Letter Sequence Approval |
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EPID:L-2019-LLA-0054, Supplement to License Amendment Request to Revise Technical Specifications for Testing of Main Turbine Control Slave Relay (LDCN 18-0025) (Approved, Closed) |
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Category:Letter
MONTHYEARIR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections IR 05000483/20240022024-07-18018 July 2024 and Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 ML24185A1032024-07-16016 July 2024 2024 Biennial Problem Identification and Resolution Inspection Report ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ML24144A0492024-06-11011 June 2024 Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML24178A1132024-06-0606 June 2024 Ameren Missouris Intent to Adopt Revision 1 to Amendment 0 of Certificate of Compliance No. 1040 as Applicable to the ISFSI at the Callaway Plant Site ML24158A5222024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition (LDCN 24-0008) ML24143A1632024-05-23023 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Storage Canister HGMPC0001 ML24137A2342024-05-16016 May 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Canister HGMPC0011 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 IR 05000483/20244022024-05-0606 May 2024 Security Baseline Inspection Report 05000483/2024402 (Full Report) ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report IR 05000483/20240112024-05-0101 May 2024 NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011 ML24122A1132024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radioactive Effluent Release Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ML24108A1082024-04-17017 April 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0009 IR 05000483/20240012024-04-16016 April 2024 Integrated Inspection Report 05000483/2024001 IR 05000483/20244042024-04-0909 April 2024 Cyber Security Inspection Report 05000483/2024404 05000483/LER-2024-001, Submittal of LER 2024-001-00 for Callaway Plant, Unit 1, Reactor Trip Due to Turbine Trip2024-04-0404 April 2024 Submittal of LER 2024-001-00 for Callaway Plant, Unit 1, Reactor Trip Due to Turbine Trip ML24088A3212024-04-0101 April 2024 Notification of Commercial Grade Dedication Inspection (05000483/2024013) and Request for Information ML24086A5132024-03-26026 March 2024 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024 Submittal of Annual Exposure Report for 2023 ML24079A1622024-03-19019 March 2024 Re Nuclear Property Insurance Reporting ML24066A1932024-03-0707 March 2024 2024 Callaway Plant Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024 Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26 IR 05000483/20230062024-02-28028 February 2024 Annual Assessment Letter for Callaway Plant Report 05000483/2023006 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation IR 05000483/20230022024-02-21021 February 2024 Amended Integrated Inspection Report 05000483/2023002 ML24036A1712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0079 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds 2024-08-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ML22361A0702023-02-24024 February 2023 Issuance of Amendment No. 231 for Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ML23019A1752023-01-30030 January 2023 Issuance of Amendment No. 230 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23067A1512022-12-29029 December 2022 Facility Operating License, Table of Contents ML23067A1502022-12-29029 December 2022 Renewed Facility Operating License ML23067A1522022-12-29029 December 2022 67, Operating License Amendment Index ML23067A1482022-12-29029 December 2022 Operating License, Appendix C, Revision 078, Additional Conditions ML22301A0072022-12-0202 December 2022 Issuance of Amendment No. 229 to Revise Technical Specifications to Adopt TSTF-505, Revision 2, and TSTF-439, Revision 2 ML22220A1322022-10-21021 October 2022 Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed Approach ML22220A1302022-10-21021 October 2022 Exemptions from the Requirements of 10 CFR 50.46 and 10 CFR Part 50 Appendix a, General Design Criteria 35, 38, and 41 (EPID L-2021-LLE-0021) (Cover Letter) ML22220A2812022-08-15015 August 2022 Withdrawal of Requested Licensing Action LAR for TS Change and Exemption Request Transition to Allow Use of Framatome Gaia Fuel Submitted to NRC for Acceptance Review ML22053A2832022-04-0707 April 2022 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules ML21344A0052021-12-29029 December 2021 Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML21195A2942021-06-22022 