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Category:Letter type:CP
MONTHYEARCP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters CP-202400107, (CPNPP) - 2023 Annual Radiological Environmental Operating Report2024-04-18018 April 2024 (CPNPP) - 2023 Annual Radiological Environmental Operating Report CP-202400099, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2024-04-0909 April 2024 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202400092, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-04-0101 April 2024 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400089, Property Damage Insurance2024-03-25025 March 2024 Property Damage Insurance CP-202400087, (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable2024-03-21021 March 2024 (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable CP-202400085, (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-0707 March 2024 (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CP-202400073, (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-03-0404 March 2024 (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400072, (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation2024-02-29029 February 2024 (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300470, (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-02-28028 February 2024 (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown CP-202300474, (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-02-28028 February 2024 (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions CP-202400063, (CPNPP) - Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 23 (1RF23)2024-02-12012 February 2024 (CPNPP) - Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 23 (1RF23) CP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 CP-202300442, (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program2023-09-15015 September 2023 (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program CP-202300391, (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2023-08-24024 August 2023 (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202300411, (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20)2023-08-17017 August 2023 (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20) CP-202300361, (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report2023-08-17017 August 2023 (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 CP-202300358, (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 1122023-08-0101 August 2023 (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 112 CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 32023-07-27027 July 2023 Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 3 CP-202300348, (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48)2023-07-18018 July 2023 (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48) CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202300262, Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 22023-06-20020 June 2023 Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 2 CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300248, Response to Request for Additional Information Regarding License Renewal Application - Set 12023-06-13013 June 2023 Response to Request for Additional Information Regarding License Renewal Application - Set 1 CP-202300209, Response to Request for Additional Information - License Renewal Application Environmental Review2023-06-0606 June 2023 Response to Request for Additional Information - License Renewal Application Environmental Review CP-202300207, Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-052023-05-25025 May 2023 Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-05 CP-202300182, Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application2023-05-0808 May 2023 Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application CP-202300201, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)2023-05-0404 May 2023 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0) CP-202300159, (Cpnpp), 2022 Annual Radiological Effluent Release Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Effluent Release Report CP-202300160, (Cpnpp), 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Environmental Operating Report CP-202300165, License Renewal Application Revision 0 - Supplement 22023-04-24024 April 2023 License Renewal Application Revision 0 - Supplement 2 CP-202300096, License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements2023-04-20020 April 2023 License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300175, Submittal of 2022 Annual Environmental Operating Report (Non-Radiological)2023-04-20020 April 2023 Submittal of 2022 Annual Environmental Operating Report (Non-Radiological) CP-202300140, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-0012023-04-19019 April 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-001 2024-08-05
[Table view] Category:Report
