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Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
[Table view] Category:Report
MONTHYEARAEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1992022-11-30030 November 2022 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2) ML22340A2132022-11-30030 November 2022 R1900-0024-001, Revision 13, NFPA 805 Nuclear Safety Capability Assessment ML22340A1762022-11-30030 November 2022 Commitment Change Summary October 2020 to May 2022 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report2021-08-12012 August 2021 Form OAR-1, Owner'S Activity Report ML21125A5582021-04-19019 April 2021 Report 2019, Commitment Change Summary, May 2019 to October 2020 ML21125A5392021-04-19019 April 2021 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2), Boration System Functionality Requirement Change in Mode 4 EA-21-024, Notice of Enforcement Discretion2021-03-0404 March 2021 Notice of Enforcement Discretion for Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2021-07, Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level2021-01-28028 January 2021 Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level AEP-NRC-2020-28, CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations2020-05-0606 May 2020 CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations AEP-NRC-2020-23, Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2020-04-30030 April 2020 Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML20108E9992020-03-0505 March 2020 Enclosure 7 - LTR-SCS-19-50, Revision 0, D.C. Cook Unit 1 Low Temperature Overpressure Protection System (Ltops) Analysis for 48 EFPY, Dated March 5, 2020, Attachment 2 Only (Non-Proprietary) ML20108F0002020-02-28028 February 2020 Enclosure 5 - WCAP-18455-NP, Revision 1, D.C. Cook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation, Westinghouse Electric Company, February 2020. (Non-Proprietary) ML18274A0952018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D. C. Cook Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break, September 2018 (Non-Proprietary) ML18334A2712018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D.C. Cook, Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break. AEP-NRC-2018-36, Notification of Initial Renewable Operating Permit2018-05-0909 May 2018 Notification of Initial Renewable Operating Permit AEP-NRC-2018-21, 30-Day Report of Changes to or Errors in an Evaluation Model2018-05-0404 May 2018 30-Day Report of Changes to or Errors in an Evaluation Model ML18026A8822018-02-0505 February 2018 Staff Assessment of Flooding Focused Evaluation ML18334A2702018-01-31031 January 2018 WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis for D.C. Cook, Units 1 and 2, Using Leak-Before-Break Methodology. ML18334A2692018-01-31031 January 2018 WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology. ML18334A2682018-01-31031 January 2018 WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology (Non-Proprietary) ML17151A9672017-06-14014 June 2017 Flood Hazard Mitigation Strategies Assessment ML16313A1172016-10-10010 October 2016 1BTl1V001-RPT-01, Donald C. Cook Focused Scope Peer Review - Pre-Initiator Human Reliability Analysis. ML16127A3352016-05-0606 May 2016 Reactor Oversight Process Task Force FAQ Log-April 13, 2016 ML16113A1982016-04-20020 April 2016 Precursor Screening Analysis- Reject ML16169A1182016-03-31031 March 2016 RWA-1313-015, Rev. 1, AST Radiological Analysis Technical Report. ML15308A0932015-10-15015 October 2015 Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program. AEP-NRC-2015-83, Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-10-0101 October 2015 Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML15233A0242015-08-19019 August 2015 Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML14253A3172014-09-0404 September 2014 Enclosure 2: I&M CAP Document AR 2010-1804-10, Root Cause Evaluation Attachment, Rx Vessel Core Support Lug Bolting Anomalies ML14147A3292014-06-18018 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14181A5382014-06-0505 June 2014 Enclosure 5 to AEP-NRC-2014-42, Attachment #2 (NP-Attachment) of Westinghouse Letter, LTR-PL-14-22, Westinghouse Responses to NRC, Request for Additional Information on the Application for Amendment to Restore.. ML14073A7592014-03-31031 March 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 ML14092A3302014-03-17017 March 2014 Document No. 13Q3208-RPT-003, Revion 1, Seismic Hazard and Screening Report for the Cook Nuclear Plant (Cnp), Enclosure 2 to AEP-NRC-2014-25 AEP-NRC-2014-15, 30 Day Report of Changes to or Errors in an Evaluation Model2014-02-27027 February 2014 30 Day Report of Changes to or Errors in an Evaluation Model ML13337A3252014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14035A3572014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-232 Through Page C-353 ML14035A3662014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-92 Through Page D-169 ML14035A3642014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-1 Through Page D-91 