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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
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program 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 ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections 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 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22234A0062022-08-30030 August 2022 SLRA - Closed Public Meeting Summary - August 18, 2022 2024-02-01
[Table view] Category:Safety Evaluation
MONTHYEARML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 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 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22349A1452022-12-19019 December 2022 Non-Proprietary Safety Evaluation Related to the SLRA of Oconee Nuclear Station, Units 1, 2, and 3 ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints 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 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22096A1872022-07-15015 July 2022 Issuance of Amendment Nos. 424, 426, and 425 Revise TS 3.7.7, Low Pressure Service Water (LPSW) System to Extend the Completion Time for One Required Inoperable LPSW Pump ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22068A0252022-03-15015 March 2022 Code Case OMN-28 - Alternative Valve Position Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible to Stem-Disk Separation 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 ML22019A1352022-01-21021 January 2022 Proposed Alternative to Implement ASME Code Case OMN-24 ML21347A0102021-12-20020 December 2021 Proposed Alternative to Implement ASME Code Case OMN-26 ML21335A1062021-12-0707 December 2021 Proposed Alternative to ASME Code W, Section XI, Subsection Iwl Regarding Containment Post-Tensioning System Inservice Inspection Requirements ML21281A1412021-11-19019 November 2021 Authorization and Safety Evaluation for Alternative Reactor Pressure Vessel Inservice Inspection Intervals ML21155A2132021-08-26026 August 2021 Plant ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21006A0982021-03-15015 March 2021 Issuance of Amendment Nos. 421, 423, and 422 Revision of Licensing Basis for High Energy Line Breaks Outside of Containment (EPID L-2019-LLA-0184) (Public Version) 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 ML20335A0012021-01-26026 January 2021 Issuance of Amendment Nos. 420, 422, and 421 Measurement Uncertainty Recapture Power Uprate ML20303A0242020-12-0909 December 2020 Issuance of Amendments 419, 421, 420 TSTF-272, Refueling Boron Concentration Clarification ML20296A2812020-11-25025 November 2020 Issuance of Amendment Nos. 418, 420 and 419 TSTF-421, Revision to RCP Flywheel Inspection Program ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20055F5712020-02-26026 February 2020 Proposed Alternative Request 19-ON-001 to Use Modified American Society of Mechanical Engineer'S Boiler and Pressure Vessel Code Case N-853 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 ML19260E0842019-10-31031 October 2019 Issuance of Amendments 415, 417, and 416, Regarding the Updated Final Safety Analysis Report Description of Tornado Mitigation ML19056A0862019-09-30030 September 2019 Issuance of Amendments Nos. 414, 416 and 415 Regarding the Physical Security Plan ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19183A3172019-07-17017 July 2019 Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for Fission Gas Gap Release Rates ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML18311A1342018-12-17017 December 2018 Non Proprietary - Issuance of Amendments Regarding the Updated Final Safety Analysis Report Section for the Standby Shutdown Facility ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18040A1942018-04-12012 April 2018 Issuance of Amendments Regarding the Technical Specifications for Control Room Habitability (CAC Nos. MF9555, MF9556, and MF9557; EPID L-2017-LLA-0219) ML18051B2572018-02-28028 February 2018 Safety Evaluation for Alternative to Codes and Standards Requirements Associated with Bronze Tape Wrapped Emergency Power Cables (CAC Nos. MF7365, MF7366, and MF7367; EPID L-2016-LLR-0001) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17335A0252017-12-0505 December 2017 Correction to Safety Evaluation for Amendment Nos. 406, 408, and 407 (CAC Nos. MF7417, MF7418, and MF7419; EPID L-2016-LLA-0002) ML17124A6082017-11-20020 November 2017 Issuance of Amendments Regarding the Technical Specifications for Electrical Power Systems (CAC Nos. MF7417, MF7418, and MF7419; EPID L-2016-LLA-0002) ML17202U7912017-08-30030 August 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17167A2652017-07-12012 July 2017 Issuance of Amendments Regarding the Technical Specifications for Dry Spent Fuel Storage Cask Loading and Unloading (CAC Nos. MF8161, MF8162, and MF8163) ML17103A5092017-05-11011 May 2017 Issuance of Amendments Allowing the Use of the Copernic Fuel Performance Code ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16197A0112016-07-22022 July 2016 Relief Request Nos. 15-ON-002 and 15-ON-003, Fourth 10-Year Inservice Inspection Interval 2023-09-25
[Table view] |
Text
December 14, 2004 Mr. Ronald A. Jones, Vice President Oconee Nuclear Station Duke Energy Corporation 7800 Rochester Highway Seneca, South Carolina 29672
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 - RELIEF REQUEST 04-ON-008 FROM CERTAIN NON-DESTRUCTIVE EXAMINATION REQUIREMENTS OF THE CODE OF RECORD (TAC NOS. MC4374, MC4375, AND MC4376)
The NRC staff has reviewed the information provided by Duke Energy Company, (the licensee) in its letter dated September 13, 2004. The licensee requested that the NRC approve a request for relief from certain non-destructive examination requirements of the original Construction Code of Record for Oconee Nuclear Station, Units 1, 2, and 3. The request was made pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(a)(3)(ii).
