CNS-15-053, Response to Request for Additional Information Regarding Expedited Seismic Evaluation Process Report | 23 June 2015 | Response to Request for Additional Information Regarding Expedited Seismic Evaluation Process Report | Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
CNS-15-067, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Supplemental Response to NRC Request For.. | 15 July 2015 | License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Supplemental Response to NRC Request For.. | Hot Short Safe Shutdown Probabilistic Risk Assessment Incorporated by reference Job Performance Measure Thermoset Fire Protection Program |
CNS-15-068, Response to NRC Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and ... | 31 July 2015 | Response to NRC Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and ... | |
CNS-15-070, Supplemental Response to NRC Request for License Amendment Request to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants | 14 August 2015 | Supplemental Response to NRC Request for License Amendment Request to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants | Safe Shutdown Probabilistic Risk Assessment Incorporated by reference Fire Protection Program |
CNS-15-075, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start.. | 17 August 2015 | License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start.. | |
CNS-15-086, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start.. | 23 October 2015 | License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start.. | |
CNS-16-010, Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Clean Version. Part 4 of 4 | 19 February 2016 | Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Clean Version. Part 4 of 4 | Safe Shutdown Time of Discovery Health Physics Network High winds Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Fire Barrier Time to boil Safe Shutdown Earthquake Internal Flooding Probabilistic Risk Assessment Operating Basis Earthquake Operator Manual Action Feedwater Heater Spent Fuel Pool Instrumentation Safeguards Contingency Plan Earthquake Fuel cladding Pressure Boundary Leakage Grace period Power change Unidentified leakage |
CNS-16-022, Supplemental Information to the Final Notification of Full Compliance with Order EA-12-049,Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Et | 31 March 2016 | Supplemental Information to the Final Notification of Full Compliance with Order EA-12-049,Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Et A | |
CNS-16-035, License Amendment Request to Revise Technical Specifications Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Requests for Additional Information CAC Nos. MF7265 and MF7266 | 20 June 2016 | License Amendment Request to Revise Technical Specifications Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Requests for Additional Information CAC Nos. MF7265 and MF7266 | Internal Flooding Probabilistic Risk Assessment Coatings Large early release frequency Moisture barrier |
CNS-16-043, Additional Information Regarding Flood Hazard Reevaluation Report, Response to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Forc | 23 June 2016 | Additional Information Regarding Flood Hazard Reevaluation Report, Response to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force | FLEX Fukushima Dai-Ichi |
CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an | 2 August 2016 | License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and | Safe Shutdown Fire Barrier Probabilistic Risk Assessment Fire Protection Program |
CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 | 7 September 2016 | License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 | Safe Shutdown Probabilistic Risk Assessment Fire Protection Program |
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 |
CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 8 December 2016 | Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | Fukushima Dai-Ichi |
CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. | 26 January 2017 | Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. | Safe Shutdown High winds Fire Protection Program |
CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report | 24 May 2017 | Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report | |
CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding | 29 August 2017 | Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding | Preliminary White Finding |
CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus | 28 December 2017 | Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi | Fukushima Dai-Ichi Overspeed trip |
CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information | 21 December 2017 | Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information | Incorporated by reference Through-Wall Leak |
CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System | 8 May 2018 | (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System | Safe Shutdown Probabilistic Risk Assessment |
ML15324A083 | 16 November 2015 | License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate, Response to NRC Requests for Additional Information (Rais) | Power Uprate Measurement Uncertainty Recapture |
ML16055A227 | 19 February 2016 | Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Redline Version. Part 1 of 4 | Safe Shutdown Time of Discovery Ultimate heat sink Offsite Dose Calculation Manual Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Grace period |
ML16055A228 | 19 February 2016 | Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Redline Version. Part 2 of 4 | Safe Shutdown Health Physics Network High winds Ultimate heat sink Fire Barrier Time to boil Safe Shutdown Earthquake Internal Flooding Operating Basis Earthquake Operator Manual Action Safeguards Contingency Plan Earthquake Pressure Boundary Leakage Power change Unidentified leakage |
ML16055A230 | 19 February 2016 | Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Redline Version. Part 3 of 4 | Reactor Vessel Water Level Ultimate heat sink Feedwater Heater Fuel cladding Pressure Boundary Leakage |
ML16102A156 | 11 March 2016 | Proposed Technical Specifications Amendments, TS 3.4.1, Reactor Coolant System Pressure, Temperature and Flow Departure from Nucleate Boiling Limits, Response to NRC Request for Additional Information | Loop seal Coast down Power Uprate Measurement Uncertainty Recapture Affidavit |
ML16204A060 | 20 July 2016 | Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant, 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 |
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 | |
NRC-18-0016, Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1.. | 21 February 2018 | Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1.. | |
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 |
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 |
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 | |
RA-17-0029, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers | 8 June 2017 | Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers | Recently irradiated fuel |
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 |
RA-17-0036, Supplement to the Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers | 17 July 2017 | Supplement to the Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers | |
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-18-0097, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System | 17 August 2018 | (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System | Safe Shutdown High winds Internal Flooding Probabilistic Risk Assessment Fukushima Dai-Ichi Seismically rugged Large early release frequency Turbine Missile |
RA-18-0162, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal | 6 December 2018 | Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal | Fukushima Dai-Ichi Flooding Focused Evaluation |
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-19-0189, 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-19-0280, Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 | 10 July 2019 | Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 | Safe Shutdown High winds Mission time Internal Flooding Probabilistic Risk Assessment FLEX Large early release frequency Offsite Circuit |
RA-20-0002, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits | 13 February 2020 | Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits | Measurement Uncertainty Recapture |
RA-20-0104, Response to NRC Request for Additional Information - Catawba Nuclear Station-SG Report (RA-19-0391)-C2R23 | 6 April 2020 | Response to NRC Request for Additional Information - Catawba Nuclear Station-SG Report (RA-19-0391)-C2R23 | Stress corrosion cracking |
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-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-21-0063, 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 Potassium iodide ANS Design Report |
RA-21-0321, Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report | 14 December 2021 | Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report | |
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-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-22-0147, 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 |