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Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23118A0762023-05-0101 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 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML22096A0032022-11-18018 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 ML22046A2802022-02-23023 February 2022 Relief from ASME Code Paragraph ISTP-3540(b) Related to High Pressure Injection Pumps Vibration Measurements ML22046A2452022-02-18018 February 2022 Regarding Alternative to Implement Code Case OMN-22, Smooth Running Pumps ML22028A3652022-02-0707 February 2022 Authorization and Safety Evaluation for Alternative Acceptance Criteria for Code Case N-853 ML21029A3352021-02-16016 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 RA-20-0036, Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping2020-03-0202 March 2020 Request for Alternative to Defect Removal Prior to Performing Repair/Replacement Activities on Low Pressure Service Water (LPSW) System Piping ML20042D7142020-02-13013 February 2020 Relief Request 19-ON-002 for Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in ASME Code Case N-770-2 RA-19-0028, Submittal of Relief Request (19-ON-001) to Utilize Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress2019-03-21021 March 2019 Submittal of Relief Request (19-ON-001) to Utilize Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress 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)2019-02-11011 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 22018-11-12012 November 2018 Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML16118A2302016-04-30030 April 2016 Relief Request 14-ON-022 Alternative Requirements for Class 2 Residual Heat Removal Heat Exchange Welds ML16053A5012016-03-0101 March 2016 Relief Request ON-GRR-01 Grace Period for OM Code Frequencies (CAC Nos. MF7130, MF7131, and MF7132) ML16004A1812016-01-0707 January 2016 Relief Request 14-ON-003 Alternative Requirements for Class 1 Category B-J Piping Welds ML16004A2622016-01-0707 January 2016 Relief Request 15-ON-004: Limited Visual Examinations of the Reactor Pressure Vessel Support Skirt for the Fourth 10-Year Inservice Inspection Interval Program ML15349A4532015-12-29029 December 2015 Relief Request 15-ON-001 Repair of Low Pressure Service Water System Piping ONS-2015-087, Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-003, Limited Volume Inspections from 3EOC27 Outage2015-07-15015 July 2015 Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-003, Limited Volume Inspections from 3EOC27 Outage ONS-2015-088, Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-004, Limited Visual Examinations from 1 EOC27, 2EOC26 and 3EOC27 Outages2015-07-15015 July 2015 Fourth Ten-Year Inservice Inspection Plan, Relief Request No. 15-ON-004, Limited Visual Examinations from 1 EOC27, 2EOC26 and 3EOC27 Outages ML13365A0232014-01-17017 January 2014 Relief from the Requirements of the ASME Code for Fourth 10-Year Interval Inspection Program Request for Relief ML13066A1002013-02-27027 February 2013 End of Cycle (EOC) 27 Refueling Outage Steam Generator Inservice Inspection Report ML13045A2902013-02-15015 February 2013 Relief from the Requirements of the ASME OM Code ML13038A1522013-01-31031 January 2013 Fourth Ten-Year Inservice Inspection Plan, Request for Relief No. 12-ON-001 ML13038A1502013-01-31031 January 2013 Fourth Ten-Year Inservice Inspection Plan Request for Relief No. 12-ON-002 ML12173A3122012-06-18018 June 2012 Approval Request for the Fifth Ten-Year Inservice Test Program Interval Pump Specific Code Relief Request No. ON-SRP-HPI-03 ML12030A0892012-01-23023 January 2012 Duke Energy Carolinas - Relief Request Serial #09-GO-001 Request for NRC Clarification ML11143A0592011-06-21021 June 2011 Relief Request 10-ON-001 for Reactor Vessel Core Flood Nozzle Weld Examinations ML1106605882011-03-28028 March 2011 Relief Request (RR) Proposed Alternative for Certain Vibration Measurement Requirements RR (ON-SRP-HPI-03)) (TAC Nos. Me 3840, ME3841, ME3842, ME5790, ME5791, ME5792, ME5793, ME5794 and ME5795) ML1016604732010-06-0909 June 2010 Relief Request No. 10-ON-001, Alternative to Volumetric Examination Requirements for the Residual Heat Removal (RHR) Heat Exchanger Class 2 Nozzle-to-Shell Welds ML1008802862010-03-31031 March 2010 Relief Request 