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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 Rinmy 29, 2016 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 OF TECHNICAL SPECIFICATIONS 2.1.1.1 AND 5.6.5 TO REMOVE UNCERTAINTIES FROM THE DEPARTURE FROM NUCLEAR BOILING RATIO SAFETY LIMIT AND ADOPT WCAP-14565-P-A METHODOLOGY (CAC NO. MF6249)
Dear Mr. Diya:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 216 to Renewed 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 May 8, 2015, as supplemented by letter dated November 9, 2015.
The amendment revises TSs 2.1.1.1 and 5.6.5 to adopt the NRG-approved methodologies of Westinghouse Commercial Atomic Power reports (WCAP)-14483-A, "Generic Method for Expanded Core Operating Limits Report," and WCAP-14565-P-A Addendum 2-P-A, "VIPRE-1 Modeling and Qualification for Pressurized Water Reactor Non-LOCA [Loss-of-Coolant Accident] Thermal-Hydraulic Safety Analysis," respectively. The change in TS 2.1.1.1 would provide the Departure from Nucleate Boiling Ratio in a form that reduces the need for cycle-specific license amendments and the change in TS 5.6.5 adds an NRG-approved methodology for determining core operating limits.
F. Diya 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, <if_
?J n Klos, 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. 216 to NPF-30
- 2. Safety Evaluation cc w/encls: 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 RENEWED FACILITY OPERATING LICENSE Amendment No. 216 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 May 8, 2015, as supplemented by letter dated November 9, 2015, 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. 216 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. 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 Robert J. Pascarelli, Chief Plant Licensing Branch IV-1 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 lssuance:FEtnmy 29, 2016
ATTACHMENT TO LICENSE AMENDMENT NO. 216 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.
Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT 2.0-1 2.0-1 5.0-25 5.0-25
(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. 216 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. 216
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded:
2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained ~ 1.17 for the WRB-2 DNB correlation.
2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 58°F per 10,000 MWd/MTU of burnup.
2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained ~ 2735 psig.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
CALLAWAY PLANT 2.0-1 Amendment 216
Reporting Requirements 5.6 5.6 Reporting Requirements
- 4. WCAP-12610-P-A, "VANTAGE+ FUEL ASSEMBLY REFERENCE CORE REPORT."
- 5. WCAP-11397-P-A, "REVISED THERMAL DESIGN PROCEDURE."
- 6. WCAP-14565-P-A, "VIPRE-01 MODELING AND QUALIFICATION FOR PRESSURIZED WATER REACTOR NON-LOCA THERMAL-HYDRAULIC SAFETY ANALYSIS."
- 7. WCAP-10851-P-A, "IMPROVED FUEL PERFORMANCE MODELS FOR WESTINGHOUSE FUEL ROD DESIGN AND SAFETY EVALUATIONS."
- 8. WCAP-15063-P-A, "WESTINGHOUSE IMPROVED PERFORMANCE ANALYSIS AND DESIGN MODEL (PAD 4.0)."
- 9. WCAP-8745-P-A, "DESIGN BASES FOR THE THERMAL OVERPOWER OT AND THERMAL OVERTEMPERATURE OT TRIP FUNCTIONS."
- 10. WCAP-10965-P-A, "ANC: A WESTINGHOUSE ADVANCED NODAL COMPUTER CODE."
- 11. WCAP-11596-P-A, "QUALIFICATION OF THE PHOENIX-P/ANC NUCLEAR DESIGN SYSTEM FOR PRESSURIZED WATER REACTOR CORES."
- 12. WCAP-13524-P-A, "APOLLO: A ONE DIMENSIONAL NEUTRON DIFFUSION THEORY PROGRAM."
- 13. WCAP-14565-P-A Addendum 2-P-A, "Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications."
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
(continued)
CALLAWAY PLANT 5.0-25 Amendment No. 216
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 216 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483
1.0 INTRODUCTION
By letter dated May 8, 2015 (Reference 1), as supplemented by letter dated November 9, 2015 (Reference 2), Union Electric Company, dba Ameren Missouri (the licensee) submitted a request for changes to the Technical Specifications (TSs) for Callaway Plant, Unit 1 (Callaway).
The amendment would revise TS 5.6.5, "Core Operating Limits Report (COLR)," by adding a new U.S. Nuclear Regulatory Commission (NRC) approved methodology to the list of methodologies that are used to determine the core operating limits, and TS 2.1.1, "Reactor Core SLs [Safety Limits]," to revise the form of the departure from nucleate boiling ratio (DNBR) limit to reduce the need for cycle-specific license amendment requests (LARs) due to revised uncertainties calculated using an approved methodology.