June 2021 78 to Operating License Appendix B - Environmental Protection Plan ML21195A2972021-06-22022 June 2021 64 to Operating License Amendment Index ML21195A2952021-06-22022 June 2021 Renewed Operating License ML21195A2932021-06-22022 June 2021 8 to Operating License Appendix C ML21053A1262021-03-24024 March 2021 Issuance of Amendment No. 225 to Revise Technical Specification Administrative Control 5.3.1 to Remove Details Specified for the Qualification of Certain Positions within the Unit Staff ML20218A4102020-11-0303 November 2020 Issuance of Amendment No. 224 Performance Based Method Alternative for Thermal Insulation Material ML20246G5702020-10-16016 October 2020 Issuance of Amendment No. 223 One-Time Deferral of the Steam Generator Tube Inspections ML19283C4812019-12-0606 December 2019 Issuance of Amendment No. 221 Main Turbine Control Slave Relay Testing ML20209A1252019-11-13013 November 2019 Operating License Re EA-03-009 Errata, Issuance of Errata to Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML20209A1172019-11-13013 November 2019 Operating License, Appendix B, Environmental Protection Plan ML20209A1522019-11-13013 November 2019 Operating License Re EA-12-051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation ML20209A1482019-11-13013 November 2019 Operating License Re NRC Order ML20209A1122019-11-13013 November 2019 Operating License Re Appendix C, Additional Conditions ML20209A1052019-11-13013 November 2019 Operating License, Table of Contents ML20209A1262019-11-13013 November 2019 Operating License Amendment Index ML20209A1352019-11-13013 November 2019 Operating License Re EA-06-037, Issuance of Order Requiring Compliance with Updated Adversary Characteristic ML20209A1312019-11-13013 November 2019 Operating License Re EA-05-007, Issuance of Order for Additional Security Measures on the Transportation of Radioactive Material Quantities of Concern ML20209A1162019-11-13013 November 2019 Operating License Regarding Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML20209A1072019-11-13013 November 2019 Operating License Re EA-13-237, Issuance of Order for Implementation of Additional Security Measures and Fingerprinting for Unescorted Access for Callaway Plant Independent Spent Fuel Storage Installation ML20209A1132019-11-13013 November 2019 Operating License Re Renewed Facility Operating License ML20209A1392019-11-13013 November 2019 Operating License Re Order Modifying Licenses (Effective Immediately), EA-02-026 ML20209A1412019-11-13013 November 2019 Operating License Re Issuance of Order for Compensatory Measures Related to Fitness-for-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel ML20209A1432019-11-13013 November 2019 Operating License Re EA-12-049, Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML20209A1532019-11-13013 November 2019 Operating License Re Issuance of Order Requiring Compliance with Revised Design Basis Threat for Operating Power Reactors ML19158A2902019-07-30030 July 2019 Issuance of Amendment No. 220 Regarding Emergency Action Level Scheme Changes ML19073A0012019-04-18018 April 2019 Issuance of Amendment No. 219 to Add New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System ML18124A0262018-05-30030 May 2018 Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection ML17236A0822017-09-15015 September 2017 Issuance of Amendment No. 217 Replacement of Methodology in Technical Specification 5.6.5, Core Operating Limits Report (Colr), ML16020A5162016-02-29029 February 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 2.1.1.1 and TS 5.6.5, to Remove Uncertainties from Departure from Nucleate Boiling Ratio Safety Limit and Adopt WCAP-14565-P-A Methodology ML15324A1142016-02-0202 February 2016 Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection ML15328A0592016-01-28028 January 2016 Issuance of Amendment No. 214, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15258A5102015-10-28028 October 2015 Issuance of Amendment No. 213, Adopt Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation 2024-01-18
[Table view] Category:Safety Evaluation
