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Category:Letter type:RA
MONTHYEARRA-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 RA-22-0175, Post Accident Monitoring (PAM) Instrumentation Report2022-06-0101 June 2022 Post Accident Monitoring (PAM) Instrumentation Report RA-22-0155, Revision to Emergency Plan Annex and Implementing Procedure2022-05-26026 May 2022 Revision to Emergency Plan Annex and Implementing Procedure RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022 Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022 Duke Energy Common Emergency Plan, Revision 2, Summary of Changes RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0029, Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 20212022-04-27027 April 2022 Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 2021 RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-22-0114, Duke Energy Carolinas, LLC and Duke Energy Progress, LLC Submittal of 10CFR26.719(c)(1) Report of Unsatisfactory Performance of Health and Human Services Certified Laboratory2022-04-0101 April 2022 Duke Energy Carolinas, LLC and Duke Energy Progress, LLC Submittal of 10CFR26.719(c)(1) Report of Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-22-0095, Unit 1 Cycle 24 Core Operating Limits Report (COLR)2022-03-29029 March 2022 Unit 1 Cycle 24 Core Operating Limits Report (COLR) RA-22-0110, 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.2022-03-25025 March 2022 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. RA-22-0014, Duke Energy Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations2022-03-21021 March 2022 Duke Energy Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative RA-22-0046, Withdrawal of One-Time Exemption from 10 CFR 50, Appendix E, Section IV.F.2.d2022-01-31031 January 2022 Withdrawal of One-Time Exemption from 10 CFR 50, Appendix E, Section IV.F.2.d 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 2024-01-10
[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 July 27, 2020 Serial: RA-20-0127 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 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
Subject:
Application to Revise Technical Specifications to Adopt TSTF-568, "Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2" 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 (TSs) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2.
Duke Energy requests adoption of TSTF-568, "Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2." Technical Specifications Task Force (TSTF) Traveler TSTF-568 revises the Applicability and Actions of Technical Specification (TS) 3.6.3.2, "Primary Containment Oxygen Concentration," and presents the requirements in a manner more consistent with the Standard Technical Specifications (STS) format and content. The TSTF-568 proposed change to TS 3.6.2.5, "Drywell-to-Suppression Chamber Differential Pressure," in TSTF-568 is not applicable to BSEP and is not included. provides a description and assessment of the proposed changes. Enclosures 2 and 3 provide the existing TS pages marked-up to show the proposed changes for Units 1 and 2, respectively. Enclosures 4 and 5 provide revised (typed) TS pages for Units 1 and 2. provides Unit No. 1 TS Bases pages marked-up to show the proposed changes for information only.
Duke Energy requests that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLIIP). Approval of the proposed amendment is requested within six months of completion of the NRCs acceptance review. Once approved, the amendment shall be implemented within 120 days.
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 July 27, 2020.
Sincerely, John A. Krakuszeski MAT/mat
Enclosures:
- 1. Description and Assessment
- 2. Proposed Technical Specification Changes (Mark-Up)- Unit 1
- 3. Proposed Technical Specification Changes (Mark-Up)- Unit 2
- 4. Revised Technical Specification Pages - Unit 1
- 5. Revised Technical Specification Pages - Unit 2
- 6. Proposed Technical Specification Bases Changes (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-20-0127 Enclosure 1 Page 1 of 3 Description and Assessment
1.0 DESCRIPTION
Duke Energy Progress, LLC (Duke Energy) requests adoption of TSTF-568, "Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2." TSTF-568 revises the Applicability and Actions of Technical Specification (TS) 3.6.3.2, "Primary Containment Oxygen Concentration," and presents the requirements in a manner more consistent with the Standard Technical Specifications (STS) format and content.
2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation Duke Energy has reviewed the safety evaluation for TSTF-568 provided to the Technical Specifications Task Force in a letter dated December 17, 2019. This review included a review of the NRC staffs evaluation, as well as the information provided in TSTF-568. Duke Energy has concluded that the justifications presented in TSTF-568 and the safety evaluation prepared by the NRC staff are applicable to the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2; and justify this amendment for the incorporation of the changes to BSEP TS 3.6.3.2.
2.2 Optional Changes and Variations Duke Energy is proposing the following variations from the TS changes described in TSTF-568 or the applicable parts of the NRC staff's safety evaluation.
The proposed change to TS 3.6.2.5, "Drywell-to-Suppression Chamber Differential Pressure," in TSTF-568 is not applicable to BSEP and is not included.
The BSEP TS use different numbering than the STS on which TSTF-568 was based.
Specifically, STS 3.6.3.2, "Primary Containment Oxygen Concentration," is BSEP TS 3.6.3.1, "Primary Containment Oxygen Concentration." This difference is administrative and does not affect the applicability of TSTF-568 to the BSEP TS.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination Duke Energy Progress, LLC (Duke Energy) requests adoption of TSTF-568, "Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2." TSTF-568 revises the Applicability and Actions of Technical Specification (TS) 3.6.3.1, "Primary Containment Oxygen Concentration," and presents the requirements in a manner more consistent with the Standard Technical Specifications (STS) format and content.
