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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-035, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II2022-03-10010 March 2022 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II L-2022-027, Inservice Inspection Program Owner'S Activity Report (OAR-1)2022-02-17017 February 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2021-183, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 102021-09-30030 September 2021 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 L-2021-042, Inservice Inspection Program Owner'S Activity Report (OAR-1)2021-02-15015 February 2021 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2020-126, ln-Service Inspection Program Owner'S Activity Report (OAR-1)2020-07-24024 July 2020 ln-Service Inspection Program Owner'S Activity Report (OAR-1) L-2020-074, Response to Request for Additional Information for Relief Request No. 62020-04-15015 April 2020 Response to Request for Additional Information for Relief Request No. 6 L-2020-056, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 62020-03-30030 March 2020 Fifth Ten-Year Inservice Inspection Interval Relief Request No. 6 L-2019-175, Steam Generator Tube Inspection Report2019-09-25025 September 2019 Steam Generator Tube Inspection Report ML19189A3532019-07-0808 July 2019 Inservice Inspection Program: Owner'S Activity Report (OAR-1) L-2019-018, Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-1)2019-02-0707 February 2019 Submittal of Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2018-232, Metamic Inservice Surveillance Campaign Summary Report2018-12-13013 December 2018 Metamic Inservice Surveillance Campaign Summary Report L-2017-132, Inservice Inspection Program Owner'S Activity Reports2017-07-20020 July 2017 Inservice Inspection Program Owner'S Activity Reports L-2016-138, Inservice Inspection Program Owner'S Activity Report for Fifth Inservice Inspection Interval2016-07-12012 July 2016 Inservice Inspection Program Owner'S Activity Report for Fifth Inservice Inspection Interval L-2016-139, Fifth 10-Year Interval Inservice Testing Program Plan2016-07-0606 July 2016 Fifth 10-Year Interval Inservice Testing Program Plan L-2016-044, Inservice Inspection Program Owner'S Activity Report2016-02-26026 February 2016 Inservice Inspection Program Owner'S Activity Report L-2015-223, Fifth Ten-Year Interval Inservice Testing (IST) Program Relief Request No. PR-01-Resubmittal2015-09-25025 September 2015 Fifth Ten-Year Interval Inservice Testing (IST) Program Relief Request No. PR-01-Resubmittal L-2015-101, Submittal of Fifth Ten-Year Inservice Inspection (ISI) Interval Relief Request No. 32015-06-0808 June 2015 Submittal of Fifth Ten-Year Inservice Inspection (ISI) Interval Relief Request No. 3 L-2015-098, Fifth Ten-Year Interval Inservice Testing (IST) Program, Relief Request No. PR-012015-05-12012 May 2015 Fifth Ten-Year Interval Inservice Testing (IST) Program, Relief Request No. PR-01 L-2015-040, Submittal of Fifth 10 Year Interval Inservice Inspection (ISI) Program Plan2015-03-11011 March 2015 Submittal of Fifth 10 Year Interval Inservice Inspection (ISI) Program Plan ML15077A2142015-03-0202 March 2015 Inservice Inspection Plan - Fifth Inspection Interval, Relief Request No. 1, Revision 1 L-2015-020, Closeout of the Fourth Ten-Year Inservice Inspection (ISI) Interval Relief Requests Nos. 15, 16, 172015-02-13013 February 2015 Closeout of the Fourth Ten-Year Inservice Inspection (ISI) Interval Relief Requests Nos. 15, 16, 17 L-2015-012, Inservice Inspection Program Owner'S Activity Report (OAR-1)2015-01-16016 January 2015 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2014-105, Inservice Inspection Plan - Fifth Inspection Interval, Unit 3 Relief Request No. 1 - Response to Follow-up Request for Additional Information2014-04-14014 April 2014 Inservice Inspection Plan - Fifth Inspection Interval, Unit 3 Relief Request No. 1 - Response to Follow-up Request for Additional Information L-2014-096, Inservice Inspection Plan - Fifth Inspection