|
---|
Category:Letter type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation 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-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area 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-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require 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-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 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-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 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-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0064, Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval2023-04-24024 April 2023 Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023 Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations2023-03-30030 March 2023 Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage 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-23-0055, Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 22023-03-24024 March 2023 Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 2 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) 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-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 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-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-23-0027, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 20222023-01-30030 January 2023 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 2022 RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) 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-22-0347, Transmittal of Core Operating Limits Report2022-12-0202 December 2022 Transmittal of Core Operating Limits Report RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.162022-09-0808 September 2022 Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)2022-08-0909 August 2022 Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-07-28028 July 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0179, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2022-06-15015 June 2022 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks 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-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 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-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) RA-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-04-28028 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-02-05
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.162022-09-0808 September 2022 Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-07-28028 July 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 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-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-04-28028 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0230, Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2021-09-30030 September 2021 Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-20-0048, Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections2020-03-0404 March 2020 Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections RA-20-0018, Supplement to Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding; Integrated Assessment Submittal2020-01-23023 January 2020 Supplement to Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding; Integrated Assessment Submittal RA-19-0460, Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal2019-12-19019 December 2019 Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal RA-19-0452, Seismic Probabilistic Risk Assessment (Spra), Response to March 12, 2012, Request for Information Regarding Recommendation 2.1: Seismic, of the Near-Term Task Force Related to the Fukushima Dai-ichi Accident2019-12-12012 December 2019 Seismic Probabilistic Risk Assessment (Spra), Response to March 12, 2012, Request for Information Regarding Recommendation 2.1: Seismic, of the Near-Term Task Force Related to the Fukushima Dai-ichi Accident RA-19-0421, Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145)2019-11-13013 November 2019 Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145) RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.12019-10-24024 October 2019 Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 RA-19-0154, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2019-05-0606 May 2019 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-18-0185, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.46 Annual Report, Including Revised Robinson Large Break Loss of Coolant Accident Report2018-12-10010 December 2018 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.46 Annual Report, Including Revised Robinson Large Break Loss of Coolant Accident Report RA-18-0194, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt TSTF-425, Revision 32018-11-13013 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt TSTF-425, Revision 3 RA-18-0193, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ..2018-11-13013 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power .. RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change2018-08-0101 August 2018 Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change RA-18-0016, Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2018-06-0505 June 2018 Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ...2018-05-16016 May 2018 Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2018-01-0808 January 2018 Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RA-17-0055, Response to Second Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 02017-12-19019 December 2017 Response to Second Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 RA-17-0048, Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2)2017-10-30030 October 2017 Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2) RA-17-0043, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 02017-10-0909 October 2017 Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-09-28028 September 2017 Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) RA-16-0042, Response to Request for Additional Information Application to Revise Technical Specifications for Methodology Reports DPC-NF-2010, Revision 3 & DPC-NE-2011-P, Revision 2. Redacted Version Enclosed2016-11-17017 November 2016 Response to Request for Additional Information Application to Revise Technical Specifications for Methodology Reports DPC-NF-2010, Revision 3 & DPC-NE-2011-P, Revision 2. Redacted Version Enclosed ML16315A2722016-11-10010 November 2016 Duke Energy Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3008, Revision 0 RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. ML16280A2002016-10-0505 October 2016 Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RA-16-0036, Regarding Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-1008, Rev 02016-10-0303 October 2016 Regarding Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-1008, Rev 0 RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation RNP-RA/16-0072, Response to Request for Additional Information Regarding Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Rev. 22016-09-14014 September 2016 Response to Request for Additional Information Regarding Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Rev. 2 RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-09-14014 September 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits ML16230A2342016-07-25025 July 2016 Response to Request for Additional Information License Amendment Request to Adopt National Fire Protection Association Standard 805 RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations2016-07-14014 July 2016 Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations ML16158A0062016-05-25025 May 2016 Response to Request for Additional Information Re License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. Pages 1-21 RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-1742016-05-25025 May 2016 Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 RNP-RA/16-0031, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-05-0909 May 2016 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits RNP-RA/16-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-03-31031 March 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits RNP-RA/16-0017, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-03-16016 March 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. ML16063A1032016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/16-0011, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/15-0117, Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-12-22022 December 2015 Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits 2023-07-07
[Table view] |
Text
( ~ DUKE Ernest J. Kapopoulos, Jr.
