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	Issue date	Title	Topic
RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation	14 December 2023	Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation	Finite Element Analysis Aging Management Stress corrosion cracking Affidavit
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 Methodology	30 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	Safe Shutdown Earthquake Stress corrosion cracking License Renewal Fuel cladding Pressure Boundary Leakage Pressure boundary leak Unidentified leakage Affidavit Operational leakage
RA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations	30 March 2023	Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations	Boric Acid Affidavit
RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections	28 July 2022	Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections	Non-Destructive Examination Stress corrosion cracking Affidavit
RA-20-0382, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model	17 December 2020	30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model	Boric Acid Loop seal Hydrostatic Exclusive Use Affidavit
RA-19-0138, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections	23 July 2019	Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections	Hydrostatic Stress corrosion cracking License Renewal Through-Wall Leak Through Wall Leak Dissimilar Metal Weld DM weld Affidavit
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 Report	10 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	Fuel cladding Exclusive Use Affidavit
RA-18-0016, Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses	5 June 2018	Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses	Shutdown Margin Anticipated operational occurrence Surveillance Frequency Control Program Affidavit
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)	30 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)	Boric Acid Shutdown Margin Fuel cladding Affidavit
RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P	4 May 2016	Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P	Shutdown Margin Reactor Vessel Water Level Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Affidavit
ML16112A275	19 April 2016	Robinson Fuel Meth Pre-sub Meeting - Presentation Affidavit for Closed Pre-Submittal Meeting with Duke Energy Progress to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re H.B. Robinson and Shearon Harris Plants	Affidavit
RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.	19 November 2015	Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.	Safe Shutdown Shutdown Margin Loop seal Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Affidavit
RA-15-0041, Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted)	18 September 2015	Attachment 1, Affidavit and Attachment 3, Pre-Submittal Meeting Presentation Materials on DPC-NF-2010-A and DPC-NE-2011-P Methodologies (Redacted)	Affidavit
RA-15-0037, Transmittal of Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5	9 September 2015	Transmittal of Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5	Anticipated operational occurrence Exclusive Use Affidavit
RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.	19 August 2015	Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.	Shutdown Margin Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Annual Radiological Environmental Operating Report Process Control Program Fuel cladding Affidavit
RA-15-0004, Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermalhydraulic Statistical Core Design Methodology	5 March 2015	Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermalhydraulic Statistical Core Design Methodology	Shutdown Margin Anticipated operational occurrence Post Accident Monitoring Nondestructive Examination Annual Radiological Environmental Operating Report Process Control Program Exclusive Use Affidavit
RNP-RA/13-0072, Request for Site-Specific Information Related to Use of Gothic Be Withheld from Public Disclosure in Accordance with 10 CFR 2.390(a)(4)	8 August 2013	Request for Site-Specific Information Related to Use of Gothic Be Withheld from Public Disclosure in Accordance with 10 CFR 2.390(a)(4)	GOTHIC Affidavit
RA-11-008, Progress Energy - Evidence of Guarantee of Payment of Deferred Premiums	14 April 2011	Progress Energy - Evidence of Guarantee of Payment of Deferred Premiums	Affidavit
RNP-RA/09-0054, Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation	19 June 2009	Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation	Affidavit
RNP-RA/07-0126, Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System	29 November 2007	Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System
RNP-RA/05-0062, Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating	13 July 2005	Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating
RNP-RA/05-0039, Response to NRC Request for Additional Information Regarding Loss of Coolant Accident Alternative Source Term Dose Analysis	26 May 2005	Response to NRC Request for Additional Information Regarding Loss of Coolant Accident Alternative Source Term Dose Analysis	Ultimate heat sink Affidavit