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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARCNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML23171A9132023-06-20020 June 2023 Amse, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report ML23171A9572023-06-20020 June 2023 Replacement Steam Dryer Visual Inspection Results (U2R22) ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle . ML23024A1632023-01-24024 January 2023 Replacement Steam Dryer Visual Inspection Results (U1R14) ML22182A1632022-07-0101 July 2022 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns ML21202A2422021-07-21021 July 2021 American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucle ML21201A3112021-07-20020 July 2021 Replacement Steam Dryer Visual Inspection Results ML21036A1532021-02-0505 February 2021 Owner'S Activity Report for Cycle 13 Operation ML21032A1302021-02-0101 February 2021 Replacement Steam Dryer Visual Inspection Results (U1R13) ML20176A3652020-06-24024 June 2020 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucl CNL-20-019, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-472020-02-28028 February 2020 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47 ML19190A0722019-07-0909 July 2019 American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucle ML19051A0182019-02-20020 February 2019 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report Cycle 12 Operation CNL-18-123, Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-272018-12-27027 December 2018 Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-27 ML18186A6042018-07-0505 July 2018 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 1 CNL-18-080, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-Year Interval Request for Relief for 1-ISI-28 and 1-ISI-292018-05-31031 May 2018 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-Year Interval Request for Relief for 1-ISI-28 and 1-ISI-29 ML17180A3862017-06-29029 June 2017 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 1 CNL-17-013, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-292017-01-31031 January 2017 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-29 ML16176A2842016-06-24024 June 2016 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 17 Operation ML15190A3302015-07-0909 July 2015 ASME Section XI, Lnservice Inspection, System Pressure Test, Containment Lnservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 18 Operation ML15028A4032015-01-27027 January 2015 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 10 Operation ML14260A3652014-09-12012 September 2014 3 - ASME, Code Section XI-Inservice Inspection Program for the Unit 1 Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval and Unit 3 Third Ten-Year Inspection Interval, Request for an Alternative. ML14169A4042014-06-16016 June 2014 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Plant, Unit 3, Cycle 16 Operat ML14056A2682014-02-11011 February 2014 ASME, Section XI Code, Inservice Inspection Program for Unit I Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval, and Unit 3 Third Ten-Year Inspection Interval, Request for Relief ISI-44 ML13291A3842013-10-0202 October 2013 Inservice Testing Program for the Fourth Ten Year Interval ML13256A1012013-09-11011 September 2013 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Independent Spent Fuel Storage Installation ML13253A1392013-08-0202 August 2013 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 17 Operation ML13119A3862013-04-29029 April 2013 Ti 182 RFI 2013003_AS Doc ML13067A4012013-03-0101 March 2013 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection and Repair and Replacement Programs - Owner'S Activity Report for Cycle 9 Operation ML12240A1052012-08-24024 August 2012 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 15 Operation ML12150A3672012-05-24024 May 2012 American Society of Mechanical Engineers, Section Xl Code, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-ISI-28 ML11189A1122011-07-0606 July 2011 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 16 Operation ML1108300372011-03-21021 March 2011 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-ISI-26 ML1102603952011-01-21021 January 2011 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for the Unit 3 Third Ten-Year Inspection Interval, Request for Relief 3-ISI-25 ML1018705992010-07-0101 July 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection Program, Request to Use Subsequent Edition of ASME Section Xl Code for Repair and Replacement Activities ML1014700692010-05-24024 May 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, System Pressure Test Program for the Fourth 10-Year Inspection Interval ML1009205422010-03-31031 March 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection Program for the Fourth Ten-Year Inspection Interval ML1005704132010-02-24024 February 2010 American Society of Mechanical Engineers, Section