MONTHYEARML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML22361A0702023-02-24024 February 2023 Issuance of Amendment No. 231 for Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ML23019A1752023-01-30030 January 2023 Issuance of Amendment No. 230 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22301A0072022-12-0202 December 2022 Issuance of Amendment No. 229 to Revise Technical Specifications to Adopt TSTF-505, Revision 2, and TSTF-439, Revision 2 ML22220A1302022-10-21021 October 2022 Exemptions from the Requirements of 10 CFR 50.46 and 10 CFR Part 50 Appendix a, General Design Criteria 35, 38, and 41 (EPID L-2021-LLE-0021) (Cover Letter) ML22220A1322022-10-21021 October 2022 Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed Approach ML22053A2832022-04-0707 April 2022 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules ML21344A0052021-12-29029 December 2021 Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML21053A1262021-03-24024 March 2021 Issuance of Amendment No. 225 to Revise Technical Specification Administrative Control 5.3.1 to Remove Details Specified for the Qualification of Certain Positions within the Unit Staff ML20218A4102020-11-0303 November 2020 Issuance of Amendment No. 224 Performance Based Method Alternative for Thermal Insulation Material ML20246G5702020-10-16016 October 2020 Issuance of Amendment No. 223 One-Time Deferral of the Steam Generator Tube Inspections ML20230A3872020-08-31031 August 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20216A6812020-08-0606 August 2020 Operating Quality Assurance Manual Change Revision 34B (EPID L-2020-LLQ-0004 (COVID-19)) ML20141L7452020-06-0808 June 2020 Operating Quality Assurance Manual Change Revision 34A ML20107H9782020-04-20020 April 2020 COVID-19 Relief Request CC-01 Containment Tendon Inspection ML19283C4812019-12-0606 December 2019 Issuance of Amendment No. 221 Main Turbine Control Slave Relay Testing ML19158A2902019-07-30030 July 2019 Issuance of Amendment No. 220 Regarding Emergency Action Level Scheme Changes ML19073A0012019-04-18018 April 2019 Issuance of Amendment No. 219 to Add New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System ML19079A1482019-04-0101 April 2019 Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051 ML18313A0692018-11-26026 November 2018 Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping ML18124A0262018-05-30030 May 2018 Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection ML17262A7002017-10-0303 October 2017 Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval ML17254A1202017-09-25025 September 2017 Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval ML17236A0822017-09-15015 September 2017 Issuance of Amendment No. 217 Replacement of Methodology in Technical Specification 5.6.5, Core Operating Limits Report (Colr), ML17170A3202017-06-20020 June 2017 Safety Evaluation Input - for Ameren Missouri Request to Amend Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report - ML17058A4432017-03-0606 March 2017 Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval ML17010A3322017-02-0202 February 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16223A7122016-08-30030 August 2016 Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval ML16089A1672016-04-0101 April 2016 Review and Approval of Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 14-05A, Revision 1 ML16055A4642016-03-17017 March 2016 Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737) ML16020A5162016-02-29029 February 2016 Issuance of Amendment No. 216, Revise Technical Specification (TS) 2.1.1.1 and TS 5.6.5, to Remove Uncertainties from Departure from Nucleate Boiling Ratio Safety Limit and Adopt WCAP-14565-P-A Methodology ML15324A1142016-02-0202 February 2016 Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection ML16027A1582016-01-29029 January 2016 Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval ML15328A0592016-01-28028 January 2016 Issuance of Amendment No. 214, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date ML15258A5102015-10-28028 October 2015 Issuance of Amendment No. 213, Adopt Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15251A4932015-10-0707 October 2015 Issuance of Amendment No. 212, Request to Upgrade the Emergency Action Level Scheme by Adopting Nuclear Energy Institute NEI 99-01, Revision 6 ML15064A1252015-05-12012 May 2015 Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval ML15064A0282015-03-31031 March 2015 Issuance of Amendment No. 211, Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML15035A1482015-02-10010 February 2015 Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval ML14350B2392015-01-20020 January 2015 Issuance of Amendment No. 210, Revise Technical Specification LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4-6 ML14234A4512014-09-0404 September 2014 Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval ML14178A7692014-07-15015 July 2014 Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval ML14175A3902014-07-0101 July 2014 Issuance of Amendment No. 209, Adoption of Technical Specification Task Force Change Traveler TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using CLIIP ML14027A0572014-01-29029 January 2014 Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval 2024-01-18
