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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:Report
MONTHYEARRA-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) 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 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. 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). ML16102A1582009-05-31031 May 2009 DPC-NE-3001-A, Rev 0a, Multidimensional Reactor Transients & Safety Analysis Physics Parameters Methodology. ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version 2022-07-07
[Table view] Category:Miscellaneous
MONTHYEARRA-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 ML0306306812003-02-25025 February 2003 Fitness-for-Duty Program, Performance Data Reports ML0226600412002-09-12012 September 2002 Response to Request for Additional Information - Topical Report DPC-NE-1005P, Revision 0, Nuclear Design Methodology Using CASMO/4SIMULATE-3 MOX (Proprietary) 2022-04-21
[Table view] |
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Duke OkEnergy JAMES R. MORRIS, Duke Energy VICELLCPRESIDENT Carolinas, Catawba Nuclear Station Carolinas 4800 Concord Road / CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax June 23, 2008 U.S. Nuclear Regulatory'Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Unit 1 Docket Number 50-413 Operating Report for Cycle 17 Operation with Mixed Oxide (MOX) Fuel Lead Assemblies
Reference:
Letter from NRC to H.B. Barron, Duke, "Final Safety Evaluation for Duke Topical Report DPC-NE-1005P, "Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX"," dated August 20, 2004 The reference letter constituted the NRC staff's Safety Evaluation (SE) associated with Duke's use of MOX lead assemblies at Catawba. In Section 1.0 of the SE (item 4), the NRC stipulated that Duke will prepare an operating report for each operating cycle with MOX fuel lead assemblies and for each unit operating with partial MOX fuel cores until the equilibrium cycle is reached. Each operating report will contain comparisons of predicted to measured monthly power distribution maps and monthly boron concentration letdown values. Duke will provide each cycle operating report to the NRC within 60 days of the end of the fuel cycle.
Pursuant to the above requirement, this letter provides the associated report.
This submittal contains information that is proprietary to Duke.
The specific information that is proprietary in Attachment 1 is identified by enclosure in brackets. In accordance with 10 CFR 2.390, Duke requests that this information be withheld from public disclosure. Attachment 2 is a redacted version of the www. duke-energy.co
U.S. Nuclear Regulatory Commission Page 2 June 23, 2008 report with proprietary information removed. An affidavit is included that attests to the proprietary nature of the information in this submittal.
There are no regulatory commitments contained in this submittal.
Inquiries on this matter should be directed to L.J. Rudy at (803) 701-3084.
Very truly yours, James'-R. Morris LJR/s Attachments
U.S. Nuclear Regulatory Commission Page 3 June 23, 2008 xc (with attachments):
L.A. Reyes, 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 G9A Rockville, MD 20852-2738 A.T. Sabisch, NRC Senior Resident Inspector Catawba Nuclear Station
U.S. Nuclear Regulatory Commission Page 4 June 23, 2008 xc (with attachments),:
R.D. Hart L.J. Rudy L.A. Keller R.C. Harvey J.L. Eller P.F. Bailey Document Control File 801.01 RGC Date File ELL-EC050 NCMPA-1 NCEMC PMPA SREC
AFFIDAVIT OF James R. Morris i am Vice President of Duke Energy Caroli~nas, LLC (Duke), and as such have the responsibility of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear plant licensing and am authorized to apply for its withholding on behalf of Duke.
- 2. I am making this affidavit in conformance with the provisions of 10 CFR 2.390 of the regulations of the Nuclear Regulatory Commission (NRC) and in conjunction with Duke's application for withholding which
,accompanies this affidavit.
- 3. I have knowledge of the criteria used by Duke in designating information as proprietary or confidential.
- 4. Pursuant to 10 CFR 2.390, Duke seeks to protect from disclosure specific analytical information contained in the document "Special Operation Report for Catawba Unit 1 Cycle 17 with Mixed Oxide Fuel Lead Assemblies."
- 5. Pursuant to the provisions of 10 CFR 2.390(b) (4), the following is furnished for consideration by the NRC in determining whether the
'proprietary information sought to be'protected should be withheld from public disclosure:
(i) The information is of a type that is customarily held in confidence by Duke. This information is proprietary to Duke, and Duke seeks to protect it as such. The information consists of analysis methodology details, analysis results, and supporting data that provide a competitive advantage to Duke.- Duke submits that a rational basis therefore exists for treatment, of this information as proprietary.
(ii) The information was transmitted to the NRC in confidence and, under the provisions of 10 CFR 2.390, it is to be receivedin confidence by the NRC.
(iii) The information sought to be withheld is not available from public sources to the best of Duke's knowledge and belief.
(iv) Public disclosure of the proprietary information Duke seeks to protect is likely to cause substantial harm to Duke's competitive position within the meaning 'of 10 CFR 2.390(b) (4) (v) . The proprietary information has substantial commercial value to Duke.
For example:
(a) Duke uses this information to reduce vendor and consultant expenses associated with supporting the operation and licensing of its nuclear power plants.