Xl, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-1S1-18, Revision 2 ML1004801252010-02-11011 February 2010 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for Unit 1 Second Ten-Year Inspection Interval, Request for Relief 1-ISI-26, Risk-Informed Inservice Inspection Program ML1001917972010-01-15015 January 2010 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for Browns Ferry Unit 1 Second Ten-Year Inspection Interval and Units 2 & 3 Third Ten-Year Inspection Interval, Request for Relief ISI-23 ML0928005122009-10-0505 October 2009 Comments Regarding NRC Letter and Associated Safety Evaluation for the Browns Ferry Nuclear Plant, Unit 2, Inservice Inspection Program Related to Examination of Piping Weld Overlays ML0926606142009-09-21021 September 2009 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Summary Report for Cycle 15 Operation ML0928707662009-09-17017 September 2009 Response to NRC Request for Additional Information for Third 10-Year Interval Inservice Inspection Program Plan, Relief Request 2-ISI-19, Revision 1 ML1019002472009-07-0707 July 2009 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Summary Report for Cycle 14 Operation ML0914702082009-05-22022 May 2009 American Society of Mechanical Engineers (ASME) Section Xl, Inservice Inspection Program for the Third Ten-Year Inspection Interval - Request for Relief 2-1Sl-21, Revision 1 - Resubmittal ML0913906422009-05-18018 May 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Request for Relief 2-ISI-21, Revision 1 - Examination of Piping Weld Overlays ML0907808612009-03-0202 March 2009 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Third Ten-year Inspection Interval - Request for Relief 2-ISI-19, Revision 1 ML0906304232009-03-0202 March 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inspection (IWE, and Repair and Replacement Programs - Summary Reports for Cycle 7 Operation 2023-07-03
[Table view] Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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Post Office Box 2000, Decatur, Alabama 35609-2000 June 20, 2023 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260
Subject:
Unit 2 Replacement Steam Dryer Visual Inspection Results (U2R22)
Enclosed is a summary of the results of the visual inspections of the Unit 2 Replacement Steam Dryer that were performed during the recent refueling outage (U2R22). The inspections are required to be performed in accordance with Operating License Condition 2.C(18)(g) during the first two scheduled refueling outages after reaching full Extended Power Uprate conditions which requires that the results of the inspection be submitted in a report within 90 days following startup. This second report for Unit 2 is being submitted pursuant to Operating License Condition 2.C(18)(h) which requires that the results of the inspection be submitted in a report within 90 days following startup.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Christopher L. Vaughn, Nuclear Site Licensing Manager, at (256) 729-2636.
Respectfully, Manu Sivaram Sivaraman BFN Site Vice President
U.S. Nuclear Regulatory Commission Page 2 June 20, 2023
Enclosure:
Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate cc (w/ Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant
ENCLOSURE Browns Ferry Nuclear Plant Unit 2 Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate See Enclosed
Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate
Purpose This report provides the results of visual inspections of the Replacement Steam Dryer (RSD) as required by the Browns Ferry Unit 2 Renewed Facility Operating License No. DPR-52, License Condition 2.C.(18).(h). This license condition requires that the results of the visual inspections of the RSD be submitted to the NRC within 90 days following startup from each of the first two respective refueling outages.
Summary The Unit 2 RSD was inspected from February 20 through March 6, 2023, during the Spring 2023 refueling outage (Unit 2 Refueling Outage 22: U2R22). This was the second refueling outage following installation of the RSD in March 2019 during Unit 2 Refueling Outage 20 (U2R20) and operation at Extended Power Uprate (EPU) conditions since June 2019. The inspections were performed in accordance with GE Hitachi Nuclear Energy Report No.
003N5663, Revision 2 (Tennessee Valley Authority (TVA) Browns Ferry Nuclear Station (BFNS): Recommendations for Future Inspections - Replacement Steam Dryer). The RSD design and the materials and fabrication processes utilized are expected to result in significantly improved resistance to stress corrosion cracking. Therefore, the inspection recommendations in the GEH report focus primarily on the locations that may be susceptible to fatigue from flow-induced vibration. The locations identified are those indicated to have relatively significant cyclic loading during the dryers operation, as determined by detailed stress analyses.