Interval Unit 3 Relief Request No. 12014-04-0404 April 2014 Inservice Inspection Plan - Fifth Inspection Interval Unit 3 Relief Request No. 1 L-2014-040, Letter Regarding Inservice Testing Program-Extension of Interval for Turkey Point, Units 3 and 42014-02-13013 February 2014 Letter Regarding Inservice Testing Program-Extension of Interval for Turkey Point, Units 3 and 4 L-2013-113, Inservice Inspection Plan Submittal of Relief Request No. 122013-05-24024 May 2013 Inservice Inspection Plan Submittal of Relief Request No. 12 L-2012-435, Inservice Inspection Program Fourth Interval-Third Period-First Refueling Outage Owner'S Activity Report (OAR-1)2012-12-0303 December 2012 Inservice Inspection Program Fourth Interval-Third Period-First Refueling Outage Owner'S Activity Report (OAR-1) L-2012-214, License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program2012-05-16016 May 2012 License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program ML11361A3812012-01-27027 January 2012 Summary of the Staff'S Review of the Steam Generator Tube Inservice Inspection Refueling Outage 25 L-2011-254, Inservice Inspection Program Fourth Interval-Second Period-Third Refueling Outage Owner'S Activity Report (OAR-1)2011-08-0505 August 2011 Inservice Inspection Program Fourth Interval-Second Period-Third Refueling Outage Owner'S Activity Report (OAR-1) L-2011-119, Submittal of Steam Generator Tube Inspection Report2011-04-19019 April 2011 Submittal of Steam Generator Tube Inspection Report L-2011-042, Inservice Inspection Program Fourth Interval-Second Period-Third Refueling Outage Owner'S Activity Report (OAR-1)2011-02-0707 February 2011 Inservice Inspection Program Fourth Interval-Second Period-Third Refueling Outage Owner'S Activity Report (OAR-1) L-2010-250, Fourth Inservice Inspection Interval, Relief Request No. 9, Visual Examination of Containment Liner Repair2010-10-27027 October 2010 Fourth Inservice Inspection Interval, Relief Request No. 9, Visual Examination of Containment Liner Repair L-2010-042, Inservice Inspection Program Fourth Interval-Second Period-Second Refueling Outage Owner'S Activity Report (OAR-1)2010-02-26026 February 2010 Inservice Inspection Program Fourth Interval-Second Period-Second Refueling Outage Owner'S Activity Report (OAR-1) L-2009-167, Inservice Inspection Program Fourth Interval-Second Period-Second Refueling Outage Owner'S Activity Report (OAR-1)2009-08-0606 August 2009 Inservice Inspection Program Fourth Interval-Second Period-Second Refueling Outage Owner'S Activity Report (OAR-1) L-2008-003, Inservice Inspection Report2008-01-10010 January 2008 Inservice Inspection Report L-2007-036, Inservice Inspection Report2007-03-0808 March 2007 Inservice Inspection Report L-2006-158, Inservice Inspection Record2006-06-28028 June 2006 Inservice Inspection Record L-2006-062, Response to Request for Additional Information Regarding Steam Generator Tube Plugging Inservice Inspection Report2006-02-27027 February 2006 Response to Request for Additional Information Regarding Steam Generator Tube Plugging Inservice Inspection Report L-2005-190, 2005 Inservice Inspection Report2005-09-0808 September 2005 2005 Inservice Inspection Report L-2005-137, Steam Generator Tube Plugging Inservice Inspection 12-Month Special Report2005-06-17017 June 2005 Steam Generator Tube Plugging Inservice Inspection 12-Month Special Report L-2005-046, Refueling Outage Summary of Inservice Inspection Examinations.2005-02-15015 February 2005 Refueling Outage Summary of Inservice Inspection Examinations. L-2004-217, Steam Generator Tube Plugging Inservice Inspection 12-Month Special Report2004-10-12012 October 2004 Steam Generator Tube Plugging Inservice Inspection 12-Month Special Report L-2004-046, Inservice Inspection (ISI) Program Missing Pages from Fpl'S Letter L-2004-046, Dated March 11, 20042004-04-29029 April 2004 Inservice Inspection (ISI) Program Missing Pages from Fpl'S Letter L-2004-046, Dated March 11, 2004 L-2004-043, Submittal of Fourth 10-year Testing Interval IST Program, Revision 0, Beginning February 22, 2004 for Turkey Point Unit 3 and April 15, 2004 for Turkey Point Unit 42004-03-11011 March 2004 Submittal of Fourth 10-year Testing Interval IST Program, Revision 0, Beginning February 22, 2004 for Turkey Point Unit 3 and April 15, 2004 for Turkey Point Unit 4 2024-03-19