ENERGY H. B. Robinson Steam Electric Plant Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 O: 843 951 1701 F: 843 857 1319 Serial: RA-19-0386 10 CFR 50.90 October 24, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H.B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 RENEWED LICENSE NO. DPR-23
SUBJECT:
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING LICENSE AMENDMENT REQUEST PROPOSING TO REVISE TECHNICAL SPECIFICATION 3.8.2, AC SOURCES - SHUTDOWN, SURVEILLANCE REQUIREMENT 3.8.2.1 Ladies and Gentlemen:
By letter dated June 4, 2019 (ADAMS Accession No. ML19155A037), Duke Energy Progress, LLC (Duke Energy) submitted a license amendment request (LAR) for H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The proposed change would revise HBRSEP Technical Specification (TS) 3.8.2, AC Sources - Shutdown, Surveillance Requirement (SR) 3.8.2.1 to reflect that HBRSEP SR 3.8.1.18 is not required to be met in the TS 3.8.2 Applicability (i.e.,
Modes 5 and 6 and during movement of irradiated fuel assemblies).
By correspondence dated September 26, 2019 (ADAMS Accession No. ML19283A037), the Nuclear Regulatory Commission (NRC) staff requested additional information from Duke Energy to complete the LAR review.
The Enclosure to this letter provides Duke Energys response to the NRC RAI. The Attachment contains color highlighted electrical one-line diagrams that support the RAI response.
The conclusions of the original No Significant Hazards Consideration and Environmental Consideration in the original LAR are unaffected by this RAI response.
There are no regulatory commitments contained in this letter.
In accordance with 10 CFR 50.91, Duke Energy is notifying the State of South Carolina of this LAR by transmitting a copy of this letter and enclosure to the designated State Official.
U.S. Nuclear Regulatory Commission RA-19-0386 Page 2 If there are any questions or if additional information is needed, please contact Mr. Art Zaremba, Manager - Nuclear Fleet Licensing at 980-373-2062.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 24, 2019.
Sincerely, Ernest J. Kapopoulos, Jr.
Site Vice President EJK/jlv
Enclosure:
Response to NRG Request for Additional Information
Attachment:
Electrical One-Line Diagrams
U.S. Nuclear Regulatory Commission RA-19-0386 Page 3 cc (with Enclosure and Attachment):
L. Dudes, USNRC Region II - Regional Administrator M. Fannon, USNRC Senior Resident Inspector - RNP N. Jordan, NRR Project Manager - RNP A. Gantt, Chief, Bureau of Radiological Health (SC)
A. Wilson, Attorney General (SC)
S. E. Jenkins, Manager, Radioactive and Infectious Waste Management (SC)
U.S. Nuclear Regulatory Commission RA-19-0386 Page 1 H.B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23 Response to NRC Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 Enclosure Response to NRC Request for Additional Information
U.S. Nuclear Regulatory Commission RA-19-0386 Page 2 NRC Request for Additional Information By application dated June 4, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19155A037, Duke Energy (the licensee) requested a license amendment to revise the H.B. Robinson Steam Electric Plant Unit 2 (HBRSEP), Technical Specification (TS) 3.8.2, AC Sources - Shutdown, Surveillance Requirement (SR) 3.8.2.1.
The SR change would reflect that HBRSEP SR 3.8.1.18 is not required to be met in the TS 3.8.2 Applicability.
The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following additional information is needed to complete its review.
Regulatory Requirement Title 10 of Code of Federal Regulations (CFR) 50.36, Technical specifications, establishes the requirements related to the content of the TS. Pursuant to 10 CFR 50.36(c) TS are required to include items in five specific categories related to station operation: (1) Safety limits, limiting safety system settings, and limiting control settings, (2) Limited conditions of operation (LCOs),
(3) Surveillance requirements (SR), (4) Design features; and (5) Administrative controls. The proposed change in this LAR relates to the SR category.
Request for Additional Information (RAI) No. 1 In the LAR, Enclosure 1, Page 2, the licensee stated: Both the 115 kV and 230 kV startup transformers are capable of energizing Emergency Buses E1 and E2. Should a failure of either startup transformer occur, the other startup transformer would be capable of supplying power to the onsite distribution system. A manual transfer is made to the alternate offsite circuit upon a loss of either startup transformer.
