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MONTHYEARML14064A3762014-03-0505 March 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review 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 Project stage: Approval 2014-03-05
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Category:Letter
MONTHYEARULNRC-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 ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report 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) 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) ML23305A0942023-10-0202 October 2023 10-CW-2023-09 Post-Exam Submittal ML23270B9662023-09-27027 September 2023 10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval 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 ML23206A1992023-09-15015 September 2023 Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 ML23240A7572023-08-31031 August 2023 NRC Initial Operator Licensing Examination Approval 05000483/2023301 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ML23219A1392023-08-15015 August 2023 Request for Withholding Information from Public Disclosure ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) ULNRC-06223, Minor Correction to License Amendment Request 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 (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request 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 (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23171A9942023-06-22022 June 2023 Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ML23129A7942023-05-0909 May 2023 Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030) ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections ML23118A3492023-05-0808 May 2023 Request for Withholding Information from Public Disclosure 2024-01-29
[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 ML23067A1482022-12-29029 December 2022 Operating License, Appendix C, Revision 078, Additional Conditions ML23067A1512022-12-29029 December 2022 Facility Operating License, Table of Contents ML23067A1522022-12-29029 December 2022 67, Operating License Amendment Index ML23067A1502022-12-29029 December 2022 Renewed Facility Operating License 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 ML20209A1482019-11-13013 November 2019 Operating License Re NRC Order 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 ML20209A1262019-11-13013 November 2019 Operating License Amendment Index ML20209A1122019-11-13013 November 2019 Operating License Re Appendix C, Additional Conditions ML20209A1052019-11-13013 November 2019 Operating License, Table of Contents 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 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 ML20209A1392019-11-13013 November 2019 Operating License Re Order Modifying Licenses (Effective Immediately), EA-02-026 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 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) ML23067A1692022-12-29029 December 2022 Technical Specifications, Chapter 3.4, Reactor Coolant System ML23067A1602022-12-29029 December 2022 Technical Specifications, Chapter 3.6, Containment Systems ML23067A1612022-12-29029 December 2022 Technical Specifications, Chapter 1, Use and Application ML23067A1622022-12-29029 December 2022 Technical Specifications, Chapter 3.1, Reactivity Control Systems ML23067A1642022-12-29029 December 2022 Technical Specifications, Chapter 5, Administrative Controls ML23067A1652022-12-29029 December 2022 Technical Specifications, Chapter 3.8, Electrical Power System ML23067A1672022-12-29029 December 2022 Technical Specifications, List of Effective Pages ML23067A1582022-12-29029 December 2022 Technical Specifications, Chapter 3.5, Emergency Core Cooling Systems (ECCS) ML23067A1682022-12-29029 December 2022 Technical Specifications, Chapter 4, Design Features ML23067A1702022-12-29029 December 2022 Technical Specifications, Chapter 3.9, Refueling Operations ML23067A1562022-12-29029 December 2022 Technical Specifications, Chapter 3.7, Plant Systems ML23067A1572022-12-29029 December 2022 Technical Specifications, Chapter 3.3, Instrumentation ML23067A1632022-12-29029 December 2022 Technical Specifications, Chapter 2, Safety Limits (Sls) ML23067A1592022-12-29029 December 2022 Technical Specifications, Chapter 3, Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) Applicability ML23067A1662022-12-29029 December 2022 Technical Specifications, Table of Contents 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 ML21194A2842021-06-22022 June 2021 Technical Specification, Chapter 3.7, Plant Systems 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 ML21194A2832021-06-22022 June 2021 Technical Specification, Chapter 3.2, Power Distribution Limits 2024-01-18
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 20, 2015 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE: REVISION TO TECHNICAL SPECIFICATION 3.4.12, "COLD OVERPRESSURE MITIGATION SYSTEM (COMS)" (TAC NO. MF3391)
Dear Mr. Diya:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 210 to Facility Operating License No. NPF-30 for the Callaway Plant Unit 1.
The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated January 23, 2014.
