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Issue date | Title | Topic | |
---|---|---|---|
ML23256A088 | 25 September 2023 | Issuance of Alternative to Steam Generator Welds | Hydrostatic Probabilistic Risk Assessment Incorporated by reference Finite Element Analysis |
ML23230A065 | 31 August 2023 | William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code | Incorporated by reference |
ML23159A271 | 20 June 2023 | William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds | Nondestructive Examination VT-2 Incorporated by reference |
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 |
ML23118A076 | 1 May 2023 | Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI | 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 |
ML22096A003 | 18 November 2022 | McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations | Aging Management Stress corrosion cracking License Renewal Subsequent License Renewal |
ML22266A078 | 26 September 2022 | William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request | Stroke time Incorporated by reference |
ML22213A253 | 31 August 2022 | Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method | Non-Destructive Examination Stress corrosion cracking |
ML22242A160 | 30 August 2022 | Hardship Relief Request Pilot-Operated Relief Valve Acceptance Review Results | |
ML22007A345 | 11 January 2022 | Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 | |
ML21306A159 | 16 November 2021 | Request to Use Provisions of Later Edition and Addenda of the ASME Code, Section XI (EPID; L-2021-LLR-0048) | Incorporated by reference |
ML21029A335 | 16 February 2021 | Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI | VT-2 Incorporated by reference |
ML20230A205 | 21 August 2020 | Relief Request RA-20-0031, Delay to Update the Code of Record for Inservice Inspection | Nondestructive Examination Incorporated by reference |
ML19217A324 | 14 August 2019 | Relief Request MC-SRV-NC-03, Alternate Testing for Pressurizer Power Operated Relief Valve Block Valve 2NC-35B | Packing leak Operational leakage |
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-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 | 12 November 2018 | Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 | Eddy Current Testing |
ML18016A178 | 24 January 2018 | Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032) | VT-2 Incorporated by reference Stress corrosion cracking Liquid penetrant Through-Wall Leakage Dissimilar Metal Weld Operational leakage |
ML17331A086 | 26 December 2017 | Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads | Stress corrosion cracking Thermal fatigue |
ML17104A110 | 26 April 2017 | Relief Request CN Grr 01, Alternative to the Testing Frequencies in the American Society of Mechanical Engineers Operation and Maintenance Code, by Adoption of Code Case OMN-20, Inservice Test Frequencies (CAC Nos. MF9595-6) | Operability Determination |
CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing | 11 April 2017 | Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing | Incorporated by reference Operability Determination |
ML17034A362 | 22 February 2017 | Mcguire Nuclear Station, Unit 1 - Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping Relief | Weld Overlay Coatings VT-2 Liquid penetrant Through-Wall Leakage |
ML16358A696 | 17 January 2017 | Proposed Relief Request MC-SRV-NC-02, Alternate Testing for Pressurizer Power Operated Relief Valve (Porv) Block Valve 2NC-31B | Packing leak Stroke time Operational leakage |
ML16266A026 | 18 October 2016 | Proposed Relief Request Serial No. 16-MN-003 for Alternate Repair of Nuclear Service Water Piping | Liquid penetrant Through-Wall Leak |
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 |
ML16225A654 | 11 August 2016 | Email - McGuire Unit No. 1: Acceptance REVIEW- Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping. | |
MNS-16-062, Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping | 10 August 2016 | Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping | Through Wall Leak |
ML16210A038 | 28 July 2016 | Draft Relief Request Serial No. 16-MN-003 | |
