Letter Sequence Other |
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MONTHYEARML0815607342008-07-0707 July 2008 Request for Relief 07-CN-001, Limited Weld Examinations During End-Of -Cycle 14 Refueling Outage Project stage: Other 2008-07-07
[Table View] |
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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 ML22213A2532022-08-31031 August 2022 Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML22007A3452022-01-11011 January 2022 Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 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-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 ML18016A1782018-01-24024 January 2018 Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17104A1102017-04-26026 April 2017 Relief Request CN Grr 01, Alternative to the Testing Frequencies in the American Society of Mechanical Engineers Operation and Maintenance Code, by Adoption of Code Case OMN-20, Inservice Test Frequencies (CAC Nos. MF9595-6) CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing ML15301A5442015-11-10010 November 2015 Proposed Relief Request 15-CN-001, Alternative Repair of a Main Steam System Braided Flex-Hose CNS-15-062, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2)2015-07-16016 July 2015 Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2) ML15161A3762015-06-19019 June 2015 Proposed Relief Request 14-CN-002, Alternative to American Society of Mechanical Engineers (ASME) Section XI Requirements for Class 3 Buried Piping ML15124A6992015-05-0808 May 2015 (Catawba 1 and 2) - Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section X1, for Inservice Inspection Activities ML14295A5322014-10-30030 October 2014 Proposed Relief Request 14-CN-001, American Society of Mechanical Engineers (ASME) Section IX Volumetric Examination Requirements ML14079A5462014-03-26026 March 2014 Proposed Relief Request 13-CN-003, Request for Alternative to the Requirement of IWB-2500, Table IWB-2500-1, Category B-A and Category B-D for Reactor Pressure Vessel Welds ML11187A0012011-07-14014 July 2011 Relief 10-CN-001, Alternative Requirements for Temporary Acceptance of a Through-Wall Flaw in Boric Acid Tank Nozzle Weld ML1012501702010-05-0303 May 2010 Withdrawal of Request for Relief Number 09-CN-001, Limited Weld Examinations During the End-of-Cycle 17 Refueling Outage ML0912401562009-05-27027 May 2009 Relief 06-CN-003 for Use of Polyethylene Material in Buried Service Water Piping ML0902301722009-01-16016 January 2009 Response to NRC Requests for Additional Information and Request for Relief (Alternative) Number 08-CN-002 - Reactor Vessel Hot Leg Nozzle-to-Safe End Weld Full Structural Weld Overlays ML0831506302008-11-0606 November 2008 Transmittal of Request for Relief Number 08-CN-002, Reactor Vessel Hot Leg Nozzle-to-Safe End Weld Full Structural Weld Overlays (Fswols) ML0822403862008-09-12012 September 2008 Relief 06-CN-003, Use of Polyethylene Material in Nuclear Safety-Related Piping Applications ML0815607342008-07-0707 July 2008 Request for Relief 07-CN-001, Limited Weld Examinations During End-Of -Cycle 14 Refueling Outage ML0816000032008-07-0101 July 2008 Request for Relief 07-CN-002, Limited Weld Examinations During End-of-Cycle 14 Refueling Outage ML0731804472007-08-27027 August 2007 Request for Relief Number 07-CN-004 Limited Weld Examinations During the End-of-Cycle 16 Refueling Outage ML0706504172007-02-26026 February 2007 Submittal of Request for Relief Number 07-CN-003, Request for Relief to Allow Use of Alternate Requirements for Snubber Inspection & Testing ML0636000142007-01-0909 January 2007 Relief, Request to Use a Portion of a Letter Edition of ASME Code ML0632801882006-11-16016 November 2006 Revision to Relief Request 06-GO-001 ML0623900202006-09-25025 September 2006 Request for Relief 05-CN-004, Limited Weld Examinations During End-of-Cycle 15 Refueling Outage, MC8337, MC9171, MC9172, MC9173, MC9174, MC9175, MC9176, MC9177, MC9178, and MC9179) ML0626202612006-09-11011 September 2006 Relief Request 06-GO-001 Request for Additional Information ML0622304212006-09-0707 September 2006 Relief, Request for Relief for Snubber Visual Examination and Functional Testing Related to the Third 10-year Interval Inservice Inspection Program ML0634903992006-07-27027 July 2006 Relief Request 06-GO-001 ML0616603262006-07-20020 July 2006 Request for Use of Later Edition and Addenda of the ASME Code ML0616800102006-07-19019 July 2006 Regarding Request for Relief 05-CN-001, Limited Weld Examinations During End-of-Cycle 14 Refueling Outage ML0535503702006-04-0303 April 2006 Relief, O5-CN-003 Limited Weld Examination Coverage ML0517801882005-07-25025 July 2005 RR 04-CN-001, Volumetric Weld Inspection Requirements ML0519403672005-07-13013 July 2005 Relief Request MC3057, 04-CN-002, Limited Weld Examinations During End-of-Cycle 12 Refueling Outage ML0518901432005-06-28028 June 2005 Submittal of Third Ten-Year Interval Inservice Inspection Plan for Steam Generator Tubing