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Category:Letter type:RS
MONTHYEARRS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 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 Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location RS-23-034, Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program2023-02-0202 February 2023 Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-033, Request for Exemption from 10 CFR 2.109(b)2023-01-27027 January 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023 Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves RS-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair2022-12-14014 December 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-119, Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval2022-10-31031 October 2022 Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022 Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage 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 Penetration2022-10-0303 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 RS-22-102, Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times2022-08-18018 August 2022 Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022 Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28 RS-22-094, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements2022-07-25025 July 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-077, Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Requests RV-08, Safety Relief Valves RS-22-078, Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs2022-06-30030 June 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-09, MSSVs RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station2022-05-25025 May 2022 Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station RS-22-059, CFR50.46 Annual Report2022-05-0404 May 2022 CFR50.46 Annual Report RS-22-056, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-054, Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval2022-04-13013 April 2022 Withdrawal of Relief Request RV-10 Associated with the Sixth Inservice Testing Interval RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-040, Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel2022-04-11011 April 2022 Response to Request for Additional Information Related to the License Amendment Request to Transition to GNF3 Fuel RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations 2024-01-03
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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 Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location 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 Penetration2022-10-0303 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 RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments RS-21-108, Application to Revise Technical Specification 3.1.4, Control Rod Scam Times2021-11-16016 November 2021 Application to Revise Technical Specification 3.1.4, Control Rod Scam Times RS-21-065, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12021-10-25025 October 2021 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 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 Position2021-09-27027 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 ML21257A4202021-09-14014 September 2021 Request for Licensing Amendment Regarding Transition to GNF3 Fuel RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.32020-04-0101 April 2020 Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-12-0505 December 2018 Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-18-032, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2018-04-25025 April 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) RS-18-006, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2018-02-26026 February 2018 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. ML18053A1902018-01-31031 January 2018 Enclosure 9 - Information Related to Review of Proposed Changes by the State ML18053A1852018-01-31031 January 2018 Enclosure 6 - Quad Cities - Evaluation of Proposed Changes ML18053A1782018-01-31031 January 2018 Attachment 6B - Quad Cities Clean Emergency Plan EP-AA-1000 Pages ML18053A1772018-01-31031 January 2018 Attachment 6A - Quad Cities - Marked-up Emergency Plan EP-AA-1000 Pages RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements RS-17-051, Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-04-27027 April 2017 Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process RS-16-201, Quad Cities Nuclear Power Station, Units 1 and 2 - License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition2016-10-20020 October 2016 Quad Cities Nuclear Power Station, Units 1 and 2 - License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition RS-16-201, License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition2016-10-20020 October 2016 License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition ML16280A4022016-10-0606 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. RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-09-28028 September 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel 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 Frequencies2016-09-19019 September 2016 Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-16-162, Request for License Amendment to Revise Loss of Voltage Relay Settings2016-09-12012 September 2016 Request for License Amendment to Revise Loss of Voltage Relay Settings ML16209A2182016-07-26026 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. RS-16-105, Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel2016-04-26026 April 2016 Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings RS-16-016, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-01-20020 January 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel RS-15-326, Request for License Amendment Regarding Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge2015-12-14014 December 2015 Request for License Amendment Regarding Spent Fuel Storage Pool Criticality Methodology for Fuel Channel Bow/Bulge ML16258A1522015-11-20020 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 2023-06-08
[Table view] Category:Technical Specification