[Table view] Category:Technical Specifications
MONTHYEARML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML23052A0462023-02-21021 February 2023 Enclosure 4 - Revised Technical Specifications (Retyped Version) ML23052A0452023-02-21021 February 2023 Enclosure 3 - Revised Technical Specifications (Red Line Version) ML23067A1682022-12-29029 December 2022 Technical Specifications, Chapter 4, Design Features ML23067A1592022-12-29029 December 2022 Technical Specifications, Chapter 3, Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) Applicability ML23067A1602022-12-29029 December 2022 Technical Specifications, Chapter 3.6, Containment Systems ML23067A1612022-12-29029 December 2022 Technical Specifications, Chapter 1, Use and Application ML23067A1632022-12-29029 December 2022 Technical Specifications, Chapter 2, Safety Limits (Sls) ML23067A1642022-12-29029 December 2022 Technical Specifications, Chapter 5, Administrative Controls ML23067A1662022-12-29029 December 2022 Technical Specifications, Table of Contents ML23067A1672022-12-29029 December 2022 Technical Specifications, List of Effective Pages ML23067A1572022-12-29029 December 2022 Technical Specifications, Chapter 3.3, Instrumentation ML23067A1692022-12-29029 December 2022 Technical Specifications, Chapter 3.4, Reactor Coolant System ML23067A1702022-12-29029 December 2022 Technical Specifications, Chapter 3.9, Refueling Operations ML23067A1562022-12-29029 December 2022 Technical Specifications, Chapter 3.7, Plant Systems ML23067A1622022-12-29029 December 2022 Technical Specifications, Chapter 3.1, Reactivity Control Systems ML23067A1582022-12-29029 December 2022 Technical Specifications, Chapter 3.5, Emergency Core Cooling Systems (ECCS) ML23067A1652022-12-29029 December 2022 Technical Specifications, Chapter 3.8, Electrical Power System ML23067A1712022-12-29029 December 2022 Technical Specifications, Chapter 3.2, Power Distribution Limits ML22301A0072022-12-0202 December 2022 Issuance of Amendment No. 229 to Revise Technical Specifications to Adopt TSTF-505, Revision 2, and TSTF-439, Revision 2 ML22334A2572022-11-30030 November 2022 Proposed Technical Specification TOC Page (Markup) ML22334A2602022-11-30030 November 2022 Revised Technical Specification Pages (Clean Pages) ML22334A2592022-11-30030 November 2022 Revised Technical Specification Pages (Markup) ML22334A2582022-11-30030 November 2022 Proposed Technical Specification TOC Page (Clean Page) ML22285A1182022-10-12012 October 2022 Attachment 1 to Enclosure 1: Marked-Up Existing Technical Specifications ML22285A1192022-10-12012 October 2022 Attachment 2 to Enclosure 1: Revised Clean Technical Specifications ML22251A3452022-09-0808 September 2022 Attachment 2: Retyped TS Pages for TS 3.6.8 ML22251A3442022-09-0808 September 2022 Attachment 1: Marked-Up TS Pages for TS 3.6.8 ULNRC-06744, Revised Technical Specification Pages2022-08-0404 August 2022 Revised Technical Specification Pages ML22181B1322022-06-30030 June 2022 Attachment 2 - Replacement for Attachment 2, Proposed Technical Specification Changes (Mark-up), of ULNRC-06688 ML22181B1332022-06-30030 June 2022 Attachment 3 - Replacement for Attachment 3, Revised Technical Specification Pages, of ULNRC-06688, as Corrected in ULNRC-06702 ML22153A1772022-06-0202 June 2022 Attachment 1 - Marked-Up Existing Technical Specifications ML22153A1782022-06-0202 June 2022 Attachment 2 - Revised Clean Technical Specifications ML21343A0972021-12-0909 December 2021 Attachment 3: Revised Technical Specifications Pages ML21343A0962021-12-0909 December 2021 Attachment 2: Proposed Technical Specifications Changes (Mark-Up) ML21335A4562021-12-0101 December 2021 Enclosure 4: Retyped Technical Specification Pages ML21335A4552021-12-0101 December 2021 Enclosure 3: Proposed Technical Specification Changes (Mark-Up) ULNRC-06702, Enclosureplacement Version of Attachment 3 to ULNRC-06688, Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-5052021-11-24024 November 2021 Enclosureplacement Version of Attachment 3 to ULNRC-06688, Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505 ML21194A2832021-06-22022 June 2021 Technical Specification, Chapter 3.2, Power Distribution Limits ML21194A2912021-06-22022 June 2021 Technical Specification, Chapter 3.9, Refueling Operations ML21194A2902021-06-22022 June 2021 Technical Specification, Chapter 4.0, Design Features ML21194A2892021-06-22022 June 2021 Technical Specification, List of Effective Pages ML21194A2882021-06-22022 June 2021 Technical Specification, Table of Contents ML21194A2872021-06-22022 June 2021 Technical Specification, Chapter 3.8, Electrical Power Systems ML21194A2852021-06-22022 June 2021 Technical Specification, Chapter 3.6, Containment Systems ML21194A2862021-06-22022 June 2021 Technical Specification, Chapter 5.0, Administrative Controls ML21194A2842021-06-22022 June 2021 Technical Specification, Chapter 3.7, Plant Systems 2024-01-18