MONTHYEARML24136A1352024-07-30030 July 2024 LRA - Record of Decision ML23355A2682023-12-21021 December 2023 NRC Comments - Comanche Peak LRA Supplement 3 (1) CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202200419, (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report2022-11-0303 November 2022 (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report CP-202200247, (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 0172022-06-30030 June 2022 (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 017 ML22020A1792021-11-0404 November 2021 Fall 2021 Steam Generator Tube Inspections Discussion Input CP-202100127, Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 62021-03-16016 March 2021 Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 6 CP-202000462, Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 0162020-09-29029 September 2020 Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 016 ML20153A7442020-06-0404 June 2020 Review of the Fall 2018 Steam Generator Tube Inspection Report CP-201900467, (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings2019-08-14014 August 2019 (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings CP-201900378, Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report2019-06-10010 June 2019 Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report CP-201900126, Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report.2019-02-25025 February 2019 Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report. CP-201800652, Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report2018-09-12012 September 2018 Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report ML18044A0982018-02-0808 February 2018 Solid Waste Registration Number: 33306; Texas Waste Code: 37043902; Reference Number: 15749 CP-201700805, Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report2017-10-30030 October 2017 Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report CP-201700223, Decommissioning Funding Status Report for Financial Assurance as of 12/31/20162017-03-30030 March 2017 Decommissioning Funding Status Report for Financial Assurance as of 12/31/2016 CP-201700033, Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path2017-02-0909 February 2017 Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path CP-201600097, Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2016-02-29029 February 2016 Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. CP-201600093, Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 0132016-02-24024 February 2016 Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 013 ML16014A1252016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force ML16047A3302016-01-20020 January 2016 NEI 12-01 Phase 2 Staffing Assessment, Revision 1 ML15062A0302015-02-25025 February 2015 Work Plan for Completing a Once Through Cooling Water Study for Total Dissolved Solids, Chlorides, and Sulfates CP-201401268, Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report2014-10-21021 October 2014 Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report CP-201401027, 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 0122014-08-27027 August 2014 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 012 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 CP-201400335, . Pressure and Temperature Limits Report2014-04-0808 April 2014 . Pressure and Temperature Limits Report CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14036A0362014-03-0707 March 2014 Staff Assessments of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML13225A5752013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13338A6612013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Comanche Peak Nuclear Power Plant, TAC Nos.: MF0860 and MF0861 ML13309A0272013-10-31031 October 2013 WCAP-17728-NP, Rev. 1, Comanche Peak Nuclear Power Plant Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis CP-201301238, Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report2013-10-15015 October 2013 Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report ML12159A2882012-06-11011 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Related to Fukushima Dai-ichi Accident ML12080A1432012-03-0606 March 2012 CPNPP Systems Annual Operator Employment Notices ML12080A1502012-03-0606 March 2012 Submittal of Stc Annual Operator Employment Notices CP-201101257, Submittal of Operator Licensing Examination Data2011-09-21021 September 2011 Submittal of Operator Licensing Examination Data 2024-07-30
[Table view] Category:Miscellaneous
MONTHYEARML24136A1352024-07-30030 July 2024 LRA - Record of Decision CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202200247, (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 0172022-06-30030 June 2022 (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 017 ML22020A1792021-11-0404 November 2021 Fall 2021 Steam Generator Tube Inspections Discussion Input CP-202000462, Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 0162020-09-29029 September 2020 Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 016 ML20153A7442020-06-0404 June 2020 Review of the Fall 2018 Steam Generator Tube Inspection Report CP-201700033, Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path2017-02-0909 February 2017 Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path CP-201600093, Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 0132016-02-24024 February 2016 Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 013 ML16014A1252016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force ML15062A0302015-02-25025 February 2015 Work Plan for Completing a Once Through Cooling Water Study for Total Dissolved Solids, Chlorides, and Sulfates CP-201401268, Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report2014-10-21021 