The NRC staff has identified the following discrepancy:
The LAR does not clearly describe the alternate offsite circuits that would be used to supply power upon loss of a startup transformer. In addition, it is not clear that offsite power will remain available (uninterrupted) to at least one of the emergency buses while switching to alternate offsite circuit during various switching operations.
The staff requests the following information to address this discrepancy:
Please provide a description or highlighted drawings showing the offsite power circuits to the Emergency Buses E1 and E2 under following operating configurations when (a) Unit is operating at 100 percent power (b) Unit is tripped:
(i) Both 115 kV and 230 kV startup transformers available (ii) 115 kV startup transformer out-of-service (iii) 230 kV startup transformer out-of-service For each configuration, please explain which circuit (line-up) is considered a normal offsite circuit and which circuit (line-up) is considered an alternate offsite circuit. Also, please confirm whether offsite power will remain available (uninterrupted) to at least one of the emergency buses while switching to alternate offsite circuit during various switching operations.
U.S. Nuclear Regulatory Commission RA-19-0386 Page 3 Duke Energy Response to RAI No. 1 The Attachment to this submittal provides highlighted electrical drawings (i.e., one-line diagrams) for H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP) depicting the offsite power circuits supplying Emergency Buses E1 and E2 under the operating configurations specified in the RAI.
Figure 1 depicts the configuration when the unit is operating at 100 percent power and both the 115 kV and 230 kV startup transformers (SUTs) are available. During normal operation, each SUT feeds one emergency bus as the normal offsite circuit. The 115 kV SUT is considered the normal offsite circuit for Bus E1. The 230 kV SUT is considered the normal offsite circuit for Bus E2.
Regarding alternate circuits, the Unit Auxiliary Transformer (UAT) is the alternate circuit for Bus E1 if either the 115 kV SUT or the 230 kV SUT is out of service. The alternate circuit for Bus E2 is the 115 kV SUT; and Bus E2 is only transferred to the 115 kV SUT for a loss of the 230 kV SUT.
Figure 2 depicts the final configuration when the unit is operating at 100 percent power and the 115 kV SUT is out-of-service. If the 115 kV SUT is lost, Bus E1 is temporarily powered from EDG-A after the loss of offsite power. Manual actions will transfer Bus E1 to the UAT, as shown in Figure 2. The 230 kV SUT will remain the uninterrupted source of offsite power for Bus E2.
Figure 3 depicts the final configuration when the unit is operating at 100 percent power and the 230 kV SUT is out-of-service. If the 230 kV SUT is lost, Bus E2 is temporarily powered from EDG-B after the loss of offsite power. Manual actions will transfer Bus E1 to the UAT, as shown in Figure 3. Power to Bus E1 is uninterrupted during the transfer process via circuit interlocks.
Additionally, if the UAT is subsequently lost, Bus E1 automatically transfers back to the 115 kV SUT without a power interruption via a fast bus transfer. Manual actions will transfer Bus E2 to the 115 kV SUT, as shown in Figure 3.
Figure 4 depicts the configuration when the unit is tripped and both the 115 kV and 230 kV SUTs are available. In this condition, Bus E1 remains uninterrupted on its normal offsite source (115 kV SUT) and Bus E2 remains uninterrupted on its normal offsite source (230 kV SUT).
Figure 5 depicts the configuration when the unit is tripped and the unit auxiliary transformer (UAT) and the 115 kV SUT are out-of-service. In this condition, the 230 kV SUT is the only available source of offsite power.
x Scenario with 115 kV SUT out-of-service prior to plant trip.
o Bus E1: For the postulated 115 kV SUT being out-of-service, Bus E1 would have been supplied by the UAT (Figure 2 configuration) prior to the unit trip. In the event of a unit trip, Bus E1 automatically transfers to the 230 kV SUT via a fast bus transfer. The power to Bus E1 is uninterrupted in this condition.
o Bus E2: The 230 kV SUT will remain the uninterrupted source of offsite power for Bus E2 throughout the event and transfer.