MONTHYEARRS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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 Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location 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 Penetration2022-10-0303 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 ML21300A3392021-10-21021 October 2021 Revised Technical Specification Bases RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.32020-04-0101 April 2020 Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-19-023, Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.12019-03-0505 March 2019 Application to Increase Technical Specifications Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance Requirement 3.6.4.1.1 RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-12-0505 December 2018 Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits RS-17-126, Technical Specification Bases2017-10-19019 October 2017 Technical Specification Bases RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-09-28028 September 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel 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 Frequencies2016-09-19019 September 2016 Request for License Amendment to Revise Technical Specifications Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16209A2182016-07-26026 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. 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.2014-12-22022 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. 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 Process2014-07-14014 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 RS-12-036, License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr).2012-04-0303 April 2012 License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr). ML11305A1472011-10-19019 October 2011 Technical Specifications Bases Affected Page List ML11305A1352011-10-19019 October 2011 Technical Specification Bases RS-11-159, Quad Cities, Units 1 and 2 - Technical Specifications Bases Affected Page List2011-10-19019 October 2011 Quad Cities, Units 1 and 2 - Technical Specifications Bases Affected Page List RS-11-159, Quad Cities, Units 1 and 2 - Technical Specification Bases2011-10-19019 October 2011 Quad Cities, Units 1 and 2 - Technical Specification Bases RS-11-022, Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit2011-06-0707 June 2011 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit RS-10-028, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-03-0303 March 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. 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)2010-02-16016 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) RS-09-152, Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System2009-11-10010 November 2009 Request for Amendment to Technical Specification 3.1 .7, Standby Liquid Control (SLC) System 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 Leakage2009-08-28028 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 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 3.8.4.52008-12-0909 December 2008 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 3.8.4.5 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses 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 I2008-06-0909 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 ML0735400492007-12-19019 December 2007 Letter 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 Pages RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program2007-08-0808 August 2007 Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program RS-07-066, Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function2007-08-0101 August 2007 Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function 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 Process2007-04-12012 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 ML0702305402007-01-16016 January 2007 NF-BEX-06-281, Rev 0, Quad Cities, Unit 1 Cycle 20 SLMCPR, NP-Attachement 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 Report2006-12-15015 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 RS-06-147, Quad, Units 1 & 2 - Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment2006-11-0707 November 2006 Quad, Units 1 & 2 - Request for License Amendment to Increase Main Steam Safety Valve Lift Setpoint Tolerance and Standby Liquid Control System Enrichment ML0613103962006-05-10010 May 2006 Correction of Typographical Errors in Issuance of Amendments Dated March 9, 2006 ML0531301922005-10-17017 October 2005 Technical Specification Pages Pressure and Temperature Limits RS-05-075, Request for Amendment to Technical Specifications Associated with Feedwater System and Main Turbine High Water Level Trip Instrumentation2005-06-15015 June 2005 Request for Amendment to Technical Specifications Associated with Feedwater System and Main Turbine High Water Level Trip Instrumentation RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program SVP-04-099, Renewal of National Pollutant Discharge Elimination System (NPDES) Permit No. Il 00050372004-11-17017 November 2004 Renewal of National Pollutant Discharge Elimination System (NPDES) Permit No. Il 0005037 RS-04-133, Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits.2004-11-0404 November 2004 Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits. RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-04-30030 April 2004 Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process 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 Testing2003-08-0808 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-03-087, Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Relief Valves and Relief Request RV-30D2003-04-25025 April 2003 Request for Amendment to Technical Specifications Surveillance Requirements for the Main Steam Line Relief Valves and Relief Request RV-30D RS-03-038, Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function2003-03-28028 March 2003 Request for Amendment to TS for Main Steam Line Low Pressure Isolation Function ML0234505702002-11-27027 November 2002 Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process 2023-05-25
[Table view] Category:Bases Change
