following:
(1) The system pressure test for buried components that are isolable by means of valves shall consist of a test that determines the rate of pressure loss. Alternatively, the test may determine the change in flow between the ends of the buried components. The acceptable rate of pressure loss or flow shall be established by the Owner.
(2) The system pressure test for nonisolable buried components shall consist of a test to confirm that flow during operation is not impaired.
Licensees Request for Relief Relief is requested from performing the system pressure test or the system leakage test for buried portions that are isolable by means of valves by determining the rate of pressure loss or the change in flow between the ends of buried components.
Licensees Basis for Requesting Relief The buried cooling water piping at PINGP, Units 1 and 2, consists of approximately 200 feet of 30-inch diameter piping supplying to a common ring header that is shared by both units. Each of the cooling water lines that feed into the ring header extend underground from the screen house to the turbine building. Part of this buried piping is also under the administrative building. There are no branch lines that are buried. Each segment of the buried piping has two 18-inch and two 24-inch butterfly valves for the purpose of isolation. The instrumentation upstream of the buried piping consists of pressure indication at the discharge of the cooling water pumps. There is no flow measuring instrument upstream of the supply header.
However, there is a flow meter on the downstream of the supply header in the turbine building. There is no access to the buried sections of piping without excavation. Further, no annulus was provided during original construction that would allow for examination of these buried sections of piping. In order to perform a rate of pressure loss test required under IWA-5244(b)(1), it would be necessary to close several large butterfly valves to isolate the buried portions of piping. These valves are not suitable for performing a pressure isolation function since they were not designed to be leak tight.
Extensive maintenance or system modification would be required to conduct a rate of pressure loss test. The alternative test would be to determine the change in flow between the ends of buried components. However, the cooling water supply header was not designed with plant instrumentation and flow orifices on both sides of the buried sections of piping to determine the change in flow rates.
Therefore, the configuration of the buried cooling water system will not allow for determining the change in flow between the ends of the buried components.
Licensees Proposed Alternative In lieu of performing a system pressure test in accordance with the requirements of IWA-5244(b)(1) for PINGP, Units 1 and 2, NMC proposed an alternative to use the provision of IWA-5244(b)(2) of the 1998 Edition with the 2000 Addenda of the ASME Code,Section XI, to confirm that flow during operation is not impaired in non-isolable buried piping. The unimpaired flow in the buried piping will be verified during cooling water pump testing performed under the IST program. During these tests, the flow and the pressure of the cooling water pumps will be plotted against a test reference value.
The pressure will be measured at the discharge of the pump and the flow measurement will be done using the flow meter located downstream of the header in the turbine building. The head developed and the flow rate are interdependent variables which together define the hydraulic performance of the pump. As the pump degrades, the total discharge head will decrease at the reference flow rate.
However, due to the location of the flow rate instruments (downstream of the buried piping), a decrease in pump head during testing may also indicate leakage from the cooling water system between the pump discharge and the flow meter in the turbine building. A leak in the underground portion of the cooling water header would result in reduced pump performance on the pump curve.
Satisfactory quarterly IST of the cooling water pump will verify the integrity of the buried piping.
If the performance of a cooling water pump drops below the reference range on the performance curve, and the cause of the deviation is not attributed to the test instruments being used, corrective actions will be initiated to evaluate the cause of the reduced performance as required by the PINGP IST program. If the pump performance falls into the action range, the pump would be declared inoperable and further corrective actions (i.e., maintenance on the pump, system walkdown, etc.)
would be initiated to restore the pump and/or system to an operable status.
If a pump is declared inoperable and later determined that the pump met applicable criteria, a further investigation into the cause of the apparent reduced performance would be performed. This would include aligning one of the other safeguards pumps to the affected header supply piping.
Downstream flow and pump head during performance of these safeguards pumps will be trended as part of the IST program.
