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MONTHYEARML0726304632007-10-31031 October 2007 Request for Additional Information Related to the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief Nos. RR-19 & RR-20 for Point Beach Plant, Units 1& 2 Project stage: RAI ML0801600092008-02-19019 February 2008 the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief Nos. RR-18, RR-19, and RR-20 (TAC Nos. MD6346 & MD6347) Project stage: Other NRC 2008-0017, CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels, Fourth Ten-Year Inservice Inspection Program Interval2008-03-14014 March 2008 CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels, Fourth Ten-Year Inservice Inspection Program Interval Project stage: Request ML0816908872008-08-25025 August 2008 the Fourth 10-Year Interval Inservice Inspection Program Plan Requests for Relief Nos. RR-18, RR-19, and RR-20 (Tac Nos. MD6346 and MD6347) Project stage: Other 2008-02-19
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-2022-161, U1R40 Steam Generator Tube Inspection Report2022-10-13013 October 2022 U1R40 Steam Generator Tube Inspection Report NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan L-2022-124, Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections2022-07-20020 July 2022 Refueling Outage U1R40 Owner'S Activity Report (OAR-1) for Inservice Inspections NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2019-0040, Owner'S Activity Report: 48th Year Iwl for Class CC Examinations2019-12-18018 December 2019 Owner'S Activity Report: 48th Year Iwl for Class CC Examinations NRC 2019-0020, Refueling Outage U1 R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2019-07-11011 July 2019 Refueling Outage U1 R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2018-0005, Refueling Outage U1R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2018-01-26026 January 2018 Refueling Outage U1R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2017-0046, Spring 2017 (U2R35) Steam Generator Tube Inspection Report2017-09-21021 September 2017 Spring 2017 (U2R35) Steam Generator Tube Inspection Report NRC 2017-0030, Refueling Outage U2R35 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2017-07-12012 July 2017 Refueling Outage U2R35 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2016-0044, Spring 2016 U1R36 180-Day Steam Generator Tube Inspection Report2016-09-20020 September 2016 Spring 2016 U1R36 180-Day Steam Generator Tube Inspection Report NRC 2016-0026, Refueling Outage U1 R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2016-06-30030 June 2016 Refueling Outage U1 R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2016-0004, Refueling Outage U2R34 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2016-01-26026 January 2016 Refueling Outage U2R34 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2015-0025, Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B2015-05-14014 May 2015 Requests Relief from Performing Inservice Testing (ISI) of Relief Valve 1CC-00763B NRC 2015-0010, Filing of Owner'S Inservice Inspection Summary Report for Tendon Surveillance and Concrete Containment Examinations2015-02-27027 February 2015 Filing of Owner'S Inservice Inspection Summary Report for Tendon Surveillance and Concrete Containment Examinations NRC 2015-0009, Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueliong Outage U1R352015-01-29029 January 2015 Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueliong Outage U1R35 NRC 2015-0008, Filing of Owner'S Inservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U1R352015-01-29029 January 2015 Filing of Owner'S Inservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U1R35 NRC 2014-0048, Submittal of Filing of Owner'S Lnservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R332014-07-15015 July 2014 Submittal of Filing of Owner'S Lnservice Inspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R33 NRC 2014-0049, Submittal of Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueling Outage U2R332014-07-15015 July 2014 Submittal of Filing of Owner'S Inservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Refueling Outage U2R33 NRC 2014-0022, 10 CFR 50.55a Requests Relief Requests RR-8 and RR-9 Fifth Ten-Year Lnservice Inspection Program Interval2014-05-13013 May 2014 10 CFR 50.55a Requests Relief Requests RR-8 and RR-9 Fifth Ten-Year Lnservice Inspection Program Interval NRC 2013-0108, Response to 10 CFR 50.54(f) Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns2013-11-27027 November 2013 Response to 10 CFR 50.54(f) Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns NRC 2013-0067, Spring 2013 Unit 1(U1R34) Steam Generator Tube Inspection Report2013-09-24024 September 2013 Spring 2013 Unit 1(U1R34) Steam Generator Tube Inspection Report NRC-2013-0008, Submittal of Fall 2012 Steam Generator Tube Inspection Report2013-05-16016 May 2013 Submittal of Fall 2012 Steam Generator Tube Inspection Report NRC 2013-0018, CFR 50.55a Request. Relief Request RR-4L1 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspections Program Interval2013-03-19019 March 2013 CFR 50.55a Request. Relief Request RR-4L1 Inservice Inspection Impracticality Examination Limitations Due to Configuration Fourth Ten-Year Inservice Inspections Program Interval NRC 2013-0016, Filing of Owner'S Inservice Inspection Summary Report, IWE Class Mc and Iwl Class CC for Refueling Outage U2R322013-02-19019 February 2013 Filing of Owner'S Inservice Inspection Summary Report, IWE Class Mc and Iwl Class CC for