The NRC staff finds the licensees request acceptable as discussed in the enclosed Safety Evaluation. The relief is authorized for the fourth 10-year inservice inspection (ISI) interval for Oconee, Units 1 & 2, and the third 10-year ISI interval for Oconee, Unit 3. However, for inservice inspections of the replaced, upgraded piping, and the embedded piping during future intervals, the licensee will be required to submit a request for relief for the embedded piping pursuant to 10 CFR 50.55a(a)(3)(ii).
Sincerely,
/RA/
John A. Nakoski, Section Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
As stated cc w/encl: See next page
ML043490084 **Na major changes to SE NRR-028 OFFICE PDII-1/PM PDII-1/LA EMCB//DE OGC PDII-1/SC NAME LOlshan CHawes EReichelt** TSmith* JNakoski DATE 12/14/04 12/14/04 12/8/04 12/13/04 12/14/04 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF 04-ON-008 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DUKE ENERGY COMPANY DOCKET NOS. 50-269, 50-270, AND 50-287
1.0 INTRODUCTION
By letter dated September 13, 2004, Duke Energy Company, (the licensee), requested that the Nuclear Regulatory Commission (NRC) approve Relief Request 04-ON-008 from certain non-destructive examination (NDE) requirements of the construction code of record for Oconee Nuclear Station, Units 1, 2, and 3. The licensee provided additional clarifying information, which is available under ADAMS accession number ML043350023.
2.0 REGULATORY EVALUATION
Inservice inspection (ISI) of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components is performed in accordance with Section XI of the ASME Code and the applicable addenda as required by Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(g), except where relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). 10 CFR 50.55a(a)(3) states that alternatives to the requirements of (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the ASME Code for the applicable nuclear power plants are listed below:
PLANT ISI INTERVAL EDITION Oconee Nuclear Station Fourth 1998 Edition, 2000 Addenda Unit 1 Oconee Nuclear Station Fourth 1998 Edition, 2000 Addenda Unit 2 Oconee Nuclear Station Third 1989 Edition Unit 3 System/Components for Which Relief is Requested The system/component that is affected is a section of piping that is part of the drain path from the Oconee Reactor Building Emergency Sump (RBES) to the Liquid Waste Disposal (LWD)
System. The licensee stated that following implementation of Oconee specification Nuclear Station Modification (NSM) ON-33106, this piping system will provide part of the High Pressure Injection (HPI) Pump minimum flow return path to the RBES following a loss-of-coolant accident (LOCA).
The licensee stated the particular section of piping of concern is the 4-inch drain piping from the RBES (located in the Reactor Building) up to the edge of the Auxiliary Building wall. The 4-inch and 2-inch section of pipe in the Auxiliary Building will be inspected. The licensee stated that using the definition in the Updated Final Safety Analysis Report (UFSAR), Problem Investigation Process (PIP) O-02-1233 identified a discrepancy for this pipe. Section 3.2.2.1 of the UFSAR states the following:
Class II (Duke Class B) systems normally contain radioactive fluid whose temperature is above 212EF, and in addition, those portions of Engineered Safeguard Systems outside the Reactor Building which may see recirculated reactor building sump water following a Loss of Coolant Accident (LOCA). Class III (Duke Class C) systems, or portions of systems, are those which would normally be Class II except that the contained fluid is less than 212EF.
PIP O-02-1223 also states that the current design temperature for the RBES drain piping is 300EF.
