Letter Sequence Request |
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EPID:L-2021-LLA-0022, Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume (Approved, Closed) |
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Category:Letter type:RA
MONTHYEARRA-24-0180, Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change2024-08-29029 August 2024 Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change RA-24-0178, Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks2024-07-10010 July 2024 Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks RA-24-0166, Revision to Emergency Plan Implementing Procedure2024-06-27027 June 2024 Revision to Emergency Plan Implementing Procedure RA-24-0163, Registration for Use of General License Spent Fuel Casks2024-06-19019 June 2024 Registration for Use of General License Spent Fuel Casks RA-24-0164, Inservicee Inspection Program Owners Activity Report Refueling Outage 252024-06-19019 June 2024 Inservicee Inspection Program Owners Activity Report Refueling Outage 25 RA-24-0030, Duke Energy - Annual Radioactive Effluent Release Report - 20232024-04-29029 April 2024 Duke Energy - Annual Radioactive Effluent Release Report - 2023 RA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-24-0031, Annual Radiological Environmental Operating Report - 20232024-04-23023 April 2024 Annual Radiological Environmental Operating Report - 2023 RA-24-0094, Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Traini2024-04-17017 April 2024 Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Training RA-24-0075, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization2024-04-10010 April 2024 Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization RA-24-0074, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-10010 April 2024 Primary Containment Penetration Local Leak Rate Testing Failure RA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations RA-24-0085, Onsite Property Insurance Coverage2024-04-0101 April 2024 Onsite Property Insurance Coverage RA-24-0086, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-04-0101 April 2024 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-24-0058, Cycle 25 Core Operating Limits Report (COLR)2024-03-0101 March 2024 Cycle 25 Core Operating Limits Report (COLR) RA-24-0015, Submittal of 2023 Sea Turtle Annual Report2024-01-10010 January 2024 Submittal of 2023 Sea Turtle Annual Report RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-23-0199, Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2023-08-18018 August 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner RA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023 License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . RA-23-0045, Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 262023-06-28028 June 2023 Inservice Inspection Program Owner'S Activity Report for Unit 2 Refueling Outage 26 RA-23-0145, Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks2023-06-15015 June 2023 Independent Spent Fuel Storage Installation (Isfsi), Registration for Use of General License Spent Fuel Casks RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0139, Registration for Use of General License Spent Fuel Casks2023-06-0606 June 2023 Registration for Use of General License Spent Fuel Casks RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0096, Post Accident Monitoring (PAM) Instrumentation Report2023-04-12012 April 2023 Post Accident Monitoring (PAM) Instrumentation Report RA-23-0063, Notification of Deviation from BWRVIP Guidelines2023-04-11011 April 2023 Notification of Deviation from BWRVIP Guidelines RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0021, Unit 2 Cycle 26 Core Operating Limits Report (COLR)2023-02-22022 February 2023 Unit 2 Cycle 26 Core Operating Limits Report (COLR) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-23-0010, 2022 Sea Turtle Annual Report2023-01-0909 January 2023 2022 Sea Turtle Annual Report RA-22-0616, Revision to Brunswick Snubber Program Plan2023-01-0505 January 2023 Revision to Brunswick Snubber Program Plan RA-22-0308, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2022-12-16016 December 2022 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner RA-22-0342, Revision to Emergency Plan On-Shift Staffing Analysis2022-12-0808 December 2022 Revision to Emergency Plan On-Shift Staffing Analysis RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0344, Notification of Deviation from BWRVIP Guidelines2022-11-30030 November 2022 Notification of Deviation from BWRVIP Guidelines RA-22-0261, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2022-09-15015 September 2022 Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks RA-22-0271, Accident Monitoring Instrumentation Special Report2022-09-13013 September 2022 Accident Monitoring Instrumentation Special Report RA-22-0252, Registration for Use of General License Spent Fuel Casks2022-08-25025 August 2022 Registration for Use of General License Spent Fuel Casks RA-22-0190, Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 28, 10 CFR 54.37 Update, Technical Requirements Manuals, Quality Assurance Program Description, Technical Specification Bases, 10 CFR 50.59 and 10 CFR .2022-08-11011 August 2022 Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 28, 10 CFR 54.37 Update, Technical Requirements Manuals, Quality Assurance Program Description, Technical Specification Bases, 10 CFR 50.59 and 10 CFR . RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 2024-08-29
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023 License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-21-0239, Application to Revise Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2021-12-0202 December 2021 Application to Revise Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RA-21-0272, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-11-0101 November 2021 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-21-0141, Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2021-04-26026 April 2021 Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative RA-18-0183, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-04-0101 April 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-21-0009, Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume2021-02-23023 February 2021 Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume RA-20-0361, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, Dated September 24, 2020, ADAMS Accession Number ML20272A0912020-11-17017 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, Dated September 24, 2020, ADAMS Accession Number ML20272A091 RA-20-0165, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-24024 