Duke Energy has evaluated if 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:
RA-20-0127 Enclosure 1 Page 2 of 3
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change revises the Applicability and Actions of TS 3.6.3.1, "Primary Containment Oxygen Concentration," and presents the requirements in a manner more consistent with the STS format and content. Primary containment oxygen concentration is not an initiator to any accident previously evaluated. As a result, the probability of any accident previously evaluated is not affected by the proposed change.
Primary containment oxygen concentration is assumed in the mitigation of some accidents previously evaluated. The Applicability of TS 3.6.3.1 is changed from Mode 1 when thermal power is greater than 15% to Modes 1 and 2. This expands the Applicability of the TS and will not have an effect on the consequences of an accident. The existing Applicability exceptions are removed and replaced with a longer Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The consequences of an event that could be affected by primary containment oxygen concentration are no different during the proposed Completion Times than the consequences of the same event during the existing Completion Times. A note referencing Limiting Condition for Operation (LCO) 3.0.4.c is added to the Actions to permit entering the Applicability with the LCO not met. The note replaces the existing Applicability exceptions. This change is administrative and has no effect on the consequences of an accident.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change revises the Applicability and Actions of TS 3.6.3.1, "Primary Containment Oxygen Concentration," and presents the requirements in a manner more consistent with the STS format and content. The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed). No credible new failure mechanisms, malfunctions, or accident initiators that would have been considered a design basis accident in the Updated Final Safety Analysis Report (UFSAR) are created because the Nuclear Regulatory Commission has determined that hydrogen generation is not risk significant for design basis accidents.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
RA-20-0127 Enclosure 1 Page 3 of 3
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No The proposed change revises the Applicability and Actions of TS 3.6.3.1, "Primary Containment Oxygen Concentration," and presents the requirements in a manner more consistent with the STS format and content. No safety limits are affected. No Limiting Conditions for Operation or Surveillance limits are affected.
The primary containment oxygen concentration TS requirements assure sufficient safety margins are maintained, and that the design, operation, surveillance methods, and acceptance criteria specified in applicable codes and standards (or alternatives approved for use by the NRC) will continue to be met as described in the plants' licensing basis. The proposed change does not adversely affect existing plant safety margins, or the reliability of the equipment assumed to operate in the safety analysis. As such, there are no changes being made to safety analysis assumptions, safety limits, or limiting safety system settings that would adversely affect plant safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Duke Energy concludes that the proposed change 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.
3.2 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.
- 4. ENVIRONMENTAL CONSIDERATION The proposed change 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 change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change 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 change.
RA-20-0127 Enclosure 2 Proposed Technical Specification Changes (Mark-Up) -
Unit 1
Primary Containment Oxygen Concentration 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Oxygen Concentration LCO 3.6.3.1 The primary containment oxygen concentration shall be < 4.0 volume percent.
APPLICABILITY: MODES 1 and 2. during the time period:
- a. From 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 15% RTP following startup, to
- b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled reduction of THERMAL POWER to
< 15% RTP.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. Primary containment oxygen A.1 -------------NOTE-------------- 24 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> concentration not within LCO 3.0.4.c is applicable.
limit. -----------------------------------
Restore oxygen concentration to within limit.
B. Required Action and B.1 Be in MODE 3.Reduce 8 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time THERMAL POWER to not met. 15% RTP.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify primary containment oxygen concentration is In accordance with within limits. the Surveillance Frequency Control Program Brunswick Unit 1 3.6-26 Amendment No. 276
RA-20-0127 Enclosure 3 Proposed Technical Specification Changes (Mark-Up) -
Unit 2
Primary Containment Oxygen Concentration 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Oxygen Concentration LCO 3.6.3.1 The primary containment oxygen concentration shall be < 4.0 volume percent.
APPLICABILITY: MODES 1 and 2.during the time period:
- a. From 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 15% RTP following startup, to
- b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled reduction of THERMAL POWER to
< 15% RTP.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. Primary containment oxygen A.1 -------------NOTE-------------- 24 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> concentration not within LCO 3.0.4.c is applicable.
limit. -----------------------------------
Restore oxygen concentration to within limit.
B. Required Action and B.1 Be in MODE 3.Reduce 8 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time THERMAL POWER to not met. 15% RTP.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify primary containment oxygen concentration is In accordance with within limits. the Surveillance Frequency Control Program Brunswick Unit 2 3.6-26 Amendment No. 304
RA-20-0127 Enclosure 4 Revised Technical Specification Pages - Unit 1
Primary Containment Oxygen Concentration 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Oxygen Concentration LCO 3.6.3.1 The primary containment oxygen concentration shall be < 4.0 volume percent.
APPLICABILITY: MODES 1 and 2.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. Primary containment oxygen A.1 -------------NOTE-------------- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> concentration not within LCO 3.0.4.c is applicable.
limit. -----------------------------------
Restore oxygen concentration to within limit.
