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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) 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-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] 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
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NExTerao ENERGYv BEACH May 16, 2013 NRC 2013-0008 TS 5.6.8 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 2 Docket 50-301 Renewed License No. DPR-27 Fall 2012 Unit 2 (U2R32)Steam Generator Tube Inspection Report Pursuant to the requirements of Point Beach Nuclear Plant (PBNP) Technical Specification (TS)5.6.8, "Steam Generator Tube Inspection Report," NextEra Energy Point Beach, LLC is submitting the 180-day Steam Generator Tube Inspection Report. The enclosure to this letter provides the results of the fall 2012, Unit 2 (U2R32) steam generator tube in-service inspections.
This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.
If you have questions or require additional information, please contact Mr. Andrew Watry at 920/755-7393.
Very truly yours, NextEra Energy Point Beach, LLC Mike Millen Licensing Manager Enclosure cc: Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW ho,¢NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 ENCLOSURE I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 2 FALL 2012 UNIT 2 (U2R32)STEAM GENERATOR TUBE INSPECTION REPORT 6 pages follow
1.0 Introduction
Point Beach Nuclear Plant (PBNP) Unit 2 is a two loop Westinghouse-designed Pressurized Water Reactor (PWR) with Model D47F replacement steam generators (SGs). The original 44 Series SGs, which had mill annealed Ni-Cr-Fe Alloy 600 tubing, were replaced because of various types of tube degradation.
The replacement SGs were installed in U2R22. They have been in service since August 1997 and have operated for 12.97 effective full power years (EFPY) by refueling outage U2R32.The U2R32 inspection scope and plan were based on the Degradation Assessment prepared prior to U2R32 refueling outage. No crack-like indications were reported during the U2R32 SG eddy current inspection.
The only damage mechanisms observed during the inspection were tube wear at anti-vibration bars (AVB) and at broached tube support plate (TSP) locations.
No new degradation due to maintenance related activities was detected.
No new wear due to suspected foreign objects was identified.
The secondary side inspection showed no significant degradation.
All of the AVB wear depths identified were below the condition monitoring limit defined in the U2R32 degradation assessment.
Therefore, condition monitoring was satisfied for AVB wear in SG 2A. No AVB wear was detected in SG 2B.The depths of the wear indications at TSP were below the condition monitoring limit defined in the degradation assessment.
Therefore, condition monitoring was satisfied for tube wear at TSPs in SG 2A. No TSP wear was detected in SG 2B.No primary-to-secondary leakage was reported during normal operation in the last three operating cycles. This satisfied the performance criterion for leakage integrity during normal operation.
In summary, all SG performance criteria were satisfied.
2.0 Scope
of Inspections Performed 2.1 Inspection for Steam Generator A and Steam Generator B consisted of: a. Bobbin Inspection
-All Accessible Tubes: 100% bobbin full length examination of tubes, except for Rows 1 and 2 which were inspected from tube end to the top TSP from both the hot leg (HL) and cold leg (CL).b. Motorized Rotating Pancake Coil (MRPC) Inspection
+PointTM):
- 33% +PointTM examination of Row 1 and Row 2 U-bends.* +PointTM examination of all peripheral tubes (2 tubes deep within the "no tube lane" and 3 tubes deep at the circumference) on the HL and CL top of tubesheet (TTS) (+/-3 inches) for loose part wear.Page 1 of 6 20% (excluding peripheral tubes) +PointTM examination at the HL TTS from TSH +/-3 inches. This sample population was taken from tubes that were not +PointTM inspected at the HL TTS during U2R24, U2R26, or U2R29.100% +PointTM examination of all dings > 5 volts in the HL and U-bend, including all new dings > 5 volts identified during U2R32.+PointTM examination of PLP signals from U2R29.c. Diagnostic and special interest (SI) inspections based on historical data and the results of the initial bobbin and MRPC inspections were performed to characterize and/or size any identified indications.