ML0517801642005-06-23023 June 2005 RR 04-CN-004, Class 1 ISI Pressure Test Boundaries Requirement (Tac No. MC3276, MC3277) ML0510203642005-03-31031 March 2005 Relief, Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities at Catawba Nuclear Station, Unit 2 in Accordance with 10 CFR 50.55a(g) (4) (IV) ML0504105322005-03-17017 March 2005 RR, Alternative Code of Prv Nozzle Welds for Volumetic Examination RR-04-GO-001 ML0504904622005-02-17017 February 2005 Relief, RR No. 03-001, 10 CFR Section 50.55a (a)(3)(ii) for Second ISI Intervals ML0428106012004-10-20020 October 2004 Relief Request, Alternate to the American Society of Mechanical Engineers Section XI for Reactor Vessel Examinations RR-04-GO-001 ML0427400272004-09-30030 September 2004 Relief, Amended Relief Request 03-GO-010 Requesting Use of Subsequent Edition and Addenda of the ASME Code for Class Mc and CC Components (MC9674-MC9680) ML0427302912004-09-29029 September 2004 Request for Relief, 04-GO-006, for Use of an Alternate Code Case to Use Ultrasonic Techniques Equipment ML0420403942004-07-20020 July 2004 Request for Relief 03-004, Minimum Percentage Requirements for Second Period of the Second Inservice Inspection Interval 2023-09-25
[Table view] Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 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 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 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 IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 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 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 IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 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 ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 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 ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:Safety Evaluation
MONTHYEARML23256A0882023-09-25025 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 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 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22213A2532022-08-31031 August 2022 Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public 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 ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML22007A3452022-01-11011 January 2022 Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21266A0112021-10-0505 October 2021 Staff Evaluation Related to Aging Management Program and Inspection Plan of Reactor Vessel Internals Per MRP-227, Revision 1-A ML21253A0822021-09-20020 September 2021 Proposed Alternative Request RA-21-0145 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML21155A2132021-08-26026 August 2021 Plant ML21131A0262021-06-23023 June 2021 Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage 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 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 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 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 ML20174A0452020-08-0404 August 2020 Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits ML19296D1192020-01-31031 January 2020 Issuance of Amendment Nos. 305 and 301 to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability 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 ML19212A6552019-08-27027 August 2019 Issuance of Amendment Nos. 304 and 300 to Technical Specification 3.8.1, AC Sources - Operating ML19191A0612019-07-15015 July 2019 Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2018 Refueling Outage 24 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 ML19121A5512019-06-17017 June 2019 Issuance of Amendments Related to the Removal of Containment Valve Injection Water System Supply from Specified Containment Isolation Valves ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18275A2782018-11-28028 November 2018 Issuance of Amendments Related to the Nuclear Service Water System New Condition for Single Pond Return Header Configuration ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18016A1782018-01-24024 January 2018 Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032) ML17296A2082018-01-0404 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF8971 & MF8972, EPID L-2016-LLA-0026) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17261B2902017-10-23023 October 2017 Issuance of Amendment Nos. 296 and 292, Adopt TSTF-142-A, Revision 0, Increase the Completion Time When the Core Reactivity Balance Is Not within Limit (CAC Nos. MF8962 and MF8963); EPID L-2017-LLA-0024 ML17257A2972017-10-23023 October 2017 Issuance of Amendment Nos. 295 and 291, Adoption of TSTF-340-A, Revision 3, Allow 7-Day Completion Time for a Turbine-Driven AFW Pump Inoperable (CAC Nos. MF8979 and MF8980; EPID L-2017-LLA-0043) ML17254A1442017-10-23023 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 (CAC Nos. MF8969 and MF8970; EPID L-2017-LLA-0031) ML17249A1352017-09-29029 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Travelers TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 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) ML17172A4282017-07-26026 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-315-A, Revision 0 ML17165A4412017-07-21021 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-269-A, Revision 2 (CAC Nos. MF8983 and MF8984). 