[Table view] Category:Letter type:L
MONTHYEARL-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 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 L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, 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 Applications2024-03-13013 March 2024 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 L-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2024-02-0909 February 2024 Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles 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) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, 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-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) 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 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 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations 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 L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection 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 2024-08-12
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September 25, 2019 L-2019-175 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-00001 Re: Turkey Point Unit 4 Docket No. 50-251 Steam Generator Tube Inspection Report The attached Turkey Point Unit 4 Cycle 31 Refueling Outage Steam Generator Tube Inspection Report is submitted in accordance with Turkey Point Technical Specification, 6.9.1.8 and within 180 days after the initial entry to MODE 4 following completion of the inspections performed in accordance with Technical Specification 6.8.4.j, Steam Generator (SG) Program.
Should there be any questions, please contact Mr. Robert Hess, Licensing Manager, at (305) 246-4112.
SGl\\~.)------~)
R~ ss Licensing Manager Turkey Point Nuclear Plant Attachments cc: Regional Administrator, Region II, USNRC.
Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Company 9760 SW 344 St Homestead, FL 33035
L-2019-175 Page 1 of 8 Enclosure Turkey Point Unit 4 TP4-31 Steam Generator Tube Inspection Report
==
Introduction:==
The enclosed Steam Generator Tube Inspection Report for Turkey Point Unit 4 is submitted for the inspection of the SGs during refueling outage 31 (hereafter referred to as the TP4-31 inspection or outage), as required by Technical Specification section 6.9.1.8. Per the Turkey Point Unit 4 Technical Specification section 6.8.4.j.d.2.c, the 4th ISI period is 72 EFPM. The inspection in TP4-31 was performed in accordance with Technical Specification 6.8.4.j.d.2.c, and was the 2nd (and last) inspection of the SGs in the 4th ISI period. The TP4-30 outage was a SG inspection skip. At unit shutdown for the TP4-31 inspection, the SGs had operated for approximately 28.53 EFPY (342.4 EFPM) since installation, including 46.6 EFPM in the 4th ISI period. Since the last SG inspection (TP4-29), the SGs operated for approximately 1.40 EFPY (16.77 EFPM) and 1.34 EFPY (16.12 EFPM) during fuel cycles 29 and 30, respectively, leading up to the TP4-31 inspection. Initial entry into Mode 4 following completion of the TP4-31 inspection was made on April 6, 2019.
Turkey Point Unit 4 is a Westinghouse 3-loop PWR with Model 44F steam generators. The SGs are U-tube heat exchangers with tube bundles fabricated using thermally treated Alloy 600 tubing. Each SG contains 3,214 tubes arranged in 45 rows and 92 columns, in a square-pitch configuration. Nominal tube OD is 0.875" with a 0.050" nominal wall thickness. Each SG tube bundle is supported by one drilled-hole flow distribution baffle (FDB) and 6 quatrefoil, broached-hole tube support plates (TSPs) all fabricated from stainless steel. Two (2) sets of anti-vibration bars (AVBs) in the U-bends also provide tube bundle support.
