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	Issue date	Title	Topic
RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days	13 December 2023	Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days	Safe Shutdown Arc flash FLEX Missed surveillance Surveillance Frequency Control Program Offsite Circuit
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling	25 May 2023	Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling	Hydrostatic Surveillance Frequency Control Program
RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR	3 March 2023	Application to Adopt TSTF-564, Safety Limit MCPR	Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Annual Radiological Environmental Operating Report Process Control Program Fuel cladding
RS-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location	3 February 2023	Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location	Stroke time Water Inventory Control Surveillance Frequency Control Program
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration	3 October 2022	Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration	Reactor Vessel Water Level
ML21300A339	21 October 2021	Revised Technical Specification Bases
RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements	18 November 2020	Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements	Reactor Vessel Water Level Water Inventory Control Surveillance Frequency Control Program Fuel cladding Recently irradiated fuel Offsite Circuit Scaffolding
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-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3	1 April 2020	Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3	Hydrostatic Squib 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
RS-19-023, Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.1	5 March 2019	Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.1	High winds Safe Shutdown Earthquake Hydrostatic Squib Surveillance Frequency Control Program Power Operated Valves Recently irradiated fuel
RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits	5 December 2018	Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits	Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Abnormal operational transient
RS-17-126, Technical Specification Bases	19 October 2017	Technical Specification Bases
RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel	28 September 2016	Supplement to Request for License Amendment Regarding Transition to Areva Fuel	Post Accident Monitoring Surveillance Frequency Control Program
RS-16-187, Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies	19 September 2016	Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies	Safe Shutdown High winds Mission time Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Nondestructive Examination VT-2 Aging Management Fukushima Dai-Ichi Surveillance Frequency Control Program Large early release frequency Moisture barrier Scaffolding
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-14-322, License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of.	22 December 2014	License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of.	Safe Shutdown Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Hydrostatic Incorporated by reference
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-12-036, License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr).	3 April 2012	License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr).	Post Accident Monitoring
ML11305A147	19 October 2011	Technical Specifications Bases Affected Page List
ML11305A135	19 October 2011	Technical Specification Bases	Safe Shutdown Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Anticipated operational occurrence Post Accident Monitoring Qualified Offsite Circuit Missed surveillance Scram Discharge Volume Fuel cladding Recently irradiated fuel Offsite Circuit
RS-11-159, Quad Cities, Units 1 and 2 - Technical Specifications Bases Affected Page List	19 October 2011	Quad Cities, Units 1 and 2 - Technical Specifications Bases Affected Page List
RS-11-159, Quad Cities, Units 1 and 2 - Technical Specification Bases	19 October 2011	Quad Cities, Units 1 and 2 - Technical Specification Bases	Safe Shutdown Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Anticipated operational occurrence Post Accident Monitoring Qualified Offsite Circuit Missed surveillance Scram Discharge Volume Fuel cladding Recently irradiated fuel Offsite Circuit
RS-11-022, Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit	7 June 2011	Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit	Reactor Vessel Water Level Anticipated operational occurrence Minimum Critical Power Ratio Fuel cladding
RS-10-028, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.	3 March 2010	Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.	Hot Short Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level Anticipated operational occurrence Internal Flooding Enforcement Discretion Probabilistic Risk Assessment Multiple Spurious Operation Scram Discharge Volume Large early release frequency Earthquake Maintenance Rule Program Turbine Missile Fuel cladding Power change
RS-10-032, 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, Revision 3)	16 February 2010	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, Revision 3)	Safe Shutdown High winds Shutdown Margin High Radiation Area Ultimate heat sink Mission time Grab sample Stroke time Post Accident Monitoring Hydrostatic Probabilistic Risk Assessment Squib Incorporated by reference Surveillance Frequency Control Program Scram Discharge Volume Feedwater Controller Failure Spiral reload Battery sizing Overtravel Power Operated Valves Turbine Missile Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit
RS-09-152, Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System	10 November 2009	Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System	Hot Short Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level Mission time Stroke time Internal Flooding Enforcement Discretion Probabilistic Risk Assessment Design basis earthquake Scram Discharge Volume Large early release frequency Earthquake Maintenance Rule Program Turbine Missile Fuel cladding Power change
RS-09-104, Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage	28 August 2009	Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell Leakage	Grab sample Enforcement Discretion Pressure Boundary Leakage Unidentified leakage
RS-08-155, Additional Information Supporting Request for License Amendment to Establish Total Battery Connector Resistance Acceptance Criteria in Technical Specifications Surveillance Requirements 3.8.4.2 and 3.8.4.5	9 December 2008	Additional Information Supporting Request for License Amendment to Establish Total Battery Connector Resistance Acceptance Criteria in Technical Specifications Surveillance Requirements 3.8.4.2 and 3.8.4.5	Safe Shutdown Battery sizing
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
RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I	9 June 2008	Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im	Incorporated by reference Scram Discharge Volume Overtravel
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-07-044, 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-07-066, Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function	1 August 2007	Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function	Anticipated operational occurrence Scram Discharge Volume Fuel cladding
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
ML070230540	16 January 2007	NF-BEX-06-281, Rev 0, Quad Cities, Unit 1 Cycle 20 SLMCPR, NP-Attachement	Minimum Critical Power Ratio
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
RS-06-147, Quad, Units 1 & 2 - Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment	7 November 2006	Quad, Units 1 & 2 - Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment	Safe Shutdown Shutdown Margin Stroke time Feedwater Controller Failure Power change Power Uprate Affidavit
ML061310396	10 May 2006	Correction of Typographical Errors in Issuance of Amendments Dated March 9, 2006