Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation 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 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification 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)) ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report 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 ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference ML23321A0442023-11-17017 November 2023 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 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information 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 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-118, 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 IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 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 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals 2024-02-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23191A0592023-07-21021 July 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML22364A0242023-03-0101 March 2023 R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246 ML23005A1762023-02-23023 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes ML23005A1222023-02-22022 February 2023 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2 ML22305A6992022-12-28028 December 2022 Issuance of Amendment Nos. 231 and 231 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22210A0312022-08-30030 August 2022 Issuance of Amendments Nos. 230, 230, 230, and 230, Respectively, Regarding Adoption of Technical Specifications Task Force Traveler (TSTF) 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22173A1812022-08-11011 August 2022 Issuance of Amendment No. 229 to Remove License Condition ML22173A2142022-08-10010 August 2022 Issuance of Amendments Nos. 228 and 228 Revision of Technical Specifications for the Ultimate Heat Sink ML22094A1072022-06-22022 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 151 Adopt 10 CFR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22119A0942022-06-21021 June 2022 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 150 Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents ML22115A2122022-05-12012 May 2022 Summary of April 11, 2022, Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding a Future Amendment to Place One High Burnup Lead Test Assembly Into the Byron, Unit 2, Reactor ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22098A0512022-04-11011 April 2022 2 Cycle 25 High Burnup Lead Test Assembly NRC Pre-Submittal Meeting on April 22, 2022 (EPID L-2022-LRM-0022) (Slides) ML22026A4892022-03-22022 March 2022 Issuance of Amendment Nos. 225, 225, 227, 227, and 148, Respectively, Regarding Issues Identified in Westinghouse Documents (EPID L-2021-LLA-0066) Nonproprietary ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21175A0012021-07-27027 July 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 145 Regarding Technical Specifications Change to Make a One-Time Exception to the Steam Generator Tube Inspection Requirements ML21154A0462021-07-13013 July 2021 Issuance of Amendments Nos. 222 and 222 Revision of Technical Specifications for the Ultimate Heat Sink ML21090A0152021-04-0707 April 2021 Correction to Amendment Nos. 219 and 219 Regarding Revision of Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML21060B2812021-04-0202 April 2021 Issuance of Amendments Nos. 221, 221, 224, and 224 Regarding Technical Specifications 3.8.1, AC Sources-Operating ML20353A1262021-03-11011 March 2021 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 144 Implementation of WCAP-14333 and WCAP-15376, TSTF-411-A, and TSTF-418-A to Revise Reactor Trip and Engineered Safety Feature Actuation System Instrumentation ML21054A0082021-03-10010 March 2021 Issuance of Amendment Nos. 220 and 220 One-Time Deferral of Steam Generator Tube Inspections ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20317A0012020-12-28028 December 2020 Non-Proprietary, Issuance of Amendment Nos. 219, 219, 223, and 223, Revise Loss-of-Coolant Accident Methodology in TS 5.6.5, Core Operating Limits Report (COLR) ML20245E4192020-09-24024 September 2020 Issuance of Amendments Nos. 218 and 218 Revision of Technical Specifications for the Ultimate Heat Sink ML20246G8652020-09-21021 September 2020 Issuance of Amendment Nos. 222 and 222 One-Time Extension of Unit No. 2 Steam Generator Inspections (COVID-19) ML20163A0462020-09-18018 September 2020 Issuance of Amendments Nos. 217, 217, 221, and 221, Revise Technical Specification 5.6.6 to Allow Use of Areva Np Topical Report BAW-2308 ML20167A0072020-09-11011 September 2020 R. E. Ginna - Issuance of Amendment Nos. 216, 216, 220, 220, and 143 - Adoption of TSTF-567, Rev. 1, Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20149K6982020-09-10010 September 2020 Issuance of Amendment Nos. 215, 215, 219, and 219 Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20118C4292020-06-0909 June 2020 Issuance of Amendments Revision of Technical Specifications for the Ultimate Heat Sink ML20111A0002020-05-0101 May 2020 Issuance of Amendment No. 209, Revision Technical Specification 5.5.9, Steam Generator (SG) Program, for One-Time Revision to Frequency of SG Tube Inspections (Exigent Circumstances) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20057E0912020-04-0303 April 2020 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 139 Add a One-Time Note for Use of Alternative Residual Heat Removal Method ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19325D8242019-12-23023 December 2019 R. E. Ginna Nuclear Power Plant Issuance of Amendment No. 136 to Revise Technical Specification 5.5.15, Containment Leakage Rate Testing Program, to Extend Containment Integrated Leak Rate Test Frequency ML19252A2462019-10-29029 October 2019 R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 134 to Revise the Emergency Response Organization Staffing Requirements 2023-09-01
