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Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2 CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122 CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017 Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days 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 CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016 Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068 CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
[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:Technical
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-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 CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report 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-14-038, 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 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 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 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 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) 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 ML1028504742010-08-0505 August 2010 CNEI-0400-203, Revision 0, Catawba, Unit 2 Cycle 18 Core Operating Limits Report 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 CNS-16-017, DPC-NE-2005-A, Rev 4a, Thermal-Hydraulic Statistical Core Design Methodology.2008-12-31031 December 2008 DPC-NE-2005-A, Rev 4a, Thermal-Hydraulic Statistical Core Design Methodology. ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0814207582008-01-31031 January 2008 Offsite Dose Calculation Manual (Odcm), 2008, Revision 50 ML0721505862007-07-30030 July 2007 Transmittal of DPC-NF-2010-A, Nuclear Physics Methodology for Reload Design, Revision 2 ML0718002502007-04-30030 April 2007 ANP-10280NP, Revision 0, Poolside Postirradiation Examination of MOX Lead Assemblies. ML0627103142006-09-29029 September 2006 Review of Cycle 15 Steam Generator Tube Inservice Inspection Summary Reports ML0606704362006-02-28028 February 2006 LTR-CDME-06-17-NP, Steam Generator Tube Alternate Repair Criteria for the Portion of the Tube within the Tubesheet at Catawba 2 in Support of Cycle 15 Operation. ML0536301452005-12-31031 December 2005 LTR-CDME-05-180-NP, Rev 2, Steam Generator Tube Alternate Repair Criteria for the Portion of the Tube within the Tubesheet at Catawba 2. ML0409805552003-10-31031 October 2003 Population of Melcor Radionuclide (Rn) Classes: Origen Isotopic Depletion Calculation for High Burnup LOW-ENRICHED Uranium and WEAPONS-GRADE Mixed Oxide PWR Fuel Assemblies (Draft) ML0302903742003-01-21021 January 2003 Inservice Testing Program for Pumps & Valves - Manual Update, Sections 5.0 - 7.1 ML0302903572003-01-21021 January 2003 Inservice Testing Program for Pumps & Valves - Manual Update, Section 4.1, Ni - Ym ML0302900822003-01-21021 January 2003 Inservice Testing Program for Pumps & Valves - Manual Update, Detailed Description of Changes - Section 4.1 ML0215104912002-01-31031 January 2002 Offsite Dose Calculation Manual (ODCM) 2002, Revision 44 2022-07-07
[Table view] |
Text
Tom Simril
£'->DUKE Vice President
~ ENERGYai Catawba Nuclear Station Duke Energy CN01VP 14800 Concord Road York, SC 29745 o: 803. 701.3340 f: 803.701.3221 tom.simril@duke-energy.com CNS-17-036 June 29, 2017 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station (CNS), Unit 1 Docket Number 50-413 Mid-Cycle Power Uprate Ascension Startup Report On April 29, 2016, the NRC issued License Amendment No. 281 for Catawba Nuclear Station, Unit 1, which allowed an increase in the maximum reactor power level from 3411 megawatts thermal (MWth) to 3469 MWth.
Enclosed for your information is the Measurement Uncertainty Recapture (MUR) Mid-Cycle Power Uprate Ascension Startup Report. This report is submitted in accordance with the Catawba Nuclear Station UFSAR Section 14.3.4 which requires the submittal of a startup report following an amendment to the license involving a planned increase in power level.
There are no NRC commitments contained in this letter.
Please direct questions on this.matter to Cecil Fletcher, Regulatory Affairs Manager, at (803) 701-3622.
Sincerely, Tom Simril Vice President; Catawba Nuclear Station
Enclosure:
Catawba Nuclear Station, Unit 1 Mid-Cycle Power Uprate Ascension Startup Report www.duke-energy.com
U.S. Nuclear Regulatory Commission CNS-17-036 Page 12 June 29, 2017 xc (with enclosure and attachments):
C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. D. Austin, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A
- Rockville, MD 20852 S.E. Jenkins, Manager Uenkinse@dhec.sc.gov)
Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201
U.S. Nuclear Regulatory Commission CNS-17-036 Enclosure, Page I 1 June 29, 2017 Enclosure Catawba Nuclear Station, Unit 1 Mid-Cycle Power Uprate Ascension Startup Report
U.S. Nuclear Regulatory Commission CNS-17-036 Enclosure, Page I 2 June 29, 2017 Mid-Cycle Power Uprate Ascension Startup Report This mid-cycle Startup Report is submitted to the NRC in accordance with the requirements of the Catawba Nuclear Station Updated Final Safety Analysis Report (UFSAR), Section 14.3.4, Startup Report, which requires the submittal of a Startup Report after an amendment to the license involving a planned increase in power level.