The amendment revises TS 3.4.12, "Cold Overpressure Mitigation System (COMS)," to reflect the mass input transient analysis that assumes an Emergency Core Cooling System centrifugal charging pump and the normal charging pump capable of injecting into the reactor coolant system when TS 3.4.12 is applicable. The amendment also revises TS Table 3.3.1-1, "Reactor Trip System Instrumentation," to remove unnecessary page number references.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, CF~
Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosures:
- 1. Amendment No. 210 to NPF-30
- 2. Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 210 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 January 23, 2014, 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 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. 210 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the 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 Eric R. Oesterle, Acting Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-30 and Technical Specifications Date of Issuance: Jaunuary 20, 2015
ATTACHMENT TO LICENSE AMENDMENT NO. 210 FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Replace the following pages of the 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.
Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 3.3-20 3.3-20 3.4-25 3.4-25 3.4-26 3.4-26 3.4-28 3.4-28
(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 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 (1 00% 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. 210 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the 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.
Amendment No. 210
RTS Instrumentation 3.3.1 TABLE 3.3.1-1 (PAGE 2 OF 8)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 5. Source Range 2(e) 2 I, J :s: 1.6 E5 cps Neutron Flux 3. 4 . s 2 J, K :s: 1.6 E5 cps
- 6. Overtemperature 1,2 4 E Sf? 3<3. i 1 Refer to Note 1 t.T (at the end of this Table) i 7 1 10
- 7. Overpower L'.T 1,2 4 E Refer to Note 2
~~ 7 (at the end of this Table) 1 1C
- 8. Pressurizer Pressure
- a. Low 1(9) 4 M .;
'
'l ;:, 1874 psig
- b. High 1,2 4 E 1 1 :s: 2393 psig 1 r (a) The Allowable Value defines the limiting safety system setting except for Trip Functions 14.a and 14.b (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(e) Below the P-6 (Intermediate Range Neutron Flux) interlock.
(g) Above the P-7 (Low Power Reactor Trips Block) interlock.
CALLAWAY PLANT 3.3-20 Amendment No. 210
COMS 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Cold Overpressure Mitigation System (COMS)
LCO 3.4.12 COMS shall be OPERABLE with a maximum of zero safety injection pumps, one Emergency Core Cooling System (ECCS) centrifugal charging pump, and the normal charging pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:
- a. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or
- b. Two residual heat removal (RHR) suction relief valves with setpoints 2 436.5 psig and ~ 463.5 psig, or
- c. One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief valve with a setpoint 2 436.5 psig and
~ 463.5 psig, or
- d. The RCS depressurized and an RCS vent of 2 2.0 square inches.
N0 TES --------------------------------------------
- 1. Two ECCS centrifugal charging pumps may be made capable of injecting for~ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operations.
- 2. One or more safety injection pumps may be made capable of injecting in MODES 5 and 6 when the RCS water level is below the top of the reactor vessel flange for the purpose of protecting the decay heat removal function.
- 3. Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
APPLICABILITY: MODE 4 with any RCS cold leg temperature ~ 275°F, MODE 5, MODE 6 when the reactor vessel head is on.
CALLAWAY PLANT 3.4-25 Amendment No. 210
COMS 3.4.12 ACTIONS
N0 TE -----------------------------------------------------------
LCO 3.0.4.b is not applicable when entering MODE 4.
COMPLETION CONDITION REQUIRED ACTION TIME A One or more safety A.1 Initiate action to verify a Immediately injection pumps capable of maximum of zero safety injecting into the RCS. injection pumps are capable of injecting into the RCS.
B. Two ECCS centrifugal 8.1 Initiate action to verify a Immediately charging pumps capable of maximum of one ECCS injecting into the RCS. centrifugal charging pump and the normal charging pump capable of injecting into the RCS.
C. An accumulator not isolated C.1 Isolate affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> when the accumulator accumulator.
pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.