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RA-20-0127, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22020-07-27027 July 2020 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 RA-20-0142, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems2020-07-21021 July 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems RA-19-0437, Nos. 1 & 2 - License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Categorization Process2020-07-0909 July 2020 Nos. 1 & 2 - License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Categorization Process RA-19-0431, Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR2020-03-0909 March 2020 Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR ML20073F1862020-03-0606 March 2020 Issuance of Amendment Nos. 299 and 327 to Revise Technical Specification 5.6.5b to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2018-LLA-0273) (Redacted) RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-03-18018 March 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0015, Request for License Amendment: Surveillance Requirements for Safety Relief Valves2019-03-0404 March 2019 Request for License Amendment: Surveillance Requirements for Safety Relief Valves RA-18-0148, License Amendment Request to Revise Units 1 and 2 Technical Specification 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2019-02-27027 February 2019 License Amendment Request to Revise Units 1 and 2 Technical Specification 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-18-0234, (Bsep), Unit Nos. 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-269, Allow Administrative Means of Position Verification for Locked or Sealed Valves.2018-12-14014 December 2018 (Bsep), Unit Nos. 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-269, Allow Administrative Means of Position Verification for Locked or Sealed Valves. ML18291A6282018-10-18018 October 2018 Request for License Amendment - Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation RA-18-0135, Request for License Amendment - Technical Specification 3.7.4, Control Room Air Conditioning (AC) System2018-08-30030 August 2018 Request for License Amendment - Technical Specification 3.7.4, Control Room Air Conditioning (AC) System RA-18-0073, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-06-28028 June 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-04-0404 April 2018 Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2018-01-10010 January 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors BSEP 17-0111, Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-28028 November 2017 Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0108, Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-22022 November 2017 Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0017, Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2017-11-15015 November 2017 Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material BSEP 17-0078, Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.52017-10-0303 October 2017 Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.5 BSEP 17-0060, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-06-29029 June 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. ML17088A3962017-06-0707 June 2017 Issuance of Amendments Regarding Revisions of Technical Specifications to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs BSEP 17-0020, Supplement - License Amendment Request Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2017-02-27027 February 2017 Supplement - License Amendment Request Regarding Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program BSEP 16-0083, Steam Electric Plant, Units 1 And. 2 - Application to Revise Technical Specifications to Adopt TSTF-535, Revision O, Revise Shutdown Margin Definition to Address Advance Fuel Designs.2016-11-18018 November 2016 Steam Electric Plant, Units 1 And. 2 - Application to Revise Technical Specifications to Adopt TSTF-535, Revision O, Revise Shutdown Margin Definition to Address Advance Fuel Designs. BSEP 16-0082, Transmittal of Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2016-10-27027 October 2016 Transmittal of Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. BSEP 16-0087, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A.2016-09-28028 September 2016 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A. RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML16287A4222016-09-26026 September 2016 FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. BSEP 16-0078, Request for License Amendment - Revision to Technical Specification 2.1.1.2 Minimum Critical Power Ratio Safety Limit2016-09-26026 September 2016 Request for License Amendment - Revision to Technical Specification 2.1.1.2 Minimum Critical Power Ratio Safety Limit BSEP 16-0014, Request for License Amendment-Reactor Protection System(Rps) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.2 and 3.3.8.2.32016-04-13013 April 2016 Request for License Amendment-Reactor Protection System(Rps) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.2 and 3.3.8.2.3 RA-15-0040, License Amendment Request, Change in Corporate Form of Duke Energy Progress2016-02-0101 February 2016 License Amendment Request, Change in Corporate Form of Duke Energy Progress BSEP 15-0101, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2015-12-21021 December 2015 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 ML15175A4392015-06-24024 June 2015 Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-523, Rev. 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 1 of 6 RA-15-0009, Supplement to Application for Order Approving Transfer of Control of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.902015-03-0404 March 2015 Supplement to Application for Order Approving Transfer of Control of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.90 BSEP 15-0007, Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 12015-02-19019 February 2015 Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 1 2023-08-17
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John A. Krakuszeski Vice President Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 o: 910.832.3698 February 23, 2021 Serial: RA-21-0009 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume Ladies and Gentlemen:
Pursuant to 10 CFR 50.90, Duke Energy Progress, LLC (Duke Energy), is submitting a request for an amendment to the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed change increases the minimum boron solution storage tank volume requirements of Figure 3.1.7-1, "Sodium Pentaborate Solution Volume Versus Concentration Requirements," for the Standby Liquid Control (SLC) system.
