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Category:Letter
MONTHYEARML24297A6222024-10-11011 October 2024 PCA Letter to NRC Catawba Hurricane Helene IR 05000413/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000413/2024011 and 05000414/2024011 ML24255A8312024-09-23023 September 2024 Project Manager Assignment ML24261B9782024-09-19019 September 2024 Notification of an NRC Fire Protection Team Inspection NRC Inspection Report 05000413-2024010, 05000414-2024010 and Request for Information IR 05000413/20243012024-09-16016 September 2024 Operator Licensing Examination Approval 05000413/2024301 and 05000414/2024301 IR 05000414/20240912024-09-0505 September 2024 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter-NRC Inspection Report 05000414-2024091 IR 05000413/20240052024-08-26026 August 2024 Updated Inspection Plan for Catawba Nuclear Station (Report 05000413/2024005 & 05000414/2024005) ML24235A1542024-08-22022 August 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000413-2024402 and 05000414-2024402) IR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 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 ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) IR 05000413/20230062024-02-28028 February 2024 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - (NRC Inspection Report 05000413/2023006 and 05000414/2023006) IR 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 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 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 05000413/20233012023-02-17017 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 2024-09-05
[Table view] Category:Report
MONTHYEARRA-24-0208, Refuel 26 (C2R26) Inservice Inspection (ISI) Report2024-08-12012 August 2024 Refuel 26 (C2R26) Inservice Inspection (ISI) Report ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion RA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-07-0707 July 2022 Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle RA-21-0144, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-01-20020 January 2022 Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-19-0245, of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2021-10-25025 October 2021 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-21-0145, Revision to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method2021-04-24024 April 2021 Revision to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method RA-21-0133, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method2021-04-23023 April 2021 Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML20150A3322020-04-23023 April 2020 Revision of Slc'S 16-11-2, 16-11-7 and Loes RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 CNS-17-043, Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station.2017-07-0707 July 2017 Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station. CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-022, Summary of 10CFR 50.54(q) Evaluation2017-04-25025 April 2017 Summary of 10CFR 50.54(q) Evaluation ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-12-11011 December 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants ML15238A7392015-08-24024 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations2015-05-11011 May 2015 Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations ML15096A5132015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations Relating to Recommendation 2.1 of the NTTF Review ML15093A4212015-03-31031 March 2015 Submittal of CNEI-0400-281, Revision 0, Core Operating Limits Reports for Cycle 21 Reload Core, Calculation CNC-1553.05-00-0621 CNS-15-031, Commitment Change Evaluation Report for 20142015-03-24024 March 2015 Commitment Change Evaluation Report for 2014 CNS-14-129, Transmittal of Industry High Density Polyethylene (Hdpe) Test Results2014-12-0808 December 2014 Transmittal of Industry High Density Polyethylene (Hdpe) Test Results CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations2014-06-30030 June 2014 WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations ML14108A2012014-05-16016 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident CNS-14-045, Commitment Change Evaluation Report for 20132014-03-31031 March 2014 Commitment Change Evaluation Report for 2013 CNS-14-038, DUKCORP042-PR-001, Seismic Hazard & Screening Report in Response to the 50.54(f) Information Request Re Fukishima Near-Term Task Force Recommendation 2.1 Seismic2014-03-13013 March 2014 DUKCORP042-PR-001, Seismic Hazard & Screening Report in Response to the 50.54(f) Information Request Re Fukishima Near-Term Task Force Recommendation 2.1 Seismic ML14041A2952013-12-0202 December 2013 Document No. 1457690303-R-M-00005-0, Revision 0, NTTF 2.3 Seismic Peer Review Supplementary Report, Catawba Nuclear Station Unit 2. CNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology2013-11-14014 November 2013 License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology ML13276A5052013-09-25025 September 2013 Transition Report, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 2 ML13276A5042013-09-25025 September 2013 Transition Report, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 2 