- d. Installed tube plugs were visually inspected.
- e. Visual inspection of the channel head bowl in both HL and CL as recommended in Nuclear Safety Advisory Letter 12-1 (NSAL-12-1).
2.2 Secondary
Side The following secondary side work was performed in both SGs:* Sludge Lancing* FOSAR above the tubesheet* Upper Steam Drum Inspection on the following components:
feedring, J-tubes, backing ring, thermal sleeves, and primary separators.
3.0 Degradation
Mechanisms Found The following degradation mechanisms were observed in the PBNP Unit 1 SGs during U2R32: 3.1. Tube Wear at Anti-Vibration Bar There were eight indications of wear at the AVBs in six tubes in SG 2A. There were no tubes in SG 2B with indications of wear at the AVBs.3.2. Tube Wear at Tube Support Plates (TSP)The distorted support indications (DSI) reported by bobbin inspections were subjected to +PointTM inspection.
There were two bobbin DSI calls which were confirmed by +PointTM inspection to be flaws due to tube wear. They were both in SG 2A, in Tubes R12C53 and R1 5C64.ii. The DSI indication in Tube R12C53 was at the broached TSP designated as 06H, with two separate flaws at land contact points. The results of the sizing showed 3% through-wall (TW) and 2% TW wear depths in R12C53.iii. The DSI in R1 5C64 was at the 05H broached support plate. The results of the sizing showed 1% TW in R1 5C64.Page 2 of 6 3.3. PLP (Possible Loose Part)PLP signals were reported by the bobbin and top of the tubesheet
+PointTM inspections.
A +PointTM inspection was performed at all the PLP locations identified by bobbin. In addition to the identification of any PLPs, the +PointTM inspection also helped identify if any tube degradation had occurred due to the PLP. The PLP locations identified by +PointTM during U2R32 are shown below in Table 4-3. PLP signals are not a degradation mechanism.
4.0 Service
Induced Flaws 4.1 Mechanical Wear Indications at Anti-vibration Bar (AVB)4.1.1. Tube Wear at Anti-Vibration Bar There were eight indications of wear at the AVBs in six tubes in SG 2A.There were no tubes in SG 2B with indications of wear at the AVBs.During the U2R29 outage, AVB wear was reported at seven locations in SG 2A. During the current inspection, AVB wear was reported at all seven of the prior locations and at one new location in the same SG. The data is shown below in Table 4-1.Table 4-1 Wear at AVB -SG 2A 2012 2008 2003 2000 1998 U2R32 U2R29 U2R26 U2R24 U2R23 Row Col Loc % TW % TW % TW % TW % TW No 84 45 AV5 12 11 Insp. 8 NDD No 84 45 AV6 8 5 Insp. NDD NDD No 78 59 AV4 9 8 Insp. 6 NDD No 78 59 AV5 8 7 Insp. 6 NDD 79 62 AV3 12 8 10 NDD NDD 84 63 AV5 7 7 5 NDD NDD 79 66 AV5 9 6 6 NDD NDD No 82 69 AV1 8 7 Insp. NDD NDD NDD -No degradation detectable 4.2 Wear at Support Plates 4.2.1. During the U2R29 outage, TSP wear was reported at one TSP location in SG 2A with two wear scars at two of the three contact lands in the trefoil broach hole. During the current inspection, TSP wear was reported at the prior locations and at one new location in the same SG as shown in Table 4-2. No TSP wear has been reported in SG 2B.Page 3 of 6 Table 4-2 Wear at TSP SG 2A 2012 2008 2003 2000 1998 ROW COL LOC U2R32 U2R29 U2R26 U2R24 U2R23%TW %TW %TW %TW %TW 12 53 06H 3 7 No Insp. No size NDD 12 53 06H 2 4 No Insp. No size NDD 15 64 05H 1 NDD No Insp. No size NDD 4.3 Possible Loose Parts (PLP)4.3.1. During the foreign object search and retrieval (FOSAR) operation, an attempt was made to find and verify PLP reported from the eddy current inspection.