U.S. Nuclear Regulatory Commission RA-19-0386 Page 4 x Scenario with 115 kV SUT out-of-service concurrent with plant trip.
o Bus E1: Bus E1 would have been supplied by the 115 kV SUT (normal Figure 1 configuration) prior to the unit trip. Bus E1 will be temporarily powered from EDG-A after the loss of offsite power via the 115 kV SUT. If loss of the 115 kV SUT was due to a transformer fault, manual actions will transfer Bus E1 to the 230k kV SUT. If the loss of the 115 kV SUT was due to a cause other than a transformer fault, then manual actions will transfer Bus E1 to the 230 kV SUT.
o Bus E2: The 230 kV SUT will remain the uninterrupted source of offsite power for Bus E2 throughout the event and transfer.
Figure 6 depicts the configuration when the unit is tripped and the UAT and the 230 kV SUT are out-of-service. In this condition, the 115 kV SUT is the only available source of offsite power.
x Scenario with 230 kV SUT out-of-service prior to plant trip.
o Bus E1: For the postulated 230 kV SUT being out-of-service, Bus E1 would have been supplied by the UAT (Figure 3 configuration) prior to the unit trip. In the event of a unit trip, Bus E1 automatically transfers to the 115 kV SUT via a fast bus transfer. The power to Bus E1 is uninterrupted in this condition.
o Bus E2: For the postulated 230 kV SUT being out-of-service, Bus E2 would have been supplied by the 115 kV SUT (Figure 3 configuration) prior to the unit trip.
After the unit trip, power to Bus E2 will remain uninterrupted on the 115 kV SUT (Figure 6 configuration).
x Scenario with 230 kV SUT out-of-service concurrent with plant trip.
o Bus E1: Bus E1 would have been supplied by the 115 kV SUT (normal Figure 1 configuration) prior to the unit trip. The 115 kV SUT will remain the uninterrupted source of offsite power for Bus E1 throughout the event.
o Bus E2: Bus E2 would have been supplied by the 230 kV SUT (normal Figure 1 configuration) prior to the unit trip. Bus E2 will be temporarily powered from EDG-B after the loss of offsite power via the 230 kV SUT. If loss of the 230 kV SUT was due to a transformer fault, manual actions via Plant Procedure AOP-037, will transfer Bus E2 to the 115 kV SUT. If loss of the 230 kV SUT was due to a cause other than a transformer fault, then manual actions will transfer Bus E2 to the 230 kV SUT.
Duke Energy confirms for HBRSEP that offsite power will remain available (uninterrupted) to at least one of the emergency buses while switching to the alternate offsite circuit during various switching operations. The discussion above considers a loss of offsite power, via the 115 kV SUT or the 230 kV SUT, as noted. Each section has identified the uninterrupted offsite power supply for each configuration. Each configuration identified has at least one uninterrupted offsite power source.
U.S. Nuclear Regulatory Commission RA-19-0386 H.B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23 Response to NRC Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 Attachment Electrical One-Line Diagrams
)LJXUH 3RZHU WEST 115kV - - - - - - ---~-- EAST 115kV NORTH 230 k V - - - - - - ---~-- DARLING TO N CO UNTY NORTH 230 k V- - ~ - - - DA RLI NGTON NOR TH LI NE 230 k V SCPSA LINE 230 k V J,
11 5kV STAR TUP TRA NSFORM ER HV- 27 / 3 6/45/50. 4 MV A MAI N TRA NSFORMER BAN K 3 - 330 MVA lPH, 6 0H Z LV - 13.5/18/22 .5/25.2 MVA <EACH)
MAI N GE N. 2 22 kV, 8 54 MV A 29 - DISC - SW - X- SU T- 115
~ 11:~
,--======'
t 29-2
GE N. DISC . UNIT AUXILIA RY TRA NSFORMER "2 LIN K. HV44/49.2 MVA L V- 22/24.6 MVA (EACH)
BUS 9 cm o~,~:,wi OFF O SST SST 2G 20
( U 52
(") 5 0 T *W SWITCHGEAR BUILDING 469 LOADS 480V DEDICATED SHUT DOWN BU S 52 r 480V
?' ) 52 288 32B MCC - 25 1
) 52 18B 480V EMERGEN CY BUS El Tu1u DED ICATED SH UTDOWN TR ANSFORMER i_8_0V EMER GENCY BUS EZ 0 513(5HY
T t" t' 52 ~) N.O. 52 228 (") 298 DIESEL
$WWDFKPHQW(
GENERATOR SPARE 0)
(") 52 0) 52
~6 52
) 52 53 SPARE _ 5 4 3250 KVA , 4160V, 3 0, 6 0HZ 3DJH(
EMERGENCY DIESEL EMER GENC Y DIESEL J
4.16k V BUS 10 GENE RAT OR A GENERATOR B 3125 KVA, 3 0, 60 HZ 3125 KVA, 3 0, 60HZ AI EC ' 84!87 MAI NTE NANCE SAFETY I NJ ECTION PU MP B ROBI NS ON NUCLEAR PO WER CO .
