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-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values | 20 January 2021 | Request for License Amendment to Revise Degraded Voltage Relay Allowable Values | Safe 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) 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 |
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 4b | 30 April 2020 | 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 4b | Hot 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 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 |
U-604454, Transmittal of Revision 20 to Technical Specification Bases | 31 December 2018 | Transmittal of Revision 20 to Technical Specification Bases | Safe 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 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 |
U-604396, Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases | 22 December 2017 | Transmittal of Revision 19 to the Clinton Power Station Technical Specification Bases | High Radiation Area Hydrostatic Missed surveillance Surveillance Frequency Control Program Recently irradiated fuel |
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 | |
ML17180A126 | 21 June 2017 | 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 1 | 4 November 2016 | License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 1 | License Renewal |
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 |
U-604257, Transmittal of Revision 17 to the Technical Specification Bases | 21 December 2015 | Transmittal of Revision 17 to the Technical Specification Bases | Reactor Vessel Water Level Stroke time Hydrostatic Surveillance Frequency Control Program |
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 |
U-604152, Transmittal of Revision 15 to Technical Specification Bases | 31 December 2013 | Transmittal of Revision 15 to Technical Specification Bases | |
U-604075, Transmittal of Revision 14 to the Technical Specification Bases | 4 June 2012 | Transmittal of Revision 14 to the Technical Specification Bases | Safe 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 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-11-073, License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies. | 13 June 2011 | License 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 Testing | 28 October 2010 | License 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 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 |
U-603987, Transmittal of Revision 13 to Technical Specification Bases | 1 October 2010 | Transmittal of Revision 13 to Technical Specification Bases | Safe Shutdown Ultimate heat sink Stroke time Scram Discharge Volume Overtravel Recently irradiated fuel |
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-10-008, 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) | 15 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 Stroke time Internal Flooding Hydrostatic Probabilistic Risk Assessment Squib Multiple Spurious Operation Incorporated by reference Surveillance Frequency Control Program Scram Discharge Volume Large early release frequency Spiral reload Battery sizing Overtravel 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 |
U-603908, Transmittal of Revision 12 to the Technical Specification Bases | 4 August 2009 | Transmittal of Revision 12 to the Technical Specification Bases | Safe Shutdown Scram Discharge Volume |
RS-09-079, Request for Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building Temperature | 15 June 2009 | Request for Amendment to Technical Specifications Section 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, to Eliminate Requirements for Main Steam Line Isolation on High Turbine Building Temperature | Reactor Vessel Water Level Mission time Probabilistic Risk Assessment Fuel cladding |
RS-09-042, Request for Amendment to Technical Specifications Section 5.5.6, Inservice Testing Program to Incorporate Previously NRC-Approved Generic TS Changes | 22 April 2009 | Request for Amendment to Technical Specifications Section 5.5.6, Inservice Testing Program to Incorporate Previously NRC-Approved Generic TS Changes | Incorporated by reference |
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 Process | 5 September 2008 | 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 Process | |
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 |
U-603859, Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases | 23 May 2008 | Transmittal of Revision 11 to the Clinton Power Station Technical Specification Bases | Anticipated 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 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-07-074, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process | 21 June 2007 | Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process | Ultimate heat sink Incorporated by reference Recently irradiated fuel Offsite Circuit |