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) | 20 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) | Non-Destructive Examination Weld Overlay Finite Element Analysis |
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) | 20 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) | Non-Destructive Examination |
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 Require | 7 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 | Incorporated by reference Surveillance Frequency Control Program Operational leakage |
RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report | 16 March 2023 | Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report | |
RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds | 28 February 2023 | Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds | |
RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) | 15 February 2023 | End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) | |
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 Facility | 13 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 | Health Physics Network High winds |
RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology | 7 April 2022 | Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology | Affidavit |
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative | 31 January 2022 | Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative | Boric Acid Hydrostatic Finite Element Analysis Aging Management Stress corrosion cracking License Renewal Subsequent License Renewal Liquid penetrant Operational leakage |
RA-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 | 4 October 2021 | Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 | |
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 Plan | 11 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 | Safe Shutdown Health Physics Network Offsite Dose Calculation Manual Tornado Missile Met Tower Emergency Lighting Incorporated by reference FLEX Open House Earthquake Deep Dose Equivalent Minimum staff Fire Protection Program Grace period Siren Overexposure |
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)(4 | 11 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-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage | 29 January 2021 | Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage | |
RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period | 2 April 2020 | Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period | |
RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 | 8 April 2019 | Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 | |
RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 | 7 March 2019 | Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 | Safe Shutdown Time of Discovery High winds Mission time Anticipated operational occurrence Internal Flooding Probabilistic Risk Assessment Qualified Offsite Circuit Functionality Assessment FLEX Large early release frequency Operability Determination Earthquake Offsite Circuit |
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) | 11 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-19-0005, Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A | 30 January 2019 | Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A | Aging Management Design basis earthquake Stress corrosion cracking Affidavit |
RA-18-0229, Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1 | 3 December 2018 | Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1 | Safe Shutdown Time of Discovery High winds Mission time Anticipated operational occurrence Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Qualified Offsite Circuit Functionality Assessment FLEX Seismically rugged Surveillance Frequency Control Program Large early release frequency Operability Determination Commercial Grade Offsite Circuit |
RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles | 1 November 2018 | Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles | Safe Shutdown Ultimate heat sink Tornado Missile Tornado-Generated Missile Tornado Missile Protection TORMIS Earthquake |
ML18191A564 | 10 July 2018 | Attachment 3 - Response to NRC Request for Additional Information | Safe Shutdown High winds Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Earthquake |
MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles | 3 July 2018 | Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles | Tornado Generated Missile |
ML20052D936 | 3 July 2018 | Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density | |
MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies | 12 December 2017 | Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies | High winds Internal Flooding Probabilistic Risk Assessment B.5.b |
ML17349A157 | 12 December 2017 | Response to Request for Additional Information Regarding License Amendment Request for Temporary Changes to Technical Specifications to Address the 'A' Train Nuclear Service Water System Non-Conforming Condition | Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
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) | 9 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) | Finite Element Analysis Stress corrosion cracking Weak link |
RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. | 20 July 2017 | Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. | Safe Shutdown High winds Ultimate heat sink Anticipated operational occurrence Internal Flooding Probabilistic Risk Assessment Large early release frequency Offsite Circuit |
MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal | 28 June 2017 | Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal | High winds Hydrostatic FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation Flood Hazard Mitigation Strategies Assessment Flooding Focused Evaluation |
RA-17-0030, Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers | 8 June 2017 | Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers | |
MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies | 25 May 2017 | Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies | |
CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. | 20 October 2016 | Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. | Safe Shutdown Ultimate heat sink Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX B.5.b Fukushima Dai-Ichi Significance Determination Process Seismically rugged Large early release frequency Spent Fuel Pool Instrumentation Earthquake Hardened vent Backfit |
ML16294A254 | 13 October 2016 | Response to Request for Additional Information Regarding Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping | VT-2 Through-Wall Leak Through-Wall Leakage |
RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation | 3 October 2016 | Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation | |
ML16244A060 | 18 August 2016 | Response to Request for Addition Information to RR 16-MN-003 | |
MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-003 | 18 August 2016 | Response to Request for Additional Information to Relief Request 16-MN-003 | Non-Destructive Examination License Renewal Liquid penetrant |
MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 18 August 2016 | Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi |
ML16230A006 | 11 August 2016 | Response to Request for Additional Information Regarding License Amendment Request to Technical Specification 3.6.13, Ice Condenser Doors | Surveillance Frequency Control Program |
RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations | 14 July 2016 | Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations | Generic Fundamentals Examination |
MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information | 30 June 2016 | License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information | Boric Acid Coatings Aging Management Moisture barrier License Renewal |
MNS-16-023, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications | 16 March 2016 | Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications | |
ML16056A242 | 18 February 2016 | Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Change the Emergency Plan to Upgrade Emergency Action Levels Based on NEI 99-01, Revision 6 | Safe Shutdown Ultimate heat sink Offsite Dose Calculation Manual Time to boil Operating Basis Earthquake Earthquake |
MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension | 10 February 2016 | Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension | Safe Shutdown FLEX Foreign Material Exclusion Earthquake |
MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | 4 February 2016 | Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | Safe Shutdown Earthquake Probabilistic Risk Assessment FLEX B.5.b Fukushima Dai-Ichi Earthquake Power-Operated Valves |
MNS-16-009, Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c) | 4 February 2016 | Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c) | Exemption Request |
RA-16-0006, Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions | 1 February 2016 | Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions | Tornado Missile |
MNS-16-003, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation | 7 January 2016 | Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation | Safe Shutdown Safe Shutdown Earthquake Grace period |
ML15343A012 | 7 December 2015 | Response to NRC Letter Dated 10/26/2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension. | Internal Flooding FLEX Foreign Material Exclusion Earthquake |
MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System | 13 November 2015 | Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System | |
MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension | 8 October 2015 | Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension | FLEX Foreign Material Exclusion Earthquake |
MNS-15-077, Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | 8 October 2015 | Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. | Fukushima Dai-Ichi |