October 2014 Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report CP-201401027, 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 0122014-08-27027 August 2014 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 012 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14036A0362014-03-0707 March 2014 Staff Assessments of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident CP-201301238, Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report2013-10-15015 October 2013 Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report ML12159A2882012-06-11011 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Related to Fukushima Dai-ichi Accident ML12080A1432012-03-0606 March 2012 CPNPP Systems Annual Operator Employment Notices ML12080A1502012-03-0606 March 2012 Submittal of Stc Annual Operator Employment Notices CP-201101257, Submittal of Operator Licensing Examination Data2011-09-21021 September 2011 Submittal of Operator Licensing Examination Data CP-201101169, CFR50.59 Evaluation Summary Report 016, 10CFR72.48 Evaluation Summary Report 001, and Commitment Material Change Evaluation Report 0102011-08-22022 August 2011 CFR50.59 Evaluation Summary Report 016, 10CFR72.48 Evaluation Summary Report 001, and Commitment Material Change Evaluation Report 010 ML1034206512010-09-17017 September 2010 FEMA, Comanche Peak Nuclear Power Plant - After Action Report/Improvement Plan, Drill Date August 18, 2010, Radiological Emergency Preparedness (REP) Program CPSES-201001000, Operator Licensing Examination Data, Form 5362010-07-28028 July 2010 Operator Licensing Examination Data, Form 536 ML1000700042009-12-0303 December 2009 After Action Report/Improvement Plan, Drill Date - December 03, 2009 CP-200901404, Core Operating Limits2009-11-0202 November 2009 Core Operating Limits CP-200900474, Property Damage Insurance, Summary Report2009-03-26026 March 2009 Property Damage Insurance, Summary Report CP-200900127, Guarantees of Payment of Deferred Premiums2009-01-19019 January 2009 Guarantees of Payment of Deferred Premiums CP-200900010, Core Flux Maps Data, Cycle 112009-01-0707 January 2009 Core Flux Maps Data, Cycle 11 CP-200800805, Report of Unusual or Important Environmental Event, Operating License, Appendix B, Environmental Protection Plan (Non Radiological) - Mortality of Avian Species2008-06-0404 June 2008 Report of Unusual or Important Environmental Event, Operating License, Appendix B, Environmental Protection Plan (Non Radiological) - Mortality of Avian Species CP-200800612, Commanche Peak, Units 1 & 2 - Transmittal of Revised Pressure and Temperature Limits Report2008-04-24024 April 2008 Commanche Peak, Units 1 & 2 - Transmittal of Revised Pressure and Temperature Limits Report CP-200800609, Pressurizer Weld Overlay 60 Day Report and Results of the Final Pdi/Ut Examination of Weld Overlays2008-04-24024 April 2008 Pressurizer Weld Overlay 60 Day Report and Results of the Final Pdi/Ut Examination of Weld Overlays CP-200800213, Response to Request for Additional Information2008-02-26026 February 2008 Response to Request for Additional Information CPSES-200700454, Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data2007-02-28028 February 2007 Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data CPSES-200601738, Transmittal of First-Half 2006 Fitness-For-Duty Program Performance Data2006-08-31031 August 2006 Transmittal of First-Half 2006 Fitness-For-Duty Program Performance Data CPSES-200600154, Transmittal of Unit 2 Inservice Inspection Program Plan, Revision 22006-08-0202 August 2006 Transmittal of Unit 2 Inservice Inspection Program Plan, Revision 2 ML0620500122006-07-17017 July 2006 Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 1 Through 74 ML0702303962006-04-10010 April 2006 Report 06-0413 Chart 250-200 ML0702303952006-04-0606 April 2006 Report 06-0413 Chart 120-307 2024-07-30
[Table view] |
Text
Rafael Flores Luminant Power Senior Vice President P 0 Box 1002
& Chief Nuclear Officer 6322 North FM 56 rafael.flores@Luminant.com Glen Rose, TX 76043 Luminant T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-200901404 Ref: Tech. Spec. 5.6.5 TXX-09129 November 2, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NO. 50-446 CORE OPERATING LIMITS REPORTS
Dear Sir or Madam:
Enclosed is the Core Operating Limits Reports for Comanche Peak Steam Electric Station, herein referred to as Comanche Peak Nuclear Power Plant (CPNPP) Unit 2, Cycle 12. This report is prepared and submitted pursuant to Technical Specification 5.6.5.
This communication contains no new licensing basis commitments regarding CPNPP Units 1 and 2. Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.
Sincerely, Luminant Generation Company LLC Rafael Flores By: A, 27 h,,
/Fred W. Madden "
Director, Oversight & Regulatory Affairs c- E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon ' Palo Verde San Onofre
- South Texas Project ' Wolf Creek ACMY.ý I
ERX-09-001, Rev. 0 CPNPP UNIT 2 CYCLE 12 CORE OPERATING LIMITS REPORT September 2009 Prepared . - Date: _-__ 0oo0
\Jo than M. Ralston P ncipal Engineer, Westinghouse Electric Co.
Reviewed: '. 4 . Date: 9-23, Daniel E. Brozak Principal Engineer, Westinghouse Electric Co.
Reviewed: Date: q/*j' I evin N. RaTand Principal Engineer, Westinghouse Electric Co.
Approved: 41/_ Date: op/2J/O P.