[Table view] Category:Technical Specification
MONTHYEARRS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin RS-21-082, Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC2021-08-13013 August 2021 Attachment 2 - Technical Basis for NSAL-09-5 Revision 1 and Applicability to Byron, Braidwood, and R.E. Ginna Non-Proprietary Version for NRC ML21008A4132020-12-17017 December 2020 Technical Specification Bases ML21008A4172020-12-17017 December 2020 Technical Specification Bases ML20339A2212020-11-20020 November 2020 Technical Specifications Bases, Rev 101 ML20303A3262020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 3 of 5 ML20303A3252020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 2 of 5 ML20303A3272020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 4 of 5 ML20303A3232020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 1 of 5 RS-20-129, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 52020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 5 RS-20-114, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2020-09-24024 September 2020 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating2020-06-26026 June 2020 Application to Revise Technical Specifications 3.8.1, AC Sources-Operating JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections2020-04-0606 April 2020 Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections ML20063L2822020-02-28028 February 2020 Application of Westinghouse Full Spectrum LOCA Evaluation Model RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2020-02-28028 February 2020 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML19150A5112019-05-10010 May 2019 Revision 90 to Technical Specification Bases ML18176A3272018-06-25025 June 2018 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements ML16357A5322016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML16357A5792016-12-15015 December 2016 Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases ML16357A5802016-12-15015 December 2016 Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications2016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases2016-12-15015 December 2016 Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases RS-16-248, Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases2016-12-15015 December 2016 Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases ML16209A2182016-07-26026 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. ML16168A2612016-06-16016 June 2016 Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... ML15166A0752015-06-0404 June 2015 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3) RS-15-091, Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2015-03-31031 March 2015 Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-14-192, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs).2013-08-21021 August 2013 Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). RS-12-223, License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation.2012-12-21021 December 2012 License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation. RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases2012-12-14014 December 2012 Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases2012-12-14014 December 2012 Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases ML13004A0692012-12-14014 December 2012 Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases ML1212904852012-04-20020 April 2012 LAR File for Rod Indication/Attachment 1 Mrpi LAR RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2012-03-22022 March 2012 Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. RS-12-023, License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria2012-03-20020 March 2012 License Amendment Request to Revise Tech Specs Sections 5.5.9, Steam Generator (SG) Program, and TS 5.6.9, Steam Generator (SG) Tube Inspection Report, for Permanent Alternate Repair Criteria ML1117900332011-06-23023 June 2011 Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate, Attachment 3A, Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages ML1117900352011-06-23023 June 2011 Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate, Attachment 3B, Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages 2023-09-29
[Table view] Category:Amendment
MONTHYEARRS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. ML22145A5862022-06-0303 June 2022 R. E. Ginna Correction to Pages Issued for Amendments Nos. 225, 225, 227, 227, & 148, Respectively, Regarding Issues Identified in Westinghouse Documents RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML22118B1432022-04-28028 April 2022 Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML20303A3252020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 2 of 5 ML20303A3272020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 4 of 5 ML20303A3262020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 3 of 5 ML20303A3232020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 1 of 5 RS-20-129, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 52020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition, Part 5 of 5 RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating2020-06-26026 June 2020 Application to Revise Technical Specifications 3.8.1, AC