The inspection of the SGs during the TP4-31 outage met the requirements of the Turkey Point Unit 4 Technical Specifications, EPRI SGMP: PWR Steam Generator Examination Guidelines Revision 8, and EPRI SGMP: Steam Generator Integrity Assessment Guidelines Revision 4.
Appendix A provides references to recent SG Tube Inspection Reports and acronyms used in this report.
Appendix B provides a list of indications reported in TP4-31.
A. Scope of Inspections Performed on each SG The inspection scope for TP4-31 met the requirements of Turkey Point Unit 4 Technical Specification 6.8.4.j. For all sample inspections, tube selection priority was given to the ones not inspected in TP4-29 to meet the sequential period requirements in Technical Specifications. Unless otherwise noted, the defined TP4-31 base inspection scope in all 3 SGs was:
Primary-side:
100% full-length bobbin probe examination of all active tubes except U-bends of Rows 1 and 2.
50% sample of tubes in the U-bends of Rows 1 & 2 using the +Point' probe.
Peripheral tubes (2 outermost tubes of each row) exposed to the annulus, and Rows 1 and 2 in the tube-free lane were inspected in the HL and CL using the array probe. The test extent was from the first broached TSP (designated 01H or 01C) to the tube-end (TEH or TEC).
50% sample of tubes in the HL tubesheet section from 01H to TEH using the array probe, including 50% of the BLG/OXP within the H* depth (TTS-18.11) of the tubesheet.
50% sample of Dings/Dents > 5V in the HL (freespan, TSPs), and the U-bend using the +Point' probe.
+Point' probe inspection of a) all high stress (minus 2-sigma) tubes within the HL tubesheet section (TSH+3 to TEH), and b) 75% of high stress tubes at HL tube support structures and top CL TSP.
+Point' or array probe exam of all tubes adjacent to (1-tube bounding of) current and previously-reported PLP indications and foreign objects reported during FOSAR in TP4-29.
Other special interest exams based on the results of bobbin coil exams including +Point' probe inspection of all I-codes from bobbin or array probe.
L-2019-175 Page 2 of 8 Enclosure 0F Visual inspection of all mechanical and welded plugs.
Channel head visual inspection, and bowl scan per Westinghouse NSAL 12-1 Rev 1, Steam Generator Channel Head Degradation, October 2017.
Inspection Expansion: No scope expansion was required based on the TP4-31 base exam scope.
Secondary-side:
Upper bundle flush and top-of-tubesheet (TTS) Sludge Lancing in all SGs.
TTS FOSAR performed in the annulus and tube-free lane of each SG. This included TTS in-bundle inspections in each SG.
Upper tube-bundle visual inspection in SG-B at the top TSP (06H/06C).
Upper steam drum visual inspection in SG-B. UT thickness measurements were also obtained at sample locations on the feedring T-box and all J-tubes.
B. Degradation Mechanisms Found The following degradation mechanisms were identified during the TP4-31 inspection:
Wear at anti-vibration bar (AVB) contact points.
Wear at horizontal tube support structures (FDBs, TSPs).
Foreign object wear at one location in SG-B at the TTS in the HL (reported as VOL).
No degradation was identified as a result of a corrosion damage mechanism.
L-2019-175 Page 3 of 8 Enclosure C. NDE Techniques utilized for each Degradation Mechanism Table 1a is the list of the EPRI ETSSs used for degradation detection during the TP4-31 ECT inspection.