08/10/2017 ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) 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) ML16137A3082017-02-0808 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard NFPA 805 ML16277A4042016-10-20020 October 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16208A2832016-08-0808 August 2016 Correction to Issuance of Amendments Regarding Use of Optimized Zirlo ML16159A3362016-07-19019 July 2016 Issuance of Amendments Regarding Request to Use an Alternate Fission Gas Gap Release Fraction (CAC Nos. MF6480 Through MF6486) ML16105A3262016-06-21021 June 2016 Issuance of Amendments Regarding Use of Optimized Zirlo ML16124A6942016-06-0202 June 2016 Issuance of Amendments Regarding Changes to Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2023-09-25
[Table view] |
Text
July 7, 2008 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 2, REQUEST FOR RELIEF 07-CN-001, LIMITED WELD EXAMINATIONS DURING END-OF-CYCLE 14 REFUELING OUTAGE (TAC NOS. MD6269 AND MD6270)
Dear Mr. Morris:
By letter dated July 11, 2007, Duke Energy Carolinas LLC, the licensee, submitted a request for relief, Relief Request No. 07-CN-001, from the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),Section XI, 1989 Edition requirement pertaining to limited weld examination coverage at the end of operating cycle 14 during the second 10-year inservice inspection (ISI) interval at Catawba Nuclear Station, Unit 2 (Catawba 2). The second 10-year interval for Catawba 2 started August 19, 1996, and ended August 19, 2006. The licensee already performed the scheduled second 10-year interval ISI on the referenced welds and components resulting in limited volumetric and visual coverages. As a result, the licensee has proposed that no alternate examinations or testing will be performed during the end of operating cycle 14 to compensate for the limited ultrasonic examination coverage.
The enclosed Safety Evaluation contains the U. S. Nuclear Regulatory Commission (NRC) staff's evaluation and conclusions. Based on the information provided in the licensee=s request for relief, the NRC staff has determined that it is impractical for the welds identified to be examined to the extent required by the ASME Code at Catawba 2. The NRC staff has also concluded that reasonable assurance of structural integrity is provided by the examinations that were performed by the licensee.
Therefore, relief is granted and requirements are imposed pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(g)(6)(i) for the second 10-year ISI interval at Catawba 2 for referenced welds. Granting relief and imposing requirements are authorized by law and will not endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
J. Morris All other requirements of ASME Code,Section XI, for which relief has not been specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Sincerely,
/RA/
Melanie C. Wong, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-414
Enclosure:
Safety Evaluation cc w/encl: See next page
ML081560734
- SE input dated NRR-028 OFFICE LPL2-1/PM LPL2-1/LA NRR/CPNB/BC OGC LPL2-1/BC NAME JStang MO=Brien TChan* MSimon MWong DATE 7/7/08 07/01/08 01/07/08 06/25/08 7/7/08
Catawba Nuclear Station, Units 1 & 2 Page 1 of 2 cc:
Site Vice President Catawba Nulcear Station Senior Resident Inspector Duke Power Company, LLC U.S. Nuclear Regulatory Commission 4800 Concord Road 4830 Concord Road York, SC 29745 York, South Carolina 29745 Associate General Counsel and Managing Manager Attorney Division of Waste Management Duke Energy Carolinas, LLC Bureau of Land and Waste Management 526 South Church Street - EC07H Dept. of Health and Environmental Control Charlotte, North Carolina 28202 2600 Bull Street Columbia, South Carolina 29201-1708 Regulatory Compliance Duke Energy Corporation Manager 4800 Concord Road Nuclear Regulatory Issues York, South Carolina 29745 and Industry Affairs Duke Energy Corporation North Carolina Municipal Power 526 South Church Street Agency Number 1 Mail Stop EC05P 1427 Meadowwood Boulevard Charlotte, North Carolina 28202 P.O. Box 29513 Raleigh, North Carolina 27626 Saluda River Electric P.O. Box 929 County Manager of York County Laurens, South Carolina 29360 York County Courthouse York, South Carolina 29745 Vice President Customer Relations and Sales Piedmont Municipal Power Agency Westinghouse Electric Company 121 Village Drive 6000 Fairview Road Greer, South Carolina 29651 12th Floor Charlotte, North Carolina 28210 Assistant Attorney General North Carolina Department of Justice Owners Group (NCEMC)