Refueling Outage U2R32 NRC 2013-0015, Filing of Owner'S Lnservice Lnspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R322013-02-19019 February 2013 Filing of Owner'S Lnservice Lnspection Summary Report Class 1, 2 and 3 for Refueling Outage U2R32 NRC 2013-0009, Fall 2011 Refueling Outage (U1R33) Steam Generator Tube Inspection Report2013-01-31031 January 2013 Fall 2011 Refueling Outage (U1R33) Steam Generator Tube Inspection Report NRC 2012-0075, Fifth Interval Inservice Inspection Program Plan and Schedule2012-09-10010 September 2012 Fifth Interval Inservice Inspection Program Plan and Schedule NRC 2012-0015, Fall 2011 Unit 1 (U1R33) Steam Generator Tube Inspection Report2012-05-29029 May 2012 Fall 2011 Unit 1 (U1R33) Steam Generator Tube Inspection Report NRC 2012-0019, Filing of Owner'S Class 1, 2, and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R332012-03-0707 March 2012 Filing of Owner'S Class 1, 2, and 3 Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R33 NRC 2012-0014, Filing of Owner'S Containment Inservice Inspection Summary Report for Refueling Outage U1R332012-03-0202 March 2012 Filing of Owner'S Containment Inservice Inspection Summary Report for Refueling Outage U1R33 NRC 2012-0011, CFR 50.55a Request, Relief Requests RR-2 and RR-3, Fifth Ten-Year Inservice Inspection Program Interval2012-02-15015 February 2012 CFR 50.55a Request, Relief Requests RR-2 and RR-3, Fifth Ten-Year Inservice Inspection Program Interval NRC 2011-0083, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outrage U2R312011-09-12012 September 2011 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outrage U2R31 NRC 2011-0084, Filing of Owner'S Lnservice Inspection Summary Report for Refueling Outage U2R312011-09-12012 September 2011 Filing of Owner'S Lnservice Inspection Summary Report for Refueling Outage U2R31 NRC 2010-0096, Filing of Owner'S Inservice Inspection Summary Report Refueling Outage U1R322010-06-25025 June 2010 Filing of Owner'S Inservice Inspection Summary Report Refueling Outage U1R32 NRC 2010-0094, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R322010-06-24024 June 2010 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R32 ML1004707792010-02-11011 February 2010 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refuleing Outage U2R30 NRC 2009-0014, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R312009-02-10010 February 2009 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U1R31 NRC 2008-0043, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R292008-08-0404 August 2008 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R29 NRC 2008-0017, CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels, Fourth Ten-Year Inservice Inspection Program Interval2008-03-14014 March 2008 CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels, Fourth Ten-Year Inservice Inspection Program Interval ML0724806122007-09-20020 September 2007 Forth 10-Year Interval Inservice Inspection Request for Relief No. 15, Alternate Methods for Pressure Testing of Buried Components NRC 2007-0059, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R302007-08-0606 August 2007 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R30 NRC 2007-0048, Correction to Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R272007-06-15015 June 2007 Correction to Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R27 NRC 2007-0020, 10 CFR 50.55a Requests, Relief Requests RR-18, RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval2007-04-0606 April 2007 10 CFR 50.55a Requests, Relief Requests RR-18, RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval NRC 2007-0009, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R282007-02-19019 February 2007 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R28 NRC-2006-0078, 10 CFR 50.55a Request, Resubmittal of Relief Request 15, Fourth Ten-Year Interval Inservice Inspection (ISI) Program2006-11-20020 November 2006 10 CFR 50.55a Request, Resubmittal of Relief Request 15, Fourth Ten-Year Interval Inservice Inspection (ISI) Program NRC 2006-0019, Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R292006-02-22022 February 2006 Filing of Owner'S Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R29 NRC 2006-0001, Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing2006-01-20020 January 2006 Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing NRC 2005-0132, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R272005-10-11011 October 2005 Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R27 2022-09-30
[Table view] Category:Letter type:NRC
MONTHYEARNRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
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FPL Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 FPL Energy Point Beach Nuclear Pilan~t March 14,2008 NRC 2008-0017 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 10 CFR 50.55a Request, Relief Request RR-21, Examination of the Reactor Pressure Vessels Fourth Ten-Year lnservice Inspection Prosram Interval In accordance with 10 CFR 50.55a, "Codes and Standards," Paragraph (a)(3)(i), FPL Energy Point Beach, LLC (FPL Energy Point Beach) requests that the Nuclear Regulatory Commission (NRC) grant relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code),Section XI, 1998 Edition with 2000 Addenda for examinations of the Point Beach Nuclear Plant Units 1 and 2 reactor pressure vessels (RPVs). Relief is requested on the basis that alternative methods will provide an acceptable level of quality and safety.