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 6, 2019 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Ameren Missouri Callaway Energy Center 8315 County Road 459 Fulton, MO 65077
SUBJECT:
CALLAWAY PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT NO. 221 RE:
MAIN TURBINE CONTROL SLAVE RELAY TESTING (EPID L-2019-LLA-0054)
Dear Mr. Diya:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 221 to Renewed Facility Operating License No. NPF-30 for Callaway Plant, Unit No. 1 (Callaway). The amendment consists of changes to the technical specifications (TSs) in response to your application dated March 12, 2019, as supplemented by letter dated June 6, 2019.
The amendment revises the Callaway TSs to modify testing of slave relay K620 during shutdown under Surveillance Requirement (SR) 3.3.2.14 to testing during operation under SR 3.3.2.6.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, L. l Kl , Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosures:
- 1. Amendment No. 221 to NPF-30
- 2. Safety Evaluation cc: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT NO. 1 DOCKET NO. 50-483 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 221 License No. NPF-30
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Union Electric Company (UE, the licensee),
dated March 12, 2019, as supplemented by letter dated June 6, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-30 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan*
The Technical Specifications contained in Appendix A, as revised through Amendment No. 221 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This amendment is effective as of its date of issuance, and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r+xJennifer L. Dixon-Herrity, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License No. NPF-30 and Technical Specifications Date of Issuance: December 6, 2 O1 9
ATTACHMENT TO LICENSE AMENDMENT NO. 221 CALLAWAY PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Replace the following pages of the Renewed Facility Operating License No. NPF-30 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 3.3-37 3.3-37 3.3-39 3.3-39 3.3-44 3.3-44
(3) UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
( 1) Maximum Power Level UE is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal ( 100% power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan*
The Technical Specifications contained in Appendix A, as revised through Amendment No. 221 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Environmental Qualification (Section 3.11, SSER #3)**
Deleted per Amendment No. 169.
- Amendments 133, 134, & 135 were effective as of April 30, 2000 however these amendments were implemented on April 1, 2000.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Renewed License No. NPF-30 Amendment No. 221
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.2.5 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.6 --------------------------------- NOTE ---------------------------
Not applicable to slave relays K602, K622, K624, K630, K740, K741, and K750.
Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.7 --------------------------------- NOTE ---* ------------------------
Verification of relay setpoints not required.
Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.8 --------------------------------- NOTE ----------------------------
Verification of setpoint not required for manual initiation functions.
Perform T ADOT. In accordance with the Surveillance Frequency Control Program
\COnunueaJ CALLAWAY PLANT 3.3-37 Amendment No. 221
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued}
SURVEILLANCE FREQUENCY SR 3.3.2.13 --------------------------------- NOTE ----------------------------
Only applicable to slave relays K602, K622, K624, K630, K740, and K741.
Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program Prior to entering MODE 4 when in MODE 5 or6
> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if not performed within the previous 92 days SR 3.3.2.14 --------------------------------- NOTE ----------------------------
Only applicable to slave relay K750.
Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program Prior to entering MODE 3 when in MODE 5 or 6
> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if not performed within the previous 92 days CALLAWAY PLANT 3.3-39 Amendment No. 221
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 11)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 5. Turbine Trip and Feedwater Isolation
- a. Automatic 2 trains G SR 3.3.2.2 NA Actuation Logic SR 3.3.2.4 and Actuation SR 3.3.2.6 Relays (SSPS)
- b. Automatic 2 trains<0 > s SR 3.3.2.3 NA Actuation Logic and Actuation Relays (MSFIS)
- c. SG Water Level - 4 per SG SR3.3.2.1 ~ 91.4%(s) of High High (P-14) SR3.3.2.5 Narrow Range SR 3.3.2.9 Instrument SR 3.3.2.10 Span
- d. Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements. The Applicability exceptions of Footnote (j) also apply to Function 5.d.
(a) The Allowable Value defines the limiting safety system setting except for Functions 1.e, 4.e.(1 ), 5.c, 5.e.(1 ), 5.e.(2),
6.d.( 1), and 6.d.(2) (the Nominal Trip Setpoint defines the limiting safety system setting for these Functions). See the Bases for the Nominal TripSetpoints.
(j) Except when:
- 1. All MFIVs are closed and de-activated:
AND
- 2. All MFRVs are:
2.a Closed and de-activated, or 2.b Closed and isolated by a closed manual valve; AND
- 3. All MFRVBVs are:
3.a Closed and de-activated, or 3.b Closed and isolated by a closed manual valve, or 3.c Isolated by two closed manual valves.
(I) Except when all MFIVs are closed and de-activated.
(o) Each train requires a minimum of two programmable logic controllers to be OPERABLE.
(s) 1. If the as-found instrument channel setpoint is conservative with respect to the Allowable Value, but outside its as-found test acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
- 2. The instrument channel setpoint shall be reset to a value that is within the as-left setpoint tolerance band on either side of the Nominal Trip Setpoint, or to a value that is more conservative than the Nominal Trip Setpoint; otherwise, the channel shall be declared inoperable. The Nominal Trip Setpoints and the methodology used to determine the as-found test acceptance criteria band and the as-left setpoint tolerance band shall be specified in the Bases.
CALLAWAY PLANT 3.3-44 Amendment No. 221
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 221 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT NO. 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By application dated March 12, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19071A281), as supplemented by letter dated June 6, 2019 (ADAMS Accession No. ML19157A303), Union Electric Company, dba Ameren Missouri (the licensee) requested changes to Renewed Facility Operating License No. NPF-30 for the Callaway Plant, Unit No. 1 (Callaway).
The proposed amendment would revise the Callaway Technical Specifications (TSs) to remove slave relay K620 from the scope of TS Surveillance Requirement (SR) 3.3.2.14 testing during shutdown conditions at 18-month intervals and incorporate it into the scope of SR 3.3.2.6 for surveillance testing during power operations, at a frequency in accordance with the Surveillance Frequency Control Program (SFCP). Specifically, the proposed changes would revise the condition of performing the surveillance test for slave relay K620 only during Mode 5 or 6.
The change is accomplished by moving the relay from the scope of SR 3.3.2.14 to SR 3.3.2.6.
The frequency under SR 3.3.2.14 states "In accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 3 when in MODE 5 or 6 > [greater than] 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if not performed within the previous 92 days." The frequency is now placed under SR 3.3.2.6, which states, "In accordance with the Surveillance Frequency Control Program."
The supplemental letter dated June 6, 2019, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC, the Commission) staff's original proposed no significant hazards consideration determination as published in the Federal Register on June 4, 2019 (84 FR 25841 ).
Enclosure 2
2.0 REGULATORY EVALUATION
2.1 System Description The solid-state protection system (SSPS) is designed to initiate a reactor trip if safe operating limits are exceeded and to initiate engineered safety features actuations if an accident occurs.