On April 29, 2016, the NRC issued License Amendment No. 281 for Catawba Nuclear Station, Unit 1, which allowed an increase in the maximum reactor power level from 3411 megawatts thermal (MWth) to* 3469 MWth. A mid-cycle power ascension test was subsequently performed for Unit 1.
The power ascension methodology used at Catawba was to increase power gradually in one phase. Power ascension for Unit 1 was initiated during mid-cycle operations. Plant modifications were performed in previous outages and after License Amendment approval.
These actions allowed Unit 1 mid- cycle power ascensions activities to begin. Catawba Unit 1 power ascension occurred on May 21, 2016.
Purpose This Power Uprate Startup Report is submitted to the NRC to satisfy the reporting requirements of the Catawba's UFSAR section 14.3.4, which requires this report to include the following items.
- Address the Zero Power Test Phase and Power Ascension Test Phase
- Include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
- Describe corrective actions required to obtain satisfactory operation.
- Include any additional specific details required in license conditions based on other commitments.
Power Uprate Ascension Program Scope Catawba Unit 1 performed a mid-cycle Margin Recovery Uprate (MUR) in May 2016 to increase the licensed Rated Thermal Power from 3411 MWth to 3469 MWth. Leading Edge Flow Meters (LEFMs) were installed on all four feedwater lines. These meters calculate the feedwater mass flow rate and temperature. These values are used in the Unit 1 plant process computer (OAC) secondary side calorimetric calculation of thermal power.
Prior to the uprate, factory and site testing was performed on the LEFMs to verify that they were performing acceptably. Some rescaling of instrumentation was performed in advance of the uprate. At the time of uprate, final instrument rescaling was completed and a slow, deliberate, and closely monitored power escalation was performed to the new uprated power level.
USFAR chapter 14.3 testing was considered when determining the required testing to be performed for the power uprate. Since this was an at-power uprate, no Zero Power Test Phase (UFSAR section 14.3.2) activities were performed. Similarly, the Flux Symmetry Check - Low Power, Core Power Distribution - Intermediate Power, and HZP to HFP Reactivity Difference (UFSAR section 14.3.3) tests were not applicable. Core Power Distribution - High Power was performed before and after the uprate.
U.S. Nuclear Regulatory Commission CNS-17-036
. Enclosure, Page I 3 June 29, 2017 Mid-Cycle Power Uprate Ascension Testing An extensive testing and monitoring plan was developed and executed to verify performance of the new LEFMs, monitor plant performance, identify any anomalies, and ensure adequate margin is maintained. All LEFM testing was done at power.
Prior to the uprate, the following test activities were successfully completed:
- TN/1/B/EC109743/01E (EC109743 Site Acceptance Test) was performed to verify the LEFMs were installed properly and performing acceptably. This included checks of field wiring, signal quality, and LEFM performance.
- TT/1/B/EC109743/01 E (EC109743 - Functional Testing of Leading Edge Flow Meter (LEFM) OAC Gateway Acquisition, Operator Interfaces, and TPBE Input Logic) was performed to verify that the LEFM data was transferring properly to the OAC. The logic on the OAC for processing the LEFM data, calculating venturi corrections, detecting problems, and operator displays was tested and verified to be functioning properly.
- A comparison was made of 30 days of LEFM data vs. OAC venturi data, which verified the LEFMs, were reading consistently with the existing instrumentation.
- Core Power Distribution - High Power was performed on May 19, 2016 before power increase and it verified adequate margin to fuel limits existed.
The uprate test procedure was begun on May 18, 2016. The actual power escalation was performed over several hours on May 21, 2016. The evolution was controlled via test procedure TT/1/A/EC104403/01 E (EC104403 - MUR Power Uprate). During the uprate, the following testing was performed:
- Stability of the unit and all major control systems was verified.
- The Main Turbine and Generator Supervisory System and Feedwater Pump Turbine Supervisory Systems and the Hotwell, Condensate Booster and Heater Drain pumps were all verified to indicate no vibration irregularities before and after the uprate.
- The LEFMs were placed into service and the OAC thermal power calculation verified to be functioning correctly.
-* When the Unit reached stability at the uprated power level, monitoring was continued and a post-uprate plant data set was recorded including thermography of switchyard and isolated phase busses.