The enclosure provides a description and assessment of the proposed change. Attachments 1 and 2 to the enclosure provide the existing TS pages, for Units 1 and 2, respectively, marked-up to show the proposed change. Attachments 3 and 4 provide revised (i.e., typed) TS pages for Units 1 and 2, respectively. The existing Unit 1 TS Bases page, marked-up to show corresponding changes, is provided in Attachment 5 for information only.
Duke Energy request approval of the proposed amendment by March 10, 2022, to support startup of Unit 1 from the 2022 refueling outage. Once approved, the Unit 1 amendment shall be implemented prior to startup from the 2022 Unit 1 refueling outage and the Unit 2 amendment shall be implemented prior to startup from the 2023 Unit 2 refueling outage.
In accordance with 10 CFR 50.91, Duke Energy is providing a copy of the proposed license amendment to the designated representative for the State of North Carolina.
This document contains no new regulatory commitments. Please refer any questions regarding this submittal to Mr. Art Zaremba, Director - Nuclear Fleet Licensing, at (980) 373-2062.
U.S. Nuclear Regulatory Commission Page 2 of 2 I declare, under penalty of perjury, that the foregoing is true and correct. Executed on February 23, 2021 Sincerely, John A. Krakuszeski MAT/mat
Enclosure:
Description and Assessment of the Proposed Change Attachment 1: Proposed Technical Specification Changes (Mark-Up)- Unit 1 Attachment 2: Proposed Technical Specification Changes (Mark-Up)- Unit 2 Attachment 3: Revised (Typed)Technical Specification Page - Unit 1 Attachment 4: Revised (Typed)Technical Specification Page - Unit 2 Attachment 5: Technical Specification Bases Page (Mark-Up)- Unit 1 (For Information Only) cc:
Ms. Laura Dudes, Regional Administrator, Region II Mr. Andrew Hon, Project Manager Mr. Gale Smith, NRC Senior Resident Inspector Chair - North Carolina Utilities Commission Mr. W. Lee Cox, Ill Section Chief, Radiation Protection Section, NC DHHS
RA-21-0009 Enclosure Page 1 of 7 Description and Assessment of the Proposed Change
Subject:
Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume
- 1.
SUMMARY
DESCRIPTION
- 2. DETAILED DESCRIPTION 2.1 System Design and Operation 2.2 Current Technical Specification Requirements 2.3 Reason for the Proposed Change 2.4 Description of the Proposed Change
- 3. TECHNICAL EVALUATION
- 4. REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 No Significant Hazards Consideration Determination Analysis 4.4 Conclusions
- 5. ENVIRONMENTAL CONSIDERATION
- 6. REFERENCES ATTACHMENTS:
- 1. Proposed Technical Specification Changes (Mark-Up) - Unit 1
- 2. Proposed Technical Specification Changes (Mark-Up) - Unit 2
- 3. Revised (Typed) Technical Specification Pages - Unit 1
- 4. Revised (Typed) Technical Specification Pages - Unit 2
- 5. Technical Specification Bases Pages (Mark-Up) - Unit 1 (For Information Only)
RA-21-0009 Enclosure Page 2 of 7
- 1.