Slave relay K620 is part of the SSPS system and is used to energize the trip bus coil in the electro-hydraulic control (EHC) system that controls the main turbine. The SSPS system includes a built-in feature to test slave relays during operation. The slave relay test uses a low current signal that demonstrates continuity through to the trip coil without actuation. The EHC system trip bus coil that was previously installed did not meet the impedance criteria required for use with the built-in test feature and was at risk for initiating a turbine trip if tested while the plant was operating. To date, slave relay K620 was only tested while the plant was in Mode 5, "Cold Shutdown" or Mode 6, "Refueling."
The SSPS accomplishes testing of slave relays during operation by using a fixed, series resistor that is connected to an individual channel through a rotary selector switch. The resistor limits the current going to the slave relay coil such that it will not trip. This allows testing of these relays during plant operations without fully actuating the function. Because the current limiting series resistor is a fixed value, the impedance of the trip coil under test must meet a minimum value to ensure it will not cause an unintended trip.
2.2 Proposed Changes The licensee proposed changes that would remove the condition of performing the surveillance test for slave relay K620 only during Mode 5 or 6. The change is accomplished by moving the relay from the scope of SR 3.3.2.14 to SR 3.3.2.6. The frequency under SR 3.3.2.14 was "In accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 3 when in MODE 5 or 6 > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if not performed within the previous 92 days." The proposed frequency under SR 3.3.2.6 is "In accordance with the Surveillance Frequency Control Program." Notes for both SR 3.3.2.6 and SR 3.3.2.14 are modified to reflect the change. Slave relay K620 is removed from the "not applicable to" list on the 3.3.2.6 Note because it will now be performed under 3.3.2.6. Slave relay K620 is also removed from the "only applicable to" list on the 3.3.2.14 Note because slave relay K620 will no longer be performed under 3.3.2.14. The Callaway TS are modified to reflect the change as follows:
Current SR 3.3.2.6 Note states:
Not applicable to slave relays K602, K620, K622, K624, K630, K7 40, K7 41, and K750.
Revised SR 3.3.2.6 Note would state:
Not applicable to slave relays K602, K622, K624, K630, K740, K741, and K750.
Current SR 3.3.2.14 Note states:
Only applicable to slave relays K620 and K750.
Revised SR 3.3.2.14 Note would state:
Only applicable to slave relay K750.
Current Table 3.3.2-1, Function 5a, SR column states:
SR 3.3.2.2, SR 3.3.2.4, SR 3.3.2.6, SR 3.3.2.14 Revised Table 3.3.2-1, Function 5a, SR column would state:
SR 3.3.2.2, SR 3.3.2.4, SR 3.3.2.6 2.3 Regulatory Requirements and Guidance The NRC's regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical specifications." This regulation requires that the TSs include items in the following five specific categories: ( 1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) SRs; (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in plant TSs.
The regulation under 10 CFR 50.36(c)(3) states that, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The license amendment request (LAR) proposes to change the frequency of the surveillance test for slave relay K620.
The regulation under 10 CFR 50.36(a)(1) states, in part, that "A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications."
Accordingly, along with the proposed TS changes, the licensee also submitted TS Bases changes corresponding to the proposed TS changes. The NRC staff noted that the licensee included TS Bases changes in the LAR but did not review the specific TS Bases changes.
Appendix A to 10 CFR Part 50, GDC 21, "Protection System Reliability and Testability," states, in part, that the protection system shall be designed to permit periodic testing of its functioning when the reactor is in operation. The current licensing basis allows testing of slave relay K620 only when the reactor is operating in Modes 5 or 6.
Regulatory Guide (RG) 1.22 describes acceptable methods to meet GDC 21, including functional testing when the reactor is in operation. The current licensing basis allows testing of slave relay K620 only when the reactor is operating in Modes 5 or 6.
Institute of Electrical and Electronics Engineers (IEEE) 279-1971 Clause 4.10 states, in part, that for those parts of the system where the required interval between testing will be less than the normal time interval between generating station shutdowns, there shall be capability for testing during power operation. The current licensing basis allows testing of slave relay K620 only when the reactor is operating in Modes 5 or 6.