09-ON-003 for the Use of Full Structural Weld Overlay & Alternative Examination Techniques, for the Letdown Line, Reactor Vessel Core Flood & Reactor Coolant Pump Inlet & Outlet Nozzle Butt Welds. ML1006006982010-03-0303 March 2010 Relief, Request 09 ON-005 for Reactor Vessel Core Flood Nozzle Weld Examinations (ME1846, ME1847, and ME1848) ML0927403122009-09-24024 September 2009 Relief Request from Immediate ASME Code Flaw Repair of Standby Shutdown Facility Auxiliary Service Water Piping ML0921500282009-07-28028 July 2009 Fourth Ten Year Inservice Inspection Interval Request for Relief No. 09-ON-005 ML0914702652009-05-20020 May 2009 Request for Extension of Duke Response Time to Referenced Letter ML0908307262009-03-20020 March 2009 Fourth Ten Year Inservice Inspection Interval, Request for Relief No. 09-ON-003 ML0833600322008-11-20020 November 2008 Summary Ultrasonic Examination Results of Completed ML0810200532008-04-0707 April 2008 Relief Request No. 08-ON-003, from Immediate ASME Code Flaw Repair of Low Pressure Service Water Piping ML0734600272008-01-17017 January 2008 Relief Request to Use Preemptive Weld Overlay and Alternative Examination Techniques on Decay Heat Removal Line to Hotleg Nozzle Welds ML0715605102007-05-29029 May 2007 Fourth Ten Year Inservice Inspection Interval Request for Relief No. 04-ON-007, Revision 1 ML0712300902007-04-27027 April 2007 Part 21 Interim Report, Dresser Investigation File No. 2007-02, Interim Reporting of a Potential Defect Involving Power Actuated Pressure Relief Valves Supplied to Calvert Cliffs, Fort Calhoun and Oconee Plants ML0626202342006-09-11011 September 2006 Relief Request 06-ON-004 Request for Additional Information ML0622902642006-08-0909 August 2006 Response to Request for Additional Information Request for Relief No. 05-ON-004 ML0619400162006-07-0606 July 2006 Replacement of Steam Generators Request for Relief No. 04-ON-007, Rev. 1 ML0609302482006-05-0404 May 2006 Relief Request 05-ON-003 ML0608302912006-04-17017 April 2006 Relief, Volumetric Examination of Essentially 100 Percent of the Volume as Required by the ASME, Boiler and Pressure Vessel Code, Section XI, for Class 1 and 2 Welds ML0608301052006-04-14014 April 2006 SE MC5483 and MC5483, Relief Request RR-04-ON-013 ML0536302312006-03-13013 March 2006 Relief Request MC8852, Repair of Steam Generator Tubes 2023-09-25
[Table view] Category:Letter type:RA
MONTHYEARRA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0320, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2023-12-14014 December 2023 Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency2023-11-16016 November 2023 Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0304, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0)2023-11-14014 November 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0) RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0275, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-10-12012 October 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0268, Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan2023-09-29029 September 2023 Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan RA-23-0234, Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS)2023-09-28028 September 2023 Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS) RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-23-0228, Registration for Use of General License Spent Fuel Cask Number 1752023-09-14014 September 2023 Registration for Use of General License Spent Fuel Cask Number 175 RA-23-0223, Registration for Use of General License Spent Fuel Cask Numbers 173 and 1742023-08-23023 August 2023 Registration for Use of General License Spent Fuel Cask Numbers 173 and 174 RA-23-0222, On-Shift Staffing Analysis (Ossa), Revision 12023-08-23023 August 2023 On-Shift Staffing Analysis (Ossa), Revision 1 RA-23-0211, Reply to a Notice of Violation (NOV) 05000270/2023010-022023-08-17017 August 2023 Reply to a Notice of Violation (NOV) 05000270/2023010-02 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)2023-07-20020 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) 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)2023-07-20020 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) RA-23-0186, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)2023-07-18018 July 