SUMMARY
DESCRIPTION Pursuant to 10 CFR 50.90, Duke Energy Progress, LLC (Duke Energy), is submitting a request for an amendment to the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed change increases the minimum boron solution storage tank volume requirements of Figure 3.1.7-1, "Sodium Pentaborate Solution Volume Versus Concentration Requirements," for the Standby Liquid Control (SLC) system.
- 2. DETAILED DESCRIPTION 2.1 System Design and Operation The SLC system is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory, which is at the peak of the xenon transient, to a subcritical condition with the reactor in the most reactive, xenon free state without taking credit for control rod movement. The SLC System satisfies the requirements of 10 CFR 50.62, "Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants."
The SLC system consists of a sodium pentaborate (SPB) solution storage tank, two positive displacement pumps, two explosive valves that are provided in parallel for redundancy, and associated piping and valves used to transfer the SPB solution from the storage tank to the reactor pressure vessel (RPV). The borated solution is discharged near the bottom of the core shroud, where it then mixes with the cooling water rising through the core.
The SLC system is used in the event that enough control rods cannot be inserted to accomplish shutdown and cooldown in the normal manner. The SLC System injects borated water into the reactor core to add negative reactivity to compensate for all of the various reactivity effects that could occur during plant operations.
Although not required by TSs, the SLC System is also used to maintain suppression pool pH level above 7 following a loss of coolant accident (LOCA) involving significant fission product releases. Maintaining suppression pool pH levels greater than 7 following an accident ensures that iodine will be retained in the suppression pool water as reflected in the LOCA dose analysis.
2.2 Current Technical Specification Requirements To comply with 10 CFR 50.62, BSEP uses a SPB solution with boron enriched to 92 atom-percent with boron-10 (B-10) isotope. The current volume versus concentration limits in Figure 3.1.7-1 are established to ensure that the SLC system injects a quantity of boron which produces a concentration of 720 ppm equivalent of natural boron in the reactor coolant at 70°F with normal reactor vessel water level. The current Figure 3.1.7-1 was established with issuance of the amendments approving implementation of Maximum Extended Load Line Limit Analysis Plus (MELLLA+) for BSEP (i.e., Reference 1).
2.3 Reason for the Proposed Change To accommodate core reload flexibility, the assumed 720 ppm equivalent of natural boron is being increased to 925 ppm. This increase in boron concentration will add significant margin to the SLC shutdown margin analysis which will sufficiently bound future advancements in core
RA-21-0009 Enclosure Page 3 of 7 designs without impacting operation. While recent core designs have shown a reduction in SLC shutdown margin, reloads beginning in 2022 (i.e., BSEP Unit 1) will require >720 ppm to achieve the required design margin.
2.4 Description of the Proposed Change The proposed change increases the minimum boron solution storage tank volume requirements of Figure 3.1.7-1. This is accomplished by shifting the left boundary of the Acceptable region of Figure 3.1.7-1 to the right. The existing minimum volume at a concentration of 10.5 weight percent SPB is increased from 1084 gallons to 1393 gallons. The existing minimum volume at a concentration of 8.5 weight percent SPB is increased from 1353 gallons to 1738 gallons. No additional Technical Specification changes are required to support the increase in boron concentration from 720 ppm is to 925 ppm.
The Applicable Safety Analysis section of the TS 3.1.7 Bases currently refers to 720 ppm equivalent of natural boron in the reactor coolant at 70°F. This is being updated to the new value of 925 ppm. The existing Unit 1 TS Bases page, marked to show this change, is provided for information only.
- 3. TECHNICAL EVALUATION The minimum amount of SPB to inject into the reactor vessel (i.e., left boundary of Figure 3.1.7-1) results in an equivalent concentration of natural boron (i.e., concentration used in the SLC SDM calculation) in the reactor coolant based on SPB concentration and B-10 enrichment. The quantity of reactor coolant is based on water, at 70°F, in the reactor vessel at normal vessel level, the recirculation loops, and the Shutdown Cooling portion of the Residual Heat Removal (RHR) System. To account for imperfect mixing, leakage, and additional water volume found in small piping connected to the reactor vessel, the minimum amount of SPB is then increased by 25 percent.