- Engineering evaluated the data and determined that there were no issues identified and all acceptance criteria were met.
Data for approximately 500 plant parameters were recorded before and after the uprate. A sample of data were compared to acceptance criteria or existing alarm limits. Engineering evaluated the data to verify that adequate margin was maintained and that there were no unexpected performance issues. Attachment 1 is a summary of the results for key parameters for which criteria were established.
U.S. Nuclear Regulatory Commission CNS-17-036 Enclosure, Page I 4 June 29, 2017 Following the uprate, Core Power Distribution was performed on June 7, 2016. Attachment 2 is a comparison of the before and after uprate flux map results. No issues were identified.
The overall acceptance criteria for the power escalation testing are listed below. All were met.
- All required specifications, measurements, and tolerances within the test procedure are required to be met.
- Control Systems remain stable including:
a) Turbine Governor Control System b) Feedwater Pump Governor Control System c) DCS (Digital Control System) Feedwater Pump Speed Control d) DCS Steam Generator Level Control e) DCS Reactor Temperature Control f) DCS Pressurizer and Level Control
- Unit 1 is operating at uprated power level with LEFMs in service and NO unexpected alarms or annunciators.
- Core Power Distribution testing results are satisfactory and show no unexpected changes between the pre- and post-uprate tests.
- Engineering Management has provided concurrence to the Test Coordinator that plant system and equipment performance monitoring and trending indicates no adverse conditions and no margin concerns that could jeopardize continued operation at the uprated power level.
Conclusion Overall plant performance during power ascension and at the uprated 3469 MWth power level was verified to be acceptable and as expected and predicted with no significant performance or margin concerns. No corrective actions were required. All test procedures were completed successfully.
U.S. Nuclear Regulatory Commission CNS-17-036 Enclosure, Page I 5 June 29, 2017 Attachment 1 Summary Uprate Data NC =Reactor Coolant CF =Feedwater Pre- Post-Parameter (EU) Expected Change I Criteria uprate uprate REACTOR THERMAL after uprate 3459 MWt to 3469 MWt 3402.67 3462.45 POWER, BEST (MWt)
REACTOR THERMAL after uprate 99.7% to 100% 98.09 99.81 POWER, BEST(%)
THERMAL POWER BEST, 5 MIN RUNNING after uprate 99.7% to 100% 98.09 99.80 AVG(%)
3469 MWt recorded value is 1.0265 times TOTAL FEEDWATER recorded value at 3411 MWt; Tolerance:+/- 0.2 15.21 15.50 FLOW (MLBIHR)
MLBIHR 3469 MWt recorded value is 1.0265 times SIG ACF FLOW recorded value at 3411 MWt; Tolerance:+/- 0.1 3.93 4.01 AVERAGE (MLBIHR)
MLBIHR 3469 MWt recorded value is 1.0265 times SIG B CF FLOW recorded value at 3411 MWt; Tolerance:+/- 0.1 3.58 3.65 AVERAGE (MLBIHR)
MLBIHR 3469 MWt recorded value is 1.0265 times SIG C CF FLOW recorded value at 3411 MWt; Tolerance: +/- 0.1 3.86 3.93 AVERAGE (MLBIHR)
MLBIHR 3469 MWt recorded value is 1.0265 times SIG D CF FLOW recorded value at 3411 MWt; Tolerance:+/- 0.1 3.67 3.73 AVERAGE (MLBIHR)