MONTHYEARRS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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 Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location 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 Penetration2022-10-0303 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 ML21300A3392021-10-21021 October 2021 Revised Technical Specification Bases RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-046, Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.32020-04-0101 April 2020 Emergency License Amendment Request - Increase Technical Specifications Allowable MSIV Leakage Rates in TS 3.6.1.3 JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits2018-12-0505 December 2018 Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits RS-17-126, Technical Specification Bases2017-10-19019 October 2017 Technical Specification Bases RS-16-199, Supplement to Request for License Amendment Regarding Transition to Areva Fuel2016-09-28028 September 2016 Supplement to Request for License Amendment Regarding Transition to Areva Fuel ML16209A2182016-07-26026 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. 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.2014-12-22022 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. 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 Process2014-07-14014 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 RS-12-036, License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr).2012-04-0303 April 2012 License Amendment Request to Technical Specifications Section 5.6.5, Core Operating Limits Report (Colr). RS-11-159, Quad Cities, Units 1 and 2 - Technical Specification Bases2011-10-19019 October 2011 Quad Cities, Units 1 and 2 - Technical Specification Bases RS-11-159, Quad Cities, Units 1 and 2 - Technical Specifications Bases Affected Page List2011-10-19019 October 2011 Quad Cities, Units 1 and 2 - Technical Specifications Bases Affected Page List ML11305A1352011-10-19019 October 2011 Technical Specification Bases ML11305A1472011-10-19019 October 2011 Technical Specifications Bases Affected Page List 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 3.8.4.52008-12-0909 December 2008 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 3.8.4.5 RS-07-044, Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program2007-08-0808 August 2007 Amergen Energy Company, LLC, Request for Amendment to Technical Specifications Section for the Inservice Testing Program RS-07-066, Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function2007-08-0101 August 2007 Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function 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 Process2007-04-12012 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 ML0702305402007-01-16016 January 2007 NF-BEX-06-281, Rev 0, Quad Cities, Unit 1 Cycle 20 SLMCPR, NP-Attachement 2023-03-03
[Table view] |
Text
4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office 10 CFR 50.90 RS-23-032 February 3, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, "LPCI Valve Alignment Verification Note Location"
Reference:
TSTF-416, Revision 0, "LPCI Value Alignment Verification Note Location," dated August 12, 2002 (ADAMS Accession No. ML022240526)
In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Constellation Energy Generation, LLC (CEG) requests amendments to Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. Specifically, CEG requests adoption of TSTF-416, Revision 0, "Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location," (Reference), an approved change to the Standard Technical Specifications (STS), into the QCNPS TS.
The proposed change would revise TS 3.5.1, "ECCS - Operating" by moving the LPCI valve alignment note presently located in Surveillance Requirement (SR) 3.5.1.2 to Limiting Condition for Operation (LCO) 3.5.1. provides a description and assessment of the proposed change. Attachment 2 provides the existing TS pages marked-up to show the proposed TS change. Attachment 3 provides revised (clean) TS pages. Attachment 4 provides the corresponding marked-up TS Bases pages and is provided for information only.
The proposed change has been reviewed by the QCNPS Plant Operations Review Committees, in accordance with the requirements of the CEG Quality Assurance Program.
CEG requests approval of the proposed license amendment by February 2, 2024. Once approved, the amendment shall be implemented within 90 days.
February 3, 2023 U.S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), a copy of this application, with attachments, is being provided to the designated State Officials.
There are no regulatory commitments contained in this submittal. Should you have any questions concerning this submittal, please contact Ms. Rebecca L. Steinman at (630) 657-2831.
I declare under penalty of perjury that the foregoing is true and correct. This statement was executed on the 3rd day of February 2023.
Respectfully, Patrick R. Simpson Sr. Manager Licensing Constellation Energy Generation, LLC Attachments:
- 1. Evaluation of Proposed Changes
- 2. Mark-up of Technical Specifications Pages
- 3. Clean Technical Specifications Pages
- 4. Mark-up of Technical Specifications Bases Pages - For Information Only cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, Quad Cities Nuclear Power Station NRC Project Manager, Quad Cities Nuclear Power Station Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT 1 Evaluation of Proposed Changes
Subject:
Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, "LPCI Valve Alignment Verification Note Location" 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION 2.1 Applicability 2.2 Variations 2.3 Detailed Description of Proposed Change
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Precedents 4.2 No Significant Hazards Consideration 4.3 Conclusion
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
ATTACHMENT 1 Evaluation of Proposed Changes 1.0
SUMMARY
DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Constellation Energy Generation, LLC (CEG) requests amendments to Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. Specifically, CEG requests adoption of TSTF-416, Revision 0, "Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location," (Reference 6.1),
an approved change to the Standard Technical Specifications (STS), into the QCNPS TS.
The proposed change would revise TS 3.5.1, "ECCS - Operating" by moving the LPCI valve alignment note presently located in Surveillance Requirement (SR) 3.5.1.2 to Limiting Condition for Operation (LCO) 3.5.1.