W.4James Boq~wright, Manager Westinghouse Engineering Services - Texas
DISCLAIMER The information contained in this report was prepared for the specific requirement of Luminant Generation Company LLC and may not be appropriate for use in situations other than those for which it was specifically prepared. Luminant Generation Company LLC PROVIDES NO WARRANTY HEREUNDER, EXPRESS OR IMPLIED, OR STATUTORY, OF ANY KIND OR NATURE WHATSOEVER, REGARDING THIS REPORT OR ITS USE, INCLUDING BUT NOT LIMITED TO ANY WARRANTIES ON MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE.
By making this report available, Luminant Generation Company LLC does not authorize its use by others, and any such use is forbidden except with the prior written approval of Luminant Generation Company LLC. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall Luminant Generation Company LLC have any liability for any incidental or consequential damages of any type in connection with the use, authorized or unauthorized, of this report or of the information in it.
ii ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 TABLE OF CONTENTS DISCLAIMER ...................................................... ii TABLE OF CONTENTS . .............................................. iii LIST OF TABLES ................................................... iv LIST OF FIGURES ................................................. v SECTION PAGE 1.0 CORE OPERATING LIMITS REPORT .............................. 1 2.0 OPERATING LIMITS .......................................... 2 2.1 SAFETY LIMITS ........................................ 2 2.2 SHUTDOWN MARGIN ...................................... 2 2.3 MODERATOR TEMPERATURE COEFFICIENT .................... 2 2.4 ROD GROUP ALIGNMENT LIMITS ........................... 3 2.5 SHUTDOWN BANK INSERTION LIMITS ....................... 3 2.6 CONTROL BANK INSERTION LIMITS ......................... 4 2.7 PHYSICS TESTS EXCEPTIONS - MODE 2 ......................... 4 2.8 HEAT FLUX HOT CHANNEL FACTOR ......................... 4 2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR ................ 5 2.10 AXIAL FLUX DIFFERENCE ................................ . .6 2.11 REACTOR TRIP SYSTEM INSTRUMENTATION ....................... 6 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS .............................. 7 2.13 \BORON CONCENTRATION ................................... 8
3.0 REFERENCES
....................................... *......... 8 iii ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 LIST OF TABLES TABLE PAGE 1 FQ (Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD .......... 9 iv ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 LIST OF FIGURES FIGURE PAGE 1 REACTOR CORE SAFETY LIMITS .............................. 10 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER ............ 11 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT ............................................. 12 4 W(Z) AS A FUNCTION OF CORE HEIGHT -
(150 MWD/MTU) ........................................... 13 5 W(Z) AS A FUNCTION OF CORE HEIGHT -
(4,000 MWD/MTU) ......................................... 14 6 W(Z) AS A FUNCTION OF CORE HEIGHT -
(7,000 MWD/MTU) ......................................... 15 7 W(Z) AS A FUNCTION OF CORE HEIGHT -
(11,000 MWD/MTU) ........................................ 16 8 W(Z) AS A FUNCTION OF CORE HEIGHT -
(20,000 MWD/MTU) ........................................ 17 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER .................................. 18 V ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for CPNPP UNIT 2 CYCLE 12 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Specifications affected by this report are listed below:
SL 2.1 SAFETY LIMITS LCO 3.1.1 SHUTDOWN MARGIN LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT LCO 3.1.4 ROD GROUP ALIGNMENT LIMITS LCO 3.1.5 SHUTDOWN BANK INSERTION LIMITS LCO 3.1.6 CONTROL BANK INSERTION LIMITS LCO 3.1.8 PHYSICS TESTS EXCEPTIONS - MODE 2 LCO 3.2.1.2 HEAT FLUX HOT CHANNEL FACTOR LCO 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LCO 3.2.3.2 AXIAL FLUX DIFFERENCE LCO 3.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LCO 3.4.1 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING LIMITS LCO 3.9.1 BORON CONCENTRATION 1 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 5.6.5b, Items 1, 2, 14, 16 and 21 through 29.
These limits have been determined such that all applicable limits of the safety analysis are met.