B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify primary containment oxygen concentration is In accordance with within limits. the Surveillance Frequency Control Program Brunswick Unit 1 3.6-26 Amendment No. 276
RA-20-0127 Enclosure 5 Revised Technical Specification Pages - Unit 2
Primary Containment Oxygen Concentration 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Oxygen Concentration LCO 3.6.3.1 The primary containment oxygen concentration shall be < 4.0 volume percent.
APPLICABILITY: MODES 1 and 2.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. Primary containment oxygen A.1 -------------NOTE-------------- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> concentration not within LCO 3.0.4.c is applicable.
limit. -----------------------------------
Restore oxygen concentration to within limit.
B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify primary containment oxygen concentration is In accordance with within limits. the Surveillance Frequency Control Program Brunswick Unit 2 3.6-26 Amendment No. 304
RA-20-0127 Enclosure 6 Proposed Technical Specification Bases Changes (Mark-Up) - Unit 1 (For Information Only)
Primary Containment Oxygen Concentration B 3.6.3.1 B 3.6 CONTAINMENT SYSTEMS B 3.6.3.1 Primary Containment Oxygen Concentration BASES BACKGROUND The primary containment is designed to withstand events that generate hydrogen either due to the zirconium metal water reaction in the core or due to radiolysis. The primary method to control hydrogen is to inert the primary containment. With the primary containment inert, that is, oxygen concentration < 4.0 volume percent (v/o), a combustible mixture cannot be present in the primary containment for any hydrogen concentration.
For example, an event that rapidly generates hydrogen from zirconium metal water reaction could result in excessive hydrogen in primary containment, but oxygen concentration will remain < 5.0 v/o and no combustion can occur. This LCO ensures that oxygen concentration does not exceed 4.0 v/o during operation in the applicable conditions.
APPLICABLE The Reference 1 calculations assume that the primary containment is SAFETY ANALYSES inerted when a Design Basis Accident (DBA) loss of coolant accident occurs. Thus, the hydrogen assumed to be released to the primary containment as a result of metal water reaction in the reactor core will not produce combustible gas mixtures in the primary containment.
Primary containment oxygen concentration satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii) (Ref. 2).
LCO The primary containment oxygen concentration is maintained < 4.0 v/o to ensure that an event that produces any amount of hydrogen and oxygen does not result in a combustible mixture inside primary containment.
APPLICABILITY The primary containment oxygen concentration must be within the specified limit when primary containment is inerted, except as allowed by the relaxations during startup and shutdown addressed below. The primary containment must be inert in MODES 1 and 2, since this is the condition with the highest probability of an event that could produce hydrogen and oxygen.
Inerting the primary containment is an operational problem because it prevents containment access without an appropriate breathing apparatus.
Therefore, the primary containment is inerted as late as possible in the plant startup and de-inerted as soon as possible during a scheduled power reduction to 15% RTP. As long as reactor power is 15% RTP, the potential for an event that generates significant hydrogen and oxygen the potential for an event that generates significant hydrogen and oxygen is low and the primary containment need not be inert. Furthermore, the probability of an event that generates hydrogen occurring within the first (continued)
Brunswick Unit 1 B 3.6.3.1-1 Revision No. 66
Primary Containment Oxygen Concentration B 3.6.3.1 BASES APPLICABILITY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a startup, or within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before a scheduled (continued) power reduction 15% RTP, is low enough that these "windows," when the primary containment is not inerted, are also justified. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period is a reasonable amount of time to allow plant personnel to perform inerting or de-inerting.
ACTIONS A.1 If oxygen concentration is 4.0 v/o at any time while operating in MODE 1 or 2, with the exception of the relaxations allowed during startup and shutdown, oxygen concentration must be restored to < 4.0 v/o within 72 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 72 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is allowed when oxygen concentration is 4.0 v/o because of the availability of other hydrogen and oxygen mitigating systems and the low probability and long duration of an event that would generate significant amounts of hydrogen and oxygen occurring during this period.
A Note permits the use of the provisions of LCO 3.0.4.c. This allowance permits entry into the applicable MODE(S) while relying on the ACTIONS.
This allowance is acceptable because inerting the primary containment prevents containment access without an appropriate breathing apparatus.
Therefore, the primary containment is inerted as late as possible in the plant startup, after entering Modes 1 and 2, and de-inerted as soon as possible in the plant shutdown. It is acceptable to intentionally enter Required Action A.1 prior to a shutdown in order to begin de-inerting the primary containment prior to exiting the Applicability.
B.1 If oxygen concentration cannot be restored to within limits within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, power must be reduced to MODE 3 15% RTP within 12 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The 12 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time is reasonable, based on operating experience, to reduce reactor power from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.3.1.1 REQUIREMENTS The primary containment must be determined to be inerted by verifying that oxygen concentration is < 4.0 v/o. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
REFERENCES 1. UFSAR, Section 6.2.5.
- 2. 10 CFR 50.36(c)(2)(ii).
Brunswick Unit 1 B 3.6.3.1-2 Revision No. 94