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 Issue dateTitleTopic
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
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
RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values20 January 2021Request for License Amendment to Revise Degraded Voltage Relay Allowable ValuesSafe Shutdown
Reactor Vessel Water Level
Anticipated operational occurrence
Surveillance Frequency Control Program
Fuel cladding
Grace period
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
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-20-052, Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Extended Completed Times-RITSTF Initiative 4b30 April 2020Application to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Extended Completed Times-RITSTF Initiative 4bHot Short
Safe Shutdown
High winds
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Anticipated operational occurrence
Tornado Missile
Water Inventory Control
Safe Shutdown Earthquake
Internal Flooding
Hydrostatic
Enforcement Discretion
Probabilistic Risk Assessment
Operating Basis Earthquake
FLEX
Tornado-Generated Missile
Fukushima Dai-Ichi
Seismically rugged
Tornado Missile Protection
Surveillance Frequency Control Program
Scram Discharge Volume
Feedwater Controller Failure
Large early release frequency
TORMIS
Earthquake
Maintenance Rule Program
Fuel cladding
Recently irradiated fuel
Offsite Circuit
Failure to Scram
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-19-054, 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
U-604454, Transmittal of Revision 20 to Technical Specification Bases31 December 2018Transmittal of Revision 20 to Technical Specification BasesSafe Shutdown
Shutdown Margin
Reactor Vessel Water Level
High Radiation Area
Ultimate heat sink
Stroke time
Anticipated operational occurrence
Water Inventory Control
Post Accident Monitoring
Hydrostatic
Operating Basis Earthquake
Qualified Offsite Circuit
Missed surveillance
Surveillance Frequency Control Program
Scram Discharge Volume
Fuel cladding
Recently irradiated fuel
Offsite Circuit
Scaffolding
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
U-604396, Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases22 December 2017Transmittal of Revision 19 to the Clinton Power Station Technical Specification BasesHigh Radiation Area
Hydrostatic
Missed surveillance
Surveillance Frequency Control Program
Recently irradiated fuel
ML17180A12621 June 2017Technical Specification Bases - Affected Page List
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
RS-16-211, License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 14 November 2016License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 1License Renewal
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
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
U-604257, Transmittal of Revision 17 to the Technical Specification Bases21 December 2015Transmittal of Revision 17 to the Technical Specification BasesReactor Vessel Water Level
Stroke time
Hydrostatic
Surveillance Frequency Control Program
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
U-604152, Transmittal of Revision 15 to Technical Specification Bases31 December 2013Transmittal of Revision 15 to Technical Specification Bases
U-604075, Transmittal of Revision 14 to the Technical Specification Bases4 June 2012Transmittal of Revision 14 to the Technical Specification BasesSafe Shutdown
Shutdown Margin
High Radiation Area
Ultimate heat sink
Stroke time
Hydrostatic
Squib
Surveillance Frequency Control Program
Scram Discharge Volume
Feedwater Controller Failure
Battery sizing
Fuel cladding
Recently irradiated fuel
Offsite Circuit
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-11-100, 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
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-11-100, 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
RS-11-073, License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies.13 June 2011License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies.Shutdown Margin
Anticipated operational occurrence
RS-10-050, License Amendment Request to Remove Operating Mode Restrictions for Performing Division 3 AC Sources Surveillance Testing28 October 2010License Amendment Request to Remove Operating Mode Restrictions for Performing Division 3 AC Sources Surveillance Testing
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
U-603987, Transmittal of Revision 13 to Technical Specification Bases1 October 2010Transmittal of Revision 13 to Technical Specification BasesSafe Shutdown
Ultimate heat sink
Stroke time
Scram Discharge Volume
Overtravel
Recently irradiated fuel
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
U-603908, Transmittal of Revision 12 to the Technical Specification Bases4 August 2009Transmittal of Revision 12 to the Technical Specification BasesSafe Shutdown
Scram Discharge Volume
RS-08-111, Supplemental Information Related to Application for Technical Specification Change TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil Using Consolidated Line Item Improvement Process5 September 2008Supplemental Information Related to Application for Technical Specification Change TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil Using Consolidated Line Item Improvement Process
U-603859, Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases23 May 2008Transmittal of Revision 11 to the Clinton Power Station Technical Specification BasesAnticipated operational occurrence
Post Accident Monitoring
Abnormal operational transient
Scram Discharge Volume
Feedwater Controller Failure
Fuel cladding
Recently irradiated fuel
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-07-020, 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
RS-06-151, Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program.16 November 2006Request for Amendment to Technical Specification 3.6.5.1, Drywell and 5.5.13, Primary Containment Leakage Rate Testing Program.Safe Shutdown
High winds
Internal Flooding
Probabilistic Risk Assessment
Coatings
Large early release frequency
Exemption Request
Earthquake
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases16 August 2006Transmittal of Revision 10 to the Clinton Power Station Technical Specifications BasesShutdown Margin
Reactor Vessel Water Level
High Radiation Area
Grab sample
Anticipated operational occurrence
Probabilistic Risk Assessment
Missed surveillance
Scram Discharge Volume
Fuel cladding
Recently irradiated fuel
Offsite Circuit
RS-04-024, Request for Amendment to Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles in Accordance with the Guidance of Generic Letter 91-0420 May 2004Request for Amendment to Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles in Accordance with the Guidance of Generic Letter 91-04
U-603640, Transmittal of Revision 8 to the Technical Specification Bases13 November 2003Transmittal of Revision 8 to the Technical Specification BasesHigh Radiation Area
Anticipated operational occurrence
Hydrostatic
Offsite Circuit
RS-03-069, Supplemental Information Supporting the License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power Operations28 March 2003Supplemental Information Supporting the License Amendment Request to Permit Inclined Fuel Transfer System Blind Flange Removal During Power OperationsSafe Shutdown
Safe Shutdown Earthquake
Hydrostatic
Anchor Darling
Seismically rugged
Earthquake
RS-02-151, Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High)16 August 2002Request for Technical Specifications Changes Related to Reactor Protection System Instrumentation (Scram Discharge Volume Water Level - High)Reactor Vessel Water Level
Scram Discharge Volume