2.0 DETAILED DESCRIPTION 2.1 Applicability The NRC documented their approval of TSTF-416, Revision 0 in Reference 6.1, which stated that moving the valve alignment note is an administrative change that does not change the design or function of any safety or non-safety related systems or components previously reviewed by the NRC. CEG has reviewed TSTF-416, Revision 0 and has determined that the proposed change and associated justification is applicable to QCNPS, Units 1 and 2 and justify this amendment for incorporation.
2.2 Variations The approved Traveler includes moving the notes located in SR 3.5.1.2 and SR 3.5.2.4 to LCO 3.5.1 and 3.5.2, respectively. However, QCNPS has already incorporated the relocation of the note in TS 3.5.2 as part of Amendments 273/268 related to the adoption of TSTF-542, "Reactor Pressure Vessel Water Inventory Control" (Reference 6.2). As a result, this amendment only requests relocation of the note currently in SR 3.5.1.2.
2.3 Detailed Description of Change On August 12, 2002, the NRC approved TSTF-416, a traveler that relocated the LPCI valve alignment notes from SRs 3.5.1.2 and 3.5.2.4 to LCO 3.5.1 "ECCS -Operating" and LCO 3.5.2, "ECCS-Shutdown," respectively. As noted in Section 2.2, only the SR 3.5.1.2 note requires relocation at QCNPS since the SR 3.5.2.4 note has already been moved. contains a marked-up version of the TS showing the proposed change. provides the revised (clean) TS pages. Supporting changes to the QCNPS TS Bases will be made in accordance with TS 5.5.10, "Technical Specifications (TS) Bases Control Program." Attachment 4 provides the marked-up TS Bases pages. The TS Bases mark-up pages are being submitted for information only.
Page 2
ATTACHMENT 1 Evaluation of Proposed Changes
3.0 TECHNICAL EVALUATION
SR 3.5.1.2 for the verification of proper valve position currently includes a note that allows both LCPI subsystems to be considered operable during the alignment and operation for decay heat removal if the subsystems are capable of being manually realigned and otherwise operable.
The note also includes the restriction that the note is only applicable with reactor steam dome pressure less than the residual heat removal (RHR) cut-in permissive pressure in MODE 3.
This note, along with the related note in LCO 3.5.2, were included in the QCNPS TS to allow the LPCI subsystems to be considered operable when the RHR System is being used for shutdown cooling.
As described in the Bases, the note is intended to apply to all LPCI/RHR subsystem shared components; however, the note proposed for relocation is currently located in the SR that only addresses valve operability. Additionally, a similar note is not included with other SRs that are not met when an RHR subsystem is aligned in the shutdown cooling mode; specifically, SR 3.5.1.5 and SR 3.5.2.6 for automatic actuation tests. Without this change, it could be interpreted that, even though the note to SR 3.5.1.2 allows LPCI subsystems to be considered OPERABLE during alignment, the affected LPCI subsystems would have to be declared inoperable due to failure to meet the other SRs that do not contain a similar note. As a result, it is preferred to relocate the note to the LCO to ensure it applies to all SRs consistent with the LCO Bases.
4.0 REGULATORY EVALUATION
4.1 Precedents The NRC approved TSTF-416, Revision 0, on August 12, 2002 (Reference 6.1) and is reflected in NUREG-1433, "Standard Technical Specifications General Electric Plants." As indicated previously, QCNPS already moved a similar note from SR 3.5.2.4 to LCO 3.5.2 as part of Amendments 273/268, so this change would improve consistency within the QCNPS TS as well as match the STS.
4.2 No Significant Hazards Consideration Overview CEG requests adoption of TSTF-416, Revision 0, "Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location," an approved change to the Standard Technical Specifications (STS), into the QCNPS TS. The proposed change would revise TS 3.5.1, "ECCS
- Operating" by moving the LPCI valve alignment note presently located in Surveillance Requirement (SR) 3.5.1.2 to Limiting Condition for Operation (LCO) 3.5.1.