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3) RA-23-0184, Registration for Use of General License Spent Fuel Cask Numbers 171 and 1722023-07-10010 July 2023 Registration for Use of General License Spent Fuel Cask Numbers 171 and 172 RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0146, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-06-20020 June 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0128, Refuel 32 (O1R32) Steam Generator Tube Inspection Report2023-05-18018 May 2023 Refuel 32 (O1R32) Steam Generator Tube Inspection Report RA-23-0018, Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 12023-05-0404 May 2023 Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1 RA-23-0111, Withdrawal of License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-27027 April 2023 Withdrawal of License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-23-0104, Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report2023-04-26026 April 2023 Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0099, Subsequent License Renewal Application Second Annual Amendment to the License Renewal Application2023-04-25025 April 2023 Subsequent License Renewal Application Second Annual Amendment to the License Renewal Application RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-22-0292, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-0404 April 2023 License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0037, Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis)2023-03-30030 March 2023 Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis) RA-23-0051, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities2023-03-0909 March 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities RA-23-0052, Refuel 32 (O1R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval2023-02-22022 February 2023 Refuel 32 (O1R32) Inservice Inspection (ISI) Report, Fifth 10-Year ISI Interval RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0334, Refuel 31 (O3R31) Steam Generator Tube Inspection Report2022-11-21021 November 2022 Refuel 31 (O3R31) Steam Generator Tube Inspection Report RA-22-0329, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 1 Cycle 33 (Revision 0 and Revision 1)2022-11-11011 November 2022 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 1 Cycle 33 (Revision 0 and Revision 1) RA-22-0285, Subsequent License Renewal - Appendix E Environmental Report Supplement 22022-11-0707 November 2022 Subsequent License Renewal - Appendix E Environmental Report Supplement 2 RA-22-0313, Emergency Action Level (EAL) Technical Basis Document, Revision 4, EAL Wallchart, Revision 3 and Alternate TSC and OSC Renovations2022-10-27027 October 2022 Emergency Action Level (EAL) Technical Basis Document, Revision 4, EAL Wallchart, Revision 3 and Alternate TSC and OSC Renovations RA-22-0270, Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations2022-10-0707 October 2022 Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations RA-22-0192, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a2022-09-0202 September 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a 2024-01-08
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Text
~ ~ DUKE J. Ed Burchfield, Jr.
~ ENERGY Vice President Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3478 t* 864. 873.4208 Ed.Burchfie/d@duke-energy.com Serial: RA-19-0028 10 CFR 50.55a March 21, 2019 U.S. Nuclear Regulatory Commission A TIN : Document Control Desk Washington, DC 20555-0001 OCONEE NUCLEAR STATION, UNIT NOS. 1, 2 AND 3 DOCKET NOS. 50-269 , 50-270, 50-287 / RENEWED LICENSE NOS. DPR-38, DPR-47 AND DPR-55
SUBJECT:
Relief Request (19-ON-001) to Utilize Code Case N-853, "PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1" Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(z)(1), Duke Energy Carolinas, LLC (Duke Energy) hereby submits Relief Request 19-ON-001 requesting U.S. Nuclear Regulatory Commission (NRC) approval to use an alternative to the defect removal requirements of American Society of Mechanical Engineers (ASME) Code,Section XI, Article IWA-4000 at Oconee Nuclear Station Units 1, 2, and 3 (ONS). Specifically, Duke Energy proposes to use ASME Code Case N-853, "PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1" with the deviations described herein. Enclosure 1 contains details regarding this request.