(b) Duke could sell the information to nuclear utilities, vendors, and consultiants for the purpose of supporting the operation and licensing -of other nuclear power plants.
(c) The subject information could only be duplicated by competitors at similar expense to that incurred by Duke.
(d) Public disclosure of this information is likely to cause harm to Duke because it would allow competitors in the nuclear industry to benefit from the results of a significant development program without requiring a commensurate expense or allowing Duke to recoup a portion of its expenditures or benefit from the sale of the information.
For all of the reasons discussed above, Duke requests that this proprietary information be withheld from public disclosure in its entirety.
I affirm that I, James R. Morris, am the person who subscribed my name to the foregoing, and that all of the matters and facts herein are true and correct to the best of my knowledge.
janj/s R. Morris, Vice President Sworn to and subscribed before me this A-3 day of JQ -e , 2008.
Witness my hand and official seal.
NotaryPublic My commission expires: 7....
SEAL
Attachment 2 Non-Proprietary Version of Catawba Unit 1 Cycle 17 Operating Report
Special Operation Report for Catawba Unit 1 Cycle 17 with Mixed Oxide Fuel Lead Assemblies Introduction Duke utilized the core design methodology defined in reference 1 for Catawba Unit 1 Cycle 17 (C1C17) which contains four mixed oxide (MOX) fuel lead assemblies. In reference 2 the Nuclear Regulatory Commission (NRC) transmitted the safety evaluation which documented NRC approval of reference 1. That safety evaluation identified Duke commitments to submit a startup report and an operation report for each fuel cycle containing MOX fuel.
The startup report identified in reference 3 compares predicted to measured data from zero power physics tests and power distribution maps taken during initial power escalation of C1C17. The startup report also describes the core arrangement, fuel assembly batch characteristics, burnable poison loading, control rod locations, incore detector locations, and MOX fuel assembly placement.
Theoperation report to follow compares measured to predicted data from monthly power distribution maps and soluble boron concentration letdown. MOX fuel lead assemblies are located in core locations C-08, H-03, H-1 3, and N-08. All 4 MOX lead assemblies are located in instrumented core locations.
Flux Maps Flux maps taken after the initial power escalation are tabulated below. All maps were taken at 100 %FP with steady state core conditions. Figures 1 through 18 compare predicted and measured assembly average relative power factors. All acceptance criteria were met for all assemblies for each flux map taken.
Flux Map EFPD %FP FCM/1/17/004 11 100 FCM/1/17/013 31 100 FCM/1/17/014 57 100 FCM/1/17/015 85 100 FCM/1/17/016 113 100 FCM/1/17/017 141 100 FCM/1/17/018 169 100 FCM/1/17/019 197 100 FCM/1/17/020 225 100 FCM/1/17/021 246 100 FCM/1/17/022 281 100 FCM/1/17/023 309 100 FCM/1/17/024 337 100 FCM/1/17/025 365 100 FCM/1/17/026 393 100 FCM/1/17/027 421 100 FCM/1/17/028 449 100 FCM/1/17/029 477 100
Soluble Boron Letdown A comparison of measured and predicted reactivity letdown is performed at approximately 30 EFPD intervals throughout the cycle depletion. Each measured boron concentration is normalized to hot full power, equilibrium xenon and samarium, a reference hot moderator temperature, all control rods out of core, and a reference boron-10 content in the soluble boron. The table below summarizes soluble boron letdown measurements and compares each to the predicted value. The acceptance criterion of 50 PPMB is easily achieved for all measurements.
Cycle Exposure Measured Predicted Difference EFPD PPMB PPMB PPMB 4 -2 15 -19 22 -17 29 -21 36 .- 11 43 -15 50 -12 78 -7 104 -9 132 0 160 -5 188 -5 216 1 244 -6 272 -5 300 -6 328 -2 351 4 384 -1 412 3 440 2 469 2 Conclusion Inclusion of four MOX fuel lead assemblies was accomplished without significant perturbation to the normal low enriched uranium fuel management techniques. Flux map power distribution measurements compared well with prediction. The MOX fuel lead assemblies operated at power levels that are representative of uranium oxide fuel, but were never the highest power assembly in the core.
References
- 1. DPC-NE-1005-P-A, Nuclear Design Methodology Using CASMO-4 / SIMULATE-3 MOX, Duke Power Company, August 2004.
- 2. Letter, Robert E. Martin (USNRC) to H.B. Barron (Duke), Final Safety Evaluation for Duke Topical Report DPC-NE-1005-P, Nuclear Design Methodology Using CASMO-4/ SIMULATE-3 MOX, August 20, 2004.
- 3. Letter, James R. Morris (Duke) to U. S. Nuclear Regulatory Commission, Catawba Unit 1 Cycle 17 Startup Report, February 28, 2007.