CEG has evaluated the proposed change against the criteria of 10 CFR 50.92(c) to determine if the proposed changes result in any significant hazards. The following is the evaluation of each of the 10 CFR 50.92(c) criteria:
Page 3
ATTACHMENT 1 Evaluation of Proposed Changes
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change makes the STS and STS Bases consistent in their consideration of an LPCI subsystem aligned for decay heat removal being considered OPERABLE for ECCS. The LCO 3.5.1 Bases state than an LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal. As a result, no initiators to accidents previously evaluated are affected and no mitigating equipment assumed in accidents previously evaluated are affected. Consequently, the probability or consequences of an accident previously evaluated is not significantly increased.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change makes the STS and STS Bases consistent in their consideration of an LPCI subsystem aligned for decay heat removal being considered OPERABLE for ECCS. The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation.
Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change makes the STS and STS Bases consistent in their consideration of an LPCI subsystem aligned for decay heat removal being considered OPERABLE for ECCS. As stated in the LCO 3.5.1 Bases, an LPCI subsystem is considered OPERABLE when aligned for decay heat removal. As the OPERABILITY requirements of the LPCI subsystem are unaffected, the margin of safety is unaffected. Therefore, this change does not involve a significant reduction in a margin of safety.
4.3 Conclusion Based on the considerations discussed above: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
The proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change Page 4
ATTACHMENT 1 Evaluation of Proposed Changes an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
6.1 TSTF-416, Revision 0, "LPCI Value Alignment Verification Note Location," dated August 12, 2002 (ADAMS Accession No. ML022240526) 6.2 Letter from Kimberly J. Green, Senior Project Manager, Office of Nuclear Reactor Regulation, to Mr. Bryan C. Hanson Senior Vice President and Chief Nuclear Officer Exelon Generation Company, LLC, " Quad Cities Nuclear Power Station, Units 1 and 2 -
Issuance of Amendment Nos. 273 and 268 Regarding Adoption of TSTF-542, 'Reactor Pressure Vessel Water Inventory Control' (EPID L-2018-LLA-0049)," dated January 28, 2019 (ADAMS Accession No. ML18353A229)
Page 5
ATTACHMENT 2 QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 Docket Nos. 50-254 and 50-265 Facility Operating License Nos. DPR-29 and DPR-30 MARK-UP OF TECHNICAL SPECIFICATIONS PAGES
NOTE----------------------------------------------------
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in ECCSOperating permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable. 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.1 ECCSOperating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of five relief valves shall be OPERABLE.
APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
ACTIONS
NOTE---------------------------------
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A. One Low Pressure A.1 Restore LPCI pump to 30 days Coolant Injection OPERABLE status.
(LPCI) pump inoperable.
B. One LPCI subsystem B.1 Restore low pressure 7 days inoperable for reasons ECCS injection/spray other than Condition subsystem to OPERABLE A. status.
OR One Core Spray subsystem inoperable.
C. One LPCI pump in each C.1 Restore one LPCI pump 7 days subsystem inoperable. to OPERABLE status.
D. Required Action and --------------NOTE------------
associated Completion LCO 3.0.4.a is not applicable Time of Condition A, when entering MODE 3.
B, or C not met. ------------------------------
D.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
Quad Cities 1 and 2 3.5.1-1 Amendment No. 273/268
ECCSOperating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray In accordance subsystem, locations susceptible to gas with the accumulation are sufficiently filled with Surveillance water. Frequency Control Program SR 3.5.1.2 -------------------NOTES-------------------
- 1. Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
- 2. Not required to be met for system vent flow paths opened under administrative control.