This submittal contains no new regulatory commitments. To support work in the ONS Unit 3 refueling outage currently scheduled in April 2020, Duke Energy requests approval of this relief request prior to that outage . If you have questions concerning this request, please contact Art Zaremba, Manager, Fleet Licensing, at (980) 373-2062 .
Sincerely, t u &Jf:J))~
J. Ed Burchfield, Jr.
Vice President Oconee Nuclear Station
Enclosure:
- 1. Relief Request 19-ON-001
U.S. Nuclear Regulatory Commission RA-19-0028 Page 2 cc: (all with Enclosure unless otherwise noted)
C. Haney, Regional Administrator USNRC Region II E. L. Crowe, USNRC Resident Inspector - ONS A. L. Klett, NRR Project Manager - ONS RA-19-0028 Enclosure 1 Relief Request 19-ON-001
Relief Request Serial #19-ON-001 RA-19-0028, Enclosure 1
- 1. ASME Code Components Affected ONS Unit 1:
- Three 1A Hot Leg RTE Mounting Boss Alloy 600 Nozzle Welds (1-PHA-13, 1-PHA-14, & 1-PHA-15).
- Three 1B Hot Leg RTE Mounting Boss Alloy 600 Nozzle Welds.
(1-PHB-13, 1-PHB-14, & 1-PHB-15).
- Four (4) Cold Leg RTE Mounting Boss Alloy 600 Nozzle Welds (1-PIA1-12, 1-PIA2-12, 1-PIB1-12, & 1-PIB2-12).
ONS Unit 2:
- Three 2A Hot Leg RTE Mounting Boss Alloy 600 Nozzle Welds.
(2-PHA-13, 2-PHA-14, & 2-PHA-15).
- Three 2B Hot Leg RTE Mounting Boss Alloy 600 Nozzle Welds.
(2-PHB-13, 2-PHB-14, & 2-PHB-15).
- Four (4) Cold Leg RTE Mounting Boss Alloy 600 Nozzle Welds (2-PIA1-12, 2-PIA2-12, 2-PIB1-12, & 2-PIB2-12).
ONS Unit 3:
- Three 3A Hot Leg RTE Mounting Boss Alloy 600 Nozzle Welds.
(3-PHA-13, 3-PHA-14, & 3-PHA-15).
- Three 3B Hot Leg RTE Mounting Boss Alloy 600 Nozzle Welds.
(3-PHB-13, 3-PHB-14, & 3-PHB-15).
- Two 3A Hot Leg Pressure Tap Alloy 600 Nozzle Welds.
(* Nearest Nozzle Butt Welds 3-RC-287-6 & 3-RC-287-7).
- Two 3B Hot Leg Pressure Tap Alloy 600 Nozzle Welds.
(* Nearest Nozzle Butt Welds 3-RC-286-14 & 3-RC-286-15).
- Two 3A Hot Leg Flow Meter Alloy 600 Nozzle Welds.
(* Nearest Nozzle Butt Welds 3-RC-287-3 & 3-RC-287-63V).
- Two 3B Hot Leg Flow Meter Alloy 600 Nozzle Welds.
(* Nearest Nozzle Butt Welds 3-RC-286-11 & 3-RC-286-58V).
- Four (4) Cold Leg RTE Mounting Boss Alloy 600 Nozzle Welds (3-PIA1-9, 3-PIA2-9, 3-PIB1-11, & 3-PIB2-9).
- One 3B1 Cold Leg Level Tap Alloy 600 Nozzle Weld.
(* Nearest Nozzle Butt Weld 3-50-37-1).
- Three Cold Leg Drain Alloy 600 Nozzle Welds.
(3PIA1-10, 3-PIA2-10, 3-PIB2-10).
Note *: Small Bore Piping (1 NPS) Nozzle Welds are not given explicit weld IDs on the original Drawings. These nine specific Small Bore Nozzle Welds are located by the nearest documented branch connection butt weld.