Figure 1 FCM/1/171004 BJMJ 12Jan07 11 EFPD 100 %FP 2 3 4 5 6 7 8 9 . 10 11 12 13 14 15 A
B C T1 r i-i i I D
I Deviation RMS 1.3%
Core Max -4.4% at H-15 MOX Max -4.2% at N-08
Figure 2 FCM/l/17/013 MWJR 01 Feb07 31 EFPD 100 %FP 2 3 4 5 6 7 8 9 10 11 12 13 14 15 If A
B C
D E
F G
K L
M N
p Deviation RMS 1.5%
Core Max, -4.2% at H-15 MOX Max -3.9% at N-08
Figure 3 FCM/1/17/014 MWJS 27Feb07 57 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 I
A B
C D
E F
i i i i i i i i i i i i i i G
H J
K L
M N
p R
Deviation RMS - 1.4% ,
Core Max -4.2% at H-15 MOX Max -3.7% at N-08
Figure 4 FCM/1/17/015 MWJT 29Mar07 85 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 f6 A
B C
D E
F G
H J
K L
M N
P V
R Deviation RMS 1.3%
Core Max -4.7% at H-15 MOX Max -4.0% at N-08
Figure 5 FCMI1/17/016 MWJV 26Apr07 113 EFPD 100%FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 f
f A
B C
D E
F G
H K
L N
P R
K Deviation RMS 1.2%
Core Max -4.4% at H-15 MOX Max -3.8% at N-08
Figure 6 FCM/1117/017 MWJB 24May07 141 EFPD 100 %FP 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A
J Deviation RMS 1.1%
Core Max -4.7% at H-15 MOX Max -3.4% at N-08
Figure 7 FCMI1117/018 MWJW 21Jun07 169 EFPD 100 %FP 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A
B D
E F
G H
K L
M N
p R
Deviation RMS 1.2%
Core Max -4.2% at H-15 MOX Max -3.7% at N-08
Figure 8 FCM/1/17/019 MWJX 19Jul07 197 EFPD 100 %FP 1 2 ý3 5 6 7 8 9 10 11 12 13 14 15 f
A B
C 0
E F
G H
J K
L M1.
N p
R V
Deviation RMS 1.1%
Core Max -3.9% at H-15 MOX Max -3.3% at N-08
Figure 9 FCM/1/17/020 MWJZ 16Aug07 225 EFPD 100 %FP 1 2 3 5 6 7 8 9 10 11 12 13 14 15 A
r B
C D
III I I I E
F G
K L
M N
-I
- I - .1 I I-I I-i-i-i-i-i 4-&
- I. .1-I
- - .1 P
J Deviation RMS 1.1%
Core Max -4.3% at H-15 MOX Max -3.5% at N-08
Figure 10 FCM/1/17/021 MWKB 06Sep07 246 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Deviation RMS 1.1%
Core Max -3.8% at H-15 MOX Max -2.8% at N-08
Figure 11 FCM/1/17/022 MWNS 07Nov07 281 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A (
B D
E F
G H
J K
L M
N P
R Deviation RMS 0.9%
Core Max -3.7/ at B-13 MOX Max -2.7% at N-08
Figure 12 FCM/1/17/023 MWKD 08Nov07 309 EFPD 100 %FP 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A
8 C
D E
F G
K L
M N
p J
Deviation RMS 0.9%
Core Max -4.0% at H-15 MOX Max -2.7% at N-08
Figure 13 FCM/I/17/024 DBXD 06Dec07 337 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 lf A
B C
F H
J K
N p
11 )
Deviation RMS 0.8%
Core Max -3.2% at H-15 MOX Max -2.3% at N-08
Figure 14 FCM/1/17/025 MWKG 03Jan08 365 EFPD 100 %FP 1 2 3 4 5 6 7 8 9. 10 11 12 13 14 15 A
(
B C
D I--. I.-H K
Deviation RMS 0.9%
Core Max -4.3% at H-15 MOX Max -2.0% at N-08
Figure 15 FCM/1/17/026 MWKH 31Jan08 393 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 If A
B C
D E
F G
H J
K L
M N
p J
Deviation RMS 1.0%
Core Max -4.1% at B-13 MOX Max -1.8% at N-08
Figure 16 FCM/1/17/027 MWKC 03Mar08 421 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A (
J Deviation RMS 0.9%
Core Max -4.1%'at N-02 MOX Max -1.5% at H-13
Figure 17 FCM/1/17/028 MWKK 27Mar08 449 EFPD 100 %FP 2 3 4 5" 6 7 8 9 10 11 12 13 14 15 A
B C
D E
F G
H K
L M
N p
R Deviation RMS 0.9%
Core Max -4.9% at B-13 MOX Max -1.5% at N-08
Figure 18 FCM/117/029 MWKH 24Apr08 477 EFPD 100 %FP 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 A (
B C
D E
F G
H J
K L
M N
p.
Deviation RMS 0.9%
Core Max -4.5% at L-15 MOX Max -1.2% at H-03