The licensee stated that Oconee specification NSM ON-33106 will replace the existing LWD pipe with new piping starting approximately 8 inches from where the embedded pipe exits the Auxiliary Building wall through valve 3LWD-103. The piping and associated components installed by NSM ON-33106 will be Class II (Duke Class B). The remaining pipe, all that is embedded plus 8 inches, must be upgraded to Class II (Duke Class B) as required by the UFSAR due to the addition of the HPI pump minimum flow return path. In addition, upgrading the piping to Class II (Duke Class B) will resolve PIP O-02-1233. The additional information provided by the licensee stated that the actual length of piping that is embedded and cannot be inspected is approximately 55 feet.
Licensees Code Requirement As stated in PIP O-02-1233, the current piping classification does not conform to the requirements set forth in UFSAR Section 3.2.2.1.
The licensee stated that following implementation of NSM ON-33106, the embedded piping will provide part of the HPI pump minimum flow return path to the RBES following a LOCA. The HPI pump minimum flow can be considered recirculated reactor building sump water and Class II requirements apply. Therefore, the embedded piping of the RBES drain line must be upgraded to Class II (Duke Class B).
The licensee stated the design requirements for Class II piping are defined in USA Standard (USAS) B31.7 Nuclear Power Piping, Section 2-701 and 2-702. The design requirements for Class III piping are defined in USAS B31.7 Section 3-701 and 3-702. The licensee stated the only difference between Class II and Class III piping as specified in USAS B31.7 are the NDE requirements.
Licensees Code Requirement from Which Relief is Requested The licensees RBES embedded drain piping is Class III (Duke Class C). This piping provides a drain path for the RBES to the LWD System. However, the licensee stated, that upon completion of NSM ON-33106, this piping will also provide a path for the HPI pump minimum flow to the RBES following a LOCA. The HPI pump flow can be considered recirculated reactor building sump water and Class II requirements would apply. The licensee stated the purpose of this document is to request relief from the NDE requirements of Class II for the existing embedded piping welds. The licensee stated that inspecting the embedded piping welds per the Class II requirements would involve extreme hardship without a compensating increase in the level of quality and safety.
The licensee stated that design requirements for Class II piping are defined in USAS B31.7 Section 2-701 and 2-702. Class II piping requires the following NDE (USAS B31.7, Sections 2-727 and 2-736.5 for Unit 1, Section 2-736.6 for Units 2 and 3, and Table A.7(b)):
a) 100 percent radiographic testing of all butt welds (girth and longitudinal) b) 100 percent radiographic testing of branch welds over 4 inches nominal pipe size c) 100 percent magnetic-particle and dye-penetrant testing (MT/PT) of all fillet/socket/seal/attachment/branch welds The licensee stated the design requirements for Class III piping are defined in USAS B31.7, Section 3-701 and 3-702. The licensee stated that weld inspection requirements during construction for Duke Class C components/piping were not as stringent as those for Class II piping components. Class III piping requires the following NDE (USAS B31.7, Section 2-736.5 for Unit 1, Section 2-736.6 for Units 2 and 3, Chapter 3-VI, and Table A.7(b)):
a) Radiographic testing 1 weld for every 10 butt welds a welder makes over 4 inches b) MT/PT one weld for every 10 fillet/socket/branch welds over 4 inches in diameter that a welder makes
The licensee stated that Class II and Class III both default to the same set of rules, specifically USAS B31.1.0-1967 Nuclear Power Piping. The licensee stated that all new piping installed by NSM ON-33106 will be installed and inspected to the current Class II requirements. The remaining piping is embedded. The licensee stated that complying with the Class II requirement would result in hardship or unusual difficulty without a compensating increase in quality or safety pursuant to 10 CFR 50.55a(a)(3)(ii).
Licensee Basis for Relief The licensee stated that Oconee Piping Specification OS-0243.00-00-0001, Appendix A, and Regulatory Guide 1.26 were used to evaluate the piping upgrade. The licensee stated that the portion of piping to be upgraded will not affect any valves, components or instruments. The affected embedded piping welds are identified as 62, 63, 64, 65, 66, 67, 68, and 69, and are shown on weld isometric 3-59-0016, which was provided to the NRC by the licensee.
The licensee stated NSM ON-33106 is installing new LWD piping approximately 8 inches from the embedded pipe through valve 3LWD-103. The licensee stated that the new piping and valves for NSM ON-33106 are being purchased, installed and inspected as Duke Class B (Class II).