2.1 SAFETY LIMITS (SL 2.1) 2.1.1 In MODES 1 and 2, the combination of thermal power, reactor coolant system highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 1.
2.2 SHUTDOWN MARGIN (SDM) (LCO 3.1.1) 2.2.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 with Keff < 1.0, and in MODES 3, 4, and 5.
2.3 MODERATOR TEMPERATURE COEFFICIENT (MTC) (LCO 3.1.3) 2.3.1 The MTC upper and lower limits, respectively, are:
The BOL/ARO/HZP-MTC shall be less positive than +5 pcm/°F.
The EOL/ARO/RTP-MTC shall be less negative than -40 pcm/*F.
2 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 2.3.2 SR 3.1.3.2 The MTC surveillance limit is:
The 300 ppm/ARO/RTP-MTC shall be less negative than or equal to -31 pcm/*F.
The 60 ppm/ARO/RTP-MTC shall be less negative than or equal to -38 pcm/°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 ROD GROUP ALIGNMENT LIMITS (LCO 3.1.4) 2.4.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODES 1 and 2.
2.5 SHUTDOWN BANK INSERTION LIMITS (LCO 3.1.5) 2.5.1 The shutdown rods shall be fully withdrawn. Fully withdrawn shall be the condition where shutdown rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.
3 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 2.6 CONTROL BANK INSERTION LIMITS (LCO 3.1.6) 2.6.1 The control banks shall be limited in physical insertion as shown in Figure 2.
2.6.2 The control banks shall always be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is control bank A, control bank B, control bank C, and control bank D. The insertion sequence is the reverse of the withdrawal sequence.
2.6.3 A 115 step Tip-to-Tip relationship between each sequential control bank shall be maintained.
2.7 PHYSICS TESTS EXCEPTIONS - MODE 2 (LCO 3.1.8) 2.7.1 The SDM shall be greater than or equal to 1.3% Ak/k in MODE 2 during PHYSICS TESTS.
2.8 HEAT FLUX HOT CHANNEL FACTOR (F. (Z) (LCO 3.2.1.2)
RTP FQ 2.8.1 FQ(Z) -<(K (Z)] for P > 0.5 P
RTP FQ FQ (Z) -< [K(Z)] for P S 0.5
0.5 where
P = £HERMAL POWER RATE:D THERMAL POWER 4 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 2.8.2 F = 2.50 2.8.3 K(Z) is provided in Figure 3.
2.8.4 Elevation and burnup dependent W(Z) values are provided in Figures 4, 5, 6, 7 and 8. The burnup dependent values can be used to interpolate or extrapolate (via a three point fit) the W(Z) at a particular burnup.
2.8.5 SR 3.2.1.2.2 If the two most recent FQ (Z) evaluations show an increase in the expression maximum over Z [ FQC(Z) / K(Z) ],
the burnup dependent values in Table 1 shall be used instead of a constant 2% to increase FQW(Z) per Surveillance Requirement 3.2.1.2.2.a. A constant factor of 2% shall be used for all cycle burnups that are outside the range of Table 1.
2.9 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAHI (LCO 3.2.2)
T 2.9.1 FNAH -5 FR PAH [1 + PFAH (l-P)]
where: P = THERMAL POWER RATED THERMAL POWER T
2.9.2 FR PAH = 1.60 for all Fuel Assembly Regions 2.9.3 PFAH = 0.3 5 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 2.10 AXIAL FLUX DIFFERENCE (AFD) (LCO 3.2.3.2) 2.10.1 The AFD Acceptable Operation Limits are provided in Figure 9.