MLBIHR TOTAL MAIN STEAM 3469 MWt recorded value is 1.0265 times FLOW, MEASURED recorded value at 3411 MWt; Tolerance: +/- 0.1 15.58 15.91 (MLBIHR) MLBIHR 1A SIG MAIN STEAM 3469 MWt recorded value is 1.0265 times 102.05 104.07 FLOW CH 1 (%) recorded value at 3411 MWt; Tolerance: +/- 2 %
1B SIG MAIN STEAM 3469 MWt recorded value is 1.0265 times 97.79 100.07 FLOW CH 1 (%) recorded value at 3411 MWt; Tolerance:+/- 2 %
1C SIG MAIN STEAM 3469 MWt recorded value is 1.0265 times 101.70 103.98 FLOW CH 1 (%) recorded value at 3411 MWt; Tolerance:+/- 2 %
1D SIG MAIN STEAM 3469 MWt recorded value is 1.0265 times 99.61 101.54 FLOW CH 1 (%) recorded value at 3411 MWt; Tolerance:+/- 2 %
SIG A FEEDWATER 3469 MWt recorded value is 2 Deg. F higher than 438.74 440.26 INLET TEMP (°F) value at 3411 MWt; Tolerance:+/- 1 Deg. F SIG B FEEDWATER 3469 MWt recorded value is 2 Deg. F higher than 438.56 440.16 INLET TEMP (°F) value at 3411 MWt; Tolerance:+/- 1 Deg. F SIG C FEEDWATER 3469 MWt recorded value is 2 Deg. F higher than 438.98 440.50 INLET TEMP (°F) value at 3411 MWt; Tolerance:+/- 1 Deg. F SIG D FEEDWATER 3469 MWt recorded value is 2 Deg. F higher than 438.31 439.81 INLET TEMP (°F) value at 3411 MWt; Tolerance: +/- 1 Deg. F
U.S. Nuclear Regulatory Commission CNS-17-036 Enclosure, Page I 6 June 29, 2017 Pre- Post-Parameter (EU) Expected Change I Criteria uprate uprate U1 S/G FINAL 3469 MWt recorded value is 2 Deg. F higher than FEEDWATER AVERAGE 439.25 440.77 value at 3411 MWt; Tolerance:+/- 1 Deg. F TEMP (°F) 3469 MWt recorded value is 0.995 times AVERAGE MAIN STEAM recorded value at 3411 MWt; Tolerance:+/- 20 981.41 979.94 PRESSURE (PSIA)
PSIA 3469 MWt recorded value is 0.995 times MAIN STEAM recorded value at 3411 MWt; Tolerance:+/- 20 981.31 980.03 PRESSURE A (PSIA}
PSIA 3469 MWt recorded value is 0.995 times MAIN STEAM recorded value at 3411 MWt; Tolerance:+/- 20 980.29 978.72 PRESSURE 8 (PSIA) PSIA .
3469 MWt recorded value is 0.995 times MAIN STEAM recorded value at 3411 MWt; Tolerance:+/- 20 982.03 980.30 PRESSURE C (PSIA)
PSIA 3469 MWt recorded value is 0.995 times MAIN STEAM recorded value at 3411 MWt; Tolerance:+/- 20 981.87 980.35 PRESSURE D (PSIA)
PSIA P/R AVG LEVEL 1 MIN 3469 MWt recorded value is 1 .0173 times AV&, QUADRANT 4 (N- 97.89 99.97 recorded value at 3411 MWt Tolerance:+/- 1 %
41)(%)
P/R AVG LEVEL 1 MIN 3469 MWt recorded value is 1.0173 times AVG QUADRANT 2 (N- 97.81 99.67 recorded value at 3411 MWt Tolerance:+/- 1 %
- 42) (%)
P/R AVG LEVEL 1 MIN 3469 MWt recorded value is 1.0173 times AVG QUADRANT 1 (N- 97.82 99.78 recorded value at 3411 MWt Tolerance:+/- 1 %
- 43) (%)
P/R AVG LEVEL 1 MIN 3469 MWt recorded value is 1.0173 times AVG QUADRANT 3 (N- 97.77 99.50 recorded value at 3411 MWt Tolerance:+/- 1 %
44_1 (%)
NC LOOP AVG COLD T cold at 3469 MWt is same as at 3411 MWt; 552.80 552.83 LEG TEMP (°F) Tolerance:+ 0.2 °F NC LOOP A NARROW Tcold at 3469 MWt is same as at 3411 MWt; RANGE COLD LEG 553.23 553.26 Tolerance:+/- 0.2 °F TEMP (°F_l NC LOOP B NARROW Tcold at 3469 MWt is same as at 3411 MWt; RANGE COLD LEG 552.27 552.28 Tolerance:+/- 0.2 °F TEMP ( r"}
0 NC LOOP C NARROW Tcold at 3469 MWt is same as at 3411 MWt; RANGE COLD LEG 552.74 552.77 Tolerance: +/- 0.2 °F TEMP (°F)
NC LOOP D NARROW Tcold at 3469 MWt is same as at 3411 MWt; RANGE COLD LEG 553.03 553.03 Tolerance:+/- 0.2 °F TEMP (°F)
