| 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 |
| 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 |
| ML12278A399 | 31 August 2012 | WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant | Operating Basis Earthquake
Nondestructive Examination
Functionality Assessment
Aging Management
Intergranular Stress Corrosion Cracking
Stress corrosion cracking
Eddy Current Testing
License Renewal
EVT-1 |
| ML11186A011 | 22 July 2011 | Request for Relief (RR-23) from ASME Code, Section XI for the Fourth 10-Year Inservice Inspection Program Interval | Incorporated by reference |
| ML103010406 | 28 December 2010 | Review of Refueling Outage 25 Inspections of the Reactor Vessel Nozzle Dissimilar Metal Butt Welds | Incorporated by reference
Finite Element Analysis
Stress corrosion cracking
Eddy Current Testing
Dissimilar Metal Weld |
| RNP-RA/10-0056, Response to NRC Request for Additional Information Regarding Review of Refueling Outage 25 Inspections of the Reactor Vessel Nozzle Dissimilar Metal Butt Welds | 24 June 2010 | Response to NRC Request for Additional Information Regarding Review of Refueling Outage 25 Inspections of the Reactor Vessel Nozzle Dissimilar Metal Butt Welds | Nondestructive Examination
Dissimilar Metal Weld |
| RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant. | 31 July 2009 | WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant. | Operating Basis Earthquake
Nondestructive Examination
Functionality Assessment
Aging Management
Intergranular Stress Corrosion Cracking
Stress corrosion cracking
Eddy Current Testing
License Renewal
EVT-1 |
| RNP-RA/09-0010, Submittal of 90 Day Inservice Inspection Summary Report for Refueling Outage 25 | 11 February 2009 | Submittal of 90 Day Inservice Inspection Summary Report for Refueling Outage 25 | Hydrostatic
Coatings
VT-2
License Renewal
Liquid penetrant
Dissimilar Metal Weld
Eddy-Current Testing |
| ML083470836 | 8 December 2008 | Results of MRP-139 Inspections of the Reactor Vessel Nozzle Dissimilar Metal Butt Welds During Refueling Outage 25 | Stress corrosion cracking
Eddy Current Testing
Dissimilar Metal Weld
DM weld |
| ML082730270 | 22 October 2008 | Request for Relief from ASME Code, Section XI, Appendix Viii, Supplement 2 and Supplement 10 Weld Examination Requirements | Nondestructive Examination
Incorporated by reference
Dissimilar Metal Weld |
| RNP-RA/08-0121, WCAP-15621-NP, Rev 1, Handbook on Flaw Evaluation for the H.B. Robinson Unit 2 Reactor Vessel. | 31 August 2008 | WCAP-15621-NP, Rev 1, Handbook on Flaw Evaluation for the H.B. Robinson Unit 2 Reactor Vessel. | Nondestructive Examination
Stress corrosion cracking |
| 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 |