2.11 REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION (LCO 3.3.1) 2.11.1 The numerical values pertaining to the Overtemperature N-16 reactor trip setpoint are listed below; K, = 1.15 K2 = 0.0139 /°F K3 = 0.00071 /psig T°o = indicated loop specific Tc at Rated Thermal Power, OF P'
- 2235 psig T, t 10 sec T2 3 sec f 1 (Aq) = -2.78 {(q,-qb) + 18%} when (q,-q,) < -18% RTP
= 0% when -18% RTP < (qt-q,) < +10.0% RTP
= 2.34 - {(qt-qb) - 10.0%} when (qt-qb) 2 +10.0% RTP 6 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 2.12 RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS (LCO 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the surveillance limits specified below:
2.12.2 SR 3.4.1.1 Pressurizer pressure Ž 2220 psig (4 channels) 2 2222 psig (3 channels)
The pressurizer pressure limits correspond to the analytical limit of 2205 psig used in the safety analysis with allowance for measurement uncertainty. These uncertainties are based on the use of control board indications and the number of available channels.
2.12.3 SR 3.4.1.2 RCS average temperature 5 592 *F (4 channels) 591 °F (3 channels)
The RCS average temperature limits correspond to the analytical limit of 595.2 'F which is bounded by that used in the safety analysis with allowance for measurement uncertainty. These uncertainties are based on the use of control board indications and the number of available channels.
7 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 2.12.4 SR 3.4.1.3 The RCS total flow rate shall be
2.12.5 SR 3.4.1.4 The RCS total flow rate based on precision heat balance shall be > 408,000 gpm.
The required RCS flow, based on an elbow tap differential pressure instrument measurement prior to MODE 1 after the refueling outage, shall be greater than 327,000 gpm.,
2.13 BORON CONCENTRATION (LCO 3.9.1) 2.13.1 The required refueling boron concentration is ý1881 ppm.
3.0 REFERENCES
Technical Specification 5.6.5.
8 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 Table 1 FQ(Z) MARGIN DECREASES IN EXCESS OF 2% PER 31 EFPD Cycle Maximum Decrease Burnup In FQ (Z) MARGIN (MWD/MTU) (Percent) 1233 2.00 1449 2.15 1666 2.00 4698 2.00 4914 2.05 5131 2.43 5347 2.53 5564 2.48 5780 2.39 5997 2.29 6214 2.18 6430 2.05 6647 2.00 8379 2.00 8596 2.06 8812 2.21 9029 2.37 9245 2.51 9462 2.57 9678 2.60 9895 2.61 10111 2.59 10328 2.55 10545 2.47 10761 2.31 10978 2.14 11194 2.04 11411 2.00 Note: All Cycle burnups outside the range of the table shall use a constant 2% decrease in F0 (Z) margin for compliance with the 3.2.1.2.2.a Surveillance Requirements. Linear interpolation is acceptable to determine the FQ(Z) margin decrease for cycle burnups which fall between the specified burnups.
9 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 Figure 1 Reactor Core Safety Limits 680 660 640 S620 I-0 600 580 560 0 20 40 60 80 100 120 140 Percent of Rated -Thermal Power 10 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER 240
- '.15.32 8 (79.6,21 8) 220 200 180 i-o 4J 160
.c --10,164)3 o-/
- ~~ - ~---- P -.
. -(1 00,146)
vi'.... -, x z
0 H
E-1 H 100 0
80
--- - - - - -- --- - - - - -BANK D 80 S60 --- - - --
H0,49) 40
-~~~ ------
20 I
ý31, 0
0 10 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER NOTES: 1. Fully withdrawn shall be the condition where control rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.
- 2. Control Bank A shall be fully withdrawn.
