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Category:Annual Operating Report
MONTHYEARAEP-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 AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report AEP-NRC-2021-50, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2021-08-25025 August 2021 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2021-27, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report AEP-NRC-2020-58, Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2020-08-26026 August 2020 Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2020-29, Submittal of Annual Radiological Environmental Operating Report2020-05-14014 May 2020 Submittal of Annual Radiological Environmental Operating Report AEP-NRC-2019-43, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2019-08-29029 August 2019 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2019-16, Annual Radiological Environmental Operating Report2019-04-29029 April 2019 Annual Radiological Environmental Operating Report AEP-NRC-2018-62, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2018-08-21021 August 2018 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes ML18123A3482018-04-30030 April 2018 Donald C. Cook, Units 1 and 2, Submittal of 2017 Annual Radioactive Effluent Release Report AEP-NRC-2018-35, Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual2018-04-30030 April 2018 Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual AEP-NRC-2017-47, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2017-08-30030 August 2017 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2016-73, Submittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2016-08-26026 August 2016 Submittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2013-32, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2013-08-30030 August 2013 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2012-69, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2012-08-31031 August 2012 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2012-22, Annual Radiological Environmental Operating Report for 20112012-05-0909 May 2012 Annual Radiological Environmental Operating Report for 2011 AEP-NRC-2011-32, Annual Radiological Environmental Operating Report2011-05-13013 May 2011 Annual Radiological Environmental Operating Report AEP-NRC-2011-27, Annual Radioactive Effluent Release Report, January 1, 2010, Through December 31, 20102011-04-29029 April 2011 Annual Radioactive Effluent Release Report, January 1, 2010, Through December 31, 2010 AEP-NRC-2010-37, Submittal of 2009 Annual Environmental Operating Report2010-04-30030 April 2010 Submittal of 2009 Annual Environmental Operating Report AEP-NRC-2009-54, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2009-08-28028 August 2009 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2009-29, Submittal of Annual Radioactive Effluent Release Report for 20082009-04-29029 April 2009 Submittal of Annual Radioactive Effluent Release Report for 2008 ML0913405232009-04-29029 April 2009 Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Cover Through Appendix Iv AEP-NRC-2009-32, Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Appendix V Through End2009-04-29029 April 2009 Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Appendix V Through End AEP-NRC-2008-27, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2008-08-29029 August 2008 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML0506302372005-02-25025 February 2005 2004 Annual Operating Report ML0425300392004-08-26026 August 2004 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML0407009102004-03-0101 March 2004 Transmittal of 2003 Annual Operating Report ML0313606492003-04-30030 April 2003 Annual Environmental Operating Report ML0312606062003-04-30030 April 2003 Annual Radiological Environmental Operating Report, Appendix D and E, Pages D-101 Through E-3 ML0312606482003-04-30030 April 2003 Annual Radiological Environmental Operating Report, Table of Contents Through Appendix D, Pages D-1 - 100 GNRO-2003/00026, South Mississippi Electric Power Association (Smep) Annual Report for 20022003-04-28028 April 2003 South Mississippi Electric Power Association (Smep) Annual Report for 2002 ML0307005302003-02-28028 February 2003 Annual Operating Report ML0214202912002-04-25025 April 2002 Part a - Donald C. Cook Nuclear Plant, Units 1 & 2 - Annual Environmental Operating Report ML0213002702002-04-25025 April 2002 Part B - Donald C. Cook Nuclear Plant, Units 1 & 2 - Annual Environmental Operating Report ML0206001322002-02-26026 February 2002 Annual Operating Report for Donald C. Cook Nuclear Plant, Units 1 & 2 for 2001 2023-08-29
[Table view] 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
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INDIANA Indiana Michigan PowerMICHIGAN Cook Nuclear PlantHWER One Cook PlaceBridgman, M1 49106A unit of American Electric Power India naMichigan Power.com August 30, 2013 AEP-NRC-2013-32 10 CFR 50.46Docket Nos.: 50-31550-316U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2ANNUAL REPORT OF LOSS-OF-COOLANT ACCIDENTEVALUATION MODEL CHANGES
References:
- 1. Letter from J. P. Gebbie, Indiana Michigan Power Company (I&M), to U. S.Nuclear Regulatory Commission (NRC), "Response to Information RequestPursuant to 10 CFR 50.54(f)
Related to the Estimated Effect on Peak CladdingTemperature Resulting from Thermal Conductivity Degradation on theWestinghouse-Furnished Realistic Emergency Core Cooling System Evaluation,"
AEP-NRC-2012-13, dated March 19, 2012, (ADAMS Accession No.ML 12088A104).
- 2. Letter from M. H. Carlson, I&M, to NRC, "Donald C. Cook Nuclear Plant Units 1and 2 Response to Request for Information 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with ThermalConductivity Degradation,"
dated June 11, 2012, (ADAMS Accession No. ML12173A025).