The supplemental letter dated November 9, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 7, 2015 (80 FR 38763).
2.0 REGULATORY EVALUATION
The primary regulatory basis for evaluation of this LAR is paragraph 50.36(c)(1) of Title 1O of the Code of Federal Regulations (10 CFR). This section imposes a regulatory requirement on licensees to include all safety limits in the TS. Safety limits are defined as limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity. The DNBR is defined as the ratio of the heat flux needed to cause departure from nucleate boiling (DNB) to the actual local heat flux of a fuel rod. If the heat flux for a rod increases to the point at which DNB occurs, then the surface of the fuel rod cladding will become insulated from the surrounding coolant by a layer of steam due to the rapid conversion of a significant quantity of liquid to vapor. The resulting loss of heat transfer will cause fuel rod heatup and probable failure of the fuel rod geometry, resulting in a loss of a primary fission product barrier. In order to prevent this from occurring, a DNBR limit is established.
Enclosure 2
The DNBR limit is evaluated using an analysis acceptance criterion consistent with Chapter 15 of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," Revision 3, March 2007 (SRP) (Reference 3). In the SRP, the fission product barrier represented by the fuel pellet and cladding is assumed to have failed if the DNBR falls below the 95/95 DNBR limit. Therefore, the DNBR limit established in the TS must be sufficiently high to ensure that DNB will not occur on the limiting fuel rods during Condition I and II events, to a 95 percent probability, with 95 percent confidence.
Finally, 10 CFR 50.36(c)(5) describes a requirement to include any provisions relating to procedures, recordkeeping, and reporting necessary to assure operation of the facility in a safe manner. NRC Generic Letter 1988-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 3, 1988 (Reference 4), provides guidance on inclusion of a section under the administrative controls listed in the TS that addresses the use of the Core Operating Limits Report (COLR) to report data to the NRC that has been calculated using NRG-approved methodologies. For Callaway, this information has previously been incorporated as Section 5.6.5 of the TS. In addition to the requirement to establish core operating limits and document them in the COLR, the Callaway TS also includes a list of specific NRG-approved analytical methodologies that can be used to determine the core operating limits.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes The licensee is requesting two changes to the Callaway TS. The first change concerns modification of TS 2.1.1.1, which provides the DNBR limit for Callaway, to update the wording in a way that is more consistent with the intent of the COLR. The second change adds a new reference to the list of NRG-approved methodologies for calculation of core operating limits in TS 5.6.5.
TS 2.1.1. Reactor Core SLs Current TS 2.1.1.1 states:
The design limit departure from nucleate boiling ratio (DNBR) shall be maintained
<:: 1.22 for transients analyzed using the revised thermal design procedure (RTDP) methodology and the WRB-2 DNB correlation. For non-RTDP transients analyzed using the standard thermal design procedure, the DNBR shall be maintained greater than or equal to the applicable DNB correlation limit (<:: 1.17 for WRB-2, <:: 1.30 for W-3).
Revised TS 2.1.1.1 would state:
The departure from nucleate boiling ratio (DNBR) shall be maintained <:: 1.17 for the WRB-2 DNB correlation.
TS 5.6.5, Reporting Requirements TS 5.6.5.b would be revised to add a new analytical method, which would state:
- 13. WCAP-14565-P-A Addendum 2-P-A, "Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications."
3.2 Modification of TS 2.1.1.1 The modification being proposed by the licensee to TS 2.1.1.1 does two things: (1) the DNBR safety limit is specified without the addition of analytical uncertainties, and (2) the DNBR safety limit is only specified for the WRB-2 DNB correlation.
The licensee stated that the intent of the modification to TS 2.1.1.1 is to specify a "true" DNBR safety limit and allow the licensee to use NRG-approved methodologies to calculate the appropriate uncertainties as part of the process of determining the DNBR limit to be placed into the COLR. The previous form of TS 2.1.1.1 provided a DNBR limit of 1.22, which was calculated with some uncertainties statistically combined into the 1.17 limit for the WRB-2 DNB correlation. The proposed TS modification does not represent a change in methodology or basis for the DNBR limit. The primary change is that the licensee would be able to use specific methodologies listed in TS 5.6.5 that have been approved for use by the NRC to calculate cycle-specific uncertainties as part of generating the COLR limits, rather than fixing them as part of the TS limit. Consequently, the new value of 1.17 being proposed for inclusion in the TS is a DNBR limit that does not include any of the uncertainties that were previously included in the old value of 1.22. The references to the revised thermal design procedure were removed, because this procedure is used to calculate the overall DNBR uncertainty factor.
The licensee also removed the references to the DNBR safety limit for the W-3 DNB correlation.