ML14035A3632014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-845 Through Page C-962 ML14035A3622014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-723 Through Page C-844 ML14035A3612014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-584 Through Page C-722 ML14035A3602014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-469 Through Page C-583 ML14035A3592014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-354 Through Page C-468 ML14035A3562014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-115 Through Page C-231 ML14035A3552014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-405 Through End ML14035A3532014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-1 Through Page C-114 ML14035A3522014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Cover Through Page B-312 2022-12-15
[Table view] Category:Miscellaneous
MONTHYEARAEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report2021-08-12012 August 2021 Form OAR-1, Owner'S Activity Report ML21125A5582021-04-19019 April 2021 Report 2019, Commitment Change Summary, May 2019 to October 2020 ML21125A5392021-04-19019 April 2021 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2), Boration System Functionality Requirement Change in Mode 4 EA-21-024, Notice of Enforcement Discretion2021-03-0404 March 2021 Notice of Enforcement Discretion for Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2020-28, CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations2020-05-0606 May 2020 CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations AEP-NRC-2018-36, Notification of Initial Renewable Operating Permit2018-05-0909 May 2018 Notification of Initial Renewable Operating Permit AEP-NRC-2018-21, 30-Day Report of Changes to or Errors in an Evaluation Model2018-05-0404 May 2018 30-Day Report of Changes to or Errors in an Evaluation Model ML18026A8822018-02-0505 February 2018 Staff Assessment of Flooding Focused Evaluation ML17151A9672017-06-14014 June 2017 Flood Hazard Mitigation Strategies Assessment ML16127A3352016-05-0606 May 2016 Reactor Oversight Process Task Force FAQ Log-April 13, 2016 ML16113A1982016-04-20020 April 2016 Precursor Screening Analysis- Reject AEP-NRC-2015-83, Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-10-0101 October 2015 Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML15233A0242015-08-19019 August 2015 Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML14181A5382014-06-0505 June 2014 Enclosure 5 to AEP-NRC-2014-42, Attachment #2 (NP-Attachment) of Westinghouse Letter, LTR-PL-14-22, Westinghouse Responses to NRC, Request for Additional Information on the Application for Amendment to Restore.. ML14073A7592014-03-31031 March 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 AEP-NRC-2014-15, 30 Day Report of Changes to or Errors in an Evaluation Model2014-02-27027 February 2014 30 Day Report of Changes to or Errors in an Evaluation Model ML12324A4182012-12-20020 December 2012 Review of the 2011 Refueling Outage Steam Generator Tube Inservice Inspection Results AEP-NRC-2012-86, Flooding Walkdown Report in Response to the 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding for the D.C. Cook Nuclear Power Plant2012-11-13013 November 2012 Flooding Walkdown Report in Response to the 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding for the D.C. Cook Nuclear Power Plant ML12362A0762012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-268 Through C-353 AEP-NRC-2012-87, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-437 Through C-4862012-11-0505 November 2012 Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-437 Through C-486 ML12362A0582012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-487 Through C-548 ML12362A0592012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-549 Through C-620 ML12362A0602012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-621 Through C-697 ML12362A0612012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-698 Through C-776 ML12362A0632012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-54 Through Page D-114 ML12362A0772012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-354 Through C-436 ML12362A0752012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-200 Through C-267 ML12362A0742012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-157 Through C-199 ML12362A0732012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-113 Through C-156 ML12362A0722012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-47 Through C-112 ML12362A0712012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Appendix C, Page C-46 ML12362A0692012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-388 Through End ML12362A0672012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-276 Through Page D-336 ML12362A0622012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-777 Through Appendix D, Page ML12362A0642012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-115 Through Page D-175 ML12362A0652012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-176 Through Page D-219 ML12362A0662012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-220 