.I,__ ms2Ti1~ u4Tb~IT( INE Z'ACHRV ONE LINE DIAG RAM OF F INAL CO NFI GURATIO N ZACHRY NUCLEAR ENGINEERING, INC.
14 LOROS HI.LRO. 255E. f-£8RONST. 184SHUMMl8LVO, SUITE175 STOHINGTOM, CT 06376 CHAAI.OTTE. NC 28273 NN'ERVILLE. L 60583 5HYLVLRQ NIA
)LJXUH 3RZHU
N9 687 226 WEST 115kV - - - - - - ---~-- EAST 115kV NORTH 230 k V - - - - - - ---~-- DARLING TO N COUNTY NORTH 230 k V- - ~ - - - DA RLI NGTON NOR TH LI NE 230 kV SCPSA LINE 230 k V
'""'~d~k s- ~"\ "~'"1 1 11 5kV ST ARTUP TRAN SFORM ER HV- 27 / 3 6/45/50. 4 MV A LV - 13.5/18/22 .5/25.2 MVA <EACH) 0o----------(1+
2 9 - DIS C- SW -
- ---~
MAI N GE N. 2 22 kV, 8 54 MV A MAI N TRA NS FORMER BAN K 3 - 330 MVA lPH, 60H Z Y- SUT-115
~~ 1111,J~~ () ~~ GE N. DISC .
LI NK.
UNIT AUXILIA RY TRA NSFORMER " 2 HV 4 4/49.2 MVA L V- 22/2 4. 6 MVA (EA CH)
BUS 9 DIS CO NNE CT BUS 6 DISCONNECT 2~
SST SST Iw 2G 20 SS T 2F SS T 2H
( ~ 52
(") 50 SWITCHGEAR BUILDING 469 LO~DS, 52 32 A
,i_8_0_Y_Q,E_D_l_CATE_D SHUT DOWN _BU S 52 r 480V
?' ) 52 28B 32B MCC - 25 l) (tB 480V EMERGEN CY BUS El T
u1u DED ICATED SH UTDO WN TR ANSFORMER
,i_8_0V EMERGENCY BUS E2 0 513(5HY
T t" t' 52 ~) N.O. 52 22B (") 29 B DIESEL
$WWDFKPHQW(
GENERA TO R SPARE 0)
(") 52 0) 52
~6 52
) 52 53 SPARE _ 5 4 3250 KVA , 4160V. 3 0, 60 HZ 3DJH(
EME RGENC Y DIESEL EMER GENC Y DIESEL J
- 4. 16k V BUS 10 GENE RA TOR A GENE RATOR B 3125 KVA, 3 0. 6 0H Z 3125 KVA, 3 0. 60HZ AI EC ' 84!87 MAI NTENANCE SAFETY I NJ EC TION PU MP B ROBI NS ON NU CLEAR PO WER CO .
.I,__ ms2Ti 1~u4Tb~IT(INE Z'ACHRV ONE LINE DIAG RAM OF F INAL CO NFI GURATIO N ZACHRY NUCLEAR ENGINEERING, INC.
