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Category:Letter type:RNP
MONTHYEARRNP-RA/21-0035, Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-18018 February 2021 Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/20-0234, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2020-07-23023 July 2020 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RNP-RA/20-0199, Registration of Use of Spent Fuel Casks2020-06-25025 June 2020 Registration of Use of Spent Fuel Casks RNP-RA/18-0063, Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal2018-11-29029 November 2018 Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal RNP-RA/18-0060, Transmittal of Core Operating Limits Report2018-10-17017 October 2018 Transmittal of Core Operating Limits Report 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 RNP-RA/18-0044, Supplement to 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 Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to 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 Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/18-0039, Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis2018-06-27027 June 2018 Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis RNP-RA/18-0041, Independent Spent Fuel Storage Installation - Register as User for Cask2018-06-13013 June 2018 Independent Spent Fuel Storage Installation - Register as User for Cask 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/18-0029, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-0808 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report RNP-RA/18-0031, (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 352018-04-23023 April 2018 (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35 RNP-RA/18-0015, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program2018-04-16016 April 2018 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) RNP-RA/18-0020, Notification of Change in Licensed Operator Status2018-02-20020 February 2018 Notification of Change in Licensed Operator Status RNP-RA/18-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-01-23023 January 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 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 RNP-RA/17-0086, Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses2017-12-14014 December 2017 Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses RNP-RA/17-0081, Submittal of Change in Licensed Operators Medical Status2017-12-11011 December 2017 Submittal of Change in Licensed Operators Medical Status RNP-RA/17-0079, Operator License Renewal Application2017-12-0707 December 2017 Operator License Renewal Application RNP-RA/17-0071, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2017-10-19019 October 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks 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 RNP-RA/17-0037, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers2017-09-27027 September 2017 License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-42017-09-22022 September 2017 Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0060, Notification of Change in Licensed Operator Status2017-08-10010 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0058, Notification of Change in Licensed Operator Status2017-08-0303 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0055, Transmittal of Core Operating Limits Report for Cycle 312017-07-26026 July 2017 Transmittal of Core Operating Limits Report for Cycle 31 RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2017-06-29029 June 2017 Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0038, (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report2017-05-0909 May 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RNP-RA/17-0036, (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 342017-04-25025 April 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 34 RNP-RA/17-0031, Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 02017-04-20020 April 2017 Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 0 RNP-RA/17-0033, Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal2017-04-12012 April 2017 Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal RNP-RA/17-0014, Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0028, Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0021, Transmittal of Core Operating Limits Report2017-03-13013 March 2017 Transmittal of Core Operating Limits Report RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RNP-RA/17-0015, Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/17-0016, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2017-02-22022 February 2017 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RNP-RA/17-0015, H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/16-0100, Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-2272017-01-24024 January 2017 Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-227 RNP-RA/16-0097, Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/20154052016-12-15015 December 2016 Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/2015405 RNP-RA/16-0089, Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2016-11-10010 November 2016 Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/16-0090, Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise2016-11-10010 November 2016 Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors 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. 2021-02-18
[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] |
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(~ DUKE R. Michael Glover H. B. Robinson Steam Electric Plant Unit 2 ENERGY~ Site Vice President Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 SEP 1 -4 20J8 0 : 843 857 1704 F: 843 857 1319 Mike.Glover@duke-energy.com Serial: RNP-RA/16-0072 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 I RENEWED LICENSE NO. DPR-23 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 COLA CONSISTENT WITH WCAP-14483, REVISION 2
Dear Sir/Madam:
By letter dated April 24, 2016 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML16116A033) Duke Energy Progress, Inc. (DEP) submitted a license amendment request (LAR) for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2). The proposed amendment would adopt Technical Specifications Task Force (TSTF)-339, Revision 2, "Relocate TS Parameters to the COLR," dated May 26, 2000 (ADAMS Accession No. ML003723269),
consistent with WCAP-14483, Revision 2, "Generic Methodology for Expanded Core Operating Limits Report," dated January 19, 1999 (ADAMS Accession No. ML003723269). This LAR would relocate Reactor Coolant System (RCS)-related cycle-specific parameters and core safety limits from the Technical Specifications (TS) to the Core Operating Limits Report (COLR).
The Nuclear Regulatory Commission (NRC) staff determined that additional information is needed to complete its LAR review. A draft of that information request was received by DEP via electronic mail message dated August 11, 2016, which provided three (3) requests for additional information (RAls). The DEP responses to these RAls are provided herein.
Please address any comments or questions regarding this matter to Mr. Tony Pile, Acting Manager
- Nuclear Regulatory Affairs at (843) 857-1409.
There are no new regulatory commitments made in this letter.
I declare under penalty of perjury that the foregoing is true and correct. Executed on 5.c.~e.(" t\ I 2016.