P.O. Box 629 Duke Energy Corporation Raleigh, North Carolina 27602 4800 Concord Road York, South Carolina 29745 NCEM REP Program Manager 4713 Mail Service Center Senior Counsel Raleigh, North Carolina 27699-4713 Duke Energy Carolinas, LLC 526 South Church Street - EC07H North Carolina Electric Membership Corp. Charlotte, NC 28202 P.O. Box 27306 Raleigh, North Carolina 27611
Catawba Nuclear Station, Units 1 & 2 Page 2 of 2 cc:
Division of Radiation Protection NC Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF NO. 07-CN-001 CATAWBA NUCLEAR STATION, UNIT 2 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-414
1.0 INTRODUCTION
By letter dated July 11, 2007, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072640194), Duke Energy Carolinas, LLC, the licensee, submitted a request for relief, Relief Request No. 07-CN-001, from the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),Section XI, 1989 edition requirement pertaining to limited weld examination coverage at the end of operating cycle 14 during the second 10-year inservice inspection (ISI) interval at Catawba Nuclear Station, Unit 2 (Catawba 2). The second 10-year interval for Catawba 2 started August 19, 1996, and ended August 19, 2006. The licensee already performed the scheduled second 10-year interval ISI on the referenced welds and components resulting in limited volumetric and visual coverages. As a result, the licensee has proposed that no alternate examinations or testing will be performed during the end of operating cycle 14 to compensate for the limited ultrasonic examination coverage.
2.0 REGULATORY REQUIREMENTS Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(g) specifies that inservice inspection (ISI) of nuclear power plant components shall be performed in accordance with the requirements of the ASME Code,Section XI, and applicable addenda, except where specific relief has been granted by the U. S. Nuclear Regulatory Commission (NRC) pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.55a(g)(6)(i). Section 50.55a(a)(3) states that alternatives to the requirements of paragraph (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. Section 50.55a(g)(5)(iii) states that if the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the NRC and submit, as specified in 10 CFR 50.4, information to support the determinations.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, 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 of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of 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 requirements of the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable code of record for the second ISI interval for Catawba 2 is the ASME Code,Section XI, 1989 Edition.
The information provided by the licensee in support of the request has been evaluated by the NRC staff and the bases for disposition are documented below.
3.0 TECHNICAL EVALUATION
3.1 Licensees Evaluation 3.1.1 Components for Which Relief is Requested Relief Request 07-CN-001:
Relief Request 07-CN-001 requests relief from the requirements listed below:
Examination Item Component Examination Requirement Category No.
B-M-1 B12.40 2ND-37A Essentially 100% volumetric examination of specified weld examination volume.
C-F-1 C5.11 2ND24-16 Essentially 100% volumetric examination of specified weld examination volume.
3.1.2 Impracticality/Burden Caused by Code Compliance During the ultrasonic examination of weld ID Number 2ND-37A, 100% coverage of the required examination volume could not be obtained due to valve body and bonnet geometry. Ultrasonic examination resulted in 70.825-percent coverage of the required examination volume; this percentage of coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material.
ASME Code,Section XI, Appendix III, III-4420 requires coverage of the examination volume in two beam path directions and Appendix III, III-4430 requires scanning the weld crown and base material in two directions. These requirements could not be met because the proximity of the machined radius on the valve bonnet prevented scanning on the bonnet side of the weld.
The 45-degree scan parallel to the weld covered 75.30 percent in two beam directions. The combination of 45-degree and 60-degree shear and refracted longitudinal wave scans perpendicular to the weld covered 37.10 percent from the valve bonnet side and 95.60 percent from the valve body side. All scans were performed using a one half V-path technique. There
were no recordable indications found during the inspection of this weld.
Two beam path direction coverage is normally obtained using one half V-path shear waves from both sides of the weld or, alternatively, full V-path shear waves from one side of the weld. The weld joint geometry prevented scanning from both sides of the weld in two beam path directions and a full V-path examination from one side is prevented because of the stainless steel weld metal properties which cause excessive attenuation with shear waves. Substituting full V-path refracted longitudinal waves for shear waves is not possible because of the mode conversion that occurs at the inside surface when using refracted longitudinal waves.