14 LOROSHI.LRO. 255E. f-£8RONST. 184SHUMMl 8LVO, SUITE175 STOHINGTOM, CT 06376 CHAAI.OTTE. NC28273 NN'ERVILLE. L 60583 5HYLVLRQ NIA
)LJXUH 3RZHU ZLWK
N9 687 226 WEST 115kV - - - - - - ---~-- EAS T 115kV NORTH 230 kV - - - - - - ---~-- DARLING TO N CO UNT Y NORTH 230 k V- - ~ - - - DAR LI NGTON NOR TH LI NE 230kV SCPSA LINE 230k V 6
115kV STAR TUP TRA NSFORMER 23 0k V STAR TUP TRANSFOR ME R MAIN TRANSFORMER BAN K
- J HV- 27 /36/45/50. 4 MVA 6-cnca;-c;e
~ ~ HV - 27 /36/45/5 0.4 MVA 3 - 330 MVA lPH, 60HZ LV - 13.5/18/22 .5/25.2 MVA <EACH) A y, LV-1 3.5/ 18/22.5/25.2 MVA (EAC H)
MAIN GE N. 2 22 kV, 854 MVA n-msc-ss-s -scn -,~
i ) 52 46
) 5-(") 4~
BUS 9 GE N. DISC .
LINK .
UNIT AUX ILIA RY TRANS FORMER "2 HV44/49.2 MVA L V- 22/24.6 MVA (EACH)
Tm DIS CO NNE C
- 1( ~
BUS !,
! I
/21s co ~NEC, - - -
BUS 9 i6 -
OISC ON 2C N!E ,
DISCONNECT ' DISC~~: EC T 2~
- ~ ub.JssT 2C ' 2G SST 20 T 2H SS T 2F SS T UJJ..J SS T T 2J (U 52 52 U)
(") 50 5 1 (")
SWITCHGEAR SWITCHGEAR BUILDING 469 BUILDING 469 LOADS LOADS
~~})
480V DEDICATED SHU TDOWN BU S
?') 32B 52 r
MCC - 25 480V l) (tB 480V EMERGENCY BUS El T
ub.J DEDICATED SH UTDOWN TRANS FORMER ~ 480V EMERGENCY BUS EZ 0 513(5HY
T t" t' 52 ~) N.O.
22B (") DIESEL 52 29 B (")
)N*0. J;)52
$WWDFKPHQW(
GENERA TOR SPARE 0)
(") 52 0) 52
~6 52
) 52 53 SPARE _ 54 3250 KVA , 4160V. 3 0, 60HZ 3DJH(
EMERGENCY DIESEL EMER GENCY DIESEL J
4.16kV BUS 10 GENERA TOR A GENE RA TOR B 3125 KVA , 3 0. 60 HZ 3125 KVA, 3 0. 60HZ AI EC ' 84!87 MAI NTE NANCE SAFETY INJE CTION PUMP B ROBI NSON NUCLEAR PO WER CO .
.I,__ ms2Ti1~u4Tb~IT(I NE Z'ACHRV ONE LINE DIAGRAM OF F INAL CO NFIG URATIO N ZACHRY NUCLEAR ENGINEERING, INC.
14LOROSHI.LRO. 255E.f-£8RONST. 184SHUMMl 8LVO,SUITE175 STOHINGTOM, CT 06376 CHAAI.OTTE. NC28273 NN'ERVILLE. L 60583 5HYLVLRQ NIA
)LJXUH 3ODQW 7ULS WEST 115kV - - - - - - ---~-- EAS T 115kV NORTH 230 kV - - - - - - ---~-- DARLING TO N CO UNTY NORTH 230 k V- - ~ - - - DARLINGTON NOR TH LI NE 230kV SCPSA LINE 230k V J,
115kV STAR TUP TRANSFORMER HV- 27 /36/45/50. 4 MVA MAIN TRANSFORMER BAN K 3 - 330 MVA lPH, 60 HZ LV - 13.5/18/22 .5/25.2 MVA <EACH)
MAIN GE N. 2 22 kV, 85 4 MVA 29 - 0ISC - SW - X- SU T- 115
~ 11:~
,--======'
t 29-2
UNIT AUX ILIA RY TRANSFORMER "2 HV44/49.2 MVA
~ L V- 22/24.6 MVA !EACH>
cmo~,~:,wi t' 4.16k._V BUS 5 l~c, 6)52 6)52 Cjl_ 24 OFF O SST Tw 2G r r r n 2E 6)~¥s 4,8 0V BUS 480V BUS 5
( ~ 52
(") 50 SWITCHGEAR BUILDING 469 LOADS 480V DEDICATED SHUT DOWN BU S 52
?') 328 52 288 MCC - 25 1
) 52 18B 480V EMERGENCY BUS El T
u1u TRANS FORMER DEDICATED SHUTDOWN i_8_0V EMERGE NCY BUS EZ 513(5HY
r 480V 0
T52 t" t' 52 ~) N.O.