Materials of construction for all locations referenced above are:
- Alloy 600 Nozzle - SB-167 UNS N06600 (P-No. 43)
ENiCrFe-3, Spec. SFA 5.11 (F-No. 43)
Page 1 of 7
Relief Request Serial #19-ON-001 RA-19-0028, Enclosure 1
2. Applicable Code Edition and Addenda
The current edition for the Inservice Inspection (ISI) interval for ONS Units 1, 2, and 3 is the American Society of Mechanical Engineers (ASME) Code,Section XI, 2007 Edition with the 2008 Addenda (Reference 1). All three units are in the fifth inspection interval with a scheduled end date of July 15, 2024.
The code of construction for ONS 1, 2, and 3 is B31.7, 1969 Edition, and was later reconciled to the ASME Code,Section III, 1983 Edition, no Addenda.
American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)
Code Case N-722-1 as conditioned by 10 CFR 50.55a (Reference 2)
American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)
Code Case N-853 (Reference 3)
- 3. Applicable Code Requirements Code Case N-722-1 (as conditioned by 10 CFR 50.55a) requires that piping hot leg/cold leg full penetration welds susceptible to PWSCC be inspected in accordance with Table 1 of the Code Case as part of the ISI program. Duke Energy has decided to preemptively mitigate/repair selected nozzle butt welds on the RCS piping, utilizing a welded reinforcing pad and replacement nozzle.
ASME Code,Section XI (Reference 1), Article IWA-4000 provides requirements for repair replacement activities:
IWA-4421 states, in part:
Defects shall be removed or mitigated in accordance with the following requirements...
IWA-4422.1(a) states, in part:
A defect is considered removed when it has been reduced to an acceptable size ...
IWA-4422.1(b) states, in part:
Alternatively, the defect removal area and any remaining portion of the defect may be evaluated, and the component accepted in accordance with the appropriate flaw evaluation provisions of Section XI ...
Article IWA-4000 does not provide specific guidance for the repair or mitigation of defects in dissimilar metal welds. Furthermore, the NRC in 10 CFR 50.55a(b)(2)(xxv) specifically prohibits the use of the provisions in IWA-4340, "Mitigation of Defects by Modification.
Page 2 of 7
Relief Request Serial #19-ON-001 RA-19-0028, Enclosure 1
4. Reason for Request
The welds identified in Section 1 are unmitigated full penetration welds fabricated from materials susceptible to PWSCC. As these welds are unmitigated, there exists the potential that flaws may develop at these locations and result in leakage. In accordance with Code Case N-722-1, these welds require frequent visual examination for the identification of any RCS leakage.
Duke Energy is proposing to apply a welded reinforcing pad on the Outer Diameter (OD) of the RCS piping using PWSCC resistant nickel Alloy 52M (ERNiCrFe-7A) filler metal. The new weld pad will be welded using the machine Gas Tungsten Arc Welding (GTAW)
Ambient Temperature Temper Bead (ATTB) welding technique. Duke Energy is proposing to attach a PWSCC resistant nozzle to the new weld pad with a full penetration nozzle corner weld using a non-temper bead manual welding technique, using PWSCC resistant nickel Alloy 52M filler metal, or with a "J" groove partial penetration weld as described in Code Case N-853. The welded pad will be designed and installed in accordance with Code Case N-853 except that the replacement nozzle material will be UNS S31600 or UNS N06690.
Code Case N-853 is not yet NRC-approved, but it has been reviewed by the NRC and is proposed to be approved for Unconditional Use (Reference 4 and 5). Therefore, Duke Energy is requesting relief under 10 CFR 50.55a(z)(1) from the defect removal requirements of ASME Code,Section XI, Article IWA-4000. The identified welds will be mitigated by a repair/replacement activity that meets the requirements of Code Case N-853 with the alternative nozzle material and weld joint geometry described herein. The repair/replacement activity provides an acceptable level of quality and safety.