Verify each ECCS injection/spray subsystem In accordance manual, power operated, and automatic valve with the in the flow path, that is not locked, Surveillance sealed, or otherwise secured in position, Frequency is in the correct position. Control Program SR 3.5.1.3 Verify correct breaker alignment to the In accordance LPCI swing bus. with the Surveillance Frequency Control Program SR 3.5.1.4 Verify each recirculation pump discharge In accordance valve cycles through one complete cycle of with the full travel or is de-energized in the INSERVICE closed position. TESTING PROGRAM (continued)
Quad Cities 1 and 2 3.5.1-4 Amendment No. 266/2615
ATTACHMENT 3 QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 Docket Nos. 50-254 and 50-265 Facility Operating License Nos. DPR-29 and DPR-30 CLEAN TECHNICAL SPECIFICATIONS PAGES
ECCSOperating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV)
WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC)
SYSTEM 3.5.1 ECCSOperating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of five relief valves shall be OPERABLE.
NOTE---------------------------
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
ACTIONS
NOTE---------------------------------
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A. One Low Pressure A.1 Restore LPCI pump to 30 days Coolant Injection OPERABLE status.
(LPCI) pump inoperable.
B. One LPCI subsystem B.1 Restore low pressure 7 days inoperable for reasons ECCS injection/spray other than Condition subsystem to OPERABLE A. status.
OR One Core Spray subsystem inoperable.
C. One LPCI pump in each C.1 Restore one LPCI pump 7 days subsystem inoperable. to OPERABLE status.
(continued)
Quad Cities 1 and 2 3.5.1-1 Amendment No. 273/268
ECCSOperating 3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and --------------NOTE-----------
associated Completion LCO 3.0.4.a is not applicable Time of Condition A, when entering MODE 3.
B, or C not met. -----------------------------
D.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E. Two LPCI subsystems E.1 Restore one LPCI 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable for reasons subsystem to OPERABLE other than Condition status.
C.
F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition E AND not met.
F.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> G. HPCI System G.1 Verify by Immediately inoperable. administrative means RCIC System is OPERABLE.
AND G.2 Restore HPCI System 14 days to OPERABLE status.
H. One ADS valve H.1 Restore ADS valve to 14 days inoperable. OPERABLE status.
I. Required Action and --------------NOTE-----------
associated Completion LCO 3.0.4.a is not applicable Time of Condition G or when entering MODE 3.
H not met. -----------------------------
I.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
Quad Cities 1 and 2 3.5.1-2 Amendment No. 245/240
ECCSOperating 3.5.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME J. Two or more ADS valves J.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.
AND J.2 Reduce reactor steam 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> dome pressure to
< 150 psig.
K. Two or more low K.1 Enter LCO 3.0.3 Immediately pressure ECCS injection/spray subsystems inoperable for reasons other than Condition C or E.
OR HPCI System and one or more ADS valves inoperable.
OR One or more low pressure ECCS injection/spray subsystems inoperable and one or more ADS valves inoperable.
OR HPCI System inoperable and either one low pressure ECCS injection/spray subsystem is inoperable or Condition C entered.
Quad Cities 1 and 2 3.5.1-3 Amendment No. 245/240
ECCSOperating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray In accordance subsystem, locations susceptible to gas with the accumulation are sufficiently filled with Surveillance water. Frequency Control Program SR 3.5.1.2 -------------------NOTE-------------------
Not required to be met for system vent flow paths opened under administrative control.
Verify each ECCS injection/spray subsystem In accordance manual, power operated, and automatic valve with the in the flow path, that is not locked, Surveillance sealed, or otherwise secured in position, Frequency is in the correct position. Control Program SR 3.5.1.3 Verify correct breaker alignment to the In accordance LPCI swing bus. with the Surveillance Frequency Control Program SR 3.5.1.4 Verify each recirculation pump discharge In accordance valve cycles through one complete cycle of with the full travel or is de-energized in the INSERVICE closed position. TESTING PROGRAM (continued)
Quad Cities 1 and 2 3.5.1-4 Amendment No. 266/2615
ATTACHMENT 4 QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 Docket Nos. 50-254 and 50-265 Facility Operating License Nos. DPR-29 and DPR-30 MARK-UP OF TECHNICAL SPECIFICATIONS BASES PAGES - For Information Only
ECCSOperating B 3.5.1 BASES LCO the limits specified in Reference 9 could be exceeded. All (continued) ECCS subsystems must therefore be OPERABLE to satisfy the single failure criterion required by Reference 9.
