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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24354A2092024-12-19019 December 2024 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inspection Service, System Procedure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear ML24176A1132024-06-23023 June 2024 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 Cycle 21 Oper 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 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, Owner’S 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, Owner’S 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, Owners 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, Owners Activity Report for Browns Ferry Nuclea ML21201A3112021-07-20020 July 2021 Replacement Steam Dryer Visual Inspection Results ML21036A1532021-02-0505 February 2021 Owners 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, Owners Activity Report for Browns Ferry Nucle 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, Owners Activity Report for Browns Ferry Nuclea 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 - Owners 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 - Owners Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 18 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 - Owners Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 19 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 - Owners Activity Report for Cycle 17 Operation ML15190A3302015-07-0909 July 2015 ASME Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owners 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 - Owners 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 - Owners Activity Report for Browns Ferry Plant, Unit 3, Cycle 16 Operati 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 - Owners 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 - Owners 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 - Owners 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 - Owners 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 2024-06-23
[Table view] Category:Letter
MONTHYEARCNL-25-009, And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 262025-01-29029 January 2025 And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 26 ML25007A0782025-01-15015 January 2025 Rci/Rai Audit Letter 05000259/LER-2024-004, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2025-01-10010 January 2025 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints CNL-25-014, Response to Request for Additional Information, Set 22025-01-0808 January 2025 Response to Request for Additional Information, Set 2 ML25014A2072025-01-0808 January 2025 EPA Letter to the Mississippi Department of Environmental Quality on Browns Ferry SLR IR 05000259/20240112024-12-26026 December 2024 Biennial Problem Identification and Resolution Inspection Report 05000259/2024011, 05000260/2024011, and 05000296/2024011 ML24312A3222024-12-23023 December 2024 Issuance of Amendment Nos. 334, 357, & 317; 368 & 362; 172 & 77 Regarding Revision to TS 5.4 & 5.7.1 ML24311A1212024-12-19019 December 2024 Evaluation of Effects of Out-of-Limit Condition as Described in ASME Section XI, IWB-3720(a) ML24354A2092024-12-19019 December 2024 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inspection Service, System Procedure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear CNL-24-009, Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations2024-12-17017 December 2024 Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations CNL-24-081, Application for Subsequent Renewed Operating Licenses, Third Safety Supplement2024-12-17017 December 2024 Application for Subsequent Renewed Operating Licenses, Third Safety Supplement CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML24347A0142024-12-12012 December 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-083, Alabama Department of Environmental Management Letter2024-12-10010 December 2024 Alabama Department of Environmental Management Letter CNL-24-049, Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements2024-12-0909 December 2024 Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements 05000296/LER-2024-004, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping2024-12-0404 December 2024 Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping ML24332A0372024-11-27027 November 2024 Updated Report of a Deviation or Failure to Comply Associated with a Valve in the High Pressure Coolant Injection System 05000260/LER-2024-002-01, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-11-25025 November 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation IR 05000260/20240912024-11-21021 November 2024 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000260/2024091 ML24324A3332024-11-20020 November 2024 Notification of Licensed Operator Initial Examination 05000259/2025301, 05000260/2025301, 05000296/2025301 IR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 2025-01-08
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Text
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 Sivaraman BFN Site Vice President Manu Sivaram
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
1
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.
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
2
Inspection Location Method Inspection
Result
Condition
Report(ifRI)
Disposition
STEAM DRYER ID Divider Plate Welds & HAZs (32)
VT-1-89 NRI Trough Side Plate to Base Plate Weld &
HAZs (6)
VT-1-89 NRI Hood Vertical / Horizontal Welds &
HAZs (12)
