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. | 29 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. | Boric Acid Time to boil Aging Management Surveillance Frequency Control Program Fuel cladding Exclusive Use |
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 Process | 7 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 | Probabilistic Risk Assessment Incorporated by reference Surveillance Frequency Control Program |
RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. | 10 August 2022 | R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. | Safe Shutdown Non-Destructive Examination Post Accident Monitoring Internal Flooding Probabilistic Risk Assessment Nondestructive Examination Cyber Security Pressure and Temperature Limits Report Surveillance Frequency Control Program Fire Protection Program |
ML22145A586 | 3 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 Sink | 2 June 2022 | License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink | Safe Shutdown Ultimate heat sink Anticipated operational occurrence Safe Shutdown Earthquake Surveillance Frequency Control Program |
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 Control | 21 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 | Safe Shutdown Surveillance Frequency Control Program |
RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin | 24 January 2022 | Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin | Shutdown Margin Anticipated operational occurrence Post Accident Monitoring Hydrostatic Coatings Pressure and Temperature Limits Report Process Control Program Power change |
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 NRC | 13 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 | |
ML21008A417 | 17 December 2020 | Technical Specification Bases | Safe Shutdown Unanalyzed Condition Boric Acid Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Non-Destructive Examination Grab sample Fire Barrier Stroke time Anticipated operational occurrence Tornado Missile Post Accident Monitoring Internal Flooding Hydrostatic Probabilistic Risk Assessment Missed surveillance Surveillance Frequency Control Program Battery sizing Power Operated Valves Turbine Missile Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit Power change Unidentified leakage |
RS-20-068, Application to Revise Technical Specifications 3.8.1, AC Sources-Operating | 26 June 2020 | Application to Revise Technical Specifications 3.8.1, AC Sources-Operating | Safe Shutdown Stroke time Anticipated operational occurrence Surveillance Frequency Control Program Offsite Circuit |
JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | 22 June 2020 | Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | Time of Discovery |
RS-20-044, Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections | 6 April 2020 | Emergency License Amendment Request for a One-Time Extension of the Steam Generator Tube Inspections | Non-Destructive Examination Anticipated operational occurrence Pandemic COVID-19 |
ML20063L282 | 28 February 2020 | Application of Westinghouse Full Spectrum LOCA Evaluation Model | Loop seal Coatings Fuel cladding |
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) | 28 February 2020 | Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) | Boric Acid Shutdown Margin Reactor Vessel Water Level Surveillance Frequency Control Program |
JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | 27 June 2019 | Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability | Fire Barrier Tornado Missile Internal Flooding Incorporated by reference Turbine Missile |
RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls | 26 June 2019 | Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls | High Radiation Area Locked High Radiation Area Process Control Program Deep Dose Equivalent |
ML16357A532 | 15 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 Bases | 15 December 2016 | Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases | |
ML16357A580 | 15 December 2016 | Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases | |
ML16357A579 | 15 December 2016 | Braidwood 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 Specifications | 15 December 2016 | Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications | |
RS-16-248, Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases | 15 December 2016 | Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases | |
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. | Shutdown Margin Reactor Vessel Water Level Packing leak High Radiation Area Stroke time Hydrostatic Squib Incorporated by reference Missed surveillance Surveillance Frequency Control Program Excess Flow Check Valve Power Operated Valves Pressure Boundary Leakage Recently irradiated fuel Power change Unidentified leakage |
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 Sink | 31 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 | Boric Acid 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 Process | 14 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 | Reactor Vessel Water Level Ultimate heat sink Stroke time Hydrostatic Surveillance Frequency Control Program Power Operated Valves |
RS-13-175, Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). | 21 August 2013 | Bryon, Units 1 and 2, License Amendment Request to Revise Technical Specifications Section 3.7.2, Main Steam Isolation Valves (Msivs). | Safe Shutdown Earthquake Earthquake |
RS-12-223, License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation. | 21 December 2012 | License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation. | Offsite Dose Calculation Manual Surveillance Frequency Control Program Recently irradiated fuel Power change |