Tables 1 (Frequency of Recommended Locations Based on Analysis) and 2 (Description of Recommended Inspections Locations) of the GEH Report list locations that are considered the most susceptible for fatigue cracking based on BWR dryer experience and stress analysis. All accessible weld and weld heat-affected zone (HAZ) base metal surfaces of the RSD were visually inspected during U2R22, with a total scope of 646 points. The summary results of the inspections can be found in the table starting on the next page.
The following explanations apply to the table:
NRI: No Relevant Indication RI: Relevant Indication The parentheses after each Inspection Location refer to the number of points inspected for each.
1
Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate
Inspection Location Method Inspection Condition Disposition
Result Report(ifRI)
STEAM DRYER ID Divider Plate Welds & HAZs (32) VT-1-89 NRI Trough Side Plate to Base Plate Weld & VT-1-89 NRI HAZs (6)
Hood Vertical / Horizontal Welds & VT-1-89 NRI HAZs (12)
Perforated Plate to Trough Side Plate VT-1-89 NRI Weld & HAZs (22)
Trough Spacer Pin Weld & HAZs (6) VT-1-89 NRI Skirt to Support Beam Weld & HAZs (8) VT-1-89 NRI Guide Channel to Tee Weld & HAZs (4) VT-1-89 NRI Skirt to Tee Weld & HAZs (12) VT-1-89 NRI Drain Pipe to Trough Base Plate Weld & VT-1-89 NRI HAZs (12)
Drain Pipe to Elbow Weld & HAZs (21) VT-1-89 NRI Drain Elbow to Pipe Weld & HAZs (11) VT-1-89 NRI Drain Elbow to Skirt Weld & HAZs (12) VT-1-89 NRI Collar to Skirt Weld & HAZs (12) VT-1-89 NRI Cover Plate to Hood Weld & HAZs (2) VT-1-89 NRI Trough Base Plate to Hood Weld & VT-1-89 NRI HAZs (4)
Hood Support Stiffener Assembly, VT-1-89 NRI Stiffener to Hood Support Tee Weld &
HAZs, 360-degree weld (16)
Hood Support Stiffener Assembly, VT-1-89 NRI Stiffener to Trough Weld & HAZs, 360 degree weld (16)
Skirt to Lower Support Ring Weld plus 2 VT-1-89 NRI Splice Bars & HAZs (2)
Skirt to Lower Support Ring Weld & VT-1-89 NRI HAZs (6)
Splice Bar Attachment Weld and HAZs VT-1-89 NRI (4)
Trans Brace to Upper Support Ring VT-1-89 NRI Weld & HAZs (2)
Trans Brace Coupler Weld & HAZs (1) VT-1-89 NRI Trans Brace Plate Welds & HAZs (8) VT-1-89 NRI Trans Brace Support Welds & HAZs VT-1-89 NRI (12)
Base Plate to Upper Support Ring Weld VT-1-89 NRI
& HAZs (4)
Base Plate to Upper Support Ring/Latch VT-1-89 NRI Assembly Welds & HAZs (2)
Base Plate to Upper Support Ring/Lifting VT-1-89 NRI Assembly Welds & HAZs (2)
Cover Plate to Upper Support Ring Weld VT-1-89 NRI
& HAZs (2)
Splice Bar to Upper Support Ring and VT-1-89 NRI Trough Welds & HAZs (2)
USR Segment Weld & HAZs (4) VT-1-89 NRI 2
Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate
Inspection Location Method Inspection Condition Disposition
Result Report(ifRI)
Skirt to Upper Support Ring Weld & VT-1-89 NRI
HAZs (6)
STEAM DRYER OD 000 Degree Pad Welds & HAZs (1) VT-1-89 NRI Steam Dryer Outer Banks Access Panel VT-1-89 NRI Welds & HAZs 000 Side (6)
Steam Dryer Outer Banks Access Panel VT-1-89 NRI Welds & HAZs 180 Side (6)
Both Sides of the Bank to Divider Plate VT-1-89 NRI Weld & HAZs (16)
Both Sides of the Bank to Exhaust VT-1-89 NRI Plenum Plate Vertical Weld & HAZs (20)
Hood to Cover Plate Horizontal Weld & VT-1-89 NRI HAZs (2)
Hood to Top Cap Horizontal Weld & VT-1-89 NRI HAZs (6)
Perforated Plate to Bank Top Cap Weld VT-1-89 NRI
& HAZs (6)