NC LOOP A AVERAGE That at 3469 MWt is 1 .0 °F more than at 3411 N/R HOT LEG 614.13 615.21 MWt; Tolerance: +/- 0.2 °F TEMPERATURE (°F)
NC LOOP B AVERAGE That at 3469 MWt is 1.0 °F more than at 3411 N/R HOT LEG 610.18 611.13 MWt; Tolerance:+/- 0.2 °F TEMPERATURE (°F)
U.S. Nuclear Regulatory Commission CNS-17-036 Enclosure, Page I 7 June 29, 2017 Pre- Post-Parameter (EU) Expected Change I Criteria uprate uprate NC LOOP C AVERAGE Thot at 3469 MWt is 1.0 °F more than at 3411 N/R HOT LEG 615.24 616.31 MWt; Tolerance:+/- 0.2 °F TEMPERATURE (°F)
NC LOOP D AVERAGE Thot at 3469 MWt is 1.0 °F more than at 3411 N/R HOT LEG 612.61 613.59 MWt; Tolerance:+/- 0.2 °F TEMPERATURE (°F)
NC LOOP A AVERAGE Thot at 3469 MWt is 0.5 °F more than at 3411 584.35 584.83 TEMP (°F) MWt; Tolerance: +/- 0.2 °F NC LOOP B AVERAGE Thot at 3469 MWt is 0.5 °F more than at 3411 582.04 582.54 TEMP (°F) MWt; Tolerance:+/- 0.2 °F NC LOOP C AVERAGE Thot at 3469 MWt is 0.5 °F more than at 3411 584.32 584.85 TEMP (°F) MWt; Tolerance:+/- 0.2 °F NC LOOP D AVERAGE Thot at 3469 MWt is 0.5 °F more than at 3411 583.35 583.83 TEMP (°F) MWt; Tolerance: +/- 0.2 °F 3469 MWt recorded value is equal to the NC FLOW BEST 5 MIN recorded value at 3411 MWt; Tolerance: +/-2% (+/- 391507 391143 RUNNING AVG (GPM) 7800 GPM) 3469 MWt recorded value is equal to the NC LOOP A COOLANT recorded value at 3411 MWt; Tolerance: +/-2% (+/- 98298.64 98165.02 FLOW, BEST (GPM) 2000 GPM) 3469 MWt recorded value is equal to the NC LOOP B COOLANT recorded value at 3411 MWt; Tolerance: +/-2% (+/- 97686.47 97552.52 FLOW, BEST (GPM) 2000 GPM) 3469 MWt recorded value is equal to the NC LOOP C COOLANT recorded value at 3411 MWt; Tolerance: +/-2% (+/- 97590.97 97507.89 FLOW, BEST (GPM) 2000 GPM) 3469 MWt recorded value is equal to the NC LOOP D COOLANT recorded value at 3411 MWt; Tolerance: +/-2% (+/- 97904.82 97963.31 FLOW, BEST (GPM) 2000 GPM)
TURBINE FIRST STAGE Verify pressure at 3469 MWt is 702.0 psig; 681.79 696.33 PRESS 1 (PSIG) Tolerance:+/- 7 psig Engineering will confirm expected output for UNIT 1 GENERATOR plants ambient and.subsequent condenser water 1215.44 1.233.52
- MEGAWATTS (MW) condition CF PUMP A SUCTION Pump Suction Flow equals recorded flow at 3411 18537.10 18888.33 FLOW (GPM) MWt times 1.0265; Tolerance: +/- 360 GPM CF PUMP A SUCTION Pump Suction Temperature is at recorded 364.01 365.27 TEMP (°F) temperature at 3411 MWt; Tolerance:+ 3 I -1 °F CF PUMP B SUCTION Pump Suction Flow equals recorded flow at 3411 16777.19 17098.97 FLOW (GPM) MWt times 1.0265; Tolerance:+/- 360 GPM CF PUMP B SUCTION Pump Suction Temperature is at recorded 365.34 366.65 TEMP (°F) temperature at 3411 MWt; Tolerance:+ 3 I -1 °F
U.S. Nuclear Regulatory Commission CNS-17-036 Enclosure, Page I 8 June 29, 2017 Attachment 2 Summary of Core Power Distribution Testing Core Power Distribution Results Date 5/19/16 6/7/16 Power 3402 MWth 3463 MWth Reaction Rate Error, Max 6.67% 7.29%
Reaction Rate Error, RMS 1.41% 1.47%
Heat Flux Hot Channel Factor (Fa) 1.772 1.771 Nuclear Enthalpy Rise Hot Channel Factor (FAH) 1.511 1.516 Axial Offset -0.209% -1.084%
Max Quadrant Tilt Ratio 1.00272 1.00299 Fa Operational Margin 8.75% 6.24%
Fa RPS Margin 18.24% 16.85%
Fa Steady State Margin 24.85% 23.44%
FAH Surveillance Margin 15.74% 13.92%
FAH Steady State Margin 20.68% 19.97%