Table 1a - NDE Detection Techniques for Degradation Mechanisms Detection Degradation ETSS used for Detection Location / Applicability probe Mechanism I96041.1 Rev 6 AVB locations 96004.1 Rev 13 Broached TSP locations I96042.1 Rev 4 Wear Drilled supports (FDB)
Foreign object wear (with/without 27091.2 Rev 2 part present) 96005.2 Rev 9 Pitting In the freespan and sludge pile Bobbin I-28411 Rev 4 At FDBs locations I-28412 Rev 4 In the freespan I-28413 Rev 5 I-28413 Rev 5 At broached TSPs 24013.1 Rev 2 At Dents/Dings 5V 10013.1 Rev 1 Axial ODSCC I-28424 Rev 4 At Dents/Dings > 5V I-28425 Rev 4 10411.1 Rev 0 All U-bends 10411.2 Rev 0 I28424 Rev 4 sludge pile/expansion transition 20511.1 Rev 8 Axial PWSCC At expansion transition
+Point I11524 Rev 0 Circ PWSCC 96511.1 Rev 16 Axial/Circ PWSCC In low row U-bends 96511.2 Rev 16 27901.1 Rev 1; 27902.1 Rev 2; 27903.1 Rev 1; 27904.1 Rev 2; 27905.1 Rev 2; 27906.1 Rev 1; 27907.1 Rev 2 Foreign object wear (with/without Wear 17901.1/ .3; 17902.1/ .3; part present) 17903.1/ .3; 17904.1/ .3; 17905.1/ .3; 17906.1/ .3 Array [All Rev 0]
20400.1 Rev 5 Axial/Circ ODSCC At expansion transition 20500.1 Rev 4 Circ PWSCC At expansion transitions / BLGs /
20501.1 Rev 4 Axial PWSCC OXPs Table 1b is the list of the EPRI ETSSs used for degradation sizing based on the degradation mechanisms reported during the TP4-31 ECT inspection.
Table 1b - NDE Sizing Techniques for Degradation Mechanisms Sizing Degradation ETSS used for Sizing Location / Applicability probe Mechanism Bobbin I96041.1 Rev 6 AVB locations 10908.4 Rev 1 96910.1 Rev 11 TSP and FDB locations 27905.1 Rev 2 Wear Just above or below TSP edges
+Point 27902.1 Rev 2 Foreign object wear at TSPs Foreign object wear (volumetric) 27901.1 Rev 1 at or slightly above TTS
L-2019-175 Page 4 of 8 Enclosure D. Location, orientation (if linear), and measured sizes (if available) of service induced indications For each SG, Attachment B provides the listing of service-induced indications identified during the TP4-31 inspection, including locations and measured sizes. Note:
For AVB wear, the indication depth as measured by the bobbin probe is provided.
For all other locations, the indication depth as measured by the +Point' probe is provided.
E. Number of tubes plugged during the inspection outage for each degradation mechanism Five (5) tubes were plugged based on the TP4-31 inspection; the tubes plugged for each degradation mechanism are summarized below in Table 2:
Table 2 - TP4-31 Tubes Plugged SG Tube Degradation Mechanism Notes R38C58 AVB wear Preventively plugged due to atypical AVB wear growth.
R28C34, Four (4) adjacent tubes reported dent signals (no B R28C35, No degradation reported wear) just above the TTS in the HL from a bounded R29C34, at dent locations legacy foreign object. The tubes were preventively R29C35 plugged and stabilized.
F. Number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator The number and percentage of SG tubes plugged to-date, and the effective plugging percentage in each SG are summarized in Table 3.
Table 3 - Tubes plugged to-date and effective plugging percentage SG-A SG-B SG-C Total Tubes Plugged 33 28 11 72 Percent Plugged 1.03% 0.87% 0.34% 0.75%
G. Results of Condition Monitoring, including the results of tube pulls and in-situ testing All indications found in TP4-31 satisfy the condition monitoring (CM) requirements of NEI 97-06 and Turkey Point Technical Specifications for structural and leakage integrity. No indication exceeded the structural limits. The tubes identified for plugging were screened against the in-situ test selection criteria contained in the EPRI SGMP Steam Generator In-Situ Pressure Test Guidelines, Rev 5, and provided for Turkey Point Unit 4 conditions. None of the tubes identified for plugging met the requirements for in-situ pressure testing, and no tube pulls were performed. The TP4-31 inspection results validate the projections and conclusions of the Operational Assessment of the previous inspection at TP4-29.
