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 Issue dateTitleTopic
RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days13 December 2023Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 DaysSafe 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 Cooling25 May 2023Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown CoolingHydrostatic
Surveillance Frequency Control Program
RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR3 March 2023Application to Adopt TSTF-564, Safety Limit MCPRReactor 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 Location3 February 2023Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note LocationStroke 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 Penetration3 October 2022Nine 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 PenetrationReactor Vessel Water Level
ML21300A33921 October 2021Revised Technical Specification Bases
ML21179A05021 June 2021Technical 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 Condition16 March 2021Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ConditionUltimate heat sink
Abnormal operational transient
Surveillance Frequency Control Program
Recently irradiated fuel
ML20323A25418 November 2020Markup of Proposed Technical Specifications Bases PagesReactor 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
RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements18 November 2020Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) EnhancementsReactor 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 Operability22 June 2020Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System OperabilityTime of Discovery
RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.31 April 2020Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3Hydrostatic
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 Operability27 June 2019Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System OperabilityFire 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 Controls26 June 2019Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative ControlsHigh 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 Control18 June 2019Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory ControlReactor Vessel Water Level
Stroke time
Water Inventory Control
Surveillance Frequency Control Program
Recently irradiated fuel
Offsite Circuit
RS-19-023, Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.15 March 2019Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.1High 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 Limits5 December 2018Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety LimitsReactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Abnormal operational transient
RS-17-126, Technical Specification Bases19 October 2017Technical Specification Bases
RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases - Affected Page List21 June 2017Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases - Affected Page List
ML17180A12621 June 2017Technical Specification Bases - Affected Page List
RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel28 September 2016Supplement to Request for License Amendment Regarding Transition to Areva FuelPost 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 Frequencies19 September 2016Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test FrequenciesSafe 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
ML16209A21826 July 2016Application 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 2015Request 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 2014License 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 Process14 July 2014Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement ProcessReactor 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 2012License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr).Post Accident Monitoring
RS-11-159, Quad Cities, Units 1 and 2 - Technical Specification Bases19 October 2011Quad Cities, Units 1 and 2 - Technical Specification BasesSafe 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
ML11305A14719 October 2011Technical Specifications Bases Affected Page List
ML11305A13519 October 2011Technical Specification BasesSafe 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 List19 October 2011Quad Cities, Units 1 and 2 - Technical Specifications Bases Affected Page List
RS-11-100, Updated Final Safety Analysis Report (Ufsar), Revision 9, Affected Page List - Technical Specification Bases, Revision 5429 June 2011Updated Final Safety Analysis Report (Ufsar), Revision 9, Affected Page List - Technical Specification Bases, Revision 54
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases29 June 2011Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification BasesSafe 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
ML11202A20529 June 2011Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification BasesSafe 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-11-022, Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit7 June 2011Request for Technical Specification Change for Minimum Critical Power Ratio Safety LimitReactor Vessel Water Level
Anticipated operational occurrence
Minimum Critical Power Ratio
Fuel cladding
RS-10-165, Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation Instrumentation6 October 2010Follow-up Information Supporting Request for License Amendment Regarding Shutdown Cooling System Isolation InstrumentationReactor 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 2010Request 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 2010Application 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-10-024, Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program16 February 2010Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled ProgramSafe 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) System10 November 2009Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) SystemHot 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 Leakage28 August 2009Request for License Amendment to Revise Technical Specification 3.4.5, RCS Leakage Detection Instrumentation, to Allow Alternate Method of Verifying Drywell LeakageGrab 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 3.8.4.59 December 2008Additional Information Supporting Request for License Amendment to Establish Total Battery Connector Resistance Acceptance Criteria in Technical Specifications Surveillance Requirements 3.8.4.2 and 3.8.4.5Safe Shutdown
Battery sizing
ML08239070721 August 2008Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating LicensesFire 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 I9 June 2008Application 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 ImIncorporated by reference
Scram Discharge Volume
Overtravel
ML07354004919 December 2007Letter 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 PagesSafeguards Contingency Plan
Fire Protection Program
RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program8 August 2007Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing ProgramTime of Discovery
Stroke time
Incorporated by reference
Grace period
RS-07-066, Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function1 August 2007Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation FunctionAnticipated operational occurrence
Scram Discharge Volume
Fuel cladding
RS-07-097, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit10 July 2007Request for Technical Specifications Change for Minimum Critical Power Ratio Safety LimitShutdown 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 Process12 April 2007Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement ProcessSafe 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
ML07023054016 January 2007NF-BEX-06-281, Rev 0, Quad Cities, Unit 1 Cycle 20 SLMCPR, NP-AttachementMinimum Critical Power Ratio