- 5. Proposed Alternative and Basis for Use Figure 1a and Figure 1b provide sketches of the existing nozzle configurations described in Section 1. The Alloy 600 nozzle and Alloy 82/182 weld are materials with known susceptibility to PWSCC. The replacement of PWSCC susceptible material with material that is resistant to PWSCC provides for an acceptable level of quality and safety. The PWSCC susceptible material, at the identified locations, is currently unmitigated.
Application of a PWSCC resistant branch connection weld metal buildup will reduce the risk of a flaw propagating through the pressure boundary.
The PWSCC resistant branch connection weld metal buildup will be designed in accordance with Code Case N-853. Code Case N-853 has been reviewed by the NRC and is proposed to be approved for Unconditional Use (Reference 4 and 5). Two optional deviations may be taken to Code Case N-853 as follows: a) the new nozzle material may be manufactured from UNS S31600 material instead of UNS N06690, and b) the new nozzle may be attached by a full penetration nozzle corner weld instead of a partial penetration J groove weld.
Reference 6 provides the technical basis supporting the use of Code Case N-853.
Code Case N-853 requires the use of UNS N06690 material for the replacement nozzle.
Duke Energy proposes as an option to use UNS S31600 material for the replacement nozzle. UNS S31600 material is used in many applications for elevated temperature reactor coolant piping at ONS. UNS S31600 is an austenitic stainless steel that has demonstrated operating experience as PWSCC resistant. The applicable ASME Code allowable stresses and material properties for UNS S31600 will be used in the design of the replacement nozzle. The reason for the requested use of UNS S31600 is that UNS S31600 is a more Page 3 of 7
Relief Request Serial #19-ON-001 RA-19-0028, Enclosure 1 readily available material, given the strict ASME Code Class 1 requirements for materials, and the small volume of material required.
Code Case N-853 requires the use of a partial penetration J groove weld for the attachment of the new nozzle to the reinforcing weld metal buildup. The partial penetration J groove weld is one of many Code approved configurations for attachment of nozzles to piping. Figure 2 provides a sketch of the Code Case configuration. Duke Energy proposes to optionally use a full penetration nozzle corner weld to join the new nozzle to the weld reinforcing pad. The technical basis for Code Case N-853 (Reference 6) includes reference for the use of full penetration nozzle welds.
The full penetration nozzle corner weld configuration shown in Figure 3 is in agreement with ASME Code,Section III, Figure NB-4244(b)-1 detail (a) (Reference 7). The full penetration corner weld will be examined in accordance with Reference 7 and Code Case N-853. The reason for the requested optional use of the nozzle corner weld detail (detail (a) of Figure NB-4244(b)-1) is that field conditions of access and interferences may result in situations where the corner weld is preferable to the J-groove weld, based on dose exposure and installation sequence. Additionally, use of a full penetration corner weld eliminates the small pocket area at the base of the nozzle which over time will collect contaminants and create a radiological hot spot in the RCS piping.
In summary, Duke Energy is requesting relief under 10 CFR 50.55a(z)(1) from the ASME Code,Section XI defect removal requirements of IWA-4000. The repair/replacement activity will follow the requirements stated in Code Case N-853 and modified herein. The requested relief from IWA-4000 is based on the use of Code Case N-853 (with the noted deviations /
exceptions) that will provide an alternative with an acceptable level of quality and safety.
The subject welds will be mitigated or repaired by application of a PWSCC resistant reinforcing pad and attachment of a PWSCC resistant nozzle. The pre-service and inservice examination requirements of Code Case N-853 will be implemented. The use of Code Case N-853 as guidance for the repair/replacement activity will provide an acceptable level of quality and safety.
- 6. Precedents Weld metal buildups with a replacement nozzle have been performed to repair leaking nozzles on reactor pressure vessels and pressurizers. These instances formed the basis of Code Case N-853. Listed below are examples with the submitted request for alternative (RR) and safety evaluation (SE).