The licensee no longer intends to use its prior W-3 correlation for analysis of certain regions, so it is appropriate to remove that specific correlation and its corresponding safety limit. However, the licensee is proposing to use two alternate DNB correlations (the ABB-NV and WLOP correlations, discussed in the next section). These DNB correlations have their own DNBR limits. The NRC staff asked the licensee to justify the non inclusion of these DNBR limits in TS 2.1.1.1. The licensee responded by stating that the content of the proposed revision to TS 2.1.1.1 was consistent with the standard TS and with the intent of the safety limit as discussed in the NRC safety evaluation report for WCAP-14483 A (Reference 5), on which the TS 2.1.1.1 format was based.
Reference 5, WCAP-14483-A, is a topical report that allows Westinghouse pressurized-water reactor (PWR) plants to relocate the Reactor Core Limits figure into the COLR and be replaced by the design basis DNB limit and the fuel centerline melt limit. Specifically for the DNBR, Reference 5, Appendix A, Insert 1, documents that TS 2.1.1.1 states that the DNBR shall be maintained greater than 1.17 for WRB-2 DNB correlations.
The basis for the current TS 2.1.1.1 format is described in Section 4. 0 of WCAP-14483-A. The DNBR safety limit provided in TS 2.1.1.1 is intended to be a design basis limit that has historically been met by ensuring that the plant stays within the bounds for the process variables
defined by the Reactor Core Limits figure in the COLR. This limit ensures that the DNB regulatory criteria are met during normal operating conditions and anticipated operational occurrences. The alternate DNB correlations are used in safety analyses where the primary WRB-2 correlation is no longer applicable. However, these analyses are either not bounding or are for events for which the DNB regulatory criteria do not apply (i.e., Condition Ill or IV events).
Therefore, the WRB-2 correlation is the only one used to establish the limiting values for the process variables used to confirm that the DNB criteria are met. Per Reference 5, Section 4.4, Revised Safety Limits, using the DNB criteria from Reference 5 satisfies 10 CFR 50.36 and is also consistent with the Standard Technical Specifications in Reference 6, in conjunction with the Appendix A markups. Therefore, the revised TS 2.1.1.1 is consistent with the Westinghouse Standard Technical Specifications in Reference 6, as well as a number of other NRG-approved TS 2.1.1.1 formulations (e.g., References 8 and 9).
In addition, cycle-specific uncertainties will be determined and applied using NRG-approved methodologies to determine the appropriate Reactor Protection System setpoints and Reactor Core Limits figure used to safeguard the DNBR limit as part of the generation of the COLR.
Therefore, the DNBR limit associated with the WRB-2 correlation is the design basis limit that satisfies the requirements for inclusion in the TS. Thus, the licensee's final TS pages meet the formatting acceptance criteria regarding revised safety limits stated in Reference 5 and the NRC staff finds this acceptable.
The proposed change to specify the WRB-2 DNBR limit with no uncertainties, and reference NRG-approved methodologies and the COLR for the final DNBR limit to be applied with uncertainties, is consistent with NRG-approved guidance for the Standard Technical Specifications for Westinghouse plants and for the relocation of certain information to the COLR. As a result, the NRC staff concludes that the proposed TS revision is acceptable.
3.3 Addition of New Methodologies to TS 5.6.5 The licensee is requesting the addition of a Westinghouse Electric Company LLC topical report, WCAP-14565-P-A Addendum 2-P-A, that has previously been reviewed and approved by the NRC for calculation of DNBR limits. The topical includes two DNB correlations, ABB-NV (for the nonmixing grid region of the fuel) and WLOP (for low flow, low pressure conditions). The NRC staff's final safety evaluation of the topical report (Reference 7), lists four limitations and conditions for any licensee that may choose to use these methodologies. The limitations and conditions require licensees to: (1) remain within the range of applicability for the ABB-NV and WLOP correlations for the analyses using these correlations; (2) use the same Fe factor as the primary DNB correlation; (3) justify the selection of the appropriate fuel-dependent parameters for each application of each correlation on a plant-specific basis; and (4) use the correlations in conjunction with the Westinghouse version of the VIPRE-01 subchannel analysis code.
In the LAR (Reference 1), Section 3.0, "COLR Analytical Method," the licensee explained how each condition would be met. In particular, the licensee indicated that it would comply with limitations 1, 2, and 4 as written in Reference 7. In addition, the licensee briefly discussed the justification for the selection of the appropriate DNB correlation, DNBR limit, and fuel-dependent parameters as they pertain to Callaway. The ABB-NV and WLOP DNB correlations will be used with the VIPRE analysis methodology and DNBR limits as approved in Reference 7. The rest of the fuel dependent parameters will not be changed from the current approved values for the fuel
loaded at Callaway. Since the fuel designs approved for use at Callaway, along with the Callaway reactor operating conditions, are consistent with those considered during the review of Reference 7, the justification was found to be appropriate based on the intended application of the methodologies to perform DNBR calculations for the fuel currently approved for use at Callaway.