- 3. Letter from P. S. Tam, NRC, to Lawrence J. Weber, I&M, "D. C. Cook NuclearPlant (DCCNP),
Units 1 and 2 -Closeout of Information Request Pursuant to50.54(f)
Related to the Estimated Effect on Peak Cladding Temperature Resulting from Thermal Conductivity Degradation in the Westinghouse-Furnished Realistic Emergency Core Cooling System Evaluation,"
dated April 2, 2012,(ADAMS Accession No. ML 12088A376).
- 4. Letter from T. J. Wengert, NRC, to L. J. Weber, I&M, "Donald C. Cook NuclearPlant, Units 1 and 2 -Evaluation of Report concerning Significant Emergency Core Cooling System Evaluation Model Error Related to Nuclear Fuel ThermalConductivity Degradation (TAC NOS. ME8322 and ME8323),"
datedMarch 7, 2013, (ADAMS Accession No. ML1 3077A1 37).
U.S. Nuclear Regulatory Commission AEP-NRC-2013-32 Page 2Pursuant to 10 CFR 50.46, Indiana Michigan Power Company, the licensee forDonald C. Cook Nuclear Plant (CNP), is transmitting an annual report of loss-of-coolant accident (LOCA) evaluation model changes affecting the peak cladding temperature (PCT) forCNP Unit 1 and Unit 2. CNP is providing, as an enclosure to this letter, the Unit 1 and Unit 2Large Break and Small Break LOCA Analyses-of-Record PCT values and error assessments forcalendar year 2012.The impacts to Large Break LOCA PCT due to fuel pellet thermal conductivity degradation werepreviously reported to the Nuclear Regulatory Commission (NRC) in Reference 1 andsupplemented by Reference
- 2. NRC staff review and acceptance of the impact to PCT due tofuel pellet thermal conductivity degradation was documented in Reference
- 4. These impacts tothe LOCA analyses are discussed in the enclosure, and are included on the PCT reporting sheets.Several other changes were made to the Large Break LOCA and Small Break LOCA evaluation models during the reporting period. The specific details of these changes were evaluated ashaving no impact on the calculated PCTs. Since there was no PCT impact due to thesechanges, they are not included in the PCT reporting sheets.There are no new or revised commitments in this letter. Should you have any questions, pleasecontact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Joel P. GebbieSite Vice President DMB/kmh
Enclosure:
Donald C. Cook Nuclear Plant Units 1 and 2, Large and Small BreakLoss-of-Coolant Accident Peak Clad Temperature Summaryc: J. T. King, MPSCS. M. Krawec, AEP Ft. Wayne, w/o enclosures MDEQ -RMD/RPSNRC Resident Inspector C. D. Pederson, NRC Region IIIT. J. Wengert, NRC Washington, DC ENCLOSURE TO AEP-NRC-2013-32 DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2LARGE AND SMALL BREAK LOSS-OF-COOLANT ACCIDENTPEAK CLAD TEMPERATURE SUMMARYAbbreviations:
CNP Donald C. Cook Nuclear PlantOF degrees Fahrenheit ECCS emergency core cooling systemEM evaluation methodology FdH nuclear enthalpy rise hot channel factorFQ heat flux hot channel factorHHSI high head safety injection (Safety Injection System at CNP)I&M Indiana Michigan Power CompanyLOCA loss of coolant accidentMWt megawatts
-thermalNRC Nuclear Regulatory Commission PCT peak cladding temperature RHR Residual Heat RemovalSGTP steam generator tube pluggingTCD thermal conductivity degradation Summary:By letter dated March 19, 2012, (ADAMS Accession No. ML12088A1 04), and supplemented byletter dated June 11, 2012, (ADAMS Accession No. ML12173A025),
I&M, the licensee for CNPUnits 1 and 2, submitted a report describing the impact of fuel pellet TCD on the Large BreakLOCA ECCS evaluation model, and an estimate of the effect on the predicted PCT for CNPUnits 1 and 2. This report was submitted pursuant to Title 10 of the Code of FederalRegulations (10 CFR) Part 50, Section 50.46, Paragraph (a)(3), and referred to a letter fromWestinghouse Electric Company dated March 7, 2012 (ADAMS Accession No. ML12072A035).
The report was subsequently found to be acceptable by NRC letter dated March 7, 2013(ADAMS Accession No. ML1 3077A1 37).A new small break LOCA analysis of record was implemented for CNP Unit 1 in 2012. Therevised small break LOCA was provided to the NRC by letter dated August 31, 2012 (ADAMSAccession No. ML12256A685).
The enclosure to the letter provides a report of the revisedanalysis.
