ML23305A041 | 1 November 2023 | Updated Steam Generator Tube Inspection Report | Non-Destructive Examination Nondestructive Examination Operational leakage |
RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | 10 October 2023 | Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections | Finite Element Analysis Aging Management Flow Accelerated Corrosion Stress corrosion cracking License Renewal Subsequent License Renewal |
ML23223A054 | 11 August 2023 | Attachment 1 - Braidwood Station, Unit 2: Form OAR-1 Owner'S Activity Report | |
BW230019, Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 2022 | 31 October 2022 | Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 2022 | Nondestructive Examination COVID-19 |
BW220019, Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22) | 27 April 2022 | Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22) | Nondestructive Examination Flow Accelerated Corrosion Stress corrosion cracking Weak link Operational leakage |
ML22031A044 | 31 January 2022 | Form OAR-1 Owner'S Activity Report | |
BW210083, Revision to Unit 1 Inservice Inspection Summary Report | 15 December 2021 | Revision to Unit 1 Inservice Inspection Summary Report | |
ML21202A193 | 21 July 2021 | Owner'S Activity Report (OAR) for Refueling Outage A1R22 | |
BW210032, Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 2028 | 28 April 2021 | Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 2028 | Safe Shutdown Boric Acid Stroke time Incorporated by reference High Energy Line Break Excess Flow Check Valve Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding Backfit Coast down |
BW200095, Inservice Inspection Summary Report | 9 December 2020 | Inservice Inspection Summary Report | Boric Acid |
BW210002, Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 3 | 25 November 2020 | Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 3 | Safe Shutdown Boric Acid Stroke time Incorporated by reference High Energy Line Break Excess Flow Check Valve Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding Backfit Coast down |
RS-20-085, Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements | 24 July 2020 | Submittal of Relief Request I4R-11 for Braidwood Station, Units 1 and 2, and Relief Request I4R-18 for Byron Station, Units 1 and 2, Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements | Coatings Incorporated by reference Fuel cladding |
ML20017A133 | 17 January 2020 | Inservice Inspection Summary Report | |
NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 | 16 October 2019 | Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 | Boric Acid Nondestructive Examination Affidavit |
RS-19-084, Relief Request Associated with the Third Ten-Year Lnservice Inspection Program Interval | 27 August 2019 | Relief Request Associated with the Third Ten-Year Lnservice Inspection Program Interval | |
NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants | 30 April 2019 | Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants | Boric Acid Loop seal Nondestructive Examination Feedwater Heater Affidavit |
ML19030B087 | 30 January 2019 | Submittal of Inservice Inspection Summary Report | Boric Acid Code Reconciliation |
ML18264A155 | 21 September 2018 | Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 1 | Safe Shutdown Boric Acid Stroke time High Energy Line Break Excess Flow Check Valve Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding Backfit Coast down |
ML18208A294 | 27 July 2018 | Fourth Ten-Year Interval Inservice Testing Program Plan | Safe Shutdown Boric Acid Stroke time High Energy Line Break Excess Flow Check Valve Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding Backfit Coast down |
ML18208A327 | 27 July 2018 | Lnservice Inspection Summary Report | Boric Acid Packing leak |
ML17236A457 | 24 August 2017 | Steam Generator Tube Inspection Report for Refueling Outage 19 | Nondestructive Examination Flow Accelerated Corrosion Operational leakage |
ML17244A233 | 18 August 2017 | Inservice Inspection Summary Report | Boric Acid VT-2 Moisture barrier Liquid penetrant |
ML17058A085 | 27 February 2017 | Steam Generator Tube Inspection Report for Refueling Outage 19 | Nondestructive Examination |
ML17024A398 | 24 January 2017 | Inservice Inspection Summary Report for Refueling Outage 19 (A1R19) | Boric Acid Moisture barrier |
ML16021A080 | 21 January 2016 | Inservice Inspection Summary Report | Moisture barrier Through-Wall Leak |
ML15198A195 | 16 July 2015 | Inservice Inspection Summary Report | Packing leak Moisture barrier Liquid penetrant Through-Wall Leak |
RS-15-155, Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | 29 May 2015 | Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | |
ML14318A211 | 14 November 2014 | Steam Generator Tube Inspection Report for Refueling Outage 17 | Nondestructive Examination Operational leakage |