11 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 3 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT 1.1 1.0 (0.01 1 '0) (6.0,1.0) 0.9
(,12.-,01,0.925) 0.8 0.7 N
0 0.6 rz 0.5 0.4 0.3 0.2 ---- H 0.1 0.0 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node K(Z) Node K (Z) Node K (Z) Node K (Z) 61 0.9250 53 0.9450 45 0.9650 37 0.9850 60 0.9275 52 0.9475 44 0.9675 36 0.9875 59 0.9300 51 0.9500 43 0.9700 35 0.9900 58 0.9325 50 0.9525 42 0.9725 34 0.9925 57 0.9350 49 0.9550 41 0.9750 33 0.9950 56 0.9375 48 0.9575 40 0.9775 32 0.9975 55 0.9400 47 0.9600 39 0.9800 1 - 31 1.0000 54 0.9425 46 0.9625 38 0.9825 Core Height (ft) = (Node - 1)
- 0.2 12 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 4 W(Z) AS A FUNCTION OF CORE HEIGHT (150 MWD/MTU) 1.650 1.600 1.550 1 I1 1.500 m t
1.450
-Iz N 1.400 1=11-1 1 1z~cz 1.350
1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node w(Z) Node w(Z) Node w(Z) Node w(Z) 58 - 61 44 1.1542 30 1.1577 16 1.2306 57 1.3589 43 1.1632 29 1.1570 15 1.2516 56 1.3421 42 1.1699 28 1.1628 14 1.2702 55 1.3280 41 1 .1774 27 1.1725 13 1.2892 54 1.3156 40 1.1839 26 1.1813 12 1.3090 53 1.3027 39 1.1880 25 1.1888 11 1.3297 52 1.2845 38 1.1903 24 1.1953 10 1.3501 51 1.2606 37 1.1918 23 1.2006 9 1.3691 50 1.2336 36 1.1920 22 1.2050 8 1.3865 49 1.2054 35 1.1901 21 1.2085 7 1.4014 48 1.1763 34 1.1862 20 1.2111 6 1.4133 47 1.1511 33 1.1804 19 1.2130 5 1.4237 46 1.1460 32 1.1728 18 1.2142 1 - 4 45 1.1469 31 1.1640 17 1.2156 Core Height (ft) = (Node - 1)
- 0.2 13 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 5 W(Z) AS A FUNCTION OF CORE HEIGHT (4,000 MWD/MTU) 1.650 1.600 I
1.550 I I I 1.500 1.450 VH\
N 1.400 - I --4 \
1.350
-A 1.250 1.200 -/
1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 . 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node w(Z) Node w(Z) Node w(Z) Node w(Z) 58 - 61 44 1.1598 30 1.1239 16 1.2487 57 1.4243 43 1.1600 29 1.1317 15 1.2734 56 1.4114 42 1.1601 28 1.1433 14 1.3036 55 1.3933 41 1.1609 27 1.1535 13 1.3331 54 .1.3704 40 1.1611 26 1.1628 12 1.3626 53 1.3444 39 1.1600 25 1.-1713 11 1.3916 52 1.3155 38 1.1574 24 1.1788 10 1.4197 51 1.2847 37 1.1532 23 1.1854 9 1.4462 50 1.2523 36 1.1474 22 1.1912 8 1.4707 49 1.2272 35 1.1413 21 1.1958 7 1.4922 48 1.2106 34 1.1363 20 1.2012 6 1.5094 47 1.1923 33 1.1322 19 1.2088 5 1.5247 46 1.1732 32 1.1277 18 1.2188 1 - 4 45 1.1619 31 1.1233 17 1.2316 Core Height (ft) = (Node- 1)
