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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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NEXTera ENERGY .
POINT BEACH November 27, 2013 NRC 2013-0108 10 CFR 50 .54(f)
U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Units 1 and 2 Docket 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
References:
(1) NRC letter to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, dated March 12, 2012, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (ML12053A340)
(2) NextEra Energy Point Beach, LLC letter to NRC, dated November 26, 2012, NextEra Energy Point Beach LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic (ML12332A070)
(3) NextEra Energy Point Beach, LLC letter to NRC, dated October 3, 2013, Update to NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic (ML13277A109)
(4) NRC letter to NextEra Energy Point Beach, LLC, dated November 1, 2013, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns (ML13304B418)
On November 26, 2012, NextEra Energy Point Beach, LLC (NextEra) responded to the NRC staff's request for information pursuant to 10 CFR 50.54(f) (Reference 1). Via Reference (2),
NextEra submitted the required reports for Units 1 and 2 regarding seismic walkdowns.
Subsequent to submitting the report, NextEra determined that there were errors in the reports.
The errors were administrative in nature and had no impact on the contents of the report.
Additionally, NextEra determined that some information in the reports could have been better presented. NextEra addressed the issues by submitting updated information to the NRC via Reference (3).
Subsequently, the NRC determined that additional information was required to allow the NRC staff to complete their assessments (Reference 4) .
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
Document Control Desk Page 2 The Enclosure provides the responses to the request for additional information contained in Reference (4).
This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments.
If you have any questions please contact Mr. Michael Millen, Licensing Manager, at 920/755-7845.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on November 27, 2013.
Very truly yours, NextEra Energy Point Beach, LLC Larry Meyer Site Vice President Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Director, Office of Nuclear Reactor Regulation, USNRC Next Era Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 NEXTERA ENERGY POINT BEACH, LLC RESPONSE TO 10 CFR 50.54(F)
REQUEST FOR ADDITIONAL INFORMATION ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 2.3, SEISMIC WALKDOWNS
REQUEST FOR ADDITIONAL INFORMATION Seismic Walkdowns On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff issued a letter requesting additional information per Title 10 of the Code of Federal Regulations, Section
- 50. 54(f) (hereafter called the 50. 54(f) letter). The 50. 54(f) letter requested that licensees conduct seismic hazard walkdowns to verify the plant configuration with the current licensing basis (CLB). The licensees stated by letter that the seismic walkdowns would be performed in accordance with Electric Power Research Institute EPRI- 1025286, "Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic" (walkdown guidance). Following the NRC staff's initial review of the walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the walkdown report reviews and site audits, the staff identified additional information necessary to allow the staff to complete its assessments.
- 1. Conduct of the walkdowns, determination of potentially adverse seismic conditions (PASCs), dispositioning of issues, and reporting As a result of the audits and walkdown report reviews, the NRC staff noted that licensees' interpretations of the seismic walkdown guidance varied, which resulted in meaningful differences in the process used to disposition identified issues and in the documentation that was provided to the NRC staff. In particular, the application of engineering judgment in determining what constituted a potentially adverse seismic condition (PASC), the threshold for conducting licensing basis evaluations (LBEs), and determining what information was to be reported to the NRC staff varied.
The NRC staff intended that conditions initially marked No (N) or Unknown (U) in the field by the seismic walkdown engineers (SWEs) for which an analysis or calculation was performed would be considered as PASCs and that an analysis or calculation constituted an LBE. The walkdown guidance allows for analysis as part of engineering judgment; however, the intent was to allow for only simple analyses that could be readily performed in support of engineering judgment.
Further, the walkdown activities were intended to allow for transparency in the licensee's process to demonstrate that PASCs were appropriately identified, that they were addressed in an appropriate manner, and the basis documented such that the current condition of the plant was clearly consistent with the CLB with regard to seismic capability.
During the audits, the NRC staff identified examples of field obseNations that were deemed not to be PASCs. However, the basis for the determination was not clearly recorded. In some cases, the field checklists were amplified by noting that the basis was engineering judgment.
During site audit discussions, the staff was able to trace the basis for the engineering judgments and found that in many cases they were appropriate. It is expected that these situations would not be included in the walkdown report.
There were other situations that a PASC and LBE were not reported; however, the NRC staff found during the audit that a calculation, analysis (more than just simple), or evaluation was conducted but informally. An example is a confirmatory calculation performed to demonstrate that six anchor bolts out of eight was not a seismically adverse condition. Another example would be an analysis to demonstrate that an existing, slightly short weld was as seismically sound as the prescribed weld length in the plant design documentation. The staff expected these types of conditions and evaluations to be captured in the licensee's normal plant Page 1 of 6
processes (e.g., condition report or corrective action program (CAP)), and also reported in the walkdown report, since*they were potentially adverse seismic conditions that required rriore than applying judgment or simple analysis to address.