ML14353A0282013-04-30030 April 2013 WCAP-16083-NP, Revision 1, Benchmark Testing of the Ferret Code for Least Squares Evaluation of Light Water Reactor Dosimetry ML13162A0702013-03-14014 March 2013 1457690303-R-M-00004-0, NTTF 2.3 Seismic Peer Review Supplementary Report ML13162A0722012-11-18018 November 2012 1457690303-R-M-00003-0, NTTF 2.3 Seismic Peer Review Report ML12167A0162012-06-21021 June 2012 Review of the 2011 Steam Generator Tube Inservice Inspection During Refueling Outage End of Cycle 19 ML12153A3292012-03-31031 March 2012 Attachment 6 - Duke Energy Methodology Report DPC-NE-1007, Revision 0, Conditional Exemption of the EOC Mtc Measurement Methodology (Non-proprietary) ML11327A1492011-11-22022 November 2011 Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML11244A0552011-09-12012 September 2011 Review of the 2010 Steam Generator Tube Inspections During Refueling Outage 17 End of Cycle 17 ML11188A1082011-06-30030 June 2011 WCAP-17330-NP, Rev 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). (Non-Proprietary) ML1109603572011-03-30030 March 2011 Submittal of Commitment Change Evaluation Report for 2010 NEI 99-04, Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 20102011-03-30030 March 2011 Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 2010 ML16102A1592010-09-30030 September 2010 DPC-NE-3002-A Rev 4b, UFSAR Chapter 15 System Transient Analysis Methodology. ML1028504722010-09-29029 September 2010 CNEI-0400-203, Revision 0, Appendix a Power Distribution Monitoring Factors ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1028504742010-08-0505 August 2010 CNEI-0400-203, Revision 0, Catawba, Unit 2 Cycle 18 Core Operating Limits Report ML1016700892010-06-10010 June 2010 Stations, Units 1 and 2 - Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1011802492010-04-22022 April 2010 2009 10CFR50.59 Summary Report ML1017303842009-08-25025 August 2009 Westinghouse LTR-SGMP-09-109 NP-Attachment, Response to NRC Request for Additional Information on H*: RAI #4; Model F and Model D5 Generators. ML1017303912009-08-12012 August 2009 Westinghouse LTR-SGMP-09-100 NP-Attachment, Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators. ML16102A1582009-05-31031 May 2009 DPC-NE-3001-A, Rev 0a, Multidimensional Reactor Transients & Safety Analysis Physics Parameters Methodology. 2024-08-12
[Table view] Category:Miscellaneous
MONTHYEARRA-24-0208, Refuel 26 (C2R26) Inservice Inspection (ISI) Report2024-08-12012 August 2024 Refuel 26 (C2R26) Inservice Inspection (ISI) Report ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion RA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 CNS-17-043, Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station.2017-07-0707 July 2017 Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station. CNS-17-022, Summary of 10CFR 50.54(q) Evaluation2017-04-25025 April 2017 Summary of 10CFR 50.54(q) Evaluation ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-12-11011 December 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants ML15238A7392015-08-24024 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations2015-05-11011 May 2015 Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations ML15096A5132015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations Relating to Recommendation 2.1 of the NTTF Review ML15093A4212015-03-31031 March 2015 Submittal of CNEI-0400-281, Revision 0, Core Operating Limits Reports for Cycle 21 Reload Core, Calculation CNC-1553.05-00-0621 CNS-15-031, Commitment Change Evaluation Report for 20142015-03-24024 March 2015 Commitment Change Evaluation Report for 2014 CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations2014-06-30030 June 2014 WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations ML14108A2012014-05-16016 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident CNS-14-045, Commitment Change Evaluation Report for 20132014-03-31031 March 2014 Commitment Change Evaluation Report for 2013 ML12167A0162012-06-21021 June 2012 Review of the 2011 Steam Generator Tube Inservice Inspection During Refueling Outage End of Cycle 19 NEI 99-04, Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 20102011-03-30030 March 2011 Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 2010 ML1109603572011-03-30030 March 2011 Submittal of Commitment Change Evaluation Report for 2010 ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1016700892010-06-10010 June 2010 Stations, Units 1 and 2 - Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1011802492010-04-22022 April 2010 2009 10CFR50.59 Summary Report ML1017303842009-08-25025 August 2009 Westinghouse LTR-SGMP-09-109 NP-Attachment, Response to NRC Request for Additional Information on H*: RAI #4; Model F and Model D5 Generators. ML1017303912009-08-12012 August 2009 Westinghouse LTR-SGMP-09-100 NP-Attachment, Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators. ML1017303892009-05-31031 May 2009 WCAP-17072-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model D5). ML0904005742009-02-0404 February 2009 Special Report, Revision 1 ML0821201412008-06-23023 June 2008 Operating Report for Cycle 17 Operation with Mixed Oxide (MOX) Fuel Lead Assemblies ML0812700912008-04-30030 