VT-1-89 NRI Perforated Plate to Trough Side Plate Weld & HAZs (22)
VT-1-89 NRI 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 &
HAZs (12)
VT-1-89 NRI 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 &
HAZs (4)
VT-1-89 NRI Hood Support Stiffener Assembly, Stiffener to Hood Support Tee Weld &
HAZs, 360-degree weld (16)
VT-1-89 NRI Hood Support Stiffener Assembly, Stiffener to Trough Weld & HAZs, 360 degree weld (16)
VT-1-89 NRI Skirt to Lower Support Ring Weld plus 2 Splice Bars & HAZs (2)
VT-1-89 NRI Skirt to Lower Support Ring Weld &
HAZs (6)
VT-1-89 NRI Splice Bar Attachment Weld and HAZs (4)
VT-1-89 NRI Trans Brace to Upper Support Ring Weld & HAZs (2)
VT-1-89 NRI 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 (12)
VT-1-89 NRI Base Plate to Upper Support Ring Weld
& HAZs (4)
VT-1-89 NRI Base Plate to Upper Support Ring/Latch Assembly Welds & HAZs (2)
VT-1-89 NRI Base Plate to Upper Support Ring/Lifting Assembly Welds & HAZs (2)
VT-1-89 NRI Cover Plate to Upper Support Ring Weld
& HAZs (2)
VT-1-89 NRI Splice Bar to Upper Support Ring and Trough Welds & HAZs (2)
VT-1-89 NRI USR Segment Weld & HAZs (4)
VT-1-89 NRI
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
3
Inspection Location Method Inspection
Result
Condition
Report(ifRI)
Disposition
Skirt to Upper Support Ring Weld &
HAZs (6)
VT-1-89 NRI
STEAM DRYER OD 000 Degree Pad Welds & HAZs (1)
VT-1-89 NRI Steam Dryer Outer Banks Access Panel Welds & HAZs 000 Side (6)
VT-1-89 NRI Steam Dryer Outer Banks Access Panel Welds & HAZs 180 Side (6)
VT-1-89 NRI Both Sides of the Bank to Divider Plate Weld & HAZs (16)
VT-1-89 NRI Both Sides of the Bank to Exhaust Plenum Plate Vertical Weld & HAZs (20)
VT-1-89 NRI Hood to Cover Plate Horizontal Weld &
HAZs (2)
VT-1-89 NRI Hood to Top Cap Horizontal Weld &
HAZs (6)
VT-1-89 NRI Perforated Plate to Bank Top Cap Weld
& HAZs (6)
VT-1-89 NRI Perforated Plate to Trough Side Plate Weld & HAZs (6)
VT-1-89 NRI Trough Side Plate to Base Plate Weld
& HAZs (6)
VT-1-89 NRI Both Sides of the Hood Support to Trough Weld & HAZs (16)
VT-1-89 NRI Perforated Plate to End Plate Weld &
HAZs (4)
VT-1-89 NRI Perforated Plate to Perforated Plate Weld & HAZs (16)
VT-1-89 NRI Perforated Plate to End Plate Weld &
HAZs from Trough Base Plate to Hood Cap (8)
VT-1-89 NRI Trough Spacer Pin Weld & HAZs (6)
VT-1-89 NRI Bank Tie Rod Bolting Welds & HAZs for all 6 locations on the 000 Deg Side (6)
VT-1-89 NRI Bank Tie Rod Bolting Welds & HAZs for all 6 locations on the 180 Deg Side (6)
VT-1-89 NRI Hood to Trough Base Plate Horizontal Weld & HAZs (4)
VT-1-89 NRI Both Sides of the Divider Plate to Inner Plate Welds & HAZs (6)
VT-1-89 NRI Drain Channel to Upper Support Ring Horizontal Weld & HAZs (4)
VT-1-89 RI 1839983 Accepted as-is Drain Channel to Support Beam Weld &
HAZs (8)
VT-1-89 NRI Drain Channel to Support Ring Tab Welds & HAZs (20)
VT-1-89 NRI Guide Channel to Drain Channel Tee Vertical Weld & HAZs (4)
VT-1-89 NRI
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
4
Inspection Location Method Inspection
Result
Condition
Report(ifRI)
Disposition
Drain Channel to Drain Channel Tee Vertical Weld & HAZs (8)
VT-1-89 NRI Skirt to Drain Channel Tee Vertical Weld
& HAZs (4)
VT-1-89 NRI Doubler Plate to Upper Support Ring &
HAZs (8)
VT-1-89 NRI General Overview of the Side Surfaces (4)
VT-1-89 NRI General Overview of the Top Surfaces (1)
VT-1-89 NRI Hood to Inlet End Plate Vertical Weld &
HAZs (18)
VT-1-89 NRI Both Hood to Hood Tee Vertical Welds
& HAZs (4)
VT-1-89 NRI Hood to Hood Tee Vertical Weld &
HAZs (18)
VT-1-89 NRI Both Sides of the Hold Down Assembly to Exhaust Plenum Plate Vertical Weld
& HAZs (4)
VT-1-89 NRI Hold Down Assembly to Trough Base Plate Horizontal Weld & HAZs (2)
VT-1-89 NRI Lifting Assembly - Support Ring Anchor Weld & HAZs (4)
VT-1-89 NRI Lifting Assembly - Bolting (4)
VT-1-89 NRI Lifting Assembly - Lower Bracket and Welds Plus HAZs (4)
VT-1-89 NRI Lifting Assembly - Middle Bracket and Welds Plus HAZs (4)
VT-1-89 NRI Lifting Assembly - Rod to Anchor Weld
& HAZs (4)
VT-1-89 NRI Lifting Assembly - Upper Bracket and Welds Plus HAZs (4)
VT-1-89 NRI Latch Box General Condition for Evidence of Handling Damage (2)
VT-1-89 NRI Lower Guide Channel General Condition for Evidence of Handling Damage (2)
VT-1-89 NRI Lower Support Ring to Guide Channel Horizontal Weld & HAZs (2)
VT-1-89 NRI Lower Support Ring to Skirt Horizontal Weld & HAZs (6)
VT-1-89 NRI Lower Support Ring Splice Bar General Condition for Evidence of Handling Damage (2)
VT-1-89 NRI Splice Bar Attachment Weld & HAZs (8)
VT-1-89 NRI Seismic Lug General Condition for Evidence of Handling Damage, also Associated Bolting, Welds & HAZs (2)
VT-1-89 NRI Bank Tie Bar Welds & HAZs (34)
VT-1-89 NRI Trough Base Plate Center Horizontal Weld & HAZs (1)
VT-1-89 NRI
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
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Inspection Location Method Inspection
Result
Condition
Report(ifRI)
Disposition
Top Flange to C-Channel to Hood Cover Weld & HAZs (2)
VT-1-89 NRI Upper Support Ring Horizontal Weld &
HAZs (26)
VT-1-89 NRI Upper Support Ring Tapered Pin Seal Weld & HAZs (8)
VT-1-89 NRI Upper Support Ring to Splice Bar Vertical Weld & HAZs (4)
VT-1-89 NRI Upper Support Ring to Guide Channel Horizontal Weld & HAZs (2)
VT-1-89 NRI Upper Support Ring to Skirt Horizontal Weld & HAZs (2)
VT-1-89 NRI 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.
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
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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).