(contmued)
CALLAWAY PLANT 3.4-26 Amendment No. 210
COMS 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of zero safety injection pumps are In accordance capable of injecting into the RCS. with the Surveillance Frequency Control Program SR 3.4.12.2 Verify a maximum of one ECCS centrifugal charging In accordance pump and the normal charging pump capable of with the injecting into the RCS. Surveillance Frequency Control Program SR 3.4.12.3 Verify each accumulator is isolated when In accordance accumulator pressure is greater than or equal to the with the maximum RCS pressure for the existing RCS cold Surveillance leg temperature allowed by the P/T limit curves Frequency provided in the PTLR. Control Program SR 3.4.12.4 Verify RHR suction isolation valves are open for each In accordance required RHR suction relief valve. with the Surveillance Frequency Control Program SR 3.4.12.5 Verify required RCS vent::::: 2.0 square inches open. In accordance with the Surveillance Frequency Control Program (continued)
CALLAWAY PLANT 3.4-28 Amendment No. 210
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 210 TO FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By application dated January 23, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14023A803), Union Electric Company (the licensee) requested changes to Facility Operating License No. NPF-30 for the Callaway Plant, Unit 1 (Callaway). The licensee proposed to revise Technical Specification (TS) 3.4.12, "Cold Overpressure Mitigation System (COMS)," to reflect the mass input transient analysis that assumes an Emergency Core Cooling System (ECCS) centrifugal charging pump (CCP) and the normal charging pump (NCP) capable of injecting into the reactor coolant system (RCS) when TS 3.4.12 is applicable. The licensee also proposed to revise TS Table 3.3.1-1, "Reactor Trip System Instrumentation," to remove unnecessary page number references.
Specifically, the proposed changes to TS 3.4.12 will differentiate between the ECCS CCPs and the non-safety- related NCP, and provide clarification that no limits are placed on operation of the NCP during applicability of TS 3.4.12. The proposed changes also revise TS Table 3.3.1-1 to correct referenced page numbers, which had been changed in Amendment No. 202 dated July 29, 2011 (ADAMS Accession No. ML111661877). The Allowable Values for Functions 6 and 7 in Table 3.3.1-1 are revised to replace the page number references with the explanatory phrase "(at the end of this Table)."
2.0 REGULATORY EVALUATION
2.1 SYSTEM DESCRIPTION The COMS controls RCS pressure at low temperatures in order to ensure the integrity of the reactor coolant pressure boundary (RCPB) is not compromised by violating the pressure-temperature (P-T) limits of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements," as specified in the licensee's Pressure Temperature Limits Report (PTLR) in low-temperature modes of operation. LCO 3.4.12 provides overpressure protection by specifying a maximum coolant input capability and an adequate pressure relief capability.
Enclosure 2
2.2 Applicable Regulatory Requirements Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. In 10 CFR 50.36, "Technical specifications," the NRC established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings, (2) LCOs, (3) SRs, (4) design features, and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plant's TSs. The regulations in 10 CFR 50.36(c)(2)(i}, state, in part, that the "[l]imiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility." More specifically, 10 CFR 50.36(c)(2)(ii) states that "A [TS LCO] of a nuclear reactor must be established for each item meeting one or more of the following criteria: [ ... ] Criterion 2.
A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier."
The COMS controls RCS pressure at low temperatures so that the integrity of the RCPB is not compromised by violating the pressure and temperature limits required by 10 CFR Part 50, Appendix G. The LCO ensures that only a limited inventory of mass input sources are available for injection into the RCS during low-temperature operation, consistent with Criterion 2 of 10 CFR 50.36(c)(2)(ii).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes The current TS LCO 3.4.12 states, in part:
COMS shall be OPERABLE with a maximum of zero safety injection pumps and one centrifugal charging pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:
The revised TS LCO 3.4.12 would state, in part:
COMS shall be OPERABLE with a maximum of zero safety injection pumps, one Emergency Core Cooling System (ECCS) centrifugal charging pump, and the normal charging pump capable of injecting into the RCS and the accumulators isolated, and one of the following pressure relief capabilities:
The current Note 1 for the LCO states:
- 1. Two centrifugal charging pumps may be made capable of injecting for
- 5 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operations.