The NRC staff also found that the process that was used to deal with a field observation that was deemed to be a PASC was also not completely described or captured in the report. In many cases, the licensee reported that an LBE was not performed. However, during the audits, it was clear that an LBE (or an equivalent determination method) was performed and used in determining whether a PASC should be entered into the CAP. The staff expects that these conditions would be reported in the walkdown report.
On the whole, through the audits, the NRC staff found that it was able to conclude that the intent of the guidance was met when the licensee's overall process was completely explained, the information was updated to reflect the actual process, and results were updated. The self-assessments conducted by the licensees of the audited plants also identified the lapse in the description of the process used by the licensee to identify a PASC and disposition it.
Therefore, in order to clarify the process that was followed, please provide a description of the overall process used by the licensee (and its contractors) to evaluate observations identified in the field by the SWEs. The process should include how a field observation was determined to be a PASC or not and how the bases for determinations were recorded. Once a determination was made that an observation was a PASC, describe the process for creating a condition report (or other tracking mechanism), performing the LBE (or other determination method), and the resultant action, such as entering it into the CAP, or documenting the result and basis.
Also, in order to confirm that the reported information supports concluding that the plant meets the CLB, please follow one of the following three acceptable alternatives:
(a) Provide a supplement to the table or text from the original walkdown report, if needed, to include similar conditions as the above examples and situations and for conditions for which a calculation, analysis (if more than a simple analysis), or evaluation was used for a determination. The supplement should include a short description of each condition, how it was dispositioned and the basis for the disposition, as follows: 1) for each condition that was entered into the CAP, provide the CAP reference number, initiation date, and (if known) the planned completion date, or 2) for all other conditions, provide the result of the LBE (or other determination method), the basis for the result, and how (or where) the result was captured in the plant's documentation or existing plant process.
(b) Following the plant's standard procedures, confirm that a new CAP entry has been made to verify if appropriate actions were taken when reporting and dispositioning identified PASCs (including conditions for which a calculation, analysis (if more than a simple analysis), or evaluation was used for a determination). The eventual CAP closeout, including the process followed and actions taken, should be in sufficient detail to enable NRC resident inspectors to follow up.
(c) If no new conditions are identified for addition to the supplement or the CAP entry mentioned above is deemed not necessary, provide a statement of confirmation that all potentially seismic adverse conditions (including conditions for which a calculation, analysis (if more than a simple analysis), or evaluation was used for a determination) identified during the walkdowns and walk-bys were addressed and included in the report to the NRC.
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NextEra Response NextEra Energy has extracted the NRC's information requests and paraphrased them below with the NextEra Energy response .
- 1. Conduct of walkdowns, determination of potentially adverse seismic conditions (PASCs), dispositioning of issues and reporting Provide a description of the overall process used by the licensee (and its contractors) to evaluate observations identified in the field by the SWEs. The process should include how a field observation was determined to be a PASC or not and how the bases for determinations were recorded.
During performance of the Fukushima Seismic Walkdowns (FSWD), the Seismic Walkdowns Engineers (SWE) had heightened awareness for PASC. In accordance with the EPRI Guidance Document, walkdown teams were made up of a minimum of two SWEs. Discussions were summarized on the checklists, briefly explaining why the condition does not present a PASC.
PBNP is a Unresolved Safety Issue (USI) A-46 plant. The PBNP Final Safety Analysis Report allows the use of the Seismic Qualification Utility Group (SQUG) Generic Implementation Procedure (GIP) to show that existing, modified and new structures, systems and components (SSCs) are capable of surviving a plant Safe Shutdown Earthquake (SSE) and remain functional during and after the seismic event.
Appendix D of the GIP allows the use of engineering judgment to decide if adjacent, non-seismic SSCs will interact with seismic SSCs. The GIP states that it is not necessary to assume that non-seismic SSCs fail on the basis that evaluation of the non-seismic SSCs does not exist.
All engineers participating in the Fukushima Seismic Walkdowns, including contractors, have attended the five day SQUG training class. Additionally, some of those engineers are also qualified to perform SQUG activities at PBNP- meaning they have a SQUG certificate, at least five years of seismic nuclear experience and have been qualified to the PBNP site specific requirements.
Field observations were first discussed between at least two SWEs to determine if there was agreement that there was a degraded condition. Once agreement was reached that a degraded condition existed, the condition was noted on the checklist. Additional discussions which may have included Subject Matter Experts (SME), simple calculations, review of drawings, or other types of design basis investigation, were then performed to determine if a degraded condition was a PASC.
Degraded conditions that were not PASC were identified on the checklists and submitted to the CAP. The CAP number is cross-referenced on the checklists.
Once a determination was made that an observation was a PASC, describe the process for creating a condition report, perlorming the license basis evaluation (or other determination method), and the resultant action, such as entering it into the corrective action program or documenting the result and basis.
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After a degraded condition was identified to be a PASC, a determination was made whether or not physical work was required to correct the condition. If there was physical work required, a Work Request (WR) was submitted. Initiation of a WR automatically initiates a Condition Report (CR). The CR is automatically entered into the site's CAP for completion of the license basis evaluation, if required.
