Category:Graphics incl Charts and Tables
MONTHYEARBW240069, CFR 50.59 Changes, Tests, and Experiments Summary Report2024-12-13013 December 2024 CFR 50.59 Changes, Tests, and Experiments Summary Report ML22031A0442022-01-31031 January 2022 Form OAR-1 Owners Activity Report ML21202A1932021-07-21021 July 2021 Owners Activity Report (OAR) for Refueling Outage A1R22 RS-20-126, EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart2020-10-13013 October 2020 EP-AA-111-F-02, Rev. 1, Braidwood PAR Flowchart BW190014, Submittal of Inservice Inspection Summary Report2019-01-30030 January 2019 Submittal of Inservice Inspection Summary Report ML15253A9132015-09-11011 September 2015 ACRS Full Committee - Corrections to the Aging Management Programs Table RS-15-059, Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application2015-02-0606 February 2015 Units 1 & 2 - Update to LRA Section 4.3.4, Class 1 Component Fatigue Analyses Supporting GSI-190 Closure, Related to License Renewal Application ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T RA-13-075, Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites2013-09-12012 September 2013 Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Sites ML12312A4192012-11-0707 November 2012 NUREG 1307 Public Meeting Revised Table A-4 NEI 08-09, Re-Submittal of the Exelon Cyber Security Plan2010-07-23023 July 2010 Re-Submittal of the Exelon Cyber Security Plan RS-10-105, Parent Guarantee Calculation RS-10-1052010-03-10010 March 2010 Parent Guarantee Calculation RS-10-105 ML0934313182009-12-0101 December 2009 Updated Decommissioning Shortfalls as of December 1, 2009 BW080080, Transmittal of Response to Request for Additional Information Regarding Fall 2007 Steam Generator Inspection2008-08-13013 August 2008 Transmittal of Response to Request for Additional Information Regarding Fall 2007 Steam Generator Inspection ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0707300272007-03-0707 March 2007 Oak Ridge Institute for Science and Education - Letter Report for 18 Water Samples from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2007-003) (Rfta No. 06-001) RS-07-022, Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification2007-02-15015 February 2007 Response to Request for Additional Information Regarding Application for Steam Generator Tube Integrity Technical Specification ML0621602722006-07-28028 July 2006 Analytical Results for Fourteen Water Samples, Batch Eight, from the Vicinity of the Braidwood Nuclear Generating Station, Braidwood, Illinois (Inspection Report No. 050-00456/2006-004)(RFTA No. 06-001) ML0617103272006-02-0606 February 2006 Tritium Sample Results ML0617102252005-12-19019 December 2005 Orise Letter Dated 12/19/05, W/Personal Notes, Analytical Results for Water Samples Near the Braidwood Nuclear Generation Station in Braidwood, Illinois, Inspection Report 456/457/2005-010 - Rfta No. 06-001 ML0610106942005-12-16016 December 2005 Schematic of Regional Hydrogeology ML0609606442005-11-17017 November 2005 Tritium Sample Results; NRC Split Sample Results ML0522300142005-03-0909 March 2005 RIC 2005 Presentation - F4 - Dale Ambler - Rop/Cross Cutting Issues RS-04-191, Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-3192004-12-16016 December 2004 Units 1 & 2 - Updated Final Safety Analysis Report (Ufsar), Braidwood Figure 2.1-1 Through 2.5-319 ML0609605552001-01-31031 January 2001 Of Table 11a (Continued) Teen Inhalation Dose Factors 2024-12-13
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML24241A0062024-08-28028 August 2024 Attachment 1: Braidwood Generating Station - Form OAR-1 Owners Activity Report ML23305A0412023-11-0101 November 2023 Updated Steam Generator Tube Inspection Report RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23223A0542023-08-11011 August 2023 Attachment 1 - Braidwood Station, Unit 2: Form OAR-1 Owners Activity Report BW230019, Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 20222022-10-31031 October 2022 Steam Generator Eddy Current Inspection Report Refueling Outage 23 (A1R23) - October 2022 BW220019, Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22)2022-04-27027 April 2022 Steam Generator Tube Inspection Report Refueling Outage 22 (A2R22) ML22031A0442022-01-31031 January 2022 Form OAR-1 Owners Activity Report BW210083, Revision to Unit 1 Inservice Inspection Summary Report2021-12-15015 December 2021 Revision to Unit 1 Inservice Inspection Summary Report ML21202A1932021-07-21021 July 2021 Owners Activity Report (OAR) for Refueling Outage A1R22 BW210032, Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 20282021-04-28028 April 2021 Inservice Testing Program Fourth Ten Year Interval July 29, 2018- July 28, 2028 BW200095, Inservice Inspection Summary Report2020-12-0909 December 2020 Inservice Inspection Summary Report BW210002, Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 32020-11-25025 November 2020 Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 3 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 Requirements2020-07-24024 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 ML20017A1332020-01-17017 