April 2008 Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0809303122008-03-26026 March 2008 Steam Generator Outage Summary 180-Day Report for End of Cycle 15 Refueling Outage ML0806505592008-02-29029 February 2008 Response to Request for Additional Information on GL-04-002 ML0731000852007-11-0101 November 2007 Transmittal of DPC-NE-2012-A, Dynamic Rod Worth Measurement Using Casmo/Simulate ML0708005462007-03-13013 March 2007 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0706504222007-02-27027 February 2007 Fitness-For-Duty Program Performance Data Reports for Period July 1, 2006 Through December 31, 2006 ML0704702722007-02-0808 February 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds ML0636100922006-12-19019 December 2006 Request for Relief Number 06-GO-001 Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0636102172006-12-14014 December 2006 Request for Relief Number 06-GO-001, Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0625501122006-08-31031 August 2006 Steam Generator Outage Summary 180-day Report for End of Cycle 14 Refueling Outage ML0624904272006-08-28028 August 2006 Fitness-For Duty Program Performance Data Reports for Period Covering January 1, 2006 Through June 30, 2006 ML0620602962006-07-18018 July 2006 Steam Generator Outage Summary Inservice Inspection Report for End of Cycle 14 Refueling Outage ML0606601682006-02-21021 February 2006 Fitness-For-Duty Program Performance Data Reports ML0524402932005-08-24024 August 2005 Fitness-For-Duty Program Performance Data Reports ML0517902102005-06-21021 June 2005 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0509702852005-03-31031 March 2005 2004 10 CFR 50.59 Report ML0506100302005-02-18018 February 2005 Duke Energy Corporation, Fitness-For-Duty Program Performance Data Reports for Period Covering 07/01/2004 Through 12/31/2004 ML0424505372004-08-20020 August 2004 Letter Transmitting Fitness-For-Duty Program Performance Data Reports for Duke Energy Corp Oconee, McGuire and Catawba Nuclear Stations and the General Office ML0410501212004-04-0505 April 2004 CFR50.59 Report Containing a Brief Description of Changes, Tests, and Experiments, Including a Summary of the Safety Evaluation of Each Unit ML0324715282003-08-22022 August 2003 Fitness-for-Duty Program Performance Data Reports ML0312100492003-04-24024 April 2003 Duke Energy Topical Report Response to Request for Additional Information Letter Dated April 4, 2003 2024-08-12
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Text
JAMES R. MORRIS
," Duke Vice President Or£nergyo Catawba Nuclear Station 4800 Concord Rd. / CN01VP York, SC 29745-9635 803 831 4251 803 831 3221 fax December 14, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Unit 1 Docket Number 50-413 Request for Relief Number 06-GO-001 Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information On July 27, 2006, as modified by letters dated September 11, 2006, September 27, 2006, and November 16, 2006, Duke submitted the subject request for relief regarding a proposed alternative approach to support application of full structural weld overlays on various pressurizer nozzle-to-safe end welds.
The September 27, 2006 letter contained the following two commitments:
- 1. The following information will be submitted to the NRC within fourteen days of completion of the final UT on each unit included in this relief request. Also included in the results will be a discussion of any repairs to the overlay material and/or base metal and the reason for the repair.
- A listing of flaw indications detected
- The disposition of all indications using the standards of ASME Section XI, IWB-3514-2 and/or IWB-3514-3 criteria and, if possible, The type and nature of the indications www. duke-energy. corn
U.S. Nuclear Regulatory Commission Page 2 December 14, 2006
- 2. Prior to entry into Mode 4 from the Catawba Unit 1 outage in the Fall of 2006, a summary of the results of the stress analyses demonstrating that the preemptive full structural weld overlay will not hinder the components from performing their design function will be submitted to the NRC.
The information required by Item 1 above is included in the attachment. The inspections were performed using Performance Demonstration Initiative (PDI) qualified ultrasonic inspection procedure and inspectors. No flaw indications were detected in the overlays, and thus no disposition of indications was required. The information required by Item 2 above will be submitted under separate correspondence prior to entry into Mode 4.
If you have any questions concerning this information, please contact L.J. Rudy at (803) 831-3084.
Very truly yours, James R. Morris LJR/s Attachment
U.S. Nuclear Regulatory Commission Page 3 December 14, 2006 xc (with attachment):
W.D. Travers, Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303-8931 J.F. Stang, Jr., NRC Senior Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 H4A Rockville, MD 20852-2738 A.T. Sabisch, NRC Senior Resident Inspector Catawba Nuclear Station
Attachment Summary of Ultrasonic Examinations of Preemptive Weld Overlays for Pressurizer Nozzle Locations Containing Alloy 600 Materials
StructuralIntegrityAssociates, Inc.