228 (")
52 DIESEL 298
$WWDFKPHQW(
GENERATOR SPARE 0)
(") 52 0) 52
~6
) 52 53 SPARE _ 5 4 3250 KVA , 4160V. 3 0, 60HZ 3DJH(
EMERGENCY DIESEL EMER GENCY DIESEL J
4.16kV BUS 10 GENERA TOR A GENERATOR B 3125 KVA, 3 0. 60 HZ 3125 KVA, 3 0. 60HZ AI EC '84!87 MAI NTE NANCE SAFETY INJE CTION PUMP B ROBI NS ON NUCLEAR PO WER CO .
..I.._ ms2Ti1~u4Tb~IT( INE Z'ACHRV ONE LINE DIAGRAM OF F INAL CO NFIG URATIO N ZACHRY NUCLEAR ENGINEERING, INC.
14LOROSHILLRO. 255E.f-£8RONST. 184SHUMMl8LVO,SUITE175 STOHINGTOM, CT 06376 CHAAI.OTTE. NC28273 NN'ERVILLE. L 60583 5HYLVLRQ NIA
3ODQW 7ULS
)LJXUH 8$7 N9 687 226 WEST 115kV - - - - - - ---~-- EAS T 115kV NORTH 230 kV - - - - - - ---~-- DARLING TO N CO UNT Y NORTH 230 k V- - ~ - - - DAR LI NGTON NOR TH LI NE 230kV SCPSA LINE 230k V 1 115kV STAR TUP TRANSFORMER HV- 27/36/ 45/50. 4 MVA LV - 13.5/18/22 .5/25.2 MVA <EACH) 0o----------(1+
29 - DISC - SW -
- ---~
MAIN GE N. 2 22 kV, 854 MVA MAIN TRANSFORMER BAN K 3 - 330 MVA lPH, 60HZ Y- SUT-115 UNIT AUX ILIA RY TRANS FORMER " 2 HV 4 4/49.2 MVA L V- 22/24.6 MVA (EACH)
DIS CO NNE CT BUS 6 f
DISCONNECT 2~
J,:,
Iw SS T ll>.l~, 52 c
2F J 30B SS T 2H t4"80V- Bl:JS-5
( ~ 52
(") 50 SWITCHGEAR BUILDING 469 LD~DS, 52 32A
,i_8_0_Y_Q,E_D_l_CATE_D SHUT DOWN _BU S 52 r 480V
?' ) 52 28B 32B MCC - 25 D(ts 480V EMERGENCY BUS El T
u1u DEDICATED SHUTDOWN TRANS FORMER i_8_0V EMERGENCY BUS E2 0 513(5HY
T t" t' 52 ~) N.O. 52 22B (") 29 B DIESEL
$WWDFKPHQW(
GENERA TOR SPARE 0)
(") 52 0) 52
~6 52
) 52 53 SPARE _ 5 4 3250 KVA , 4160V. 3 0, 60HZ 3DJH(
EMERGENCY DIESEL EMER GENCY DIESEL J
4.16kV BUS 10 GENERA TOR A GENE RA TOR B 3125 KVA, 3 0. 60 HZ 3125 KVA, 3 0. 60HZ AI EC '84!87 MAI NTE NANCE SAFETY INJE CTION PUMP B ROBI NSON NUCLEAR PO WER CO .
.I,__ ms2Ti1~u4Tb~IT(INE Z'ACHRV ONE LINE DIAGRAM OF F INAL CO NFIG URATIO N ZACHRY NUCLEAR ENGINEERING, INC.