Specifically, relief is requested to use the qualification requirements for weld examinations conducted from the inside piping surface contained in ASME Code Case N-695, along with the vendor's root mean squared error achieved under the Performance Demonstration Initiative (PDI) at the Electric Power Research Institute (EPRI) Nondestructive Examination (NDE) Center. The Enclosure contains the details of the request for relief.
FPL Energy Point Beach requests approval of this request prior to October 1, 2008. The Unit 1 RPV examinations will be conducted during the fall 2008 refueling outage. The Unit 2 RPV examinations will be conducted during the fall 2009 refueling outage. The requested duration of these relief requests is for the remainder of the Fourth Ten-Year lnservice lnspection Program, which is scheduled to end on June 30, 2012, for both PBNP units.
An FPL Group company
Document Control Desk Page 2 Summary of Commitments This submittal contains no new commitments or revisions to existing commitments.
Very truly yours, FPL Energy Point Beach, LLC
( James H. McCarthy Site Vice President Enclosure cc: Regional Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Mr. Mike Verhagan, Department of Commerce, State of Wisconsin
ENCLOSURE RELIEF REQUEST RR-21 FPL ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT UNITS 1 and 2 REQUEST FOR RELIEF IN ACCORDANCE WITH 10 CFR 50.55a(a)(3)(i)
ALTERNATIVE REQUIREMENTS TO ASME SECTION XI APPENDIX VII, (SUPPLEMENTS 2 AND 10)
EXAMINATIONS OF CLASS 1 PRESSURE RETAINING WELDS CONDUCTED FROM THE INSIDE SURFACE ASME Code Component(s) Affected Code Class: 1 Examination Categories: Category R-A Item Numbers: R1.20 (Nozzle-to-Pipe, Elbow-to-Nozzle)
Component Numbers: See Table 1 Drawing Numbers: See Table 1
Applicable Code Edition and Addenda
The current inservice inspection program is based on the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 1998 Edition with 2000 Addenda. Testing of personnel, procedures and equipment for the ultrasonic examination of applicable Class 1 and 2 components is governed by Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," of the ASME Code,Section XI.
Applicable Code Requirements The examination of Class 1 and 2 piping welds are required to be performed using procedures, personnel and equipment qualified to the criteria of the ASME Code,Section XI, Appendix VIII, Supplement 10, "Qualification Requirements for Dissimilar Metal Pipe Welds," for the examination of ltem R1.20 nozzle-to-piping welds.
Paragraph 3.2, "Sizing Acceptance Criteria," Subparagraph (b) of Supplement 10, states that the "examination procedures, equipment, and personnel are qualified for depth-sizing when the RMS [root mean square] error of the flaw depth measurements, as compared to the true flaw depths, is less than or equal to 0.125-inch (3.2mm)."
Code Case N-695, "Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, Division 1," provides alternative requirements to Appendix VIII, Supplement 10 and is unconditionally approved for use through Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 15.
Paragraph 3.3(c) of Code Case N-695 states, "Examination procedures, equipment, and personnel are qualified for depth-sizing when the RMS error of the flaw depth measurements, as compared to the true flaw depths, do not exceed 0.125-in. (3 mm)."