The licensee stated that the original construction code requirements will be considered in this evaluation for the embedded piping since no modifications or weld repairs have ever been performed on this portion of the RBES drain line. The licensee stated the original code of construction is USAS B31.7 (February 1968 edition and the June 1968 errata) for Unit 1, and USAS B31.7 (August 1969 edition) for Units 2 and 3. The licensee considered the following items as part of its evaluation:
Piping Design The licensee stated that the existing 4-inch drain piping from the RBES is shown on Oconee drawing OFD-107D-3.2 as Duke Class C (Class III) piping. However, Oconee Piping Summary (OPS-59.00-3) and original documentation indicates that the original piping was Duke Class E.
The licensee states that PIP O-02-04984 documents that this piping was upgraded from Duke Class E to Duke Class C. PIP O-02-04984 also identifies, and the licensee confirmed, that the correct NDE was performed on this piping and that the weld isometrics were revised.
The licensee stated that according to OS-0243.00-00-0001, Appendix A, original Duke Class E piping was designed and installed to the same code requirements as Duke Class C (Class III).
Therefore, Duke Class E piping was essentially treated as if it were Duke Class C, with the exclusion of the seismic design considerations. Since Duke Class B (Class II) and Duke Class C (Class III) were designed and constructed to the requirements of USAS B31.7, the licensee performed a comparison between the chapters within USAS B31.7 that defined the requirements for Class II and Class III piping.
The licensee concluded that the design requirements for Class II and Class III piping both default to the same set of rules, specifically USAS B31.1.0-1967.
Piping Components The licensee stated that the piping design requirements for Class II piping are defined in USAS B31.7, Sections 2-703 through 2-709. The design requirements for Class III piping are defined in USAS B31.7, Sections 3-703 through 3-709. The licensee stated that both Class II and Class III piping fall back to the same set of rules, specifically, USAS B31.1.0-1967. The licensee identified two differences that existed with respect to the pressure design of components:
- 1) Class III piping allowed the use of Table A.9 stress values.
- 2) Flanges for Class II piping were designed to a different standard than those for Class III piping.
Following a review of the applicable drawings, the licensee determined that no flanges are installed in the embedded section of the piping.
Materials The licensee stated the Oconee Piping Summary 59.00-03, Revision 1, shows that the embedded RBES drain line between the emergency sump and valve 3LWD-103 was originally installed as stainless steel piping per Pipe Specification 151.4, which is used for Duke Class C and E piping. Pipe Specification 151.2 is used for Duke Class B piping. A comparison of the two pipe specifications show that the material requirements are the same except as listed below:
- Pipe Specification 151.4: ASME A-312 material is specified, however SA-312 material may be used per the original requirements of Oconee.
- Pipe Specification 151.2: ASME SA-312 material is specified, however A-312 material may be used per the original requirements of Oconee.
The licensee stated the material used for the embedded piping was ASME A-312, which is acceptable for Class II and Class III.
The licensee stated that after the piping upgrade, Oconee specification Oconee Flow Diagram 107D-3.2 will show that the embedded piping is Duke Class B and any future modification to this line will have to be performed in accordance with Class B guidelines.
Examination and Inspection of Welds The licensee stated that PIP 02-04984 documents that the weld tickets for the embedded piping were reviewed to ensure that the correct NDE for Class III piping was performed when the piping was upgraded from Duke Class E to Duke Class C.
The licensee stated that all new piping installed by NSM ON-33106 will be installed and inspected to the current Class II requirements. The remaining embedded piping cannot be inspected to the NDE requirements for Class II piping without significant hardship.
Fabrication, Assembly, and Erection The licensee stated that after reviewing the welding details, the documentation shows that only consumable inserts were allowed for use on the embedded stainless steel piping welds for which relief is requested. The licensee stated the consumable inserts were allowed for both Class II and Class III piping.
The licensee reviewed the weld records for the original code of construction and identified the welding process used was the Gas Tungsten Arc Welding process and all welding was performed by a single welder. Additionally, the licensee verified that the proper NDE examination had been performed.
Pressure Test The licensee reviewed the pressure test requirements and concluded that the leak testing for Class III piping during construction was the same as the leak testing requirements for Class II piping. The licensee stated that no additional leak testing is required for the embedded piping since the existing embedded piping will not be modified.