3.0 TECHNICAL EVALUATION
As described in Section 2.2 of this safety evaluation, the licensee is proposing to revise the Callaway TSs to move the surveillance testing of slave relay K620 from SR 3.3.2.14 to SR 3.3.2.6. The change impacts the frequency of the surveillance because the frequency of the new SR is not limited to being performed while the plant is in Mode 5 or 6.
The NRC staff reviewed the technical discussion of the proposed changes provided in the LAR to ensure that the reasoning was logical, complete, and clearly written. Specifically, the staff reviewed the proposed changes for continued compliance with the regulation in 10 CFR 50.36(c)(3), GDC 21, RG 1.22, and IEEE 279-1971.
The NRC staff previously made an exception for the testing of relay K620 only during Modes 5 and 6 as acceptable with allowances stated in IEEE 279-1971 Clause 4.10 because the SSPS' built-in test for slave relays had a high risk of tripping the main turbine at that time. However, recent changes to the main turbine's EHC system included a new relay that is compatible with the SSPS' built-in test function which therefore now allows testing while the reactor is in operation without the previous exception applied. Therefore, the NRC staff finds that because slave relay K620 can now be tested while the reactor is operating, the related SR is now consistent with the online-test criteria of GDC 21, RG 1.22, and IEEE 279-1971 Clause 4.10 and that the proposed changes are acceptable.
Callaway TS LCO 3.3.2 states that the" [Engineered Safety Feature Actuation System] ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE." Slave relay K620 is associated with TS Table 3.3.2-1, "Engineered Safety Feature Actuation System Instrumentation," Function 5a, "Turbine trip and Feedwater Isolation, Automatic Actuation Logic and Actuation Relays (SSPS)." SR 3.3.2.6 and SR 3.3.2.14 are both SSPS slave relay tests that determine operability for several ESFAS functions, including ESFAS Function 5a. The surveillances differ only in which relays are tested and the frequency of testing. The frequency for SR 3.3.2.6 is "In accordance with the Surveillance Frequency Control Program". The frequency for SR 3.3.2.14 is "In accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 3 when in MODE 5 or 6 > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if not performed within the previous 92 days." The NRC staff notes the proposed change removes the limitation of the surveillance being performed only in Mode 5 or 6, stating instead that the relay should be tested as determined by the SFCP. The NRC staff review concludes that there is reasonable assurance that the requirements and criteria found in 10 CFR 50.36(c)(3) will continue to be met. Therefore, the staff finds the proposed change is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Missouri State official was notified of the proposed issuance of the amendment on September 26, 2019. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
T~e amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation
exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, published in Federal Register on June 4, 2019 (84 FR 25841), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b ), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that 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.
Principal Contributors: S. Wyman H. Kodali Date: December 6 , 2 O1 9
SUBJECT:
CALLAWAY PLANT, UNIT NO. 1 - ISSUANCE OF AMENDMENT NO. 221 RE:
MAIN TURBINE CONTROL SLAVE RELAY TESTING (EPID L-2019-LLA-0054)
DATED DECEMBER 6, 2019 DISTRIBUTION:
PUBLIC RidsNrrDeEeob Resource PM File Copy RidsNrrLAPBlechman Resource RidsACRS MailCTR Resource RidsNrrPMCallaway Resource RidsNrrDorlLpl4 Resource RidsRgn4MailCenter Resource RidsNrrDssStsb Resource SWyman, NRR RidsNrrDeEicb Resource HKodali, NRR ADAMS A ccess1on No. ML19283C481 *b1yema1*1 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DE/EEOB* NRR/DSS/STSB/BC NAME JKlos PBlechman DWilliams VCusumano DATE 9/27/19 10/17/19 9/26/19 10/22/19 OFFICE NRR/DE/EICB/BC (A)* OGC* NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RAlvarado (WMorton for) KGamin J Dixon-Herrity JKlos DATE 11/13/2019 11/21/19 11/22/19 12/6/19 OFFICIAL RECORD COPY