RS-14-251, Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | 8 September 2014 | Revision to the Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | Weld Overlay Nondestructive Examination Stress corrosion cracking Liquid penetrant |
ML14232A324 | 20 August 2014 | Inservice Inspection Summary Report | Boric Acid Integrated leak rate test Moisture barrier |
ML13358A400 | 20 December 2013 | Inservice Inspection Summary Report for Refueling Outage 17 | Moisture barrier Liquid penetrant |
ML13037A506 | 6 February 2013 | Inservice Inspection Summary Report | Boric Acid Moisture barrier |
ML12251A359 | 17 August 2012 | (Returned to DCD) Braidwood Station, Unit 1, Steam Generator Tube Inspection Report for Refueling Outage 15 | Nondestructive Examination Stress corrosion cracking Operational leakage |
ML12230A226 | 17 August 2012 | Inservice Inspection Summary Report | Integrated leak rate test Moisture barrier |
ML11227A253 | 10 August 2011 | Inservice Inspection Summary Report | Boric Acid Packing leak Non-Destructive Examination Weld Overlay Hydrostatic VT-2 Stress corrosion cracking Eddy Current Testing Moisture barrier Liquid penetrant Through-Wall Leak Through Wall Leak DM weld Thermal fatigue |
RS-11-069, Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | 19 April 2011 | Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations | Weld Overlay Nondestructive Examination Stress corrosion cracking Liquid penetrant |
RS-11-050, Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside. | 11 April 2011 | Third 10-Year Inservice Inspection Interval Relief Request I3R-08, Alternative Requirements to ASME Section XI Appendix VII (Supplements 2 and 10), Examinations of Class 1 Pressure Retaining Welds Conducted from the Inside. | Stress corrosion cracking Dissimilar Metal Weld DM weld |
ML110350512 | 4 February 2011 | Inservice Inspection Summary Report | Boric Acid Packing leak Non-Destructive Examination Weld Overlay Hydrostatic VT-2 Eddy Current Testing Moisture barrier Liquid penetrant Dissimilar Metal Weld |
ML100330273 | 27 January 2010 | Inservice Inspection Summary Report | Boric Acid Packing leak Non-Destructive Examination Weld Overlay Hydrostatic VT-2 Eddy Current Testing Moisture barrier Liquid penetrant Pressure Boundary Leakage |
ML092110538 | 27 July 2009 | Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval | Safe Shutdown Boric Acid Stroke time High Energy Line Break Local Leak Rate Testing Excess Flow Check Valve Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding |
ML092050251 | 16 July 2009 | Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14) | Boric Acid Packing leak Non-Destructive Examination Weld Overlay Hydrostatic VT-2 Eddy Current Testing Moisture barrier Liquid penetrant |
ML092050259 | 16 July 2009 | Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report | Nondestructive Examination |
ML090860715 | 25 March 2009 | Submittal of Third Inservice Inspection (ISI) Interval Program Plan | Boric Acid Weld Overlay Hydrostatic Nondestructive Examination VT-2 Incorporated by reference High Energy Line Break Flow Accelerated Corrosion Stress corrosion cracking Integrated leak rate test Moisture barrier EVT-1 Through-Wall Leakage Dissimilar Metal Weld Thermography Thermal fatigue |
RS-08-160, Third 10-Year Inservice Inspection Interval, Relief Request 1313-01, Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure . | 10 December 2008 | Third 10-Year Inservice Inspection Interval, Relief Request 1313-01, Request for Relief for Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure . | Probabilistic Risk Assessment VT-2 Stress corrosion cracking Dissimilar Metal Weld Thermal fatigue |
ML082900707 | 13 August 2008 | Inservice Inspection Summary Report for: Interval 2, Period 3, Outage 2 A2R13 Outage | Boric Acid Packing leak Weld Overlay Hydrostatic Nondestructive Examination VT-2 Stress corrosion cracking EVT-1 Liquid penetrant Pressure Boundary Leakage Dissimilar Metal Weld |
ML080220526 | 22 January 2008 | Inservice Inspection Summary Report | Boric Acid Ultimate heat sink Mission time Weld Overlay Hydrostatic VT-2 Missed surveillance Stress corrosion cracking Eddy Current Testing EVT-1 Liquid penetrant Through-Wall Leak Dissimilar Metal Weld |
ML080180437 | 18 January 2008 | Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report | Nondestructive Examination |
ML072740389 | 17 October 2007 | Review of Twelfth Refueling Outage Steam Generator Tube Inservice Inspection Report | |
ML070540346 | 23 February 2007 | Second 10-Year Inservice Inspection Interval, Relief Request I2R-48, Structural Weld Overlays on Pressurizer Spray, Relief, Safety and Surge Nozzle Safe-Ends and Associated Alternative Repair Techniques | Weld Overlay Hydrostatic Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld Thermal fatigue |
ML070290671 | 29 January 2007 | Inservice Inspection Summary Report | Boric Acid Hydrostatic Coatings VT-2 Eddy Current Testing Moisture barrier Commercial Grade Liquid penetrant |