January 2020 Inservice Inspection Summary Report NMP2L2711, Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 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 RS-19-084, Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval2019-08-27027 August 2019 Relief Request Associated with the Third Ten-Year Inservice Inspection Program Interval NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants BW190014, Submittal of Inservice Inspection Summary Report2019-01-30030 January 2019 Submittal of Inservice Inspection Summary Report BW180096, Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 12018-09-21021 September 2018 Fourth Ten-Year Interval Inservice Testing Program Plan, Revision 1 BW180077, Fourth Ten-Year Interval Inservice Testing Program Plan2018-07-27027 July 2018 Fourth Ten-Year Interval Inservice Testing Program Plan BW180078, Inservice Inspection Summary Report2018-07-27027 July 2018 Inservice Inspection Summary Report BW170080, Steam Generator Tube Inspection Report for Refueling Outage 192017-08-24024 August 2017 Steam Generator Tube Inspection Report for Refueling Outage 19 BW170084, Inservice Inspection Summary Report2017-08-18018 August 2017 Inservice Inspection Summary Report BW170017, Steam Generator Tube Inspection Report for Refueling Outage 192017-02-27027 February 2017 Steam Generator Tube Inspection Report for Refueling Outage 19 BW170006, Inservice Inspection Summary Report for Refueling Outage 19 (A1R19)2017-01-24024 January 2017 Inservice Inspection Summary Report for Refueling Outage 19 (A1R19) BW160006, Inservice Inspection Summary Report2016-01-21021 January 2016 Inservice Inspection Summary Report BW150073, Inservice Inspection Summary Report2015-07-16016 July 2015 Inservice Inspection Summary Report RS-15-155, Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2015-05-29029 May 2015 Response to Preliminary RAI Regarding Braidwood and Byron Stations Relief Request for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations BW140098, Steam Generator Tube Inspection Report for Refueling Outage 172014-11-14014 November 2014 Steam Generator Tube Inspection Report for Refueling Outage 17 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 Penetrations2014-09-0808 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 BW140070, Inservice Inspection Summary Report2014-08-20020 August 2014 Inservice Inspection Summary Report BW130110, Inservice Inspection Summary Report for Refueling Outage 172013-12-20020 December 2013 Inservice Inspection Summary Report for Refueling Outage 17 BW130007, Inservice Inspection Summary Report2013-02-0606 February 2013 Inservice Inspection Summary Report BW120081, Inservice Inspection Summary Report2012-08-17017 August 2012 Inservice Inspection Summary Report ML12251A3592012-08-17017 August 2012 (Returned to DCD) Braidwood Station, Unit 1, Steam Generator Tube Inspection Report for Refueling Outage 15 BW110084, Inservice Inspection Summary Report2011-08-10010 August 2011 Inservice Inspection Summary Report RS-11-069, Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2011-04-19019 April 2011 Third 10-Year Inservice Inspection Interval Requests for Relief for Alternative Requirements for the Repair of Reactor Vessel Head Penetrations 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 Inside2011-04-11011 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 BW110012, Inservice Inspection Summary Report2011-02-0404 February 2011 Inservice Inspection Summary Report BW100010, Inservice Inspection Summary Report2010-01-27027 January 2010 Inservice Inspection Summary Report BW090073, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval2009-07-27027 July 2009 Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval BW090069, Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14)2009-07-16016 July 2009 Submittal of Inservice Inspection Summary Report, Fourteenth Refueling Outage (A1R14) BW090068, Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report2009-07-16016 July 2009 Fourteenth Refueling Outage Steam Generator Inservice Inspection Summary Report BW090029, Submittal of Third Inservice Inspection (ISI) Interval Program Plan2009-03-25025 March 2009 Submittal of Third Inservice Inspection (ISI) Interval Program Plan 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 Pressure2008-12-10010 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 ML0829007072008-08-13013 August 2008 Inservice Inspection Summary Report for: Interval 2, Period 3, Outage 2 A2R13 Outage BW080002, Inservice Inspection Summary Report2008-01-22022 January 2008 Inservice Inspection Summary Report BW080003, Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report2008-01-18018 January 2008 Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report ML0727403892007-10-17017 October 2007 Review of Twelfth Refueling Outage Steam Generator Tube Inservice Inspection Report BW070013, 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 Techniques2007-02-23023 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 2024-08-28
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