Two sludge rocks were observed at two PLP locations during FOSAR. The +PointTM inspection of the tubes with PLP and surrounding tubes showed no degradation in the tubes around the reported PLP locations.
Table 4-3 Possible Loose Parts Location -U2R32 SG Row Column Location Elevation A 32 7 TSC +1.52" B 3 40 TSH +0.10" 5.0 NDE Techniques for Damaqe Mechanisms The following is the list of EPRI technique sheets used for detection for the degradation modes that may be present during the steam generator inspection in U2R32.AVB Wear 96004.1 Revision 13, (bobbin)(diff mode)TSP/FDB Wear 96004.1 Revision 13, (bobbin;96910.1 Revision 10 (+Point')Mechanical Wear 27091.2 Revision 0 (bobbin), 27901.3 through 27907.3 Revision 1 (+PointTM)
Loose Part Wear 27091.2 Revision 0 (bobbin);27901.3 through 27907.3 Revision 1 (+PointmM), 21998.1 Revision 4 (+PointTM)
Axial ODSCC at TTS and Expansion 128424 Revision 3, Transitions 128425 Revision 3, 128431 Revision 3, 128432 Revision 3 (+PointTM Circumferential ODSCC at Expansion 21410.1 Revision 6 (+Point T")transitions Page 4 of 6 Axial ODSCC at Ding/Dent, Freespan, and 128411 Revision 3, Supports 128413 Igevision 3 (bobbin), 128424 Revision 3, 128425 Revision 3, 128431 Revision 3, 128432 Revision 3 (+PointTm Circumferential ODSCC at Ding/Dent, 21410.1 Revision 6 (+Point"')
Freespan and Supports 6.0 Plugging Two tubes were plugged during U2R23 due to minor loose parts wear. Two tubes were plugged administratively during U2R24 due to excessive noise in the eddy current test data. No other tubes have been plugged in the PBNP Unit 2 SGs.Table 6-1 Total Tubes Plugged and Plugging Percentage SG 2A SG 2B Total Tubes Plugged 0 4 Plugging Percentage 0.000% 0.114%7.0 Condition Monitoring Assessment Results All of the AVB wear depths identified were below the condition monitoring limit. No AVB wear was detected in SG 2B. Therefore, condition monitoring was satisfied for AVB wear in SG 2A and 2B.The depths of the wear indications at TSP were below the condition monitoring limit. No TSP wear was detected in SG 2B. Therefore, condition monitoring was satisfied for tube wear at TSPs in SG 2A and 2B.No tube wear due to loose parts was reported during U2R32. Hence, condition monitoring was satisfied for this degradation mechanism in both SGs.No primary-to-secondary leakage was reported during normal operation in the last three operating cycles. This satisfied the performance criterion for leakage integrity during normal operation.
In summary, all SG performance criteria were satisfied for the current outage.Page 5 of 6
8.0 Secondarv
Side InsDections/Cleanincl Secondary side sludge lancing and FOSAR above the tubesheet were performed in each SG during U2R32. In addition, a steam drum inspection was performed by manual entry into the SG through the secondary side manway. The upper steam drum along with the feedring, J-tubes, backing ring, thermal sleeves, and primary separators were visually inspected in both SGs and no anomalies were noted.No anomalous conditions adverse to structural integrity were reported from the above inspections.
The FOSAR operation was performed in the annulus and tube lane in both SGs. One foreign object (judged to be a piece of flexitallic gasket) was retrieved from the annulus region of SG 2A. The PLP indications, by eddy current testing, reported slightly above the top of the tubesheet location were subjected to FOSAR as access allowed. Sludge rocks were identified at the two PLP locations.
The sludge rocks are benign to tubing and were not removed.Page 6 of 6