The results of the revised small break LOCA analysis conform to the emergency corecooling system acceptance criteria of 10 CFR 50.46. The calculated peak cladding temperature of 17250F is below the 10 CFR 50.46 limit of 22001F.The following pages summarize the impact of TCD, peaking factor burndown, and plantmodification evaluations on the CNP Units 1 and 2 Large Break LOCA analyses of record. Inaddition, pages are included that summarize the small break LOCA PCT analyses of record forCNP Units 1 and 2.
Enclosure to AEP-NRC-2013-32 Page 2CNP UNIT 1LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large BreakEvaluation Model: ASTRUM (2004)FQ= 2.15 FdH = 1.55 SGTP = 10%(a) Break Size: SplitAnalysis Date: November 20, 2007LICENSING BASISAnalysis-of-Record MARGIN ALLOCATIONS (Delta PCT)A. PREVIOUS 10 CFR 50.46 ASSESSMENTS
- 1. NonePCT = 2128°FB.C.D.PLANNED PLANT MODIFICATION EVALUATIONS NEW 10 CFR 50.46 ASSESSMENTS OTHER0OF-381 °F(a)3840F(a)0OFPCT = 2131°FLICENSING BASIS PCT + MARGIN ALLOCATIONS Notes:a. These assessments are coupled via an evaluation of burnup effects which includethermal conductivity degradation, peaking factor burndown and design input changes(e.g., reduction in the maximum allowed steam generator tube plugging from 10% to 2%and maximum FdH reduced to 1.545). Evaluation details provided in a letter datedMarch 19, 2012, (ADAMS Accession No. ML12088A104),
and supplemented by letterdated June 11, 2012, (ADAMS Accession No. ML12173A025),
and subsequently foundacceptable by NRC letter dated March 7, 2013 (ADAMS Accession No. ML1 3077A1 37).
Enclosure to AEP-NRC-2013-32 Page 3CNP UNIT 1LOCA Peak Clad Temperature Summary for Appendix K Small BreakEvaluation Model: NOTRUMPFQ=2.32 FdH=1.55 SGTP=10%
3.25 inch cold leg breakAnalysis Date: January 6, 2012Notes: 3304 MWt (plus 0.34% calorimetric uncertainty)
LICENSING BASISAnalysis-of-Record PCT = 1725°FMARGIN ALLOCATIONS (Delta PCT)A. PREVIOUS 10 CFR 50.46 ASSESSMENTS
- 1. NoneB. PLANNED PLANT MODIFICATION EVALUATIONS C. NEW 10 CFR 50.46 ASSESSMENTS D. OTHERLICENSING BASIS PCT + MARGIN ALLOCATIONS 0OF0OF0OF0OFPCT = 1725°F Enclosure to AEP-NRC-2013-32 Page 4CNP UNIT 2LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large BreakEvaluation Model: ASTRUM (2004)FQ = 2.335 FdH = 1.644 SGTP = 10%(a) Break Size: SplitAnalysis Date: February 9, 2009LICENSING BASISAnalysis-of-Record PCT = 2107°FMARGIN ALLOCATIONS (Delta PCT)A. PREVIOUS 10 CFR 50.46 ASSESSMENTS
- 1. NoneB.PLANNED PLANT MODIFICATION EVALUATIONS C. NEW 10 CFR 50.46 ASSESSMENTS D. OTHERLICENSING BASIS PCT + MARGIN ALLOCATIONS 0OF-2390F(a)730F(a)0OFPCT = 19410FNotes:a. These assessments are coupled via an evaluation of burnup effects which includethermal conductivity degradation, peaking factor burndown and design input changes(e.g., reduction in the maximum allowed steam generator tube plugging from 10% to 1%and maximum FdH reduced to 1.61). Evaluation details provided in a letter datedMarch 19, 2012, (ADAMS Accession No. ML12088A104),
and supplemented by letterdated June 11, 2012, (ADAMS Accession No. ML12173A025),
and subsequently foundacceptable by NRC letter dated March 7, 2013 (ADAMS Accession No. ML13077A137).
Enclosure to AEP-NRC-2013-32 Page 5CNP UNIT 2LOCA Peak Clad Temperature Summary for Appendix K Small BreakEvaluation Model: NOTRUMPFQ= 2.32 FdH= 1.62 SGTP = 10% 4 inch cold leg breakAnalysis Date: April 25, 2011Notes: 3600 MWtLICENSING BASISAnalysis-of-Record PCT = 1274°F (a)MARGIN ALLOCATIONS (Delta PCT)A. PREVIOUS 10 CFR 50.46 ASSESSMENTS
- 1. None 0°FB. PLANNED PLANT MODIFICATION EVALUATIONS 0OFC. NEW 10 CFR 50.46 ASSESSMENTS 0OFD. OTHER 0°FLICENSING BASIS PCT + MARGIN ALLOCATIONS PCT = 1274°FNotes:a. The 3600 MWt power level used in this analysis bounds the Unit 2 3468 MWt steadystate power limit in the operating license.