Through Page D-275 ML12362A0682012-11-0505 November 2012 Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix D, Page D-337 Through Page D-387 AEP-NRC-2012-83, Communications Assessment Requested by Nuclear Regulatory Commission Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulation 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3.2012-10-31031 October 2012 Communications Assessment Requested by Nuclear Regulatory Commission Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulation 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3. AEP-NRC-2012-38, Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation2012-06-11011 June 2012 Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation AEP-NRC-2009-25, Small Break Loss-of-Coolant Accident Evaluation Model Reanalysis2009-03-30030 March 2009 Small Break Loss-of-Coolant Accident Evaluation Model Reanalysis ML0807704042008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 5, Figure A5-41, Scotch 77 Fire Retardant Tape Test 1 Post-Test Picture to Attachment 7, Regulatory Commitments. ML0807400532008-02-29029 February 2008 Response to Request for Additional Information Regarding Reanalysis of Small Break Loss-Of-Coolant Accident ML0807703952008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 1, References, Through Attachment 3, Supplemental Response to GL 2004-02 and Request for Additional Information. ML0807200622008-02-29029 February 2008 License Amendment Request to Revise Ice Condenser Licensing Basis ML0807703962008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 3, I&M Response to Information Item 3.f.4, to NRC Information Item 3 - Conclusions. ML0807704002008-02-29029 February 2008 AEP:NRC:8054-02, Attachment 4, Figure A4-1, General Arrangement of Recirculation Sump to Attachment 5, Figure A5-40, Scotch 77 Fire Retardant Tape Test 1 Pre-Test Picture. ML0806600732008-02-22022 February 2008 Cycle 21 End of Life Moderator Temperature Coefficient Limit Report ML0706605162007-02-27027 February 2007 Steam Generator Tube Inspection Report. 2022-12-12
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Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman, MI 49106 POWERO AERcom A unit of American Electric Power February 22, 2008 AEP:NRC:8132 10 CFR 50.4 Docket No.: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 Unit I Cycle 21 End of Life Moderator Temperature Coefficient Limit Report
Reference:
Letter from J. N. Jensen, Indiana Michigan Power Company, to U. S. Nuclear Regulatory Commission Document Control Desk, "Supplement to License Amendment Request on the Conditional Exemption from Measurement of End of Life Moderator Temperature Coefficient," AEP:NRC:5132-01, dated June 2, 2005.
Indiana Michigan Power Company, the licensee for the Donald C. Cook Nuclear Plant (CNP), made a commitment in the referenced letter to submit the following information for the first three uses of the WCAP-13749-P-A methodology for each unit at CNP as a condition for approval of the conditional exemption of the most negative end of life moderator temperature coefficient measurement technical specification change:
- 1. A summary of the plant data used to confirm that the Benchmark Criteria of Table 3-2 of WCAP-13749-P-A, Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement, have been met; and,
- 2. The Most Negative Moderator Temperature Coefficient Limit Report (as found in Appendix D of WCAP- 13749-P-A).
The information is attached. This transmittal is the second of the three submittals for Unit 1. There are no new or revised commitments made in this submittal.
4w'
U. S. Nuclear RegLulatory Commission AEP:NRC:8132 Page 2 Should you have any questions, please contact Mr. James M. Petro, Jr., Regulatory Affairs Manager, at (269) 466-2491.
Sincerely, Joseph N. Jensen Site Support Services Vice President RSP/rdw Attachments:
- 1. Plant Data Used to Confirm Benchmark Requirements
- 2. Most Negative End of Life Moderator Temperature Coefficient Limit Report for Donald C. Cook Nuclear Plant Unit 1, Cycle 21 c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o attachments J. T. King, MPSC MDEQ - WHMD/RPMWS NRC Resident Inspector P. S. Tam, NRC Washington, DC
Attachment 1 to AEP:NRC:8132 PLANT DATA USED TO CONFIRM BENCHMARK REQUIREMENTS
Attachment I to AEP:NRC:8132 Page 2 Plant Data Used to Confirm Benchmark Requirements To facilitate the review of this information, a list of acronyms used in this attachment is provided.
OF degrees Fahrenheit
% percent BOL beginning of life CNP Donald C. Cook Nuclear Plant EOL end of life HZP hot zero power ITC isothermal temperature coefficient M measured MTC moderator temperature coefficient MTU metric tons of uranium MWD megawatt-day NRC Nuclear Regulatory Commission pcm percent-millirho P predicted This attachment presents a comparison of the CNP Unit 1 Cycle 21 core characteristics with the requirements for use of the Conditional Exemption of the Most Negative EOL MTC Measurement methodology and presents plant data demonstrating that the Benchmark Criteria presented in WCAP-13749-P-A are met.
