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	Issue date	Title	Topic
RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals	21 September 2023	Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals	Safe Shutdown Unanalyzed Condition Non-Destructive Examination Nondestructive Examination Functionality Assessment Aging Management Stress corrosion cracking Eddy Current Testing License Renewal Subsequent License Renewal EVT-1 Power change Power Uprate Measurement Uncertainty Recapture Thermal fatigue
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-23-0154, 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
ML23151A348	30 May 2023	Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)	Incorporated by reference
ML23142A273	22 May 2023	Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)	Incorporated by reference
RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)	17 February 2023	Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)	Weld Overlay Hydrostatic Finite Element Analysis Flow Accelerated Corrosion Stress corrosion cracking
ML18283B544	20 November 2018	Relief from the Requirements of the ASME Code, Section XI, Reactor Vessel Closure Head Penetration Nozzle Repair Technique	Nondestructive Examination Liquid penetrant
HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval	18 April 2018	Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant Exclusive Use Affidavit
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-17-0016, Duke Energy - Proposed Alternative in Accordance with 10 CFR 50.55(z)(1) for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange (17-GO-001)	29 March 2017	Duke Energy - Proposed Alternative in Accordance with 10 CFR 50.55(z)(1) for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange (17-GO-001)	Finite Element Analysis Stress corrosion cracking Weak link
ML16343A220	27 December 2016	Relief Request 13R-16 for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Ispection Program - Third 10-Year Interval	Nondestructive Examination Liquid penetrant
HNP-16-092, Relief Request I3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval	19 October 2016	Relief Request I3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld Affidavit
ML15203A702	18 September 2015	Relief Request 13R-15 for Reactor Vessel Closure Head Penetration Nozzle Repair Technique, Inservice Inspection Program - Third 10 - Year Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant
HNP-15-039, Relief Request I3R-15 Revision 2, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval	29 April 2015	Relief Request I3R-15 Revision 2, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval	Non-Destructive Examination Hydrostatic Nondestructive Examination Finite Element Analysis Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld Exclusive Use Affidavit
HNP-15-034, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval	15 April 2015	Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval	Boric Acid Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld Exclusive Use Affidavit
HNP-15-010, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval	2 April 2015	Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld
ML14093A075	11 April 2014	Relief Request I3R-13 for Reactor Vessel Closure Head Penetration Nozzle 37 Repair Inservice Inspection Program - Third 10-Year Interval	Nondestructive Examination Incorporated by reference Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld
HNP-13-119, Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval	22 November 2013	Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld
ML13238A154	13 September 2013	Relief Request I3R-11 for Reactor Vessel Closure Head Penetration Nozzles Repair Inservice Inspection Program - Third 10-Year Interval	Non-Destructive Examination Weld Overlay Incorporated by reference Stress corrosion cracking Liquid penetrant
HNP-13-057, Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Lnservice Inspection Program - Third Interval	22 May 2013	Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Lnservice Inspection Program - Third Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld
ML12270A258	2 October 2012	Relief Request 13R-09 for Reactor Vessel Closure Head Penetration Nozzles Repair Inservice Inspection Program Third 10-Year Interval	Weld Overlay Nondestructive Examination Incorporated by reference Stress corrosion cracking Liquid penetrant
HNP-12-054, Relief Request I3R-09 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval	3 May 2012	Relief Request I3R-09 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld
ML12128A007	3 May 2012	Relief Request 13R-09 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval	Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld
ML102910129	29 December 2010	Shearon Harrris Nuclear Power Plant, Unit 1 - Relief Request for Approval of an Alternative Inservice Inspection Method for Six Pressure Retaining Dissimilar Metal Welds in the Reactor Pressure Vessel Nozzles	Incorporated by reference Stress corrosion cracking Dissimilar Metal Weld
ML102150340	3 August 2010	Request for Additional Information TAC No. ME3984)	Stress corrosion cracking
HNP-10-059, Request for Approval of Proposed Alternative I3R-07 in Accordance with 10 CFR 50.55a(a)(3)(i) for the Third Ten-Year Interval Inservice Interval	27 May 2010	Request for Approval of Proposed Alternative I3R-07 in Accordance with 10 CFR 50.55a(a)(3)(i) for the Third Ten-Year Interval Inservice Interval	Stress corrosion cracking Eddy Current Testing Dissimilar Metal Weld
ML090060737	30 November 2008	NUREG-1916, Volume 1, (2:2) Chpt 3 - End, Safety Evaluation Report Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1	Safe Shutdown Boric Acid Ultimate heat sink Non-Destructive Examination Fire Barrier Stroke time Weld Overlay Coatings Temporary Modification VT-2 Aging Management Local Leak Rate Testing Foreign Material Exclusion Flow Accelerated Corrosion Feedwater Heater Intergranular Stress Corrosion Cracking Stress corrosion cracking Eddy Current Testing Operability Determination Moisture barrier License Renewal Maintenance Rule Program Biofouling Through-Wall Leak Through-Wall Leakage Fire Protection Program Dissimilar Metal Weld Eddy-Current Testing Thermography Thermal fatigue
ML081330464	30 January 2008	Rev. 0 to PEN02.G03, Shearon Harris Nuclear Plant ISI Program Plan, Third 10-Year Inspection Interval. Cover to Page 8-2	High Radiation Area Weld Overlay Hydrostatic Probabilistic Risk Assessment Nondestructive Examination VT-2 Incorporated by reference High Energy Line Break Flow Accelerated Corrosion Stress corrosion cracking Moisture barrier EVT-1 Liquid penetrant Dissimilar Metal Weld Scaffolding Thermography Thermal fatigue
HNP-07-041, Inservice Inspection Relief Request 1, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs	14 May 2007	Inservice Inspection Relief Request 1, Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs	Weld Overlay Hydrostatic Nondestructive Examination Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld
ML060870043	7 April 2006	Relief, Relief Request 2R1-016 and 2R1-017 for the Second 10 Yr Inservice Inspection Interval	Incorporated by reference Dissimilar Metal Weld
ML031140549	7 November 1991	Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability	Safe Shutdown Unanalyzed Condition Fitness for Duty Probabilistic Risk Assessment Condition Adverse to Quality Missed surveillance Operability Determination Exemption Request Pressure Boundary Leakage Backfit Operational leakage

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