4.0 NRC STAFF EVALUATION The Code of Record requires a system pressure test for the buried portion of the cooling water piping that will determine either a rate of pressure loss or a change in flow at the ends of the buried piping. The buried cooling water piping at PINGP, Units 1 and 2, uses butterfly valves at the ends which were not designed for pressure isolation and, therefore, are unsuitable to determine meaningful rate of pressure loss. One end of buried piping is not instrumented for flow measurement and does not permit measurement of change in flow. Therefore, the ASME Code-required test cannot be performed. The ASME Code, however, allows for non-isolable buried components to confirm that flow during operation is not impaired. The NRC staff agrees with the licensees approach that unimpaired flow in the buried piping can be qualitatively assessed during quarterly IST surveillance of cooling water pumps. Using the flow instrument downstream from the pump discharge, a reference flow rate could be established which would correspond to a target pump head. A decrease in pump head may indicate increase in flow due to any through-wall leakage in the buried piping. From trending of head loss (pressure drop) during a pump test at the reference flow, an assessment can be made on the integrity of buried piping. An issue related to this mode of testing is that pump head loss may be caused by the deterioration of the pump performance rather than by leakage in the buried pipe. As the performance of the pump deteriorates, the developed head decreases at the reference flow. The licensee has stated that if during an IST surveillance, the minimum flow could not be achieved and the cause of the deviation was not attributed to the test instruments being used, the pump would be declared inoperable and corrective actions would be initiated to evaluate the cause of the reduced performance as required by the PINGP IST program. If the pump performance falls into the action range, the pump would be declared inoperable and further corrective actions (i.e.,
maintenance on the pump, system walkdown, etc.) would be initiated to restore the pump and/or system to an operable status. The licensee further stated that if a pump is declared inoperable and later determined to have met applicable criteria, a further investigation into the cause of the apparent reduced performance would be performed. This would include aligning one of the other safeguards pumps to the affected header supply piping. Downstream flow and pump head during performance of these safeguards pumps will be trended as part of the IST program.
The NRC staff has determined that the licensees proposed alternative to test the buried portion of the cooling water piping in conjunction with quarterly testing of cooling water pumps would detect significant through-wall leakage if present in the subject line and would provide reasonable assurance of operational readiness. Compliance with the ASME Code requirement would require installation of additional flow measuring device at the inlet end of buried piping which would result in hardship without a compensating increase in the level of quality and safety.
5.0 CONCLUSION
The NRC staff concludes that for the buried portion of cooling water piping, compliance to the ASME Code requirement to perform a test that determines the rate of pressure loss or the change in flow would result in hardship to the licensee without a compensating increase in the level of quality and safety and, further, that the licensees proposed alternative would provide reasonable assurance of operational readiness.
The licensees proposed alternative provides reasonable assurance of detecting any degradation in the buried portion of cooling water piping. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the proposed alternative in RR Nos. 1-RR-4-7 and 2-RR-4-7, is authorized for the fourth 10-year ISI interval of the PINGP Units 1 and 2.
All other requirements of the ASME Code,Section XI, for which relief has not been specifically requested, remain applicable, including a third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Pat Patnaik, DCI/CSGB Date: October 31, 2007
Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Tribal Council Vice President, Counsel & Secretary Prairie Island Indian Community Nuclear Management Company, LLC ATTN: Environmental Department 700 First Street 5636 Sturgeon Lake Road Hudson, WI 54016 Welch, MN 55089 Manager, Regulatory Affairs Nuclear Asset Manager Prairie Island Nuclear Generating Plant Xcel Energy, Inc.
Nuclear Management Company, LLC 414 Nicollet Mall, R.S. 8 1717 Wakonade Drive East Minneapolis, MN 55401 Welch, MN 55089 Michael B. Sellman Manager - Environmental Protection Division President and Chief Executive Officer Minnesota Attorney Generals Office Nuclear Management Company, LLC 445 Minnesota St., Suite 900 700 First Street St. Paul, MN 55101-2127 Hudson, MI 54016 U.S. Nuclear Regulatory Commission Douglas E. Cooper Resident Inspector's Office Senior Vice President and Chief 1719 Wakonade Drive East Nuclear Officer Welch, MN 55089-9642 Nuclear Management Company, LLC 700 First Street Administrator Hudson, WI 54016 Goodhue County Courthouse Box 408 Joel P. Sorensen Red Wing, MN 55066-0408 Director, Site Operations Prairie Island Nuclear Generating Plant Commissioner Nuclear Management Company, LLC Minnesota Department of Commerce 1717 Wakonade Drive East 85 7th Place East, Suite 500 Welch, MN 55089 St. Paul, MN 55101-2198