- 1. Wear at AVB locations has been the dominant mode of degradation for the Turkey Point Unit 4 SGs and accounts for the majority of the indications reported (Attachment B). One tube showed an atypical growth rate history having reported indication growths of 8% and 10% TW at two AVB locations over the last 2 cycles, and was preventively plugged. The maximum observed AVB wear indication in TP4-31 for all SGs was 32% TW and meets the CM requirements
L-2019-175 Page 5 of 8 Enclosure for burst and leakage integrity. The largest wear indications at TSP and FDB locations also fell well-below the CM limits.
- 2. A FO wear (volumetric) indication was reported in the HL at the TTS (tube R27C22) in SG-B.
Since a FO was not detected in the vicinity of this indication, it was likely removed during bundle flush and sludge lancing. The NDE depth of the FO wear indication was 31% TW and met the performance requirements when evaluated against the ISPT screening charts for CM.
- 3. No degradation was detected during the +Point inspection of high stress tubes, and the DNG/DNT sample inspection scope. During the array probe inspection of tubes in the tubesheet, no indication was detected at locations where BLGs/OXPs were located. No corrosion degradation mechanisms were observed during the TP4-31 inspection. All wear reported at broached TSP and FDB locations fell well below the CM limits; therefore, these indications met the acceptance criteria of NEI 97-06 structural performance criterion for burst and leak integrity.
- 4. Channelhead Components Visual Inspection:
Tube Plug Inspection: During the inspection of tube plugs in TP4-31, all installed plugs were confirmed to be in their correct location. In addition, all plugs were found to be dry; no dripping plugs were identified. No degradation or visible signs of leakage were noted on the plugs during the visual inspection.
Other Channelhead Inspections: Visual inspection of various channelhead components were performed to identify degradation per guidance in Westinghouse NSAL 12-1 Rev 1, Steam Generator Channel Head Degradation and LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components. Areas inspected include the divider plate-to-channelhead weld, the weld at the top of the channelhead bowl drain tube, the channelhead-to-tubesheet girth weld seam region, the divider plate, and all cladded surfaces of the channelhead bowl and tubesheet. No degradation was found; the observed condition during the TP4-31 inspection is consistent with the manufacturing process.
- 5. Secondary-side Inspections and Maintenance:
A total of 116 lbs. of sludge was removed from the 3 SGs based on upper bundle flush and sludge lancing in TP4-31 (36, 31 and 49 lbs. in SGs A, B and C, respectively). The TTS locations of all legacy FOs were visually inspected, and 5 newly-identified objects were removed during TTS FOSAR. One newly-identified FO in SG-B (in the shape of a button-head bolt) could not be removed since it was fixed in place between 4 adjacent tubes. The object appears to have been in place since the SG was manufactured. ECT results also reported dent signals (but no degradation) on these tubes just above the TTS; these tubes were plugged and stabilized. The other FOs remaining in the SGs were mostly small sludge rocks, hard deposits and scale. An evaluation is in place for all irretrievable FOs that have the potential to cause tube damage. Upper tube-bundle visual inspection in SG-B at the top TSP reported no fouling/deposit material or abnormal conditions.
Upper Internals Inspection: Visual inspections performed in SG-B (for erosion/corrosion, mechanical damage, foreign material and unusual conditions) included the moisture separators, swirl vanes, feedring and J-nozzles. A light deposit material was noted on the surfaces of the steam drum. No fouling was observed in the flow holes of the moisture separators, and no erosion or corrosion was apparent on the separators or swirl vanes. A minimal amount of scouring was observed inside some of the J-tubes at the interface with the feedring; these have been noted previously and do not appear to have changed. The welds of all steam drum components were noted to be intact. Some wall-thinning (external) was noted based on UT thickness measurements taken on the feedring in SG-B in TP4-31. The condition appears to have been caused by impingement of feedwater as it discharges from the neighboring j-tube.