MNS-16-053, Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping | 23 June 2016 | Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping | Weld Overlay Coatings Liquid penetrant Through-Wall Leakage |
ML16152A601 | 8 June 2016 | Withdrawal of Relief Request | |
ML15301A544 | 10 November 2015 | Proposed Relief Request 15-CN-001, Alternative Repair of a Main Steam System Braided Flex-Hose | Stress corrosion cracking |
ML15232A543 | 27 August 2015 | Proposed Relief Request 15-MN-001 | Stress corrosion cracking Through-Wall Leak Dissimilar Metal Weld DM weld |
CNS-15-062, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2) | 16 July 2015 | Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2) | Unanalyzed Condition Functionality Assessment Operability Determination Operational leakage |
ML15161A376 | 19 June 2015 | Proposed Relief Request 14-CN-002, Alternative to American Society of Mechanical Engineers (ASME) Section XI Requirements for Class 3 Buried Piping | VT-2 |
ML15124A699 | 8 May 2015 | (Catawba 1 and 2) - Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section X1, for Inservice Inspection Activities | Incorporated by reference |
ML14295A532 | 30 October 2014 | Proposed Relief Request 14-CN-001, American Society of Mechanical Engineers (ASME) Section IX Volumetric Examination Requirements | VT-2 Incorporated by reference |
ML14188C348 | 14 July 2014 | Proposed Relief Request 13-MN-002 | Non-Destructive Examination Internal Flooding Probabilistic Risk Assessment VT-2 Incorporated by reference Flow Accelerated Corrosion Large early release frequency Dissimilar Metal Weld Thermal fatigue |
ML14079A546 | 26 March 2014 | Proposed Relief Request 13-CN-003, Request for Alternative to the Requirement of IWB-2500, Table IWB-2500-1, Category B-A and Category B-D for Reactor Pressure Vessel Welds | Probabilistic Risk Assessment Incorporated by reference License Renewal |
ML14013A242 | 17 January 2014 | Proposed Relief Request Nos. MC-SRP-KC-01 and MC-SRP-ND-01 (TAC Nos. MF1164, MF1165, MF1166 and MF1167 | |
ML13294A609 | 8 November 2013 | Proposed Relief Request 12-MN-004 (TAC Nos. MF0508, MF0514, and MF0515) | VT-2 Pressure Boundary Leakage Unidentified leakage Operational leakage |
ML13010A554 | 14 January 2013 | Proposed Relief Request 12-MN-002 | VT-2 Incorporated by reference Thermal fatigue |
ML12355A149 | 29 November 2012 | Relief Request Serial # 12-MN-004 Limited Weld Examinations | VT-2 |
ML12264A338 | 24 September 2012 | Correction Letter for Approval Letter and Safety Evaluation for Relief Request 11-MN-002 Regarding the Extension of the Inservice Inspection Interval for Reactor Vessel Category B-A and B-D Welds | |
ML12123A112 | 9 May 2012 | Request for Relief 12-MN-001, Relief Request for a Alternative Depth Sizing Criteria | |
ML11187A001 | 14 July 2011 | Relief 10-CN-001, Alternative Requirements for Temporary Acceptance of a Through-Wall Flaw in Boric Acid Tank Nozzle Weld | Boric Acid Incorporated by reference Stress corrosion cracking Liquid penetrant Through-Wall Leak Through-Wall Leakage |
ML11160A144 | 23 June 2011 | Relief 10-MN-002, Extension of Volumetric Inspection of Steam Generator Primary Manway Studs for One Operating Cycle Beyond the Third 10-Year Inservice Inspection Interval End Date | VT-2 Incorporated by reference Eddy Current Testing |
ML101580422 | 14 June 2010 | Relief 09-MN-005 for Alternative Leakage Testing for Various American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Class 1 Piping and Components During the Third 10-Year Inservice | Hydrostatic VT-2 Incorporated by reference Stress corrosion cracking Pressure boundary leak Through-Wall Leakage Thermal fatigue |
ML101250170 | 3 May 2010 | Withdrawal of Request for Relief Number 09-CN-001, Limited Weld Examinations During the End-of-Cycle 17 Refueling Outage | |
ML100620018 | 4 March 2010 | Relief 09-MN-007 for Reactor Vessel Core Flood Nozzle Weld Examinations During the Third 10-Year Inservice Inspection | Incorporated by reference Dissimilar Metal Weld |
ML091240156 | 27 May 2009 | Relief 06-CN-003 for Use of Polyethylene Material in Buried Service Water Piping | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Finite Element Analysis |