The Conditional Exemption of the Most Negative EOL MTC Measurement methodology is described in WCAP-13749-P-A. This report was approved by the NRC with two requirements:
- only PHOENIX/ANC calculation methods are used for the individual plant analyses relevant to determinations for the EOL MTC plant methodology, and
- the predictive correction is reexamined if changes in core fuel designs or continued MTC calculation/measurement data show significant effect on the predictive correction.
The PHOENIX/ANC calculation methods were used for the CNP Unit 1 Cycle 21 core design and relevant analyses. Also, the Unit 1 Cycle 21 core design does not represent a major change in core fuel design and the MTC calculation-to-measurement physics database shows no significant effect on the predictive correction. Therefore, the predictive correction of -3 pcm/°F remains valid for this cycle. The Unit 1 Cycle 21 core meets both of the above requirements.
Attachment I to AEP:NRC:8132 Page 3 The following data tables are provided in support of the benchmark criteria:
- Table I - Benchmark Criteria for Application of the 300 ppm MTC Conditional Exemption Methodology (per WCAP-13749-P-A)
- Table 2 - Flux Map Data: Assembly Powers
- Table 3 - Flux Map Data: Core Tilt Criteria
- Table 4 - Core Reactivity Balance Data
- Table 5 - Low Power Physics Test Data (BOL, HZP): ITC
- Table 6 - Low Power Physics Test Data (BOL, HZP): Total Control Bank Worth
Attachment I to AEP:NRC:8132 .Page 4 Table I Benchmark Criteria for Application of the 300 ppm MTC Conditional Exemption Methodology (per WCAP-13749-P-A)
Parameter Criteria Assembly Power (Measured Normal Reaction Rate) +/-0.1 or 10%
Measured Incore Quadrant Power Tilt (Low Power) +/-4%
Measured Incore Quadrant Power Tilt (Full Power) +2 %
Core Reactivity Difference - 1000 pcm BOL HZP ITC +/- 2 pcm/°F Individual Control Bank Worth NA*
Total Control Bank Worth +/- 10%
- Not required when "The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement" has been performed; see letter from J. D. St. John, Westinghouse Electric Company, to M. L. Bellville, American Electric Power Nuclear Generation Group, "NRC Staff Interpretation of WCAP-16260-P-A," NF-AE-06-72, dated May 30, 2006.
Attachment I to AEP:NRC:8132 Page 5 Table 2 Flux Map Data: Assembly Powers Assembly Power Determination Map Date Power (Maximum Magnitude of Relative Error)
(%) Measured Predicted [Predicted - 10% of Acceptable Power Power Measuredi Predicted 121-01 11/14/06 23.99 0.428 0.397 0.031 0.040 YES 121-02 11/15/06 46.71 1.174 1.109 0.065 0.111 YES 121-03 11/17/06 87.15 0.347 0.330 0.017 0.033 YES 121-04 * * * * * *
- 121-06 11/18/06 97.43 0.353 0.332 0.021 0.033 YES 121-07 11/20/06 99.93 0.351 0.332 0.019 0.033 YES 121-08 11/22/06 99.95 0.352 0.331 0.021 0.033 YES 121-09 11/27/06 99.90 0.439 0.415 0.024 0.042 YES 121-10 12/11/06 99.85 0.352 0.329 0.023 0.033 YES 121-11 01/15/07 99.84 0.347 0.326 0.021 0.033 YES 121-12 02/12/07 99.87 0.343 0.325 0.018 0.033 YES 121-13 03/12/07 99.84 0.447 0.422 0.025 0.042 YES 121-14 04/16/07 99.91 0.345 0.327 0.018 0.033 YES 121-15 05/14/07 99.86 1.159 1.099 0.060 0.110 YES 121-16 * * * * *
- 121-17 06/11/07 99.89 0.353 0.334 0.019 0.033 YES 121-18 07/16/07 99.85 0.359 0.340 0.019 0.034 YES 121-19 08/13/07 99.95 0.367 0.346 0.021 0.035 YES 121-20 09/10/07 99.87 0.372 0.351 0.021 0.035 YES 121-21 10/15/07 99.89 0.381 0.359 0.022 0.036 YES 121-22 11/12/07 99.86 0.387 0.365 0.022 0.037 YES 121-23 12/10/07 99.88 0.396 0.370 0.026 0.037 YES Acceptance Criteria: +/- 0.1 or 10%.
- Flux maps 121-04, 121-05, and 121-16 were not full core flux maps. As a result, they do not constitute a valid measurement of the indicated parameter.