- 0.2 14 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 6 W(Z) AS A FUNCTION OF CORE HEIGHT (7,000 MWD/MTU) 1.650 1.600 1.550 1.500 1.450 N 1.400 1.350 1.300 1.250 1.200 1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node W(Z) Node w(Z) Node w (Z) Node w(Z) 58 - 61 --- 44 1.2224 30 1.1192 16 1.1986 57 1.4158 43 1.2166 29 1.1181 15 1.2187 56 1.4057 42 1.2082 28 1.1228 14 1.2447 55 1.3898 41 1.1998 27 1.1310 13 1.2699 54 1.3731 40 1.1941 26 1.1386 12 1.2952 53 1.3601 39 1.1888 25 1.1451 11 1.3202 52 1.3468 38 1.1824 24 1.1511 10 1.3443 51 1.3310 37 1.1776 23 1.1562 9 1.3673 50 1.3118 36 1.1708 22 1.1608 8 1.3884 49 1.2899 35 1.1619 21 1.1649 7 1.4069 48 1.2656 34 1.1514 20 1.1682 6 1.4213 47 1.2419 33 1.1394 19 1.1723 5 1.4338 46 1.2294 32 1.1275 18 1.1791 1 -4 45 1.2253 31 1.1223 17 1.1869 Core Height (ft) = (Node - 1)
- 0.2 15 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 7 W(Z) AS A FUNCTION OF CORE HEIGHT (11,000 MWD/MTU) 1.650 1.600 iý 1.550 1.500 1.450 7
N 1.400 1.350
/
- 1.300 -- T- I I I I hi~7'~ I I r4z1/I I-1.250 1.200 1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node w(Z) Node w(Z) Node w(Z) Node w(Z) 58 - 61 44 1.2523 30 1.1285 16 1.1711 57 1.4639 43 1.2517 29 1.1292 15 1.1844 56 1.4579 42 1.2459 28 1.1343 14 1.2014 55 1.4415 41 1.2383 27, 1. 1380 13 1.2176 54 1.4274 40 1.2283 26 1.1409 12 1.2338 53 1.4183 39 1.2181 25 1.1437 11. 1.2496 52 1.4014 38 1. 2083 24 1.1460 10 1.2651 51 1.3796 37 1.1966 23 1.1474 9 1.2807 50 1.3560 36 1.1909 22 1.1486 8 1.2956 49 1.3297 35 1.1851 21 1.1524 7 1.3085 48 1.3013 34 1.1757 20 1.1566 6 1.3181 47 1.2770 33 1.1646 19 1.1599 5 1.3259 46 1.2644 32 1.1515 18 1.1627 1 - 4 45 1.2558 31 1.1370 17 1.1646 Core Height (ft) = (Node - 1)
- 0.2 16 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 8 W(Z) AS A FUNCTION OF CORE HEIGHT (20,000 MWD/MTU) 1.650 1.600 1.550 I I 1.500 1.450 1.400 i I M '
1.350
- 1. i_
/_
1.250
_X 1.200 1.150 1.100 1.050 1.000 0 1 2 3 4 5 6 7 8 9 10 11 12 BOTTOM CORE HEIGHT (FEET) TOP Axial Axial Axial Axial Node W (Z) Node w(Z) Node w(Z) Node w (Z) 58 - 61 --- 44 1.2188 30 1.2023 16 1.1760 57 1.3907 43 1.2170 29 1.1988 15 1.1940 56 1.3903 42 1.2238 28 1.2002 14 1.2094 55 1.3811 41 1.2304 27 1.2007 13 1.2252 54 1.3673 40 1.2374 26 1.1992 12 1.2406 53 1.3519 39 1.2436 25 1.1972 11 1.2556 52 1.3342 38 1.2477 24 1.1942 10 1.2702 51 1.3137 37 1.2516 23 1.1895 9 1.2841 50 1.2919 36 1.2526 22 1.1847 8 1.2969 49 1.2669 35 1.2504 21 1.1808 7 1.3079 48 1.2450 34 1.2454 20 1.1769 6 1.3161 47 1.2367 33 1.2376 19 1.1722 5 1.3225 46 1.2335 32 1.2273 18 1.1671 1 - 4 45 1.2268 31 1.2138 17 1.1659 Core Height (ft) = (Node - 1)
- 0.2 17 ERX-09-001, Rev. 0
COLR for CPNPP Unit 2 Cycle 12 FIGURE 9 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 . . . . . .
S(-15,100) -- -- - -
90 UNACCEPTABLE OPERATION 80 ACCEPTAI
--- OPERATI 70 -j~i1------
W.
60 F -
-- 0 , 10 - .. . . . . . .
60 ll--4 30 (3,0----------------------- ,
0 E
30 711 0 ------- ----- -------
10-.-.----------------
- --------- 1 .....
-t
-40 -30 -20 -10 0 10 20 30 40 AXIAL FLUX DIFFERENCE (%)
18 ERX-09-001, Rev. 0