This was entered in the corrective action program and repairs were performed in TP4-31 to address this condition.
L-2019-175 Page 6 of 8 Enclosure H. Primary-to-secondary leakage rate observed in each SG during the previous cycle No primary-to-secondary leakage was observed during the previous 2 fuel cycles (Cycles 29 and 30).
I. Calculated accident induced leakage rate As described in the H* alternate repair criteria (ARC) for the Turkey Point Plant1, the accident induced leakage rate from the portion of the tubes below 18.11 inches from the TTS is calculated from any observed normal operating leakage that cannot be attributed to a source other than the tubesheet expansion region. For Turkey Point Unit 4, the maximum operational primary-to-secondary leakage rate from the portion of the tubes below 18.11 inches from the top of the tubesheet is determined by multiplying any normal operating leakage by a factor of 1.82 to determine the accident induced leakage rate. Since no operational primary-to-secondary leakage has been observed (per section H of this report), the calculated accident induced leakage rate is zero.
J. Results of monitoring for tube axial displacement (slippage)
A condition for licensing H* was to monitor for tube slippage within the tubesheet region. Monitoring for tube slippage was completed during the TP4-31 inspections. No tube slippage was reported.
1 Turkey Point Nuclear Generating Station Unit Nos. 3 and 4 - Issuance of Amendments Regarding Permanent Alternate Repair Criteria for Steam Generator Tubes (TAC NOS. ME8515 and ME8516); ADAMS Accession No. ML12292A342
L-2019-175 Page 7 of 8 Enclosure APPPENDIX A - Additional Information References to recent SG Tube Inspection Reports (SGTIR)
EOC # Outage ADAMS Accession No.
EOC-26 TP4-27 ML13277A358 EOC-27 TP4-28 Inspection skip (no SGTIR)
EOC-28 TP4-29 ML16298A391 EOC-29 TP4-30 Inspection skip (no SGTIR)
Abbreviations and Acronyms:
ARC Alternate Repair Criteria NEI Nuclear Energy Institute AVB Anti Vibration Bar NSAL Nuclear Safety Advisory Letter BAC Baffle plate cold OD Outside Diameter BAH Baffle plate hot OXP Over-expansion BLG Bulge PLP Possible Loose Part CL Cold Leg PWSCC Primary Water SCC CM Condition Monitoring SCC Stress Corrosion Cracking DNG Ding SG Steam Generator DNT Dent SGMP SG Management Program ECT Eddy Current Testing TEC Tube End Cold EFPM Effective Full Power Months TEH Tube End Hot EFPY Effective Full Power Years TS Tubesheet EPRI Electric Power Research Institute TSC Tubesheet Cold ETSS Exam Technique Spec Sheet TSH Tubesheet Hot FDB Flow Distribution Baffle TSP Tube Support Plate FO Foreign Object TTS Top of Tube Sheet FOSAR Foreign Object Search and Retrieval TW Through Wall HL Hot Leg VOL Volumetric indication (used to report ISPT In-Situ Pressure Test FO-wear in TP4-31)
L-2019-175 Page 8 of 8 Enclosure Appendix B - TP4-31 Listing of Indications Note: Designation used for tube support structures: TSPs: 01H thru 06H on the HL; 01C thru 06C on the CL.