Attachment I to AEP:NRC:8132 Page 6 Table 3 Flux MaD Data: Core Tilt Criteria Top Half Incore Quadrant Power Tilt Map # Power(%) Maximum Tilt Minimum Tilt Acceptable 121-01 23.99 1.00695 0.99487 Yes 121-02 46.71 1.00437 0.99418 Yes 121-03 87.15 1.00608 0.99498 Yes 121-04 * * *
- 121-06 97.43 1.00445 0.99551 Yes 121-07 99.93 1.00504 0.99533 Yes 121-08 99.95 1.00402 0.99623 Yes 121-09 99.90 1.00486 0.99507 Yes 121-10 99.85 1.00560 0.99446 Yes 121-11 99.84 1.00345 0.99717 Yes 121-12 99.87 1.00202 0.99631 Yes 121-13 99.84 1.00186 0.99607 Yes 121-14 99.91 1.00158 0.99679 Yes 121-15 99.86 1.00152 0.99752 Yes 121416 * * *
- 121-17 99.89 1.00207 0.99579 Yes 121-18 99.85 1.00302 0.99546 Yes 121-19 99.95 1.00260 0.99579 Yes 121-20 99.87 1.00344 0.99345 Yes 121-21 99.89 1.00324 0.99275 Yes 121-22 99.86 1.00454 0.99531 Yes 121-23 99.88 1.00479 0.99183 Yes Acceptance Criteria: High power maps - maximum power tilt: 1.02; minimum power tilt: 0.98 Low power maps - maximum power tilt: 1.04; minimum power tilt: 0.96 Flux maps 121-04, 121-05, and 121-16 were not full core flux maps. As a result, they do not constitute a valid measurement of the indicated parameter.
to AEP:NRC:8132 Page 7 Table 3 (continued)
Flux Mat Data: Core Tilt Criteria Bottom Half Incore Quadrant Power Tilt Map # Power(,) Maximum Tilt Minimum Tilt Acceptable 121-01 23.99 1.00702 0.99307 Yes 121-02 46.71 1.00484 0.99327 Yes 121-03 87.15 1.00230 0.99608 Yes 121-04 * * *
- 121-06 97.43 1.00391 0.99654 Yes 121-07 99.93 1.00473 0.99521 Yes 121-08 99.95 1.00595 0.99393 Yes 121-09 99.90 1.00384 0.99463 Yes 121-10 99.85 1.00348 0.99456 Yes 121-11 99.84 1.00405 0.99364 Yes 121-12 99.87 1.00533 0.99565 Yes 121-13 99.84 1.00360 0.99500 Yes 121-14 99.91 1.00393 0.99566 Yes 121-15 99.86 1.00447 0.99690 Yes 121-16 * * *
- 121-17 99.89 1.00364 0.99710 Yes 121-18 99.85 1.00230 0.99826 Yes 121-19 99.95 1.00482 0.99725 Yes 121-20 99.87 1.00491 0.99582 Yes 121-21 99.89 1.00405 0.99581 Yes 121-22 99.86 1.00510 0.99595 Yes 121-23 99.88 1.00506 0.99496 Yes Acceptance Criteria: High power maps - maximum power tilt: 1.02; minimum power tilt: 0.98 Low power maps - maximum power tilt: 1.04; minimum power tilt: 0.96 Flux maps 121-04, 121-05, and 121-16 were not full core flux maps. As a result, they do not constitute a valid measurement of the indicated parameter.