Sincerely, C}~ f\ -\~ \;JR R. Michael Glover Site Vice President RMG/jmw
U. S. Nuclear Regulatory Commission Serial: RNP-RA/16-0072 Page2 Attachment - Response to Request for Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF)-339, Revision 2, "Relocate TS Parameters to the COLA" cc: Region Administrator, NRC, Region II Mr. Dennis Galvin, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP2 Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)
U.S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 1 of 9 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF)-
339, REVISION 2, "RELOCATE TS PARAMETERS TO THE COLA"
U. S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 2 of 9 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF)-339, REVISION 2, "RELOCATE TS PARAMETERS TO THE COLR," CONSISTENT WITH WCAP-14483, REVISION 2, "GENERIC METHODOLOGY FOR EXPANDED CORE OPERATING LIMITS REPORT" DUKE ENERGY PROGRESS, INC.
DOCKET NO. 50-261 RAl-1 The licensee states in its application that the Limiting Condition for Operation (LCO) and Surveillance values in TS 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," for RCS pressure and temperature do not currently account for instrument uncertainty and are therefore non-conservative. The LCO and surveillance values for RCS flow do account for instrument uncertainty. Administrative controls were implemented in accordance with the guidance in NRC Administrative Letter 98-10, "Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety," dated December 19, 1998. These administrative controls were implemented to utilize conservative limits for RCS pressure and temperature that do account for instrument uncertainty. The licensee states it intends to incorporate RCS pressure and temperature LCO and surveillance values, which do account for instrument uncertainty, into the COLA as part of the implementation of the proposed amendment. It is unclear to the NRC staff what the uncertainty values are associated with the LCO and Surveillances for TS 3.4.1 for RCS pressure and temperature. In order to ensure that conservatism is preserved, the NRC staff requests that the licensee provide a discussion of the uncertainty values and their magnitudes for RCS pressure and temperature limits in TS 3.4.1 .
DEP Response:
As indicated in the Bases of Technical Specification 3.4.1, the Pressurizer pressure indications are averaged to come up with a value for comparison to the DNB Technical Specification limit. The uncertainty associated with the average Pressurizer pressure is dependent on the indicator used (Main Control Board meter or Plant Computer indication) and the number of operable channels used in the average (2 or 3 operable channels). The uncertainty associated with the average Pressurizer Pressure is as follows:
Number of Channels Main Control Board Plant Computer In Avera e Indicator Indication 3 Channels +/- 20.78 +/-14.41 2 Channels The above uncertainties include consideration of the uncertainty of all of the components included in the instrument loop which provide the indication (i.e. the pressure transmitter, isolator and indicator).
The Bases of Technical Specification 3.4.1 also indicates that the indications of temperature are averaged to determine a value for comparison to the Technical Specification limit. The uncertainty associated with the average RCS Tavg is also dependent on the indicator used (Main Control
U. S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 3 of 9 Board meter or Plant Computer indication) and the number of operable channels used in the average (2 or 3 operable channels). The uncertainty associated with the average RCS Tavg is as follows:
Number of Channels Main Control Board Plant Computer In Average Indicator Indication 3 Channels +/- 2.27°F +!- 1.67°F 2 Channels +/- 2.65°F +/- l.91°F The above uncertainties include consideration of the uncertainty of all of the components included in the instrument loop which provides the indication.
The uncertainties on the average Pressurizer pressure and average RCS Tavg cited above reflect the uncertainties currently being used and may be revised in the future as a result of changes such as instrumentation replacements and increases in calibration intervals resulting from the transition to 24 month fuel cycles. Any future changes in uncertainties will be appropriately factored into the Pressurizer pressure and RCS Tavg limits in the COLR to ensure that the values used in the Safety Analyses remain bounding.
RAl-2 10 CFR 50.36{b) states in part, "the technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34."
The application provided by the licensee did not state whether the safety analyses for the RCS pressure and temperature needed to be revised for the proposed amendment. The NRC staff requests that the licensee confirm if reanalysis was performed or if the current analysis remains bounding to support these new values for RCS pressure and temperature that are being relocated to the COLR for effects to the Updated Final Safety Analysis Report {UFSAR) Chapter 15 safety analyses.
DEP Response:
The administrative limits which account for the uncertainties in Pressurizer pressure and RCS Tavg are currently being utilized in the plant surveillance procedures to protect the current Technical Specification 3.4.1 Pressurizer Pressure limit of~ 2205 psig and the Tavg limit of s. 579.4°F.
Although the plant is able to operate within these limits, the operating margin to the Pressurizer pressure administrative limit is very small. In order to regain operating margin the Chapter 15 analyses were rerun to support a Pressurizer Pressure limit of~ 2195 psig using the NRC approved methods cited in RNP Technical Specification Section 5.6.5. It is RNP's intent to implement Pressurizer pressure limits in the COLR which utilize this new analysis value and account for instrumentation uncertainty.
