ML13217A093: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 14: | Line 14: | ||
| page count = 184 | | page count = 184 | ||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:}} | |||
Revision as of 16:27, 4 July 2018
| ML13217A093 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/29/2013 |
| From: | Kearney F A Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 1.10.0101, BYRON 2013-0100 | |
| Download: ML13217A093 (184) | |
Similar Documents at Byron | |
|---|---|
Category:Inservice/Preservice Inspection and Test Report
MONTHYEARBYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023
[Table view]Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) 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 ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) BYRON 2023-0002, Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-04-0606 April 2023 Unit 2, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements BYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)2022-07-15015 July 2022 Day Inservice Inspection Report for Interval 4, Period 2, (B2R23) ML21355A4072021-12-21021 December 2021 Day Inservice Inspection Report for Interval 4, Period 2, (81 R24) BYRON 2021-0001, Day Inservice Inspection Report for Interval 4, Period 2, (B2R22)2021-01-13013 January 2021 Day Inservice Inspection Report for Interval 4, Period 2, (B2R22) ML20240A1422020-09-17017 September 2020 Day Inservice Inspection Report for Interval 4, Period 2, (B1R23) BYRON 2020-0053, Steam Generator Tube Inspection Report for Refueling Outage 232020-09-10010 September 2020 Steam Generator Tube Inspection Report for Refueling Outage 23 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 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-8792019-10-16016 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 ML19192A0492019-07-11011 July 2019 Day Inservice Inspection Report for Interval 4, Period 1, (B2R21) 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 BYRON 2018-0130, Transmittal of 90-Day Lnservice Inspection Report for Interval 4, Period 1, (B1R22)2018-12-20020 December 2018 Transmittal of 90-Day Lnservice Inspection Report for Interval 4, Period 1, (B1R22) BYRON 2018-0027, Steam Generator Tube Inspection Report for Refueling Outage 202018-04-0505 April 2018 Steam Generator Tube Inspection Report for Refueling Outage 20 BYRON 2018-0002, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (B2R20)2018-01-18018 January 2018 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (B2R20) RS-17-163, Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval2017-11-20020 November 2017 Withdrawal of Relief Request RV-2 Associated with the Fourth Inservice Testing Interval BYRON 2017-0048, Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (BYR21)2017-06-15015 June 2017 Day Inservice Inspection Report for Interval 3, Period 3 and Interval 4, Period 1, (BYR21) RS-16-224, Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval2016-11-0808 November 2016 Relief Request for Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval ML16300A0362016-10-26026 October 2016 Fourth Ten-Year Interval Inservice Inspection Program BYRON 2016-0076, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R19)2016-08-11011 August 2016 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R19) ML16203A1082016-07-21021 July 2016 Fourth Ten-Year Interval Inservice Testing Program BYRON 2016-0011, Steam Generator Tube Inspection Report for Refueling Outage 202016-02-0505 February 2016 Steam Generator Tube Inspection Report for Refueling Outage 20 BYRON 2015-0152, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 4, (B1R20)2015-12-29029 December 2015 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 4, (B1R20) ML15216A6092015-08-20020 August 2015 Review of Fall 2014 Steam Generator Tube Inservice Inspection Report RS-15-170, Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval2015-06-22022 June 2015 Submittal of Relief Requests Associated with the Fourth Inservice Testing Interval 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 BYRON 2015-0009, 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R18)2015-01-21021 January 2015 90-Day Inservice Inspection Report for Interval 3, Period 3, (B2R18) 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 BYRON 2014-0078, Day Inservice Inspection Report for Interval 3, Period 3, (B1R19)2014-06-24024 June 2014 Day Inservice Inspection Report for Interval 3, Period 3, (B1R19) BYRON 2013-0100, Day Inservice Inspection Report for Interval 3, Period 3, (B2R17)2013-07-29029 July 2013 Day Inservice Inspection Report for Interval 3, Period 3, (B2R17) ML13008A0772013-01-0303 January 2013 Inservice Inspection Summary Report, for Inspection Activities from April 24, 2011 to October 8, 2012 ML13008A0932013-01-0303 January 2013 Inservice Inspection Summary Report, Chapter 6.0, Containment ISI Program, Part 7 of 7-08X ML13008A0752013-01-0303 January 2013 Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XI ML13008A0732013-01-0303 January 2013 Inservice Inspection Summary Report, Form NIS-2 Owner'S Report for Repair/Replacement Activity, as Required by the Provisions of the ASME Code Section XI ML13008A0882013-01-0303 January 2013 Inservice Inspection Summary Report, Form NIS-1 Owner'S Report for Inservice Inspections, Part 4 of 7-05 ML13008A0802013-01-0202 January 2013 Inservice Inspection Summary Report, Weld/Component Outage Summary, Part 2 of 7-03 ML13008A0762013-01-0202 January 2013 Inservice Inspection Summary Report, Common-3rd Interval ASME Section XI Examination Status Report ML1129907832012-02-0101 February 2012 Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations BYRON 2012-0001, Steam Generator Inservice Inspection Summary Report for Refueling Outage 162012-01-0404 January 2012 Steam Generator Inservice Inspection Summary Report for Refueling Outage 16 BYRON 2011-0103, Day Inservice Inspection Report for Interval 3, Period 2, (B1R17)2011-07-21021 July 2011 Day Inservice Inspection Report for Interval 3, Period 2, (B1R17) 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 ML1110105352011-04-0808 April 2011 Supplement to Byron Unit 1, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations RS-11-045, Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations2011-03-24024 March 2011 Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations BYRON 2010-0042, Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15)2010-08-0303 August 2010 Submittal of 90-Day Inservice Inspection Report for Interval 3, Period 2, (B2R15) BYRON 2010-0041, Steam Generator - Inservice Inspection Summary Report for Refueling Outage 152010-07-23023 July 2010 Steam Generator - Inservice Inspection Summary Report for Refueling Outage 15 ML1000503572010-01-0505 January 2010 90-Day Inservice Inspection Report for Interval 3, Period 1, (B1R16) ML1000503622009-12-17017 December 2009 B1R16 Lsi Outage Report - Form NIS-1 Owner'S Report for Inservice Inspections ML1000503602009-12-17017 December 2009 B1R16 Lsi Outage Report, Bolts, Pumps, and Valves Outage Summary ML0902600752009-01-22022 January 2009 Inservice Inspection Report for Interval 3, Period 1, (B2R14), Cover Through Section 2.0 2023-06-08 Category:Letter MONTHYEARML24222A6772024-08-0909 August 2024
[Table view]Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000454/20240112024-08-0808 August 2024 Phase 2 Post- Approval License Renewal Report 05000454/2024011 IR 05000454/20240022024-07-26026 July 2024 Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller ML24170A7652024-06-19019 June 2024 Confirmation of Initial License Examination RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation IR 05000454/20240012024-05-10010 May 2024 Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001 BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24116A1192024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors IR 05000454/20244012024-04-0303 April 2024 Cyber Security Inspection Report 05000454/2024401 and 05000455/2024401 (Public) RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles 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 ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 2024-08-09 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML13217A093&oldid=802629"