Perforated Plate to Trough Side Plate VT-1-89 NRI Weld & HAZs (6)
Trough Side Plate to Base Plate Weld VT-1-89 NRI
& HAZs (6)
Both Sides of the Hood Support to VT-1-89 NRI Trough Weld & HAZs (16)
Perforated Plate to End Plate Weld & VT-1-89 NRI HAZs (4)
Perforated Plate to Perforated Plate VT-1-89 NRI Weld & HAZs (16)
Perforated Plate to End Plate Weld & VT-1-89 NRI HAZs from Trough Base Plate to Hood Cap (8)
Trough Spacer Pin Weld & HAZs (6) VT-1-89 NRI Bank Tie Rod Bolting Welds & HAZs for VT-1-89 NRI all 6 locations on the 000 Deg Side (6)
Bank Tie Rod Bolting Welds & HAZs for VT-1-89 NRI all 6 locations on the 180 Deg Side (6)
Hood to Trough Base Plate Horizontal VT-1-89 NRI Weld & HAZs (4)
Both Sides of the Divider Plate to Inner VT-1-89 NRI Plate Welds & HAZs (6)
Drain Channel to Upper Support Ring VT-1-89 RI 1839983 Accepted as-is Horizontal Weld & HAZs (4)
Drain Channel to Support Beam Weld & VT-1-89 NRI HAZs (8)
Drain Channel to Support Ring Tab VT-1-89 NRI Welds & HAZs (20)
Guide Channel to Drain Channel Tee VT-1-89 NRI Vertical Weld & HAZs (4) 3
Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate
Inspection Location Method Inspection Condition Disposition
Result Report(ifRI)
Drain Channel to Drain Channel Tee VT-1-89 NRI Vertical Weld & HAZs (8)
Skirt to Drain Channel Tee Vertical Weld VT-1-89 NRI
& HAZs (4)
Doubler Plate to Upper Support Ring & VT-1-89 NRI HAZs (8)
General Overview of the Side Surfaces VT-1-89 NRI (4)
General Overview of the Top Surfaces VT-1-89 NRI (1)
Hood to Inlet End Plate Vertical Weld & VT-1-89 NRI HAZs (18)
Both Hood to Hood Tee Vertical Welds VT-1-89 NRI
& HAZs (4)
Hood to Hood Tee Vertical Weld & VT-1-89 NRI HAZs (18)
Both Sides of the Hold Down Assembly VT-1-89 NRI to Exhaust Plenum Plate Vertical Weld
& HAZs (4)
Hold Down Assembly to Trough Base VT-1-89 NRI Plate Horizontal Weld & HAZs (2)
Lifting Assembly - Support Ring Anchor VT-1-89 NRI Weld & HAZs (4)
Lifting Assembly - Bolting (4) VT-1-89 NRI Lifting Assembly - Lower Bracket and VT-1-89 NRI Welds Plus HAZs (4)
Lifting Assembly - Middle Bracket and VT-1-89 NRI Welds Plus HAZs (4)
Lifting Assembly - Rod to Anchor Weld VT-1-89 NRI
& HAZs (4)
Lifting Assembly - Upper Bracket and VT-1-89 NRI Welds Plus HAZs (4)
Latch Box General Condition for VT-1-89 NRI Evidence of Handling Damage (2)
Lower Guide Channel General Condition VT-1-89 NRI for Evidence of Handling Damage (2)
Lower Support Ring to Guide Channel VT-1-89 NRI Horizontal Weld & HAZs (2)
Lower Support Ring to Skirt Horizontal VT-1-89 NRI Weld & HAZs (6)
Lower Support Ring Splice Bar General VT-1-89 NRI Condition for Evidence of Handling Damage (2)
Splice Bar Attachment Weld & HAZs (8) VT-1-89 NRI Seismic Lug General Condition for VT-1-89 NRI Evidence of Handling Damage, also Associated Bolting, Welds & HAZs (2)
Bank Tie Bar Welds & HAZs (34) VT-1-89 NRI Trough Base Plate Center Horizontal VT-1-89 NRI Weld & HAZs (1) 4
Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate
Inspection Location Method Inspection Condition Disposition
Result Report(ifRI)
Top Flange to C-Channel to Hood VT-1-89 NRI Cover Weld & HAZs (2)
Upper Support Ring Horizontal Weld & VT-1-89 NRI HAZs (26)
Upper Support Ring Tapered Pin Seal VT-1-89 NRI Weld & HAZs (8)
Upper Support Ring to Splice Bar VT-1-89 NRI Vertical Weld & HAZs (4)
Upper Support Ring to Guide Channel VT-1-89 NRI Horizontal Weld & HAZs (2)