As noted, LPCI subsystems may be considered OPERABLE during alignment and operation for decay heat removal when below the actual RHR cut-in permissive pressure in MODE 3, if capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable. Alignment and operation for decay heat removal includes: a) when the system is being realigned to or from the RHR shutdown cooling mode and; b) when the system is in the RHR shutdown cooling mode, whether or not the RHR pump is operating. At these low pressures and decay heat levels, a reduced complement of ECCS subsystems should provide the required core cooling, thereby allowing operation of RHR shutdown cooling when necessary.
APPLICABILITY All ECCS subsystems are required to be OPERABLE during MODES 1, 2, and 3, when there is considerable energy in the reactor core and core cooling would be required to prevent fuel damage in the event of a break in the primary system piping. In MODES 2 and 3, when reactor steam dome pressure is 150 psig, ADS and HPCI are not required to be OPERABLE because the low pressure ECCS subsystems can provide sufficient flow below this pressure. Requirements for MODES 4 and 5 are specified in LCO 3.5.2, "RPV Water Inventory Control."
ACTIONS A Note prohibits the application of LCO 3.0.4.b to an inoperable HPCI System. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable HPCI System and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.
A.1 If any one LPCI pump is inoperable, the inoperable pump must be restored to OPERABLE status within 30 days. In this Condition, the remaining OPERABLE pumps provide adequate core cooling during a LOCA. However, overall ECCS (continued)
Quad Cities 1 and 2 B 3.5.1-6 Revision 61
ECCSOperating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.1 (continued)
REQUIREMENTS environmental conditions, the plant configuration, or personnel safety. For these locations alternative methods (e.g., operating parameters, remote monitoring) may be used to monitor the susceptible location. Monitoring is not required for susceptible locations where the maximum potential accumulated gas void volume has been evaluated and determined to not challenge system OPERABILITY. The accuracy of the method used for monitoring the susceptible locations and trending of the results should be sufficient to assure system OPERABILITY during the Surveillance interval.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The Surveillance Frequency may vary by location susceptible to gas accumulation.
SR 3.5.1.2 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. For the HPCI System, this SR also includes the steam flow path for the turbine and the flow controller position.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
In MODE 3 with reactor steam dome pressure less than the actual RHR cut-in permissive pressure, the RHR System may be required to operate in the shutdown cooling mode to remove (continued)
Quad Cities 1 and 2 B 3.5.1-13 Revision 50
ECCSOperating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.2 (continued)
REQUIREMENTS decay heat and sensible heat from the reactor. Therefore, this SR is modified by Note 1 that allows LPCI subsystems to be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable. Alignment and operation for decay heat removal includes: a) when the system is being realigned to or from the RHR shutdown cooling mode and; b) when the system is in the RHR shutdown cooling mode, whether or not the RHR pump is operating. At the low pressures and decay heat loads associated with operation in MODE 3 with reactor steam dome pressure less than the RHR cut-in permissive pressure, a reduced complement of low pressure ECCS subsystems should provide the required core cooling, thereby allowing operation of RHR shutdown cooling, when necessary.
The Note 2 exempts system vent flow paths opened under administrative control. The administrative control should be proceduralized and include stationing a dedicated individual at the system vent flow path who is in continuous communication with the operators in the control room. This individual will have a method to rapidly close the system vent flow path if directed.
SR 3.5.1.3 Verification of the correct breaker alignment to the LPCI swing bus demonstrates that the AC electrical power is available to ensure proper operation of the associated LPCI injection valves and the recirculation pump discharge valves. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
SR 3.5.1.4 Cycling the recirculation pump discharge valves through one complete cycle of full travel demonstrates that the valves are mechanically OPERABLE and will close when required.
Upon initiation of an automatic LPCI subsystem injection signal, these valves are required to be closed to ensure full LPCI subsystem flow injection in the reactor via the recirculation jet pumps. De-energizing the valve in the (continued)
Quad Cities 1 and 2 B 3.5.1-14 Revision 50