Increasing the boron concentration of equivalent natural boron to 925 ppm results in an increase in the minimum acceptable SPB solution volume reflected in the revised Figure 3.1.7-1. Since there are no changes to the SPB concentration range (i.e., 8.5 to 10.5 weight percent), SPB B-10 enrichment (i.e., 92 atom-percent) or the reactor coolant volume, the increase in SPB minimum volume is directly proportional to the increase in boron concentration. This is demonstrated below for the high SPB concentration limit (i.e., 10.5 weight percent):
925
= = 1084 = 1393 720 The proposed change is more restrictive than the current Acceptable region in Figure 3.1.7-1 and does not allow SLC tank concentration and volume combinations outside the currently approved range. In addition, no plant modifications are required based on recent surveillances of SLC tank level (SR 3.1.7.1).
RA-21-0009 Enclosure Page 4 of 7
- 4. REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria The requirements for ATWS are specified in 10 CFR 50.62, "Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants," which requires, in part, that:
(4) Each boiling water reactor must have a standby liquid control system (SLCS) with the capability of injecting into the reactor pressure vessel a borated water solution at such a flow rate, level of boron concentration and boron-10 isotope enrichment, and accounting for reactor pressure vessel volume, that the resulting reactivity control is at least equivalent to that resulting from injection of 86 gallons per minute of 13 weight percent sodium pentaborate decahydrate solution at the natural boron-10 isotope abundance into a 251-inch inside diameter reactor pressure vessel for a given core design.
The current compliance with 10 CFR 50.62 is based on an equivalency equation from Section 9.3.4.6 of the BSEP UFSAR, shown below.
(Q/86)*(M251/M)*(C/13)*(E/19.8) must be 1.E Where:
Variable Description Value Q Design flow rate 43 gpm M251 Reference plant (with 251-inch diameter vessel) 628,300 lbs mass of dilution water M Mass of BSEP dilution water at reference 485,500 lbs conditions C Sodium pentaborate chemical concentration. 8.5 weight percent E Minimum boron-10 enrichment. 92 atom percent When solved for the above values:
(43/86)*(628300/485500)*(8.5/13)*(92/19.8) = 1.966 None of the variables in this equation (i.e., flow rate, vessel water mass, SPB concentration and B-10 enrichment) are impacted by this change. Therefore, the requirements of 10 CFR 50.62 continue to be satisfied with the same margin established with the approval of Reference 1.
10 CFR 50.67, "Accident source term," in part, sets limits for the radiological consequences of a postulated design-basis accident using an accident source term. The analytical methods described in Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," July 2000, and dose limits defined in 10 CFR 50.67 comprise the design basis for BSEP (i.e., Reference 2). The BSEP Alternate Source Term analyses credit the use of the SLC injection to maintain a Suppression Pool pH of 7 or greater. Maintaining this pH retains the iodine deposited in the Suppression Pool from a
RA-21-0009 Enclosure Page 5 of 7 design basis LOCA in solution. Therefore, if a design basis LOCA were to occur, the entire contents of the SLC tank are manually injected. The proposed change to increase the minimum boron solution storage tank volume requirements of Figure 3.1.7-1 does not adversely impact the ability to maintain the suppression pH at or above 7.0.
4.2 Precedent No precedent associated with increasing the minimum boron solution storage tank volume requirements was identified.
4.3 No Significant Hazards Consideration Determination Analysis Pursuant to 10 CFR 50.90, Duke Energy Progress, LLC (Duke Energy), is requesting an amendment to the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP),
Unit Nos. 1 and 2. The proposed change increases the minimum boron solution storage tank volume requirements of Figure 3.1.7-1, "Sodium Pentaborate Solution Volume Versus Concentration Requirements," for the Standby Liquid Control (SLC) system.
Duke Energy has evaluated whether a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed). The proposed change increases the minimum boron solution storage tank volume requirements included in Figure 3.1.7-1.
The plant response to design basis accidents does not change. Operation or failure of the SLC system is not assumed to be an initiator of any analyzed event in the Updated Final Safety Analysis Report (UFSAR) and cannot cause an accident. The proposed change conforms to NRC regulatory requirements regarding anticipated transients without scram (ATWS) and accident source term (AST).
Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change increases the minimum boron solution storage tank volume requirements included in Figure 3.1.7-1. It does not require any physical modification to the plant and it does not alter the design configuration, or method of operation of plant equipment beyond its normal functional capabilities. The proposed change does not reduce or adversely affect the capabilities of any plant structure, system, or component in the performance of their safety function. Also, the response of the plant and the operators following design basis accidents is unaffected by the proposed change.
RA-21-0009 Enclosure Page 6 of 7 Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change increases the minimum boron solution storage tank volume requirements included in Figure 3.1.7-1. The proposed changes conform to NRC regulatory requirements regarding ATWS and AST. To accommodate core reload flexibility, the assumed 720 ppm equivalent of natural boron is being increased to 925 ppm; which is accomplished by increasing the minimum boron solution storage tank volume requirements. This increase in boron concentration will add significant margin to the SLC shutdown margin analysis and will sufficiently bound future advancements in core designs without impacting operation. The proposed change conforms to NRC regulatory requirements regarding ATWS and AST.
Therefore, the proposed amendment does not result in a significant reduction in the margin of safety.
Based on the above, Duke Energy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.4 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
- 5. ENVIRONMENTAL CONSIDERATION A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
- 6. REFERENCES
- 1. Letter from the U.S. Nuclear Regulatory Commission to Mr. William R. Gideon, Brunswick Steam Electric Plant, Units 1 and 2 - "Issuance of Amendment Regarding Core Flow Operating Range Expansion (MELLLA+)," dated September 18, 2018, ADAMS Accession Number ML18172A258
RA-21-0009 Enclosure Page 7 of 7
- 2. Letter from the U.S. Nuclear Regulatory Commission to Mr. J. S. Keenan, Brunswick Steam Electric Plant, Units 1 and 2 - "Issuance of Amendment Re: Alternative Source Term," dated May 30, 2002, ADAMS Accession Number ML021480483
RA-21-0009 Enclosure Attachment 1 Proposed Technical Specification Changes (Mark-Up)
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Insert A RA-21-0009 Enclosure Attachment 3 Revised (Typed) Technical Specification Page Unit 1
SLC System 3.1.7 Brunswick Unit 1 3.1-23 Amendment No. 285
RA-21-0009 Enclosure Attachment 4 Revised (Typed) Technical Specification Page Unit 2
SLC System 3.1.7 Brunswick Unit 2 3.1-23 Amendment No. 313
RA-21-0009 Enclosure Attachment 5 Technical Specification Bases Page (Mark-Up) - Unit 1 (For Information Only)
SLC System B 3.1.7 B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.7 Standby Liquid Control (SLC) System BASES BACKGROUND The SLC System is designed to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory (which is at the peak of the xenon transient) to a subcritical condition with the reactor in the most reactive, xenon free state without taking credit for control rod movement. The SLC System satisfies the requirements of 10 CFR 50.62 (Ref. 1) on anticipated transient without scram.
The SLC System is also used to maintain suppression pool pH level above 7 following a loss of coolant accident (LOCA) involving significant fission product releases. Maintaining suppression pool pH levels greater than 7 following an accident ensures that iodine will be retained in the suppression pool water (Ref. 2).
The SLC System consists of a boron solution storage tank, two positive displacement pumps, two explosive valves that are provided in parallel for redundancy, and associated piping and valves used to transfer borated water from the storage tank to the reactor pressure vessel (RPV). The borated solution is discharged near the bottom of the core shroud, where it then mixes with the cooling water rising through the core. A smaller tank containing demineralized water is provided for testing purposes.
APPLICABLE The SLC System is manually initiated from the main control room, as SAFETY ANALYSES directed by the emergency operating procedures, if the operator believes the reactor cannot be shut down, or kept shut down, with the control rods.
The SLC System is used in the event that enough control rods cannot be inserted to accomplish shutdown and cooldown in the normal manner.
The SLC System injects borated water into the reactor core to add negative reactivity to compensate for all of the various reactivity effects that could occur during plant operations. To meet this objective, it is necessary for SLC to inject a quantity of boron which produces a concentration of 720 925 ppm equivalent of natural boron in the reactor coolant at 70°F with normal reactor vessel water level. To allow for (continued)
Brunswick Unit 1 B 3.1.7-1 Revision No. 34