During the ultrasonic examination of weld ID Number 2ND24-16, 100-percent coverage of the required examination volume could not be obtained due to the taper on the flange side of the weld not providing enough scanning area from that side of the weld. Ultrasonic examination resulted in 62.50 percent coverage of the required examination volume; this percentage of coverage reported represents the aggregate coverage from all scans performed on the weld and adjacent base material. The 45-degree shear wave circumferential scans, both clockwise and counter-clockwise, covered 100 percent of the weld and base metal. The 60-degree shear wave scan from the pipe side perpendicular to the weld covered 50 percent of the weld and base material.
A supplemental scan using a 70-degree shear wave search unit covered 50 percent of the examination volume on the flange side from one direction perpendicular to the weld but is not included in the coverage calculations because 10 CFR 50.55a(b)(2)(xv)(A)(1) mandates scanning from four directions two axially and two circumferentially for welds of dissimilar metal.
There were no recordable indications found during the inspection of this weld.
For both welds, in order to achieve more coverage, the welds would have to be redesigned to allow scanning from both sides of the weld.
The examinations were performed using personnel qualified in accordance with ASME Code,Section XI, Appendix VII, 1989 Edition. The ultrasonic procedures used complied with the requirements of ASME Code,Section XI, Appendix III, 1989 Edition.
3.1.3 Proposed Alternative Examinations or Testing The scheduled 10-year code examinations were performed on the referenced welds and resulted in the noted limited-coverage of the required ultrasonic volume. No alternate examinations or testing were planned for the welds during the inspection interval which ended on August 19, 2006.
3.1.4 Justification for Granting Relief The base materials for all of these welds are austenitic-based materials which (a) have high-corrosion resistance with low contribution of corrosion products to the coolant, (b) have good mechanical properties and (c) are highly weldable. Very few service-induced problems with stainless steel in pressurized-water reactor (PWR) primary system applications have been observed in operating plants. There has been limited susceptibility to stress corrosion cracking (SCC) due to chloride contamination and cracking in stagnant borated systems. Chemistry limits on chlorides, fluorides and sulfides and dissolved oxygen are controlled by selected licensee
commitments (SLC) and other administrative procedures at Catawba 2 to ensure that any favorable conditions for SCC are precluded. Additionally, controls on welding filler material consistent with Regulatory Guide 1.31, Control of Ferrite Content in Stainless Steel Weld Metal Revision 3, also have served to limit the susceptibility of these welds to SCC. No other known degradation mechanisms are applicable to this material at this particular location within the system.
The 2ND-37A body-to-bonnet weld is located inside the Unit 2 containment. The valve is a secondary boundary isolation valve which remains closed during normal operation to isolate the low pressure residual heat removal system from the high pressure reactor coolant system (i.e.,
reactor coolant pressure isolation valves). The valve is opened during plant startup and shutdown to provide core cooling. The subject weld is between the SA 182 F316 valve body and the SA 182 F316 bonnet neck.
The piping and valve body are normally covered by metal reflective insulation. During each refueling outage, multiple walkdowns of the containment area are performed to determine the presence of external leakage via evidence of active leakage or boron deposit buildups around the valve and mirror insulation. These walkdowns include a boric acid walkdown while the primary system remains at temperature and pressure. Other walkdowns performed during the outage are system engineer walkdowns, operation walkdowns at 350 pounds per square inch (psi), 1000 psi and normal operation pressure, and the ASME Code,Section XI, IWA-5000 system leakage test.
In addition, any leakage at the body-to-bonnet weld 2ND-37A would be detected by various other leakage detection systems available to the operator. These systems include:
- Containment atmosphere particulate radioactivity (EMF 38) monitor which would detect airborne radiological activity;
- Containment ventilation unit condensate drain tank level monitor which collects and measures as unidentified leakage the moisture removed from the containment atmosphere;
- Containment floor and equipment sump level monitors where identified accumulated water on the containment floor would be monitored and evaluated as sump level changes;
- A reactor coolant system water inventory balance is performed on a regular basis (i.e., at least once every 3 days). The normal operating practice is to perform this computer based program on a daily frequency and/or whenever the operators suspect any abnormal changes to other leakage detection systems. The Technical Specifications require system leakage from unidentified sources to be maintained below 1 gallon per minute (gpm); however, plant operation procedure PT/1(2)/A/4150/001D, (Reactor Coolant System Leakage Calculation) establishes an administrative limit of 0.15 gpm above which the source of leakage will be investigated. Leakage as a result of a leak in the body-to-bonnet weld 2ND-37A would show up as unidentified leakage and subject to the 0.15 gpm administrative limit; and other leakage detection systems available to the operator include (1) Volume Control Tank (VCT) level changes, (2) VCT make-up frequencies, and (3) Cold Leg Accumulator level changes.