The revised Note 1 for the LCO would state:
- 1. Two ECCS centrifugal charging pumps may be made capable of injecting for :5 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operations.
Actions A and 8 are specific actions in TS LCO 3.4.12 that are related to these pumps.
Action A applies to the given condition of, "One or more safety injection pumps capable of injecting into the RCS," and it requires action to be completed immediately to verify a maximum of zero safety injection pumps are capable of injecting into the RCS. Action 8 applies to the given condition of, "Two centrifugal charging pumps capable of injecting into the RCS," and requires action to be completed immediately to verify a maximum of one centrifugal charging pump is capable of injecting into the RCS.
Note 1 of LCO 3.4.12, and Condition 8, would each be revised to specify the CCPs as ECCS CCPs.
Current Condition 8 states:
Two centrifugal charging pumps capable of injecting into the RCS.
Revised Condition 8 would state:
Two ECCS centrifugal charging pumps capable of injecting into the RCS.
Current Required Action 8.1 states:
Initiate action to verify a maximum of one centrifugal charging pump is capable of injecting into the RCS.
Revised Required Action 8.1 would state:
Initiate action to verify a maximum of one ECCS centrifugal charging pump and the normal charging pump capable of injecting into the RCS.
Current SR 3.4.12.2 states:
Verify a maximum of one centrifugal charging pump is capable of injecting into the RCS.
Revised SR 3.4.12.2 would state:
Verify a maximum of one ECCS centrifugal charging pump and the normal charging pump capable of injecting into the RCS.
This amendment application also requests changes toTS Table 3.3.1-1, to correct references to Notes 1 and 2 for the Allowable Values for Functions 6 and 7, respectively, of Table 3.3.1-1.
The notes currently refer to pages 3.3-23 and 3.3-24 instead of the correct pages, which are 3.3-25 and 3.3-26, respectively. When the applicant made changes to the TS under License
Amendment No. 202, the pages were changed without updating the references in Table 3.3.1-1.
To correct the editorial error, the applicant has proposed to replace the page references with the explanatory phrase "(at the end of this Table)." The proposed change would remove the need to update these references in subsequent license amendments that impact these page numbers in the TSs, without changing the requirements of the TSs.
3.2 Summary of Technical Information Provided by the Licensee In its letter dated January 23, 2014, the licensee stated, in part, that The mass injection rate assumed in the design-basis mass input transient is based on 100% flow capacity of the NCP and one CCP. The maximum combined pump flow has been assumed in order to envelop the maximum flow possible by the operational configuration that uses the NCP for charging with one CCP remaining OPERABLE, or use of the CCP for charging with the NCP remaining functional, during shutdown modes.
This assumption is consistent with the TS 3.4.12 LCO, which requires all safety injection pumps and one of the two ECCS CCPs to be made incapable of injecting into the RCS and, therefore, allows an ECCS CCP and the NCP to be functional under these modes of operation. Note 1 of the LCO allows for two ECCS CCPs to be capable of injection for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during pump swap operation, which is consistent with the NRC-approved Technical Specifications Task Force (TSTF) traveler TSTF-285-A, "Charging Pump Swap LTOP Allowance" (ADAMS Accession No. ML040620093), and is mitigated by the following factors.
- At low RCS temperature and pressure, TS LCO 3.4.12 requires redundant active COMS relief valves or an adequate passive vent path for the RCS, although only one is credited by the analysis for the mass injection transient.
- In event of an ECCS actuation signal, the automatic signals to start both ECCS CCPs would be accompanied by an automatic signal to trip the NCP.
- Risk of an inadvertent ECCS actuation signal is mitigated by a procedural requirement to block the analog ECCS actuation signals, except Containment Pressure - High, below the P-11 set point (pressurizer pressure less than 1970 pounds per square inch gauge),
in Mode 3.