Licensees Justification for Relief As the licensee stated previously, a comparison of the requirements for Class II and Class III piping showed that the subject piping meets all requirements of Class II except for the NDE requirements. The licensee stated that in order to meet the full requirements of Class II piping, all of the concrete would have to be removed to allow the applicable inspection of the subject piping. The licensee stated that this would result in a significant hardship without a compensating increase in the level of quality and safety.
The licensee also noted that the subject piping has been in operation for over 30 years without the need for maintenance or repair. The licensee stated that future maintenance or repair activities will be performed in accordance with the requirements of Class II piping.
3.0 STAFF EVALUATION The licensee is performing a modification on each unit that will upgrade a section of existing piping such that additional NDE will be required. However, a portion of that piping on each unit is embedded such that NDE inspection of that portion would involve a significant hardship without a compensating increase in the level of quality and safety. The licensees request for relief was made pursuant to 10 CFR 50.55a(a)(3)(ii).
The particular section of piping of concern is the 4 inch drain piping from the RBES (located in the Reactor Building) up to the inside edge of the Auxiliary Building wall. Using the definition in the UFSAR, the licensees PIP O-02-1233 identified a discrepancy for this pipe. The UFSAR, Section 3.2.2.1 states the following:
Class 1 (Duke Class B) systems normally contain radioactive fluid whose temperature is above 212EF, and in addition, those portions of Engineered Safeguard Systems outside the Reactor Building which may see recirculated reactor building sump water following a Loss of Coolant Accident (LOCA). Class III (Duke Class C) systems, or portions of
systems, are those which would normally be Class II except that the contained fluid is less than 212EF.
PIP O-02-1233 also states that the current design temperature for the RBES drain piping is 300EF.
Additionally, following the licensees upgrade implementation of NSM ON-33106, the piping will provide part of the HPI pump minimum flow return path to the RBES following a LOCA. The HPI pump minimum flow can be considered recirculated reactor building sump water and Class II requirements apply. Therefore, the embedded piping of the RBES drain line must be upgraded to Class II (Duke Class B).
The licensee performed a comparison of the requirements for Class II and Class III of the subject piping and considered the following items:
- Examination and Inspection of Welds
- Fabrication and Inspection of Welds
- Pressure Tests The licensee concluded that the subject piping meets all the requirements of Class II piping except for the NDE requirements.
The licensee stated that Class II and Class III both default to the same set of rules, specifically USAS B31.1.0-1967. The licensee stated that all new piping installed by NSM ON-33106 will be installed and inspected to the current Class II requirements. The remaining piping is embedded.
In order for the licensee to meet the full requirements of Class II piping, all of the concrete would have to be removed to allow the inspections of the subject piping. This action would result in a significant hardship without a compensating increase in the level of quality and safety. The NRC staff agrees that removing all of the concrete to allow the inspections to meet the full requirements of Class II piping would result in hardship without a compensating increase in quality and safety.
The licensee also stated that the subject piping has been in operation for over 30 years without the need for maintenance or repair. Any future maintenance or repair activities will be performed according to the requirements of Class II piping. The NRC staff considers the licensees approach to be acceptable.
Based upon the information provided above, the NRC staff finds the licensees reasoning in support of its request for relief to be acceptable.
4.0 CONCLUSION
Based on the information provided in the licensees submittal, the NRC staff concludes that performing the required Class II NDE on a portion of embedded piping would involve hardship without a compensating increase in the level of quality and safety. Therefore, the proposed request for relief from certain NDE requirements of the Construction Code of Record pursuant to 10 CFR 50.55a(a)(3)(ii) for Oconee, Units 1, 2, and 3 is authorized for the fourth 10-year ISI interval for Oconee, Units 1, and 2, and the third 10-year ISI interval for Oconee, Unit 3. For inservice inspections of the replaced, upgraded piping, and the embedded piping during future intervals, the licensee will be required to request relief for the welds associated with the embedded piping. All other ASME Code,Section XI, requirements for which relief was not specifically requested and authorized herein by the NRC staff remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: E. Reichelt Date: December 14, 2004
Oconee Nuclear Station, Units 1, 2, and 3 cc:
Ms. Lisa F. Vaughn Ms. Karen E. Long Duke Energy Corporation Assistant Attorney General Mail Code - PB05E NC Department of Justice 422 S. Church St. P.O. Box 629 P.O. Box 1244 Raleigh, NC 27602 Charlotte, NC 28201-1244 Mr. R. L. Gill, Jr.
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