Attachment I to AEP:NRC:8132 Page 8 Table 4 Core Reactivity Balance Data Unit I Cycle 21 Boron Letdown Curve Date Burnup Delta Acceptable (MWD/MTU) Reactivity (pcm)
November 25, 2006 365.66 -151.2 Yes December 2, 2006 629.55 -45.4 Yes December 9, 2006 894.82 98.7 Yes December 12, 2006 1,008.99 11.2 Yes December 18, 2006 1,238.04 77.4 Yes January 16, 2007 2,331.74 40.0 Yes February 13, 2007 3,388.69 83.8 Yes March 13, 2007 4,446.80 114.5 Yes April 17, 2007 5,767.02 70.9 Yes May 15, 2007 6,826.59 64.3 Yes June 12, 2007 7,880.74 106.6 Yes July 17, 2007 9,202.00 47.4 Yes August 14, 2007 10,259.90 17.5 Yes September 11, 2007 11,255.30 122.4 Yes October 16, 2007 12,577.30 121.3 Yes November 13, 2007 13,638.00 68.2 Yes December 11, 2007 14,694.50 17.8 Yes Acceptance Criteria: +/- 1000 pcm
Attachment I to AEP:NRC:8132 Page 9 Table 5 Low Power Physics Test Data (BOL, HZP): ITC Measured ITC Predicted ITC ITC Error (M-P) Acceptable (pcm/°F) (pcm/°F) (pcm/°F)
-2.48 -1.08 -1.41 Yes Acceptance Criteria: ITC error within +/- 2 pcm/°F Table 6 Low Power Physics Test Data (BOL. HZP): Total Control Bank Worth Measured Predicted Delta Worth Worth %Error Worth Worth (M-P) (M-P)xlOO% Acceptable (pcm) (pcm) (pcm) P Total Measured Worth 6955 7033 -78 -1.11% Yes AcceptanceCriteria: Total Measured Worth % error within +/-10%
Attachment 2 to AEP:NRC:8132 MOST NEGATIVE END OF LIFE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 1, CYCLE 21 to AEP:NRC:8132 Page 2 Most Negative End of Life Moderator Temperature Coefficient Limit Report for Donald C. Cook Unit 1, Cycle 21 To facilitate the review of this information, a list of acronyms used in this attachment is provided.
OF degrees Fahrenheit A delta
% percent AFD axial flux difference ARO all rods out BOL beginning of life CB Reactor Coolant System boron concentration CNP Donald C. Cook Nuclear Plant COLR Core Operating Limits Report EOL end of life HFP hot full power HZP hot zero power ITC isothermal temperature coefficient M measured MTC moderator temperature coefficient MTU metric tons of uranium MWD megawatt-day pcm percent-millirho ppm parts per million P predicted RCS Reactor Coolant System RTP reactor thermal power PURPOSE:
The purpose of this document is to present cycle-specific best estimate data for use in confirming the most negative EOL MTC limit in Technical Specification 3.1.3. This document also summarizes the methodology used for determining if a HFP 300 ppm MTC measurement is required.
PRECAUTIONS AND LIMITATIONS:
The EOL MTC exemption data presented in this document apply to CNP Unit 1 Cycle 21 only and may not be used for other operating cycles.
to AEP:NRC:8 132 Page 3 The following reference is applicable to this document:
WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March, 1997.
PROCEDURE:
All core performance benchmark criteria listed in Table 1 must be met for the current operating cycle. These criteria are confirmed from startup physics test results and routine HFP CB and incore flux map surveillances performed during the cycle.
If all core performance benchmark criteria are met, then the Revised Predicted MTC may be calculated per the algorithm given in Table 2. The required cycle-specific data are provided in Tables 3 and 4, and Figure 1. This methodology is also described in the referenced document. If all core performance benchmark criteria are met and the Revised Predicted MTC is less negative than COLR Limit 2.2.2.b, then a measurement is not required.
to AEP:NRC:8132 Page 4 Table 1 Benchmark Criteria for Application of the 300 ppm MTC Conditional Exemption Methodology Parameter Criteria Assembly Power (Measured Normial Reaction Rate) +0.1 or 10%
Measured Incore Quadrant Power Tilt (Low Power) +4%
Measured Incore Quadrant Power Tilt (Full Power) 22%
Core Reactivity Difference +/- 1000 pcrn BOL HZP ITC +/- 2 pcm/°F Individual Control Bank Worth Total Control Bank Worth +/- 10%
Not required when "The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement" has been performed; see letter from J. D. St. John, Westinghouse Electric Company, to M. L. Bellville, American Electric Power Nuclear Generation Group, "NRC Staff Interpretation of WCAP-16260-P-A," NF-AE-06-72, dated May 30, 2006.
to AEP:NRC:8132 Page .5 Table 2 Algorithm for Determinin2 the Revised Predicted Near-EOL 300 ppm MTC The Revised PredictedMTC = PredictedMTC + AFD Correction - 3 pcm/°F Where:
Predicted MTC is calculated from Figure 1 at the bumup corresponding to the measurement of 300 ppm at RTP conditions, AFD Correction is the more negative value of:
0 pcm/°F, (AAFD
AAFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300 ppm.
