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Issue date | Title | |
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IR 05000456/2023002 | 3 August 2023 | Integrated Inspection Report 05000456/2023002 and 05000457/2023002 |
ML21347A038 | 13 January 2022 | Issuance of Amendments to Revise Reactor Coolant Leakage Requirements |
RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements | 4 January 2022 | Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements |
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements | 30 June 2021 | Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements |
ML21063A016 | 8 March 2021 | Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Alternative to 10 CFR 50.55a(z)(2) |
RS-21-008, Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2) | 25 January 2021 | Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2) |
ML21008A410 | 17 December 2020 | Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Appendix a, Application of NRC Regulatory Guides |
ML21008A417 | 17 December 2020 | Technical Specification Bases |
ML20287A389 | 13 October 2020 | EP-AA-1001, Addendum 3, Rev. 4, Emergency Action Levels for Braidwood Station |
ML20287A390 | 13 October 2020 | EP-AA-1001, Addendum 3, Rev. 5, Emergency Action Levels for Braidwood Station |
ML20287A391 | 13 October 2020 | EP-AA-1001, Addendum 3, Rev. 6, Emergency Action Levels for Braidwood Station |
ML20170B021 | 23 June 2020 | NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections |
ML20034G546 | 12 March 2020 | Issuance of Amendments Revising Instrument Testing and Calibration Definitions |
RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program | 25 June 2019 | Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program |
ML19155A060 | 5 June 2019 | Relief from the Requirements of the American Society of Mechanical Engineers Code |
IR 05000456/2019001 | 1 May 2019 | NRC Integrated Inspection Report 05000456/2019001; 05000457/2019001; and 07200073/2019001 |
IR 05000456/2018004 | 6 February 2019 | NRC Integrated Inspection Report 05000456/2018004 and 05000457/2018004 |
RS-18-123, Request for Alternative Follow-up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2) | 24 September 2018 | Request for Alternative Follow-up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2) |
ML18067A181 | 4 June 2018 | Correction to Technical Specification Amendment Identification Format |
RS-17-170, Company Emergency Plan Annex and Addendum Revisions | 19 December 2017 | Company Emergency Plan Annex and Addendum Revisions |
ML17073A067 | 26 May 2017 | Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) |
ML16357A534 | 15 December 2016 | Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides |
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides | 15 December 2016 | Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides |
ML16280A402 | 6 October 2016 | License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. |
ML16209A218 | 26 July 2016 | Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. |
RS-16-061, EP-AA-1001, Addendum 3, Revision 1, Emergency Action Levels for Braidwood Station. | 14 March 2016 | EP-AA-1001, Addendum 3, Revision 1, Emergency Action Levels for Braidwood Station. |
ML15336A731 | 27 January 2016 | TS 50456-Bwd-AppsABC |
ML15286A276 | 19 November 2015 | Technical Specifications |
ML15215A771 | 14 September 2015 | Summary of July 27, 2015, Meeting with Exelon Generation Company, LLC, on Request for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds (TAC Nos. MF4809, MF4801, MF4811, and MF |
IR 05000456/2015002 | 4 August 2015 | IR 05000456/20015002; 05000457/2015002, on 04/01/2015 - 06/30/2015, Braidwood Station, Units 1 & 2; Inservice Inspection Activities; Maintenance Effectiveness |
IR 05000457/2015002 | 4 August 2015 | IR 05000456/20015002; 05000457/2015002, on 04/01/2015 - 06/30/2015, Braidwood Station, Units 1 & 2; Inservice Inspection Activities; Maintenance Effectiveness |
IR 05000456/2001500 | 4 August 2015 | IR 05000456/20015002; 05000457/2015002, on 04/01/2015 - 06/30/2015, Braidwood Station, Units 1 & 2; Inservice Inspection Activities; Maintenance Effectiveness |
ML15204A505 | 23 July 2015 | EPRI Tech Basis for Brd-Byr Head RR |
ML15071A119 | 2 March 2015 | Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors |
RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors | 2 March 2015 | Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors |
IR 05000456/2014009 | 7 November 2014 | IR 05000456/2014009; 05000457/2014009; on 09/15/2014 - 11/05/2014; Braidwood Station, Units 1 and 2; License Renewal Inspection |
RS-14-314, Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds in Accordance with 10 CFR 50.55a(a)(3)(i) | 27 October 2014 | Requests for Relief for Alternate Examination Frequency Under ASME Code Case N-729-1 for Reactor Vessel Head Penetration Welds in Accordance with 10 CFR 50.55a(a)(3)(i) |
ML14164A055 | 30 May 2014 | Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Page Bw 3-80 |
RA-14-032, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pa | 30 May 2014 | Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pag |
NEI 99-01, Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pa | 30 May 2014 | Braidwood, Units 1 and 2, Attachment 2, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1001, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 2A, and 2B, Cover Through Pag |
RS-14-080, License Amendment Request for Adoption of Technical Specification Task Force (TSTF)- 513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation. | 18 March 2014 | License Amendment Request for Adoption of Technical Specification Task Force (TSTF)- 513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation. |
RS-14-037, Response to Request for Additional Information Regarding Relief Request I3R-11 Associated with the Repair/Replacement of Control Rod Drive Mechanism (CRDM) Canopy Seal Welds | 24 January 2014 | Response to Request for Additional Information Regarding Relief Request I3R-11 Associated with the Repair/Replacement of Control Rod Drive Mechanism (CRDM) Canopy Seal Welds |
RS-13-234, Relief Request I3R-ll Associated with Alternative Requirements for Repair/Replacement of Control Rod Drive Mechanism (CRDM) Canopy Seal Welds | 19 September 2013 | Relief Request I3R-ll Associated with Alternative Requirements for Repair/Replacement of Control Rod Drive Mechanism (CRDM) Canopy Seal Welds |
ML13016A515 | 30 January 2013 | Relief from the Requirements of the ASME Code for the Third 10-Year Interval of Inservice Inspection |
RS-12-153, Relief Request Associated with the Third 10-Year Inservice Inspection Program Interval | 8 October 2012 | Relief Request Associated with the Third 10-Year Inservice Inspection Program Interval |
IR 05000456/2012002 | 8 May 2012 | IR0 5000456-12-002, 05000457-12-002; Exelon Generation Company, LLC; 01/01/2012 ?03/31/2012; Braidwood Station, Units 1 & 2, Fire Protection, Flood Protection Measures Maintenance Effectiveness, Operability Determinations and Functional Ass |
IR 05000456/2010005 | 8 February 2011 | IR 05000456-10-005, 05000457-10-005, on 10/01/2010 - 12/31/2010; Braidwood Station, Units 1 & 2; Fire Protection; Identification and Resolution of Problems; Followup of Events |
IR 05000456/2010003 | 29 July 2010 | IR 05000456-10-003, 05000457-10-003, on 04/01/2010 - 06/30/2010, Braidwood Station, Units 1 & 2, Follow-Up of Events and Notices of Enforcement Discretion |
RS-10-029, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program | 15 February 2010 | Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program |
ML100330273 | 27 January 2010 | Inservice Inspection Summary Report |