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	Issue date	Title	Topic
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
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position	27 September 2021	Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position	Safe Shutdown Reactor Vessel Water Level Ultimate heat sink Stroke time Water Inventory Control Surveillance Frequency Control Program Operability Determination Control of Heavy Loads Fuel cladding Recently irradiated fuel Scaffolding
L-98-010, Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High)	27 February 2003	Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High)	Scram Discharge Volume Fuel cladding
ML022940296	10 October 2002	Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments E-2 - F-2	Shutdown Margin Reactor Vessel Water Level Stroke time Anticipated operational occurrence Hydrostatic Squib Qualified Offsite Circuit Scram Discharge Volume Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit
ML030080043	20 December 2002	Request for License Amendment Regarding Reactor Vessel Specimen Removal Schedule
ML030080053	20 December 2002	Request for License Amendment Regarding Reactor Vessel Specimen Removal Schedule	Anticipated operational occurrence Hydrostatic Nondestructive Examination
ML093280234	23 November 2009	Request for Approval of the Exelon Cyber Security Plan	Safe Shutdown Fire Barrier Cyber Security Incorporated by reference Safeguards Contingency Plan Fire Protection Program
ML113260348	22 November 2011	Request for Technical Specification Change for Safety Limit Minimum Critical Power Ratio	Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Fuel cladding
ML14164A054	30 May 2014	License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
ML14164A064	30 May 2014	Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76	Safe Shutdown High winds Ultimate heat sink Operating Basis Earthquake Operator Manual Action Spent Fuel Pool Instrumentation Severe Accident Management Guideline Earthquake Fuel cladding Pressure Boundary Leakage Power change
ML14164A065	30 May 2014	Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160	Safe Shutdown High winds Ultimate heat sink Fire Barrier Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action Nuclear Accident Reporting System Severe Accident Management Guideline Earthquake Fuel cladding Pressure Boundary Leakage Power change
ML15055A154	6 February 2015	Dresden, Units 2 & 3, Quad Cities, Units 1 & 2, Request for License Amendment Regarding Transition to Areva Fuel
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
ML16258A150	20 November 2015	Design Analysis QDC-6700-E-2173, Evaluation of Degraded Voltage 5 Minute Timer on Normally Running Safety-Related Loads, Revision 000
ML16258A152	20 November 2015	Design Analysis QDC-6700-E-0939, Loss of Voltage Relay Set Point for Buses 13-1, 14-1, 23-1, and 24-1, Revision 001	Safe Shutdown
ML16280A402	6 October 2016	License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.	Shutdown Margin Reactor Vessel Water Level Packing leak High Radiation Area Stroke time Hydrostatic Squib Surveillance Frequency Control Program Excess Flow Check Valve Power Operated Valves Pressure Boundary Leakage Recently irradiated fuel Power change Unidentified leakage
ML17252A480	10 December 1974	Letter Requesting an Amendment to the Facility Operating Licenses -Dresden Station Units 2 and 3. Purpose of This Change Is to Incorporate Technical Specifications Concerning Surveillance of Snubbers and Primary Coolant and Safeguard System	Earthquake
ML17252B421	23 June 1976	Proposed Amendment to Appendix a Technical Specification to Eliminate Requirement to Inert Containment
ML18053A173	31 January 2018	Attachment 4A - Dresden Marked-up Emergency Plan EP-AA-1000 Pages	Safe Shutdown Fitness for Duty Health Physics Network Nuclear Accident Reporting System Severe Accident Management Guideline Minimum staff
ML18053A174	31 January 2018	Attachment 4B - Dresden Clean Emergency Plan EP-AA-1000 Pages	Nuclear Accident Reporting System Severe Accident Management Guideline Minimum staff
ML18053A177	31 January 2018	Attachment 6A - Quad Cities - Marked-up Emergency Plan EP-AA-1000 Pages	Safe Shutdown Fitness for Duty Health Physics Network Nuclear Accident Reporting System Severe Accident Management Guideline Minimum staff
ML18053A178	31 January 2018	Attachment 6B - Quad Cities Clean Emergency Plan EP-AA-1000 Pages	Nuclear Accident Reporting System Severe Accident Management Guideline Minimum staff
ML18053A183	31 January 2018	Enclosure 4 - Dresden Units 1, 2 & 3 - Evaluation of Proposed Changes	Safe Shutdown Fitness for Duty Cyber Security Severe Accident Management Guideline Fuel cladding Minimum staff
ML18053A185	31 January 2018	Enclosure 6 - Quad Cities - Evaluation of Proposed Changes	Safe Shutdown Fitness for Duty Cyber Security Design basis earthquake Severe Accident Management Guideline Fuel cladding Minimum staff
ML18053A190	31 January 2018	Enclosure 9 - Information Related to Review of Proposed Changes by the State
ML19036A586	21 March 2019	Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements	Health Physics Network Severe Accident Management Guideline Minimum staff Fire Protection Program
ML20323A254	18 November 2020	Markup of Proposed Technical Specifications Bases Pages	Reactor Vessel Water Level Ultimate heat sink Water Inventory Control Qualified Offsite Circuit Surveillance Frequency Control Program Control of Heavy Loads Fuel cladding Recently irradiated fuel Offsite Circuit Scaffolding
ML21057A273	25 February 2021	Application for Order Approving License Transfers and Proposed Conforming License Amendments	Decommissioning Funding Plan
ML21257A420	14 September 2021	Request for Licensing Amendment Regarding Transition to GNF3 Fuel