- When present, a vapor bubble in the pressurizer will mitigate the pressure spike associated with a mass injection transient. Operation without a vapor bubble in the pressurizer (pressurizer water-solid) has been evaluated to be an Infrequently Performed Test or Evolution (I PTE) with potential for high consequences if the activity is performed incorrectly. As an IPTE, this activity receives additional oversight from Callaway senior management, including an evaluation of whether Just-In-Time Training (JITT) is needed prior to performing the activity.
For the Callaway Replacement Steam Generator (RSG) project (License Amendment No. 168, dated September 29, 2005; available at ADAMS Accession No. ML052570086), the licensee's contractor, Westinghouse Electric Company LLC, reanalyzed the COMS heat injection transient
due the steam generator design changes, and concluded that the mass injection analysis results would not be impacted. The analysis was discussed in Section 4.3.5 ofWCAP-16265-P, "Callaway Replacement Steam Generator program NSSS Licensing Report," August 2004 (proprietary, non-publically available) and Section 4.3.5 of the RSG license amendment request dated September 17, 2004 (ADAMS Accession No. ML042870372), and in Section 3.4.3.5 of the NRC staff's license amendment safety evaluation.
The licensee also notes that the staff has reviewed and approved a similar amendment for Wolf Creek Generating Station (WCGS), WCGS License Amendment No. 207, dated December 6, 2013 (ADAMS Accession No. ML13282A534). Callaway is the same design (standard nuclear power system; SNUPS) as WCGS. The proposed revisions toTS 3.4.12 LCO Note 1, Condition 8, Action 8.1, and SR 3.4.12.2 are the same as those approved by the NRC staff in the WCGS amendment, except for plant-specific nomenclature. The revised TS LCO 3.4.12 would be the same as the approved WCGS TS LCO 3.4.12 except that the Callaway LCO uses "COMS ... ",
instead of the WCGS nomenclature of "An LTOP System ... ", to reflect that the system that performs the LTOP function at Callaway is called the COMS.
3.3 NRC Staff Evaluation The NRC staff reviewed the license amendment request by evaluating the submitted information, verifying that the proposed LCO is consistent with the assumptions in the applicable safety analysis, and verifying the current licensing basis. The staff also verified that the revised Note 1, which provides limited exceptions to the LCO, is augmented by adequate station procedures and additional safety considerations to ensure that the exceptions will continue to provide adequate protection of the public health and safety.
The proposed LCO would continue to allow two ECCS CCPs to be in an operable configuration for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (Note 1 of LCO 3.4.12). The mass input analysis does not address this condition, but it is consistent with NRC-approved TSTF-285-A, Insert 1, which states the following:
The LCO is modified by two Notes. Note 1 allows [two charging pumps] to be made capable of injecting for :s; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during pump swap operations. One hour provides sufficient time to safely complete the actual transfer and to complete administrative controls and surveillance requirements associated with the swap.
The intent is to minimize the actual time that more than [one] charging pump is physically capable of injection.
Based on its review of TSTF-285-A, Insert 1, the NRC staff confirmed that the licensee's proposed revision is consistent with the TSTF. The licensee's proposed LCO Note will similarly minimize the actual time that more than one or two charging pumps at a time will be physically capable of injection. The licensee provided additional justification, as discussed in Section 3.2 of this safety evaluation, which would mitigate the possible impact of having both ECCS CCPs and the NCP capable of injecting into the RCS during a pump swap. Therefore, the NRC staff determined that having two ECCS CCPs capable of injection for pump swap conditions remains acceptable.
In the NRC staff's safety evaluation for Callaway License Amendment No. 124 dated April 2, 1998 (ADAMS Accession No. ML021640371), the staff discussed that one ECCS CCP and the NCP could be operable consistent with LCO 3.5.4.5. Specifically, Section 2.2.1 of the evaluation states, in part, The mass input transient analysis assumes simultaneous injection of both a centrifugal charging pump and the "normal" charging pump into the water-solid RCS while the RHRS [residual heat removal system] and the letdown line are isolated. This assumption is consistent with LCO 3.5.4, which requires all safety injection pumps and one of the two centrifugal charging pumps to be inoperable while in MODE 5 and MODE 6 operation with the reactor vessel head on, and therefore, allows a centrifugal charging pump and the "normal" charging pump to be operable under these modes of operation.
