| 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-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 |
| ML21179A050 | 21 June 2021 | Technical Specification Bases | |
| RS-21-036, Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition | 16 March 2021 | Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition | Ultimate heat sink
Abnormal operational transient
Surveillance Frequency Control Program
Recently irradiated fuel |
| 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 |
| 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 |
| 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 |
| 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-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control | 18 June 2019 | Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control | Reactor Vessel Water Level
Stroke time
Water Inventory Control
Surveillance Frequency Control Program
Recently irradiated fuel
Offsite Circuit |
| 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 |
| ML17180A126 | 21 June 2017 | Technical Specification Bases - Affected Page List | |
| RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases - Affected Page List | 21 June 2017 | Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases - Affected Page List | |
| 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 |
| 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-15-297, Request for License Amendment to Dresden Nuclear Power Station Technical Specification 3.8.1, AC Sources - Operating. | 14 December 2015 | Request for License Amendment to Dresden Nuclear Power Station Technical Specification 3.8.1, AC Sources - Operating. | Safe Shutdown
Surveillance Frequency Control Program
Fuel cladding |
| 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 |
| RS-11-100, Updated Final Safety Analysis Report (Ufsar), Revision 9, Affected Page List - Technical Specification Bases, Revision 54 | 29 June 2011 | Updated Final Safety Analysis Report (Ufsar), Revision 9, Affected Page List - Technical Specification Bases, Revision 54 | |
| ML11202A205 | 29 June 2011 | Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases | Safe Shutdown
Unanalyzed Condition
Shutdown Margin
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Stroke time
Anticipated operational occurrence
Post Accident Monitoring
Hydrostatic
Squib
Qualified Offsite Circuit
Missed surveillance
Abnormal operational transient
Scram Discharge Volume
Feedwater Controller Failure
Spiral reload
Overtravel
Fuel cladding
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
Power change
Coast down |
| RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases | 29 June 2011 | Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases | Safe Shutdown
Unanalyzed Condition
Shutdown Margin
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Stroke time
Anticipated operational occurrence
Post Accident Monitoring
Hydrostatic
Squib
Qualified Offsite Circuit
Missed surveillance
Abnormal operational transient
Scram Discharge Volume
Feedwater Controller Failure
Spiral reload
Overtravel
Fuel cladding
Pressure Boundary Leakage
Recently irradiated fuel
Offsite Circuit
Power change
Coast down |
| RS-10-165, Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation | 6 October 2010 | Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation | Reactor Vessel Water Level
Met Tower
Condition Adverse to Quality
Significance Determination Process
Fatality |
| 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-10-024, Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program | 16 February 2010 | Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program | Safe Shutdown
High winds
Shutdown Margin
High Radiation Area
Ultimate heat sink
Mission time
Grab sample
Stroke time
Tornado Missile
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Squib
Incorporated by reference
Surveillance Frequency Control Program
Design basis earthquake
Scram Discharge Volume
Feedwater Controller Failure
Spiral reload
Overtravel
Power Operated Valves
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 |
| 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 |
| 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-07-097, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit | 10 July 2007 | Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit | Shutdown Margin
Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
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 |
| 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 | |
| ML063170083 | 7 November 2006 | Technical Specification, 2.0 Safety Limits | Reactor Vessel Water Level |
| ML060880251 | 17 March 2006 | Technical Specification Pages Regarding Offsite Power Instrumentation and Voltage Control | |
| ML053130192 | 17 October 2005 | Technical Specification Pages Pressure and Temperature Limits | Hydrostatic |
| 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-04-133, Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits. | 4 November 2004 | Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits. | Unanalyzed Condition
Shutdown Margin
Anticipated operational occurrence
Hydrostatic |
| 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 | |
| ML033210419 | 26 November 2003 | Amendment, Reactor Coolant System Pressure and Temperature Limits | Hydrostatic
Finite Element Analysis |
| RS-03-165, Additional Information Supporting the Request for Technical Specifications Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing | 8 August 2003 | Additional Information Supporting the Request for Technical Specifications Surveillance Requirement 3.6.1.3.8 Change Related to Excess Flow Check Valve Testing | |
| RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function | 28 March 2003 | Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function | Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio |
| ML023450570 | 27 November 2002 | Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process | Offsite Dose Calculation Manual
Incorporated by reference
Annual Radioactive Effluent Release Report |
| RS-02-151, Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High) | 16 August 2002 | Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High) | Reactor Vessel Water Level
Scram Discharge Volume |
| ML17037B779 | 7 February 1974 | Letter Regarding Petition for Derating of Certain Boiling Water Reactors and Enclosed Before the Atomic Safety and Licensing Appeal Board in the Matter of Vermont Yankee Nuclear Power Corporation - Vermont Yankee Nuclear ... | |