ML21277A193	16 November 2021	Enclosure 2, Draft Conforming License Amendments	Safe Shutdown Fire Barrier Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Cyber Security Aging Management Annual Radioactive Effluent Release Report Safeguards Contingency Plan Preemption Authority License Renewal Subsequent License Renewal Fuel cladding Liquid penetrant Fire Protection Program Scaffolding Unidentified leakage Power Uprate
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76	30 May 2014	Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76	Safe Shutdown High winds Ultimate heat sink Operating Basis Earthquake Operator Manual Action Spent Fuel Pool Instrumentation Severe Accident Management Guideline Earthquake Fuel cladding Pressure Boundary Leakage Power change
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160	30 May 2014	Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160	Safe Shutdown High winds Ultimate heat sink Fire Barrier Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action Nuclear Accident Reporting System Severe Accident Management Guideline Earthquake Fuel cladding Pressure Boundary Leakage Power change
NEI 99-01, License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.	30 May 2014	License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.	21 April 2008	Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.	Fitness for Duty Offsite Dose Calculation Manual Process Control Program 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
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76	30 May 2014	Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76	Safe Shutdown High winds Ultimate heat sink Operating Basis Earthquake Operator Manual Action Spent Fuel Pool Instrumentation Severe Accident Management Guideline Earthquake Fuel cladding Pressure Boundary Leakage Power change
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160	30 May 2014	Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160	Safe Shutdown High winds Ultimate heat sink Fire Barrier Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action Nuclear Accident Reporting System Severe Accident Management Guideline Earthquake Fuel cladding Pressure Boundary Leakage Power change
RA-14-032, License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.	30 May 2014	License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8	29 August 2014	License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8	Safe Shutdown Cyber Security Safeguards Contingency Plan Fire Protection Program
RS-02-044, Request for Technical Specification Change, Revises Emergency Diesel Generator Required Start Time	1 May 2002	Request for Technical Specification Change, Revises Emergency Diesel Generator Required Start Time	Qualified Offsite Circuit Fuel cladding Offsite Circuit
RS-02-073, Request for Amendment, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit	8 April 2002	Request for Amendment, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit	Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Fuel cladding
RS-02-080, Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation	15 April 2002	Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation	Reactor Vessel Water Level Fuel cladding
RS-02-095, Application for Amendment to License DPR-29 for Quad Cities, Unit 1 Ts. Amendment Would Revise Values of Safety Limit for Minimum Critical Power Ratio (Slmcpr)In TS 2.1.1 for Cycle 18	30 May 2002	Application for Amendment to License DPR-29 for Quad Cities, Unit 1 Ts. Amendment Would Revise Values of Safety Limit for Minimum Critical Power Ratio (Slmcpr)In TS 2.1.1 for Cycle 18
RS-02-152, . Request for Technical Specifications Surveillance Requirement 3.3.4.1.2 Change Related to Anticipated Transient Without Scram- Recirculation Pump Trip Instrumentation	22 August 2002	. Request for Technical Specifications Surveillance Requirement 3.3.4.1.2 Change Related to Anticipated Transient Without Scram- Recirculation Pump Trip Instrumentation	Reactor Vessel Water Level Fuel cladding
RS-02-159, Revision to Technical Specifications Change Request - Clarification of Requirements for Licensed Operator Qualifications & Training	9 September 2002	Revision to Technical Specifications Change Request - Clarification of Requirements for Licensed Operator Qualifications & Training
RS-02-168, Request for License Amendment Related to Heavy Loads Handling	26 September 2002	Request for License Amendment Related to Heavy Loads Handling	Safe Shutdown Design basis earthquake Control of Heavy Loads Affidavit
RS-02-169, Request for License Amendment Related to Appendix B, Environmental Protection Plan (Non-Radiological)	27 September 2002	Request for License Amendment Related to Appendix B, Environmental Protection Plan (Non-Radiological)
RS-02-171, Request for License Amendment Related to Heavy Loads Handling	1 October 2002	Request for License Amendment Related to Heavy Loads Handling	Safe Shutdown Design basis earthquake Earthquake Control of Heavy Loads Affidavit
RS-02-174, Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1	10 October 2002	Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1	Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Stroke time Anticipated operational occurrence Safe Shutdown Earthquake Hydrostatic Squib Qualified Offsite Circuit B.5.b Scram Discharge Volume Excess Flow Check Valve Deep Dose Equivalent Fuel cladding Pressure Boundary Leakage Recently irradiated fuel Offsite Circuit Unidentified leakage Power Uprate Affidavit
RS-02-175, Request for Technical Specification Changes Related to Main Steam Safety Valve Operability Requirements	10 October 2002	Request for Technical Specification Changes Related to Main Steam Safety Valve Operability Requirements

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