- a. Palo Verde Nuclear Generation Station (RR Reference 8; SE Reference 9)
- b. Limerick Generation Station (RR Reference 10; SE Reference 11)
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Relief Request Serial #19-ON-001 RA-19-0028, Enclosure 1
- 7. Duration of Proposed Alternative The duration of this relief request is for the remainder of the current licensed operating life of each ONS unit, shown below. The repairs will be designed to meet the requirements of Code Case N-853 and ASME Code,Section III (Reference 7). The design will consider operation until the end of the current operating licenses for each unit.
Docket Number License Expires Unit 1 05000269 02/06/2033 Unit 2 05000270 10/06/2033 Unit 3 05000287 07/19/2034
- 8. References
- 1. American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI, 2007 Edition with the 2008 Addenda.
- 2. ASME Code Case N-722-1, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials,Section XI, Division 1, Approval Date: January 26, 2009.
- 3. ASME Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking,Section XI, Division 1, Approval Date: June 27, 2016.
- 4. Federal Register; Proposed Rules; Vol. 83, No. 159; August 16, 2018.
- 5. NRC Draft Regulatory Guide DG-1342; Proposed Revision 19 to Regulatory Guide RG 1.147; August 2018 (ADAMS Accession No. ML18114A225).
- 6. Waskey, D., McCracken, S., (2016); Technical Basis for Code Case N-853 - A600 Branch Connection Weld Repair for SCC Mitigation; Proceedings of the ASME 2016 Pressure Vessels and Piping Conference; PVP2016; July 17-21, 2016, Vancouver, British Columbia, Canada; PVP2016-63902.
- 7. ASME Code Section III, 2013 Edition.
- 8. Arizona Public Service Company letter, American Society of Mechanical Engineers (ASME) Code,Section XI, Request for Approval of an Alternative to Flaw Removal and Characterization - Relief Request 51, dated November 8, 2013 (ADAMS Accession No. ML13317A071).
- 9. NRC letter, Palo Verde Nuclear Generating Station, Unit 3 - Request for Relief from ASME Code,Section XI Requirements Regarding Half-Nozzle Repair and Flaw Evaluation as an Alternative to Flaw Removal and Flaw Characterization for Flaw in Bottom-Mounted Instrument Nozzle Penetration No.3 (TAC No. MF3051), dated April 10, 2014 (ADAMS Accession No. ML14093A407).
- 10. Exelon Generation letter, Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs, dated May 15, 2017 (ADAMS Accession No. ML17135A423).
- 11. NRC letter, Limerick Generating Station, Unit 2 - Relief Request I4R-17, Associated with the Alternate Repair of a 2-Inch Instrument Line Nozzle at Penetration N-16D on the Reactor Pressure Vessel (CAC No. MF9702), dated August 14, 2017 (ADAMS Accession No. ML17208A090)
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Relief Request Serial #19-ON-001 RA-19-0028, Enclosure 1 Figure 1a: Sketch of Example Existing Nozzle Configuration RCS RUN PIPE AU.DY 82/182 BUTTER (UNIT 3 ONLY)
AU.DY 82/182 WELD AU.DY 600 NOZZLE Figure 1b: Sketch of Example Fast RTE Nozzle Connection Page 6 of 7
Relief Request Serial #19-ON-001 RA-19-0028, Enclosure 1 NEW NOZZLE ALLOY 52/v\ J Prep Weld CC N-853 ALLOY 82/182/
Figure 2: Sketch of Example Repaired Nozzle Configuration with Code Case N-853 J-Groove Weld NEW NOZZLE ALLOY 52M CORNER WELD Figure NB-4244(b)-1 CJP ALLOY 82/182/ ALLOY 600 Figure 3: Sketch of Example Repaired Nozzle Configuration with Proposed Alternative Full Penetration Corner Weld Page 7 of 7