Upper Support Ring to Skirt Horizontal VT-1-89 NRI Weld & HAZs (2)
Inspection Results One relevant indication was noted during the U2R22 RSD visual examination campaign. It is described as follows:
(1) BFN2-SD OD DC02 H01: During inspection of the Drain Channel 02 to Upper Support Ring H01 Weld, a relevant indication was observed in the lower heat-affected zone. The indication was measured at 0.389 with a ruler deployed by the vendors inspection services. The inspection data from U2R21 was reviewed and the indication appeared to be present but not as apparent in the video data provided by the standard definition cameras available at the time of the first RSD baseline. High-definition cameras in U2R22 revealed the indication with more clarity.
Disposition of Indications Condition Report (CR) 1839983 was initiated to document and disposition the relevant indication reported on the RSD. The disposition is as follows:
(1) BFN2-SD OD DC02 H01: The indication reported on the Drain Channel 02 to Upper Support Ring H01 Weld was evaluated by the inspection vendor. This document was subsequently reviewed by Asset Management Programs-Materials which concluded that the indication was acceptable as-is without repair for one fuel cycle (U2C23), at which point the indication will be re-inspected in concurrence with vendor recommendations. The Steam Dryer performs no safety function. However, the potential for lost parts generated could pose a threat to safety-related equipment if not considered. Due to the nature of this indication, and the evaluation that concludes the flaw will not result in failure between inspection cycles, lost parts are considered extremely improbable thus further evaluation is not warranted and reinspection will ensure any increase in lost parts probability will be detected prior to an event. The flaw in the Drain Channel 02 to Upper Support Ring H01 Weld will be re-examined during Unit 2 Refueling Outage 23 (U2R23) in Spring 2025 with an emphasis on identifying any signs of change.
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Browns Ferry Unit 2 Replacement Steam Dryer (RSD) Inspection Results from the Second Refueling Outage (U2R22) Following Installation of RSD and Implementation of Extended Power Uprate
Conclusion A completed second baseline inspection of the Browns Ferry Unit 2 Replacement Steam Dryer (RSD) was performed during the Spring 2023 Refueling Outage 22. This re-baseline inspection included successful visual inspection of all RSD locations required by the Facility Operating License Condition 2.C.(18).(h). All observations were acceptable for the locations inspected.
There was one inspection area with a relevant indication that was subsequently dispositioned by engineering evaluation and will be reinspected in U2R23 per vendor recommendation to confirm stability by assessing the indication for signs of growth or change. Since two baseline inspections of the RSD have now been completed, future inspections (aside from the reinspection of the before described indication) will be performed in accordance with the guidelines specified in GE Hitachi Nuclear Energy Report No. 007N4785, Revision 0 (Tennessee Valley Authority (TVA) Browns Ferry Nuclear Station (BFNS): Recommendations for Future Inspections - Replacement Steam Dryer).
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