|
---|
Category:Code Relief or Alternative
MONTHYEARML24233A3082024-08-29029 August 2024 Relief Request (RA-24-0152) to Utilize a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML23256A0882023-09-25025 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) 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 ML16004A1812016-01-0707 January 2016 Relief Request 14-ON-003 Alternative Requirements for Class 1 Category B-J Piping Welds 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 ML13038A1502013-01-31031 January 2013 Fourth Ten-Year Inservice Inspection Plan Request for Relief No. 12-ON-002 ML13038A1522013-01-31031 January 2013 Fourth Ten-Year Inservice Inspection Plan, Request for Relief No. 12-ON-001 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 2024-08-29
[Table view] Category:Letter
MONTHYEARIR 05000269/20240032024-10-31031 October 2024 Integrated Inspection Report 05000269/2024003 and 05000270/2024003 and 05000287/2024003 (2) ML24255A3322024-10-16016 October 2024 SLRA - Revised SE Letter ML24297A6172024-10-11011 October 2024 PCA Letter to NRC Oconee Hurricane Helene ML24269A0912024-10-0909 October 2024 Request for Withholding Information from Public Disclosure ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr 05000270/LER-2023-001, Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee2024-02-29029 February 2024 Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee 05000287/LER-2023-002, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications2024-02-29029 February 2024 Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24019A1442024-02-13013 February 2024 Letter to Reid Nelson, Executive Director, Achp; Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24011A1532024-02-13013 February 2024 Letter to Tracy Watson EPA-Oconee Nuclear Sta, Unites 1, 2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, SHPO; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML24011A1482024-02-13013 February 2024 Letter to Steven M. Snider-Oconee Nuclear Sta, Unites 1,2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staff’S 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 2024-08-26
[Table view] Category:Safety Evaluation
MONTHYEARML24255A3322024-10-16016 October 2024 SLRA - Revised SE Letter ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 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 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) 2024-08-26
[Table view] |
Text
Mr. Scott Batson Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 7, 2016 \
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 -RELIEF REQUEST 14-0N-003 ALTERNATIVE REQUIREMENTS FOR CLASS 1 CATEGORY B-J PIPING WELDS (CAC NOS. MF6299, MF6300, AND MF6301)
Dear Mr. Batson:
By letter dated May 4, 2015, Duke Energy Carolinas, LLC (the licensee) requested U.S. Nuclear Regulatory Commission (NRC) authorization to use an alternative to the requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the Oconee Nuclear Station, Units 1, 2, and 3 (ONS) as identified in relief request no. 14-0N-003.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1
), the licensee requested to use the applicable Code Case N-609-1, as a proposed alternative to the method of selection of Class 1 Category B-J Piping welds for examination, on the basis that the alternative provides an acceptable level of quality and safety. The NRC staff has concluded, that the use of the proposed alternative described in relief request 14-0N-003, provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes, as stated in the enclosed Safety Evaluation, that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1
). Therefore, the NRC staff authorizes the use of the proposed alternative described in relief request 14-0N-003 at ONS, for the remainder of the fifth 10-year ISi interval, which commenced on July 15, 2014, and will end on July 15, 2024. All other ASME Code requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
S. Batson If you have any questions, please contact the ONS Senior Project Manager, Mr. James R Hall, at randy.hall@nrc.gov or 301-415-4032.
Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ Sincerely, Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING RELIEF REQUEST 14-0N-003 REGARDING CLASS 1 CATEGORY B-J PIPING WELDS DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287
1.0 INTRODUCTION
By letter dated May 4, 2015, 1 Duke Energy Carolinas, LLC (Duke, the licensee) requested U.S. Nuclear Regulatory Commission (NRG) authorization to use an alternative to the requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the Oconee Nuclear Station, Units 1, 2, and 3 (ONS) as identified in relief request no. 14-0N-003.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1
), the licensee requested to use the applicable Code Case N-609-1, as a proposed alternative to the method of selection of Class 1 Category B-J Piping welds for examination, on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
The licensee requested authorization of an alternative to the lnservice Inspection (ISi) requirements of article IWB-2500, Table IWB-2500-1 of the ASME Code,Section XI, pursuant to 10 CFR 50.55a(z)(1
). Pursuant to 1 O CFR 50.55a(g)(4), the ASME Code Class 1, 2, and 3 components (including supports) must 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 lnservice Inspection of Nuclear Power Plant Components," to extent practical within the limitations of design, geometry, and materials of construction of the components.