If no physical work was performed, the PASC was entered directly into the plant's CAP for completion of the license basis evaluation, if required .
All PASCs identified were determined to be in conformance with the license basis.
If no new conditions are identified for addition to the supplement or the CAP entry mentioned above is deemed*not necessary, provide a statement of confirmation that all potentially seismic adverse conditions (including conditions for which a calculation, analysis (if more than a simple analysis), or evaluation was used for a determination) identified during the wa/kdowns and walk-bys were addressed and included in the report to the NRC.
PBNP meets alternative 1(c), and provides the following statement of confirmation :
All potentially adverse seismic conditions (including conditions for which a calculation, analysis (if more than a simple analysis), or evaluation was used for a determination) identified during the walkdowns and walk-bys were addressed and included in the report to the NRC (References 2 and 3, Tables 5-2 and 5-3). As no new items were identified as part of this review, there are no additional CAP items to report.
- 2. Conduct of the Peer Review Process As a result of the walkdown report reviews, the NRC staff noted that some descriptions of the peer reviewers and the peer review process that was followed were varied and, in some cases, unclear. In some cases, the staff could not confirm details of the process, such as if the entire process was reviewed by the peer review team, who were the peer reviewers, what was the role of each peer reviewer, and how the reviews affected the work, if at all, described in the walkdown guidance.
Therefore, in order to clarify the peer review process that was actually used, please confirm whether the following information on the peer review process was provided in the original submittal, and if not, provide the following.
(a) Confirmation that the activities described in the walkdown guidance on page 6-1 were assessed as part of the peer review process.
(b) A complete summary of the peer review process and activities. Details should include confirmation that any individual involved in performing any given walkdown activity was not a peer reviewer for that same activity. If there were cases in which peer reviewers reviewed their own work, please justify how this is in accordance with the objectives of the peer review efforts.
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Also, if there are differences from the original submittal, please provide a description of the
- above information. If there are differences in the review areas or the manner in which the peer reviews were conducted, describe the actual process that was used.
NextEra Response
- 2. Clarify the peer review process that was actually used, please confirm whether the following information on the peer review process was provided in the original submittal, and if not, provide the following:
(a) Confirmation that the activities described in the walkdown guidance on page 6-1 were assessed as part of the peer review process The requested information can be found in the Table in Section 3.1, Peer Review Team of Appendix F of reference 3. As a clarification to this information, the following table lists the activities found on page 6-1 of the EPRI guidance document and the Peer Reviewer(s) for the activity:
Page 6-1 Activity Peer Reviewer Peer Reviewer Role Review the selection of the SSCs R. Severson Peer Reviewer #1 included on the SWEL T. K. Ram Peer Reviewer #2 Review a sample of the checklists D. N. Carter prepared for the Seismic Walkdowns N. Juryadini and Area Walk-Bys D. J. Nuttall C. A. McDonald S.D. Kahl R. L. LaPlante M. C. Nielsen J. Buboltz D.P. Brown Review the licensing basis evaluations M. C. Nielsen (LBE) D. J. Nuttall Review the decisions for entering the M. C. Nielsen potentially adverse conditions into the D. J. Nuttall CAP process Review the submittal report D.P. Brown Peer Review Report Preparer S. E. Guokas Peer Review Report Reviewer Summarize the results of the peer D.P. Brown Peer Review Report review process in the submittal report Preparer S. E. Guokas Peer Review Report Reviewer The Peer Review of a sample of Seismic Walkdown Checklists (SWC) and Area Walk-by Checklists (AWC) was performed, as a group, by all Seismic Walkdown Engineers (SWE). In order to avoid conflict, the SWE that performed the SWC and AWC were excluded from the peer review discussion.
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Based on the above table, PBNP has followed the EPRI guidance for performing peer reviews with regard to qualifications, tasks performed and roles. *
(b) Provide a complete summary of the peer review process and activities. Details should include confirmation that any individual involved in performing any given walkdown activity was not a peer reviewer for that same activity. If there were cases in which peer reviewers reviewed their own work, please justify how this is in accordance with the objectives of the peer review efforts.
A description of the Peer Review process and activities can be found in Appendix F of the PBNP submittal reports, reference 2 and reference 3.
The RAI requests confirmation that any individual involved in performing any given walkdown activity was not a peer reviewer for that same activity. If there were cases in which peer reviewers reviewed their own work, please justify how this is in accordance with the objectives of the peer review efforts.
As shown in the table above, Mr. D. P. Brown served as Team Leader of the Peer Review Team. During the Peer Review of the completed submittal report, Mr. Brown did Peer Review some of the walkdown activities that he performed. However, each activity in which Mr. Brown participated had a separate Peer Review of the individual activity.
There are no activities for which Mr. Brown was the sole Peer Reviewer of his own work.
If there are differences from the original submittal, please provide a description of the above information.
There are no differences from the original submittal in regard to the Peer Review process.
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