The 2ND24-16 pipe to flange weld is between 12 XS wall piping and a 12, 600 pound (lb),
raised face flange. It is located downstream of the residual heat removal heat exchanger 2A on ASME Class 2 piping with a design temperature of 400 degrees Fahrenheit and design pressure of 615 psia. This piping is located in the Catawba 2 mechanical penetration room of the auxiliary building and is not normally pressurized during reactor operation. The weld maintains the pressure boundary as part of the emergency core cooling system (ECCS) flow path under accident conditions. The subject weld is between the SA 312 TP304 piping and a SA182 F304 flange.
This piping and flange are normally covered by calcium silicate insulation. Leakage during normal operation would be seen as active leakage due to ambient temperature conditions and readily identified on the 543 foot floor elevation below. The room is accessible during normal operation and is within the scope of the weekly operation walkdowns. Periodic system engineer walkdowns are also performed that include leakage identification on the residual heat removal (RHR) system.
In addition to walkdowns, an operational leak rate test (PT/2/A/4202/002) for the RHR system is performed with the system pressurized on an annual basis. An ASME Code,Section XI, IWA-5000 system leakage test is also performed every ISI period. Either of these tests would identify leakage at this particular weld. These walkdowns and leakage tests provide a high level of confidence that any leakage would be promptly identified at this welded joint in the auxiliary building mechanical penetration room.
3.2 NRC Staffs Evaluation By letter dated July 11, 2007, Duke Energy Carolinas, LLC, requested pursuant to 10 CFR 50.55a(g)(5)(iii) approval of Relief Request 07-CN-001 which involved limited weld examination coverage at Catawba 2. Specifically, during the ultrasonic examination conducted for the third period of the second 10-year inservice inspection interval (Request for Relief 07 CN 001), 100-percent coverage of the required examination volume could not be obtained for welds 2ND-37A, and 2ND24-16 because of weld configuration and the geometry of associated components.
NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability - ASME Section XI, Division 1 endorses ASME Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds. Code Case N-460 defines weld examination coverage greater than 90%
to meet the essentially 100% requirement specified in ASME Code,Section XI. The applicable code of record for the second ISI interval for Catawba 2 is the ASME Code,Section XI, 1989 Edition.
The NRC staffs review of the data submitted for the subject welds regarding the inspection volumes found that 100-percent coverage of the required examination volume could not be obtained due to the geometry of the welds and associated components. The coverage limitations and inspection results for each component are listed in the following table:
Component Exam Category/Item No. Coverage Limitation Recordable ID Figure No. Indications Aggregate Coverage Obtained (Yes/No) 2ND-37A B-M-1/B12.40 Proximity of machined radius No IWB-2500-1 on valve bonnet prevented 70.825-percent coverage scanning on the bonnet side of the weld.
2ND24-16 C-F-1/C5.11 Taper on the flange side of No IWC-2500-1 the weld does not provide 62.50-percent coverage enough scanning area from that side.
The licensee also stated that in order to achieve more coverage, in each case, the welds and the associated components would have to be redesigned to allow more scanning area. The staff finds that this alternative would be impractical and would impose undue burden on the licensee.
Based on our review of the information provided, the NRC staff finds that the licensees proposed alternative provides reasonable assurance of structural integrity for the subject welds.
This conclusion is based on the fact that the subject welds have been examined to the extent practical using 45-degree and 60-degree shear waves and 60-degree refracted longitudinal waves achieving an aggregate coverage of 37.50 percent to 78.70 percent with no recordable indications found during the inspections. Therefore, the NRC staff finds that any significant degradation, if present, should have been detected.
3.0 CONCLUSION
S Based on the above reviews, the NRC staff concludes that due to the geometry of the welds and associated components, the Code-required examinations are impractical to perform to the extent required by the Code. Furthermore, the examinations performed by the licensee provide reasonable assurance of continued structural integrity of the subject components. Therefore, request for Relief 07-CN-001 is granted pursuant to 10 CFR 50.55a(g)(6)(i) for the second 10-year ISI interval. This grant of relief is authorized by law and will not endanger life or property or common defense and security, and is otherwise in the public interest, giving due consideration to the burden upon the licensee and facility that could result if the requirements were imposed on the facility.
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: C. Nove Date: July 7, 2008