14LOROSHI.LRO. 255E.f-£8RONST. 184SHUMMl 8LVO,SIJITE175 STOHINGTOM, CT 06376 CHAAI.OTTE. NC28273 NN'ERVILLE. L 60583 5HYLVLRQ NIA
)LJXUH 8$7 DQG N9 687 226 WEST 115kV - - - - - - ---~-- EAS T 115kV NORTH 230 kV - - - - - - ---~-- DARLING TO N CO UNTY NORTH 230 k V- - ~ - - - DARLI NGTON NOR TH LI NE 230kV SCPSA LINE 230k V J, T -f!Jf 115kV STAR TUP TRA NSFORMER TUP TRANSFOR ME R HV- 27 /36/45/50. 4 MVA MAIN TRANSFORMER BANK 230k V 6/ 4 5/5 0.tv~v ~EAC H) 3 - 330 MVA lPH, 60 HZ LV - 13.5/18/22 .5/25.2 MVA <EACH) L V-1 3~J/ 18/22.5/25.2 MAIN GE N. 2 b"'" " ,
22 kV, 85 4 MVA T
29 - DISC - SW - X- SU T- 115 t
29 -D ISC - SW -
- .r
"'f-:' = ~ , rnsscrn"" "'
I
- - - - - * - - - - - """ ,,,~\*::,m,:;1""'
Y- SUT-115 n-msc- ss-, -son -,~ , " ' ""' - L v - 22124.6 M cm ,rn
) 52 LIN K.
1)~~
41 4 .!6kV BUS~ 7
.16~,.=.....:...._~ -] )
- ~ ! - -'t 7 ~ _:_____ )~
20 SPA REJ* )~§ U ) ~~
"'"'"~,~:,wi ;1( Tm . ~ ,_ ,
- -P ) 52
_J ~ 12 **-* --- _ 4 .16k-V 4.1_6.!sV BU.S 4 4.16k._V BUS 5
/4 lP;l!
) 52 ) 52 1) ~2 1~"
6 ) 52 6 ) 52
£_
l ,c, 13 10 1sco ~ NEci - - - 0 Cjl_ 2 4 i6 - )p~
6 BUS 9
ssT - SH - ZH DIS CON OFF O " O OFF DISCONN1 2A 0 ? ] 2C N!E ,
DISCONNECT ' DISC~~: : _
~
2~
rrrn
- u.1..J ssT SST 2C
- 2G SST fYT('l 2A 28 20 r r r , 2E 6,) 52 h~~B T2J T 2H I 6)~¥B 0
IB 52 SS T UJJ..J SS T o)* 52 1
6 ) 52 9B
)
480V 4,8 0V BUS 4 480V BUS 5 4 80VI BUS ' 28~ BUS 2e....1 480V 88 BU S 2B (U 52 52 U)
() 50 5 1 ()
SWITCHGEAR BUILDING 469 SWITCHGEAR BUILDING 469
§§ J) N.O.
LOADS LOADS 480V DEDICATED SHUTDOWN BU S J),
I'"
52 52 2Bs !
?') 32B MCC - 25 1
) 52 188 480V EMERGENCY BUS El T
u.1..J DEDICATED SHUTDOWN TRANS FORMER ~
csrnccsc, BUS EZ 513(5HY
r 480V 0
T t" t' 52 ~) N.O. 52 ) N0 J;) 52 228 () DIESEL 296 () * .
$WWDFKPHQW(
GENERATOR SPARE 0)
() 52 0) 52
~6 52
) 52 53 SPARE _ 5 4 3250 KVA , 4160V. 3 0, 60HZ 3DJH(
EMERGENCY DIESEL EMER GENCY DIESEL J
4.16kV BUS 10 GENERA TOR A GENERATOR B 3125 KVA, 3 0. 60 HZ 3125 KVA, 3 0. 60HZ AI EC '84!87 MAI NTENANCE SAFETY INJE CTION PUMP B ROBI NS ON NUCLEAR PO WER CO .
.I.._ ms2Ti1~u4Tb~IT( INE Z'ACHRV ONE LINE DIAGRAM OF F INAL CO NFIG URATIO N ZACHRY NUCLEAR ENGINEERING, INC.
14LOROSHI.LRO. 255E.f-£8RONST. 184SHUMMl8LVO,SUITE175 STOHINGTOM, CT 06376 CHAAI.OTTE. NC28273 NN'ERVILLE. L 60583 5HYLVLRQ NIA