No new analysis for RCS Tavg were required. The current analyses support an RCS Tavg of s.579.9°F which is slightly higher than the current Technical Specification RCS Tavg limit of s.575.4°F. It is RNP's intent to implement RCS Tavg limits which are based on the current analysis value of 579.9°F and account for instrumentation uncertainty.
U. S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 4 of 9 RAl-3 TSTF-339 identifies WCAP-14483-A as the methodology that will be used to relocate TS parameters to COLR. WCAP-14483-A, Section 3.0, "Relocation of the OTDT and OPDT Setpoint Parameter Values to the COLA," provides the basis for Overtemperature /1 T {OTDT) and Overpower /1 T (OPDT) setpoints, including typical setpoint equations, and the basis for moving the OTDT and OPDT TS parameters to a COLR. WCAP-14483-A, Appendix 8, "Sample COLA Revisions," provides a sample COLA revision for reactor trip system instrumentation setpoints and departure from nucleate boiling parameters.
The licensee proposed to revise the TS Table 3.3.1-1, "Reactor Protection System Instruments," by relocating the numerical values of the Note 1 (Overtemperature /1 T) and Note 2 (Overpower /1 T) to the COLA and adding the notes. The proposed notes state The values denoted with [*] are specified in the COLR." However, the HBRSEP2 TS OTDT and OPDT equations differs from those in TSTF-339 and WCAP-14483-A and thus have somewhat different OTDT and OPDT TS parameters. Thus the sample COLA revision in WCAP-14483-A, Appendix B is not fully applicable to the proposed HBRSEP2 TS change. In addition, the licensee did not specify how the changes would appear in the proposed COLR. Therefore, the NRC staff requests that the license provide pages of the proposed COLA that show changes resulting from the LAR.
DEP Response:
See pages 5 - 9 of this Attachment.
U. S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 5 of 9 ADDITIONAL CORE OPERATING LIMITS REPORT (COLR) PAGES (Note that these pages may be renumbered and reformatted when the final COLA is produced.)
U.S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 6 of 9 ISl!la 00 tfOT OPERATI w IN THIS AAF.J.
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U.S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 7 of 9 Overtemperature AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T' .s 575.9 °F Nominal RCS Operating Pressure P' ~ 2235 psig Overtemperature I!!.T reactor trip setpoint K1 .S 1.1265 Overtemperature I!!. T reactor trip heatup setpoint penalty coefficient K 2 = 0.01228/°F Overtemperature I!!. T reactor trip depressurization setpoint penalty coefficient K 3 = 0.00089/psig Time constants utilized in the lead-lag compensator for Tavg r 1 ~ 20.08 sec
- 2 .S 3.08 sec f(/!!.I) "positive" breakpoint = 12%/!!.I f(/!!.I) "negative" breakpoint = -17%/!!.I f(/!!.I) "positive" slope =2.4%1!!.To/%1!!.I f(/!!.I) "negative" slope = 2.4%/!!.To/%1!!.I (referred to in Technical Specification 3.3.1)
U. S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 8 of 9 Overpower AT Setpoint Parameter Values Parameter Nominal Value Nominal Tavg at RTP T' =:; 575.9 °P Overpower AT reactor trip setpoint Ki 5 1.06 Overpower AT reactor trip penalty Ks ~ 0.02/0 P for increasing T avg Ks ~ 0/ 0 P for decreasing Tavg Overpower AT reactor trip heatup setpoint penalty coefficient K6 ~ 0.00277 / 0 P when T > T' K6 ~ 0/0 P when T =:; T' Time constant utilized in the rate Jag compensator for AT 't 3 ~ 9 sec f(AI) "positive" breakpoint = 12%AI f(AD "negative" breakpoint =-17%AI f(AI) "positive" slope = 2.4%ATof%AI f(AI) "negative" slope = 2.4%ATof%AI (referred to in Technical Specification 3.3.1)
U. S. Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0072 Page 9 of 9 Table 1 Reactor Coolant System DNB Parameters Parameter Indication No. Operable Limits Channels
- 1. Indicated RCS Average Temperature meter 3 ~ 577.63 °P meter 2 ~ 577.25 °P computer 3 ~ 578.23 °P computer 2 ~ 577.99 °P
- 2. Indicated Pressurizer Pressure meter 3 ~ 2215.78 psig meter 2 ~ 2220.46 psig computer 3 ~ 2209.41 psig computer 2 ~ 2212.65 psig
- 3. RCS Total Flow Rate ~ 99.8 x 106 lbm/hr (referred to in Technical Specification 3.4.1)