In Callaway License Amendment No. 133 dated May 28, 1999 (ADAMS Accession No. ML021640446), the licensee converted from custom TSs (CTS) to Improved Technical Specifications (ITS). As part of this change, the TS LCO for COMS was relocated from TS 3.5.4 to TS 3.4.12. The safety evaluation for License Amendment No. 133, page 41, states that, "The initial conditions and assumptions for the COMS mass addition and heat injection transients will be unchanged." The evaluation also approved the relaxation to allow both ECCS CCPs to be capable of injecting into the RCS during pump swap operations during Mode 4:
Note 1 on centrifugal charging pump (CCP) swap operations is a relaxation of the CTS in Modes 4 only because it allows both CCPs to be capable of injecting into the RCS for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> throughout applicability to the low temperature overpressure protection provided by the COMS. This is different from the CTS and the STS [Standard Technical Specifications].
Based on the NRC staff's safety evaluations for License Amendment Nos. 124, 133, and 168, the proposed change to TS 3.4.12 in this amendment is consistent with the staff's previous approvals that reflect that the Callaway mass input transient analysis assumes that an ECCS centrifugal charging pump and the normal charging pump are capable of injecting into the reactor coolant system, when TS 3.4.12 is applicable (i.e., Mode 4 with any RCS cold leg temperature s 275°F, Mode 5, Mode 6 when the reactor vessel head is on).
The staff determined that the LCO as proposed will specify the lowest functional capability or performance equipment for safe operation of the facility as required by 10 CFR 50.36(c)(2)(i).
The staff made this determination because the LCO aligns with the safety analysis provided by the licensee with respect to the assumed mass input sources in the analysis.
The LCO, as proposed, will restrict the available mass input sources to be consistent with those assumed in the safety analysis, which is consistent with 10 CFR 50.36(c)(2)(ii)(B) in that the LCO will restrict operation to the initial condition assumed in the mass input transient analysis, as previously approved in Amendment Nos. 124, 133, and 168. This restriction, in turn, assures that the reactor coolant system will not exceed the pressure/temperature limits required by 10 CFR Part 50, Appendix G. Based on these considerations, the NRC staff determined that the proposed LCO revisions are acceptable.
The licensee also proposed a change unrelated to the COMS to revise TS Table 3.3.1-1, "Reactor Trip System Instrumentation," to remove page number references which currently refer to pages 3.3-23 and 3.3-24, instead of to the correct pages 3.3-25 and 3.3-26, respeCtively.
The proposed revision would refer to the "end of the table" instead of to a specific page number.
This change is considered administrative and is, therefore, acceptable.
3.4 Conclusion Based on the above, the NRC staff determined that the proposed changes to Callaway TS 3.4.12 and TS Table 3.3.1-1 will continue to comply with 10 CFR 50.36 and 10 CFR Part 50, Appendix G and, therefore, are 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. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The 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. 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 and there has been no public comment on such finding published in Federal Register on April 1, 2014 (79 FR 18348). 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 Contributor: D. Saenz, NRR/DSS/SRXB Date: January 20, 2015
ML143508239 *memo dated OFFICE NRR/DORL/LPL4-1/PM N RR/DORLILPL4-1/LA NRR/DSS/STSB/BC NRR/DSS/SRXB/BC NAME Flyon JBurkhardt REIIiott CJackson*
DATE 12/24/14 12/24/14 12/31/14 12/5/14 OFFICE OGC-NLO NRR/DORLILPL4-1/BC(A) NRR/DORLILPL4-1/PM NAME A Ghosh EOesterle Flyon DATE 1/15/15 15/17115 1/20/15