RS-12-221, Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases | 14 December 2012 | Braidwood, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases | Shutdown Margin Ultimate heat sink Anticipated operational occurrence Post Accident Monitoring Missed surveillance Fuel cladding Offsite Circuit |
ML13004A069 | 14 December 2012 | Updated Final Safety Analysis Report, Revision 14, Technical Specifications Bases | Shutdown Margin Ultimate heat sink Anticipated operational occurrence Post Accident Monitoring Missed surveillance Fuel cladding Offsite Circuit |
RS-12-028, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. | 22 March 2012 | Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. | Non-Destructive Examination Nondestructive Examination |
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 Criteria | 20 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 | Safe Shutdown Earthquake Nondestructive Examination |
ML111790033 | 23 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 | Shutdown Margin Process Control Program |
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 | Safe Shutdown Boric Acid High winds Shutdown Margin High Radiation Area Ultimate heat sink Stroke time Hydrostatic Probabilistic Risk Assessment Incorporated by reference Surveillance Frequency Control Program Power Operated Valves Turbine Missile Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit Power change Unidentified leakage |
RS-09-071, Units 1 and 2 - License Amendment Request to Revise Technical Specifications (TS) for Permanent Alternate Repair Criteria | 24 June 2009 | Units 1 and 2 - License Amendment Request to Revise Technical Specifications (TS) for Permanent Alternate Repair Criteria | Safe Shutdown Earthquake Nondestructive Examination |
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases | 15 December 2008 | Braidwood, Units 1 and 2 - Technical Specification Bases | Safe Shutdown Unanalyzed Condition Boric Acid Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Non-Destructive Examination Grab sample Offsite Dose Calculation Manual Stroke time Anticipated operational occurrence Post Accident Monitoring Hydrostatic Probabilistic Risk Assessment Missed surveillance Battery sizing Power Operated Valves Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit Power change Unidentified leakage |
ML090270474 | 15 December 2008 | Technical Specification Bases | Safe Shutdown Unanalyzed Condition Boric Acid Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Non-Destructive Examination Grab sample Offsite Dose Calculation Manual Stroke time Anticipated operational occurrence Post Accident Monitoring Hydrostatic Probabilistic Risk Assessment Missed surveillance Battery sizing Power Operated Valves Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit Power change Unidentified leakage |
ML082390707 | 21 August 2008 | Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses | Fire Protection Program |
ML073540049 | 19 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 | Safeguards Contingency Plan Fire Protection Program |
RS-07-132, Stations, Units 1 and 2 - Application for Steam Generator Tube Alternate Repair Criteria Technical Specification Amendment | 29 November 2007 | Stations, Units 1 and 2 - Application for Steam Generator Tube Alternate Repair Criteria Technical Specification Amendment | Nondestructive Examination Finite Element Analysis Liquid penetrant Through-Wall Leak |
RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program | 8 August 2007 | Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program | Time of Discovery Stroke time Incorporated by reference Grace period |
RS-07-087, Request for License Amendment Related to Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. | 31 July 2007 | Request for License Amendment Related to Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. | Offsite Dose Calculation Manual |
RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process | 12 April 2007 | Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process | Safe Shutdown Offsite Dose Calculation Manual Probabilistic Risk Assessment Incorporated by reference Annual Radioactive Effluent Release Report Surveillance Frequency Control Program Process Control Program Recently irradiated fuel Fire Protection Program |
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 Report | 15 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 | |
ML063340487 | 27 November 2006 | Tech Spec Pages for Amendments 148 & 142 Regarding Reactor Coolant System Pressure and Temperature Limits Report | Post Accident Monitoring Hydrostatic Pressure and Temperature Limits Report Recently irradiated fuel |
RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program | 29 November 2004 | Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program | Safe Shutdown Unanalyzed Condition |
RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | 30 April 2004 | Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process | |
ML040620068 | 18 March 2004 | Technical Specifications Pages, Amendment No. 130 | |
ML021280298 | 30 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 | Time of Discovery Missed surveillance |
RS-02-045, Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles | 19 April 2002 | Request for License Amendment for Technical Specifications Surveillance Requirement for Containment Spray Nozzles | Foreign Material Exclusion |
ML021130263 | 19 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 | |