Sources-Operating JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls ML18176A3272018-06-25025 June 2018 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements ML16168A2612016-06-16016 June 2016 Supplement No. 2 to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Rev. 3).... RS-15-091, Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2015-03-31031 March 2015 Response to Request for Additional Information Regarding Request for a License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink ML14191A2552014-07-10010 July 2014 Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process RS-09-071, Units 1 and 2 - License Amendment Request to Revise Technical Specifications (TS) for Permanent Alternate Repair Criteria2009-06-24024 June 2009 Units 1 and 2 - License Amendment Request to Revise Technical Specifications (TS) for Permanent Alternate Repair Criteria ML0908901912009-03-23023 March 2009 R. E. Ginna - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions for TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0835308062009-02-23023 February 2009 R. E. Ginna Nuclear Power Plant - Amendment Re Revised Methodology for Determining Reactor Coolant System Pressure and Temperature and Low Temperature Over-Pressure Limits ML0834600512008-12-0404 December 2008 R. E. Ginna Nuclear Power Plant - License Amendment Request: Revision of Tech Spec. 3.9.3 to Allow Refueling Operations Inside Containment with Both Personnel Hatch Air Lock Doors Open Under Administrative Control, and Obtain Regulatory Rev ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0735400492007-12-19019 December 2007 Letter to C. Pardee Correction of Administrative Error in Amendment - the Consistency of TSs to Exelon Generation Company Quality Assurance TR (Tac. MD3937 Thru MD3940 and MD3943 Thru MD3948). - Rplacement Pages RS-07-132, Stations, Units 1 and 2 - Application for Steam Generator Tube Alternate Repair Criteria Technical Specification Amendment2007-11-29029 November 2007 Stations, Units 1 and 2 - Application for Steam Generator Tube Alternate Repair Criteria Technical Specification Amendment ML0723504322007-08-16016 August 2007 R. E. Ginna - Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process RS-07-087, Request for License Amendment Related to Technical Specification 5.5.2, Primary Coolant Sources Outside Containment.2007-07-31031 July 2007 Request for License Amendment Related to Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. RS-06-181, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report2006-12-15015 December 2006 Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report ML0633404872006-11-27027 November 2006 Tech Spec Pages for Amendments 148 & 142 Regarding Reactor Coolant System Pressure and Temperature Limits Report ML0604802442006-02-15015 February 2006 Technical Specification Pages Re Relaxed Axial Offset Control ML0534702012005-12-0808 December 2005 R. E. Ginna Nuclear Power Plant, 5.5.1 Offsite Dose Calculation Manual (ODCM) ML0519501232005-07-0707 July 2005 License Amendment Request Regarding Extended Power Uprate ML0507603812005-03-10010 March 2005 R. E. Ginna - Application for Amendment to Facility Operating License Proposed License Amendment to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension ML0506203062005-03-0101 March 2005 R. E. Ginna, Tech Spec Pages for Amendment 88 Regarding Increased Flexibility in Mode Restraints RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program ML0426800472004-09-22022 September 2004 Tech Spec for R. E. Ginna Nuclear Power Plant, Issuance of Amendment Revision to Core Safety Limits and Safety System Instrumentation Setpoints RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-04-30030 April 2004 Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML0406200622004-03-18018 March 2004 Technical Specifications Pages, Amendment #136 ML0406200682004-03-18018 March 2004 Technical Specifications Pages, Amendment No. 130 ML0402307292004-01-22022 January 2004 R. E. Ginna Nuclear Power Plant, Revised Technical Specification Pages 3.1.3-1, 3.1.3-2, 3.3.6-1, 3.3.6-2, 3.3.6-3, Attachments 1 and 2 ML0326913152003-09-22022 September 2003 Amended TS Pages Re the Surveillance Frequency of the Containment Spray System Nozzles from 10 Years to Following Maintenance Which Could Result in Nozzle Blockage, or Following Fluid Flow Through the Nozzles ML0212802982002-04-30030 April 2002 Byron/Braidwood, Units 1 and 2, Tech. Spec. Pages for Amendment Nos. 128 and 123 - Review Surveillance Requirement 3.0.3 to Extend the Delay Period, Before Entering a Limiting Condition for Operation Following a Missed Surveillance RS-02-045, Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles2002-04-19019 April 2002 Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles ML0211302632002-04-19019 April 2002 Units 1 & 2, Technical Specification Pages for License Amendment Nos. 127 & 122, Will Revise the Reactor Core Safety Limit for Peak Fuel Centerline Temperature RS-02-028, Request for License Amendment for Technical Specifications - DC Electrical Power Systems2002-03-0808 March 2002 Request for License Amendment for Technical Specifications - DC Electrical Power Systems ML18142B9481977-12-22022 December 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18142B9501977-11-21021 November 1977 R. E. Ginna - Letter Transmitting 3 Signed Originals and 19 Copies of Document Entitled, Application for Amendment to Operating License. ML18143A2121977-01-0606 January 1977 R. E. Ginna - Forwards Copies of Application for Amendment to Operating License 2023-09-29
[Table view] |