Based on the fact that the licensee is adopting methodologies described in a topical report that has previously been reviewed and approved by the NRC, and has adequately demonstrated that all conditions in the corresponding safety evaluation are met, the NRC staff concludes that the proposed addition to TS 5.6.5 is acceptable.
3.4 Departures from NRG-Approved Methodology No departures from NRG-approved methodologies were identified in the proposed Callaway TS changes.
3.5 NRC Staff Conclusion
The NRC staff concludes that the licensee's proposed changes to the Callaway TS 2.1.1.1 is acceptable based on NRC guidance on the Reactor Core Limits figure in the COLR (Reference 5) and the existing Standard Technical Specifications format (Reference 6). The NRC staff also concludes that the licensee's proposed changes to the Callaway TS 5.6.5 is acceptable, based on an implementation of the new methodologies that is consistent with the limitations and conditions established as part of the generic NRC staff approval of the aforementioned methodologies in Reference 7.
4.0 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 July 7, 2015 (80 FR 38763). 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.
5.0 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.
6.0 REFERENCES
- 1. Maglio, S. A., Ameren Missouri, letter to U.S. Nuclear Regulatory Commission, "Docket Number 50-483, Callaway Plant Unit 1, Union Electric Co., Facility Operating License NPF-30, Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-145650P-A Methodology," dated May 8, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15132A137).
- 2. Maglio, S. A., Ameren Missouri, letter to U.S. Nuclear Regulatory Commission, "Docket Number 50-483, Callaway Plant Unit 1, Union Electric Co., Renewed Facility Operating License NPF-30, Revision of TS 2.1.1.1 and 5.6.5 to Remove Uncertainties from the DNBR Safety Limit and Adopt Approved WCAP-145650P-A Methodology," dated November 9, 2015 (ADAMS Accession No. ML15313A192).
- 3. U.S. Nuclear Regulatory Commission, NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," Chapter 15, Revision 3, March 2007 (ADAMS Accession No. ML070710376).
- 4. U.S. Nuclear Regulatory Commission, Generic Letter 1988-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," dated October 3, 1988 (ADAMS Accession No. ML031150407).
- 5. Sepp, H. A., Westinghouse Electric Company LLC, letter to U.S. Nuclear Regulatory Commission, transmittal of approved version of proprietary WCAP-14483-A, "Generic Methodology for Expanded Core Operating Limits Report," dated October 25, 1999 (ADAMS Accession No. ML020430092).
- 6. NUREG-1431, Revision 4, Volume 1, "Standard Technical Specifications -
Westinghouse Plants," April 2012 (ADAMS Accession No. ML 121 OOA222).
- 7. Nieh, H. K., U.S. Nuclear Regulatory Commission, letter to James A. Gresham, Westinghouse Electric Company, "Final Safety Evaluation for WCAP-14565-P-A, Addendum 2-P-A, "Extended Application of ABB-NV Correlation and Modified ABB-NV Correlation WLOP for PWR Low Pressure Applications," dated February 14, 2008 (ADAMS Accession No. ML080360381).
- 8. Peters, S., U.S. Nuclear Regulatory Commission, letter to D. M. Jamil, Duke Energy Corporation, "Catawba Nuclear Station, Units 1 and 2 RE: Issuance of Amendments (TAC Nos. MB8359 and MB8360," dated December 19, 2003 (ADAMS Accession No. ML033570134).
- 9. Clark, R., U.S. Nuclear Regulatory Commission, letter to Mary G. Korsnick, R. E. Ginna Nuclear Power Plant, "R. E. Ginna Nuclear Power Plant - Amendment Re: Revision to Core Safety Limits and Safety System Instrumentation Setpoints (TAC No. MB4789),"
dated September 22, 2004 (ADAMS Accession No. ML041180309).
Principal Contributor: S. Krepel, NRR/DSS/SRXB Date: .R:b:tmy 29, 2016
ML16020A516 *SE memo dated OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DSS/SRXB/BC* NRR/DSS/SNPB/BC NAME JKlos JBurkhardt CJackson (EOesterle for) JDean DATE 2/3/16 2/3/16 1/6/16 2/11/16 OFFICE NRR/DSS/STSB/BC OGC NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME RElliott MRing RPascarelli JKlos DATE 1/21/16 2/22/16 2/26/16 2/29/16