AFD Sensitivity = 0.05 pcm / 'F / %AAFD Predictive Correction is -3 pcm/°F, as included in the equation for the Revised Predicted MTC.
to AEP:NRC:8132 Page 6 Table 3 Worksheet for Calculatin2 the Revised Predicted Near-EOL 300 Dom MTC Unit: 1, Cycle 21 Date: 12/26/2007 Time: 6:27 Reference for Cycle-Specific MTC Data:
CNP, Unit I Cycle 21, COLR Part A. Predicted MTC A. 1 Cycle Average Burnup corresponding to the HFP ARO equilibrium xenon CB of 300 ppm. 15258 MWD/MTU A.2 Predicted HFP ARO MTC corresponding to burMup (A. 1) -20.83 pcm/°F Part B. AFD Correction B.1 Burnup of most recent HFP, equilibrium conditions incore flux map 14657.9 MWD/MTU B.2 Measured HFP AFD at burnup (B.1)
Reference incore flux map:
ID: 121-23 Date: 12/10/07 -2.38 % AFD B.3 Predicted HFP AFD at burnup (B.1) -2.23 % AFD B.4 MTC Sensitivity to AFD 0.05 pcm/IF/%AAFD B.5 AFD Correction, more negative of
{ 0 pcm/°F, B.4 *(B.2 - B.3)} -0.01 pcm/°F Part C. Revised Prediction C.1 Revised Prediction (A.2 + B.5 - 3 pcm/0 F) -23.84 pcm/0 F C.2 Surveillance Limit (COLR 2.2.2.b) -38.4 pcm/°F If C.1 is less negative than C.2, then the HFP 300 ppm MTC measurement is not required per Technical Specification Surveillance Requirement 3.1.3.2.
to AEP:NRC:8132 Page 7 Table 4 Data Collection and Calculations Required to Complete the Table 3 Worksheet of the Most Ne2ative Moderator Temperature Coefficient Limit Report Data at the 300 ppm Boron Point:
- RCS Boron at 300 ppm at 6:27 on 12/26/2007
- Burnup at 300 ppm: 15258 MWD/MTU (A.1)
- Predicted MTC: -20.83 pcm/0 F (A.2)
Data from Last Flux Map:
- Flux Map Number: 121-23 (B.2)
- Reactor Power (RP): 99.88% RTP
- Burnup: 14657.9 MWD/MTU (B.1)
- Measured Axial Flux Difference (MAFD): -2.38% (B.2)
MAFD = Measured Axial Offset
=-2.385%
= -2.38%
Predicted Axial Flux Difference (PAFD): -2.23% (B.3)
PAFD = Predicted Axial Offset
=-2.23%
= -2.23%
A AFD (MAFD-PAFD)
= (-2.38% - -2.23%)
= -0.15%
Determination of the Revised Predicted MTC AFD Sensitivity: 0.05 pcm/°F/ %AAFD (B.4)
AFD Correction: -0.01 pcm/°F (B.5) where: AFD Correction is the more negative of the following:
0 pcm/°F or (AAFD
- AFD Sensitivity) 0 pcm/nF or (-0.15%
- 0.05 pcm/°F/ %AAFD) 0 pcm/°F or -0.01 pcm/0 F
.*.-0.01 pcm/°F Revised Predicted MTC = Predicted MTC + AFD Correction -3 pcm/°F
= -20.83 pcm/°F + -0.01 pcm/°F -3 pcm/°F
= -23.84 pcm/°F (C.1) to AEP:N.RC:8132 Page 8 Figure 1 Unit 1 Cycle 21 Predicted HFP ARO 300 ppm MTC Versus Burnup
-Z .u I r--u q
-2.03E-04 '"
IL
.2 05E-04 j
-2.07E-04 I-*
-
.2.OgE.04 ,
E 0-NS.-
I
-2.11E-04
_______ ______ _______ _______ _______ _______ _______
-2.13E-04
-2.15E-04 --I -_L_1~~i_--
130 00 14000 15000 Cycle Bumup (MWDIMTU) 16000 17000 Burnup (MWDIMTU) MTC (Ak/kPF) 13000 -2.01 85E-4 14000 -2.0487E-4 15000 -2.0764E-4 16000 -2.1 035E-4 17000 -2.1293E-4