Pursuant to 10 CFR 50.55a(z) alternatives to the requirements of paragraph 10 CFR 50.55a(g) may be used, when authorized by the NRG, if the licensee demonstrates that: (1) the proposed
- alternative provides an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15132A280.
Enclosure Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the NRC to authorize the proposed alternative.
3.0 TECHNICAL EVALUATION 3.1 Component Affected The components affected are ASME Code Class 1 Piping Welds. In accordance with the ASME Code,Section XI, IWB-2500, Table IWB-2500-1, they are classified as Examination Category B-J Piping Welds. -3.2 Applicable Code Edition and Addenda The code of record for the fifth 10-year ISi interval at ONS is the 2007 Edition through 2008 Addenda of the ASME Code. 3.3 Duration of Relief Request The licensee requested the proposed alternative in 14-0N-003 for use during the fifth 10-year ISi interval which started on July 15, 2014, and is scheduled to end on July 15, 2024. 3.4 ASME Code Requirement The ASME Code,Section XI, IWB-2500-1 Examination Category B-J, requires Class 1 piping welds to be selected for examination in accordance with Note (2) (b), which states, in part; All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed either of the following limits under loads associated with specific events and operational conditions:
- 1. Primary plus secondary stress intensity range of 2.4Sm for ferritic steel and austenitic steel. 2. Cumulative usage factor U of 0.4. 3.5 Background In its letter dated May 4, 2015, the licensee states that the Class 1 piping at ONS was originally designed in accordance with ANSI B31.7 requirements.
This design code did not require an analysis to determine the primary plus secondary stress intensity range or cumulative usage factors, which are usually included in pipe designed in accordance with Section Ill of the ASME Code. During the previous 10-year ISi interval at ONS, Duke implemented the requirements in ASME Code Case N-609, "Alternative Requirements to Stress-Based Selection Criteria for Category B-J Welds." This code case allows the licensee to implement an alternative examination approach which does not include stress and usage factor parameters.
Code Case N-609 is included in Regulatory Guide (RG) 1.147, Revision 17, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1".2 According to the Applicability Index for Section XI Cases, the use of N-609 is limited to the 2004 Edition up to and including the 2005 Addenda of the ASME Code. For the fifth 10-year ISi interval at ONS, the Section XI Code of Record is ASME Section XI, 2007 Edition with the 2008 Addenda. In this edition of the code, the footnotes for Table IWB-2500-1, Category B-J have been edited (the stress and cumulative usage factors that were addressed in Footnote 1 are now addressed in Footnote 2). This change in the footnotes has been addressed by ASME by revising Code Case N-609. The new Code Case, N-609-1 was published in September 2010 and has not, as yet, been included in RG 1.147. Code Case N-609-1 is specifically applicable to the ONS fifth 10-year ISi interval Section XI Code of Record. Code Case N-609 is no longer valid for the fifth 10-year.ISI interval at ONS because it would conflict with which'states, "Code.Cases shall be applicable to the Edition and Addenda specified in the Inspection Plan." Consequently, Duke has chosen to pursue the use of Code Case N-609-1, since the technical requirements of Code Case N-609 and Code Case N-609-1 are identical.
3.6 Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1
), the licensee proposes to use Code Case N-609-1 as an alternative to the IWB-2500, Table IWB-2500-1, Examination Category B-J, Note (2) weld examination selection requirements.
Code Case N-609-1 states that Category B-J welds shall be selected for examination such that 25 percent of the total non-exempt welds are examined during the interval.