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Reason for the Request FPL Energy Point Beach is performing volumetric examinations of all reactor pressure vessel (RPV) nozzle-to-piping dissimilar metal (DM) welds from the inside diameter (ID) surface during the upcoming ten-year IS1 inspections. FPL Energy Point Beach will implement the NRC-approved alternative requirements of Code Case N-695 for qualification.
FPL Energy Point Beach proposes using an alternative RMS error depth-sizing requirement as compared to the 0.125-inch RMS error value stated in Code Case N-695. An FPLE Point Beach representative was at the Electric Power Research Institute (EPRI) NDE Center on August 22 and 23, 2007, and confirmed with the Performance Demonstration Initiative (PDI) Administrator that no vendor has successfully demonstrated compliance with the Code-required 0.125-inch RMS value for qualification tests for examinations conducted from the ID surface (for either stand-alone Supplement 10 or combined Supplement 2 and 10 qualifications).
FPL Energy Point Beach has verified through the PDI Administrator that the examination vendor selected to perform the scheduled examinations at FPLE Point Beach has achieved a 0.212-inch RMS error for the Supplement 10 qualification; a 0.211-inch RMS error for the Supplement 2 qualification; and a 0.211-inch RMS error for the Combined Supplement 2 and10.
Proposed Alternative and Basis for Use Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested for an alternative requirement that will provide an acceptable level of quality and safety.
For examinations of DM welds (Supplement 1O), FPL Energy Point Beach proposes to apply the difference between the examination vendor's achieved RMS error and the Code Case N-695 required 0.125-inch RMS error to actual flaw depths when depth-sizing of indications is required.
Applying the difference between the required RMS error and the achieved RMS error to the actual flaw being sized will ensure a conservative bounding flaw depth for dissimilar metal welds examined at Point Beach Nuclear Plant (PBNP) Units 1 and 2.
Duration of Proposed Alternative This relief request will be implemented during the remainder of the Fourth Ten-Year lnservice lnspection Program, which is scheduled to end on June 30, 2012, for both PBNP units.
Precedents Similar relief requests have been granted to the following plants:
NRC to Southern Nuclear Operating Company Inc. letter, "Joseph M. Farley Nuclear Plant, Unit 1, and Vogtle Electric Generating Plant, Units 1 and 2 - Evaluation of Relief Request ISI-GEN-ALT-06-02," (TAC Nos. MD 2482, MD2483 and MD2484), dated September 29,2006, (ML062770359)
NRC to Exelon Generating Company, LLC letter, "Braidwood Station, Units 1 and 2 - Relief Request (12R-49) Regarding lnservice lnspection Program Alternative Method (TAC Nos.
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MD5996 and MD5997)," dated November 8,2007, (ML072760048)
Table 1 Applicable Components at Point Beach Nuclear Plant Units 1 and 2 Unit Weld Number Description Former ASME Current XI Item RI-IS1 Item Number Number 1 RC-34-MRCL-AI-01 Outlet Nozzle to Pipe at 28.5" B5.10 R1.20 1 RC-32-MRCL-AI11-03 Elbow to Inlet Nozzle at 328.5" B5.10 R1.20 1 RC-34-MRCL-BI-01 Outlet Nozzle to Pipe at 208.5" B5.10 R1.20 1 RC-32-MRCL-Blll-03 Elbow to Inlet Nozzle at 148.5" B5.10 R1.20 1 RC-04-SI-1001-33 SI Safe-End to Nozzle (Az. 288.5") B5.10 R1.20 1 RC-04-SI-1002-19 SI Safe-End to Nozzle (Az. 108.5") B5.10 R1.20 2 RC-34-MRCL-AI-01 Outlet Nozzle to Pipe at 28.5" 85.10 R1.20 2 RC-32-MRCL-AIII-03 Elbow to Inlet Nozzle at 328.5" B5.10 R1.20 2 RC-34-MRCL-BI-01 Outlet Nozzle to Pipe at 208.5" B5.10 R1.20 2 RC-32-MRCL-BII1-03 Elbow to Inlet Nozzle at 148.5" B5.10 R1.20 2 RC-04-SI-2001-26 Safe-End to SI Nozzle at 288.5" 85.10 R1.20 2 RC-04-SI-2002-29 Safe-End to SI Nozzle at 108.5" B5.10 R1.20 RC = Reactor Coolant SI = Safety Injection Page 3 of 3