3315 Almaden Expressway Suite 24 San Jose, CA 95118-1557 Phone: 408-978-8200 Fax: 408-978-8964 wwwstrdintom mtaylor@structint.com December 13, 2006 SIR-06-492, Rev. 0 MJT-06-024 Mr. Mitch Hatley Duke Energy Corporation McGuire Nuclear Station, Mail Code MG05SE 13225 Hagers Ferry Road Huntersville, NC 28078
Subject:
Summary of Weld Overlay Ultrasonic Inspections for Pressurizer Surge, Spray and Safety/Relief Nozzle-to-Safe End Welds at Catawba Nuclear Station, Unit 1
Reference:
Duke Energy Corporation, McGuire Nuclear Station Unit 2 and Catawba Nuclear Station Unit 1, Request for Alternative 06-GO-001, Revision 1, Sept. 27, 2006
Dear Mr. Hatley:
The following attachment is transmitted in support of Duke Energy's response to commitments in the above-referenced request for alternative:
Attachment:
A report summarizing the ultrasonic inspections performed on the Catawba Unit 1 weld overlays. The inspections were performed using SI's PDI qualified ultrasonic inspection procedure and inspectors. No flaw indications were detected in the overlays, and thus no disposition of indications was required.
If you have any questions or comments regarding this summary, please contact one of the undersigned.
Austin, TX Centennial, CO Charlotte, NC Stonington, CT Silver Spring, MD Sunrise, FL Uniontown, OH Whittier, CA Toronto, Canada 512-533-9191 303-792-0077 704-597-5554 860-536-3982 301-445-8200 954-572-2902 330-899-9753 562-944-8210 905-829-9817
Mr. Mitch Hatley, Duke Energy Corporation December 13, 2006 SIR-06-492, Rev. 0/MJT-06-024 Page 2 of 2 Prepared by: Verified by:
sa-49i2U&
12/13/06 12/13/06 John J. Hayden Date Michael S. Lashley Date Senior Consultant, NDE Associate Level 3 Approved by:
12/13/06 Moses Taylor, P.E. Date Associate ii Attachment cc: D. Llewellyn M. Ruis DUKE-42Q-406 V StructuralIntegrityAssociates, Inc.
Attachment Summary of Ultrasonic Examinations of Preemptive Weld Overlays for Pressurizer Nozzle Locations Containing Alloy 600 Materials Attachment to SIR-06-492, Rev. 0 /MJT-06-024 I of 4 StructuralIntegrity Associates, Inc.
Catawba Unit 1 Summary Ultrasonic Examination Report Ultrasonic Examination Procedure SI-UT-126, Revision 0, Procedurefor the PhasedArray UltrasonicExaminationof Weld OverlaidSimilar and DissimilarMetal Welds, was used during the examinations. This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center.
Relief Nozzle Weld Overlay Examination Component Identification: PORV 1-PZR-W3SE Examination Date: 12/02/06 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Elbow Weld & Adjacent Base Material Axial Examination Angles: 00 through 830 - Circumferential Examination Angles: 0' through 630 Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Safety Nozzle NC1 Weld Overlay Examination Component Identification: 1NC1 1-PZR-W4CSE Examination Date: 12/02/06 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Elbow Weld & Adjacent Base Material Axial Examination Angles: 00 through 83' - Circumferential Examination Angles: 00 through 630 Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Attachment to SIR-06-492, Rev. 0 /MJT-06-024 2 of 4 Structural Integrity Associates, Inc.
A Safety Nozzle NC2 Weld Overlay Examination Component Identification: 1NC2 1-PZR-W4BSE Examination Date: 12/01/06 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Elbow Weld & Adjacent Base Material Axial Examination Angles: 0' through 83' - Circumferential Examination Angles: 00 through 630 Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Safety Nozzle NC3 Weld Overlay Examination Component Identification: 1NC3 1-PZR-W4ASE Examination Date: 12/02/06 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Elbow Weld & Adjacent Base Material Axial Examination Angles: 00 through 83' - Circumferential Examination Angles: 0' through 630 Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Spray Nozzle Weld Overlay Examination Component Identification: 1-PZR-W2SE Examination Date: 12/01/06 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Elbow Weld & Adjacent Base Material Axial Examination Angles: 00 through 830 - Circumferential Examination Angles: 00 through 630 Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Attachment to SIR-06-492 Rev. 0 /MJT-06-024 3 of 4 Structural Integrity Associates, Inc.
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Surge Nozzle Weld Overlay Examination Component Identification: 1-PZR-W1SE Examination Date: 11/26/06 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Axial Examination Angles: 0' through 830 - Circumferential Examination Angles: 0' through 700 Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Attachment to SIR-06-492, Rev. 0 /MJT-06-024 4 of 4 Structural Integrity Associates, Inc.