The welds selected shall include the following: (a) All terminal ends in each pipe or branch run connected to vessels. (b) All terminal ends in each pipe or branch run connected to other components. (c) All dissimilar metal welds not covered under Category B-F, between one of the following combinations:
(1) carbon or low alloy steels and high alloy steels; (2) carbon or low alloy steels and high nickel alloys; (3) high-alloy steels and high nickel alloys. (d) Additional piping welds, such that the total number of circumferential butt welds (or branch connection or socket welds) selected for examination equals 25% of the total number of nonexempt circumferential butt welds (or branch connection or socket welds) in the reactor coolant piping system. These additional piping welds shall be distributed as follows: (1) The examinations shall be distributed among the Class 1 systems prorated, to the degree practicable, on the number of nonexempt welds in each system (e.g., if a system 2 ADAMS Accession No. ML 13339A689. contains 30% of the nonexempt welds, 30% of the nondestructive examinations required by Category 8-J should be performed on that system). ' (2) Within each system, examinations shall be distributed between line sizes prorated, to the degree practicable, on the number of nonexempt welds in each line size. 3. 7 NRC' Staff Evaluation The NRC staff has evaluated relief request 14-0N-003 pursuant to 10 CFR 50.55a(z)(1).
The NRC staff's evaluation focused on whether the proposed alternative provides an acceptable . level of quality and safety. Review of the two code cases, Code Case N-609 and Code Case N-609-1, reveals that their technical aspects are identical.
The only difference between the two code cases is that Code Case N-609-1 was altered to take into account changes in the ASME Code 2004 Edition with the 2005/2006 Addenda,Section XI, IW8-2500, Table IW8-2500-1, Footnotes (1) and (2). In the 2004 Edition with the 2005 Addenda and earlier, the pertinent information was contained in Footnote (1 ), and was referenced in Code Case N-609. In the 2004 Edition with the 2005/2006 Addenda and beyond, the information previously contained in Footnote (1) was moved, word for word, to Footnote (2). Therefore, Code Case N-609-1 addresses this by specifying which footnote to reference depending on which edition of the code is the Code of Record. All other technical aspects of N-609 and N-609-1 are identical.
As stated in 10 CFR 50.55a(g)(4)(ii), the licensee must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph 1 O CFR 50.55a(a) 12 months before the start of the 120-month inspection interval (or the optional ASME Code Case listed in NRC RG 1.147, Revision 17, when using Section XI, that are incorporated by reference in paragraphs 10 CFR 50.55a(a)(3)(ii)).
As stated in 10 CFR 50.55a(z), the licensee is permitted to use alternatives to the requirements of paragraphs 10 CFR 50.55a(b) through (g), when authorized by the Director, Office of Nuclear Reactor Regulation.
The NRC staff also notes that Code Case N-609-1 has already been reviewed.
This Code Case has been proposed to be accepted in the next revision of RG 1.147. The NRC staff notes that in relief request 14-0N-003, the licensee stated that the ASME Code,Section XI, IW8-2500-1 Examination Category 8-J, requires Class 1 piping welds to be selected for examination in accordance with Note (2)(b), which states, in part; All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed either of the following limits under loads associated with specific events and operational conditions:
- 1. Primary plus secondary stress intensity range of 2.4Sm for ferritic steel and austenitic steel. 2. Cumulative usage factor U of 0.4 examination of the nozzle-to-shell welds when the inside of the vessel is accessible
.... The licensee clarified their original request by noting that Note (2)(b)(2) should only read, "Cumulative usage factor U of 0.4." The rest of the sentence (in italics above) was a typographical error in relief request 14-0N-003.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that the use of the proposed alternative described in request 14-0N-003, provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1
). Therefore, the NRC staff authorizes the use of relief request 14-0N-003 at ONS for the remainder of the fifth 10-year ISi interval, which commenced on July 15, 2014, and will end on July 15, 2024. All other ASM E Code, requirements for which relief was not 'specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor:
Donald Becker Date: January 7, 2016 S. Batson If you have any questions, please contact the ONS Senior Project Manager, Mr. James R. Hall, at randy.hall@nrc.gov or 301-415-4032.
Sincerely, /RAJ Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsAcrs_MailCTR Resource RidsNrrLASFigueroa Resource RidsNrrPMOconee Resource RidsNrrDeEpnb Resource RidsRgn2MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorllp2-1 Resource DBecker, NRR JWhited, NRR ADAMS Accesion No.: ML 16004A181
- via e-mail dated OFFICE DORL/LPLll-1/PM DORL/LPLll-1/LA DE/EPNB/BC . DORL/LPLI 1-1 /BC NAME JWhited SFigueroa DAiiey
- MMarkley DATE 12/30/15 01/05/16 11/20/15 01/07/16 OFFICIAL RECORD COPY