FDB: BAH or BAC. AVBs: AV1 thru AV4 SG-A SG-B SG-B (contd)
ROW COL %TW LOCATION ROW COL %TW LOCATION ROW COL %TW LOCATION
=== === ========= === === === ======== === === === =====
25 12 12 AV2 +0.26 13 35 10 AV3 -0.93 35 49 9 02H -0.37 26 20 7 AV1 +0.30 13 42 10 AV1 -0.04 40 25 6 01C +0.43 30 16 7 AV2 +0.16 21 6 9 AV3 +0.23 43 37 11 04C +0.56 30 30 7 AV3 +0.00 23 50 13 AV3 +0.96 43 39 10 04C +0.64 30 80 9 AV2 +0.18 23 85 10 AV3 -0.10 44 38 18 04C +0.53 31 77 13 AV1 +0.28 26 64 17 AV2 +0.00 31 80 10 AV1 +0.30 18 AV3 +0.00 10 AV2 +0.24 26 68 10 AV3 +0.00 32 74 15 AV1 +0.05 26 71 8 AV2 +0.19 SG-C 14 AV2 +0.27 26 83 7 AV2 +0.25 12 AV3 +0.20 27 72 16 AV2 +0.20 ROW COL %TW LOCATION 32 76 9 AV4 -0.14 27 82 11 AV4 +0.18 === === === =========
33 72 14 AV3 -0.18 30 65 14 AV2 +0.15 12 4 13 AV4 +0.36 33 74 7 AV1 +0.14 8 AV3 +0.18 13 4 12 AV4 +0.37 35 67 10 AV4 -0.14 30 73 8 AV2 +0.00 22 7 8 AV2 +0.17 37 20 14 AV2 +0.26 13 AV3 +0.00 22 82 10 AV1 +0.33 12 AV1 +0.30 17 AV4 +0.00 22 83 11 AV4 +0.00 37 65 17 AV3 +0.00 31 13 12 AV2 +0.18 24 12 17 AV4 -0.09 40 49 11 AV4 -0.05 10 AV3 -0.16 26 82 13 AV1 +0.35 42 63 7 AV3 +0.71 9 AV4 +0.19 27 80 9 AV3 +0.25 29 25 20 AV4 -0.11 33 16 13 AV4 -0.07 27 81 9 AV1 +0.31 33 72 20 AV1 +0.23 33 62 11 AV2 -0.23 8 AV4 +0.15 37 65 28 AV2 +0.00 33 78 9 AV1 +0.18 30 15 15 AV1 +0.35 32 AV4 +0.00 8 AV2 +0.17 30 75 13 AV2 +0.65 37 71 26 AV2 +0.48 34 46 13 AV1 +0.29 31 80 7 AV3 +0.14 20 AV3 +0.35 12 AV2 +0.58 32 16 18 AV2 +0.28 27 72 22 AV1 -0.11 33 76 8 AV1 +0.26 ROW COL %TW LOCATION 34 46 27 AV2 -0.50 34 17 7 AV1 +0.09
=== === ======== 38 58 23 AV3 +0.23 34 53 10 AV1 -0.22 4 58 6 02H +0.48 30 AV4 -0.21 16 AV2 +0.22 10 62 8 04H +0.48 34 75 15 AV4 +0.00 11 86 7 04C +0.41 ROW COL %TW LOCATION 36 74 6 AV3 +0.02 13 4 9 BAH -0.29 === === === ======== 37 71 9 AV1 +0.33 18 86 11 BAC -0.31 19 86 10 BAH -0.22 37 73 7 AV3 -0.27 39 28 5 BAH +0.05 8 BAH -0.27 39 69 7 AV2 -0.11 35 70 9 BAH -0.40 40 68 5 AV2 +0.20 40 26 8 BAH -0.32 32 70 24 AV1 +0.31 6 BAH +0.00 22 AV3 +0.18 27 22 31 TSH -0.03 35 31 20 AV2 +0.31 5 12 10 04H +0.43 5 86 8 01H +0.66 ROW COL %TW LOCATION 8 3 16 02H -0.57 === === === =====
9 80 5 02H +0.46 35 75 12 06H +0.29 28 80 6 05H -0.54 28 82 7 BAH +0.51 31 60 17 02H -0.32