Tech Spec Pages for Amendment No. 114 Addition of Methodology References to Core Operating Limits ReportML030910469 |
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Harris ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
03/28/2003 |
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NRC/NRR/DLPM |
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To: |
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TAC MB6226 |
Download: ML030910469 (3) |
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Category:Technical Specifications
MONTHYEARML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 ML21316A2482022-01-19019 January 2022 Issuance of Amendment No. 188, Regarding Revision of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML21035A1322021-03-16016 March 2021 Issuance of Amendment No. 182 Regarding Technical Specifications Related to Accident Monitoring Instrumentation, and Refueling Operations Instrumentation RA-20-0321, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Comple2020-11-11011 November 2020 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completi ML20183A4082020-07-0909 July 2020 Correction to Amendment No. 177 Regarding Elimination of Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications ML19225C0692019-09-19019 September 2019 Issuance of Amendment No. 175 Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints RA-18-0201, Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses2018-10-15015 October 2018 Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses ML17324B1292017-12-0606 December 2017 Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a TS Bases Control Program (CAC No. MD5802) - Corrected TS Pages ML17324B0482017-12-0606 December 2017 Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17074A6722017-05-25025 May 2017 Issuance of Amendment Relocation of Explosion Gas Monitoring Program Technical Specifications ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16155A1242016-07-25025 July 2016 Issuance of Amendment on Main Steam Safety Valve Lift Setting Tolerance, Nominal Reactor Trip Setpoint on Pressurizer Water Level, and Pressurizer Water Level Span in Technical Specifications RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015 Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. HNP-15-040, Transmittal of Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2015-08-18018 August 2015 Transmittal of Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML15163A0562015-06-30030 June 2015 Issuance of Amendment to Revised Technical Specifications Table 3.3-4, Engineered Safety Features Actuation System Instrumentation ML15075A2122014-11-30030 November 2014 Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data ML15075A2132014-11-30030 November 2014 Attachment 9 - DPC-NE-2005 Appendix I Harris Plant Specific Data RA-15-000, Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data2014-11-30030 November 2014 Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security HNP-12-116, License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values2012-11-29029 November 2012 License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values HNP-12-098, Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2012-10-22022 October 2012 Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process HNP-12-040, Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages2012-03-20020 March 2012 Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages ML12080A2172012-03-20020 March 2012 Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages HNP-11-067, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis2011-08-22022 August 2011 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis HNP-11-053, Transmittal of Technical Specifications Bases Revisions2011-05-0505 May 2011 Transmittal of Technical Specifications Bases Revisions ML1023707682010-08-16016 August 2010 Response to Second Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in Boiling Water Reactor Spent Fuel Pool Storage Racks ML0926402472009-10-14014 October 2009 Issuance of Amendment Regarding Lowering the Minimum Allowed Level of the Ultimate Heat Sink Main Reservoir ML0923203862009-08-25025 August 2009 Correction to Operating License and Technical Specification Page Issued with Amendment No. 131 Issued on July 2, 2009 ML0923102232009-08-25025 August 2009 Correction to Operating License and Technical Specification Page Issued with Amendment No. 131 Issued on July 2, 2009 ML0923102862009-08-20020 August 2009 Letter & Technical Specifications - Corrections to Technical Specification Pages Issued with Amendment No. 128 Issued on January 29, 2009 HNP-08-075, Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks2008-09-29029 September 2008 Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks ML0814301512008-06-12012 June 2008 Technical Specifications, Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program HNP-08-049, Request for License Amendment Technical Specification 3.7.5a2008-04-30030 April 2008 Request for License Amendment Technical Specification 3.7.5a ML0726003592007-09-19019 September 2007 Technical Specification Page Correction Issued with Amendment No. 125 Issued on July 23, 2007 HNP-07-127, Correction to Technical Specification Page in Amendment 1252007-09-13013 September 2007 Correction to Technical Specification Page in Amendment 125 ML0724707482007-08-31031 August 2007 Technical Specification, Issuance of Amendment to Revise Steam Generator Water Level Trip Setpoint Values HNP-07-005, Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.52007-06-15015 June 2007 Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.5 ML0622003982006-08-0202 August 2006 Request for License Amendment to Revise Values Associated with the Steam Generator Water Level Trip Setpoints ML0622004022006-08-0202 August 2006 Request for License Amendment HNP Calculation HNP-I/INST-1010 HNP-06-060, License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-05-23023 May 2006 License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0606803122006-03-0808 March 2006 Tech Spec Pages for Amendment 120 Regarding Temperature Limit for Dissolved Oxygen in Reactor Coolant System HNP-05-143, Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools2005-12-22022 December 2005 Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools HNP-05-002, Supplemental Information to the Proposed License Amendment Request to Technical Specification (TS) 6.8.4.k and TS Surveillance Requirement (SR) 4.6.1.6.12005-12-0909 December 2005 Supplemental Information to the Proposed License Amendment Request to Technical Specification (TS) 6.8.4.k and TS Surveillance Requirement (SR) 4.6.1.6.1 ML0525105022005-09-0101 September 2005 Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools ML0517401142005-06-21021 June 2005 TS for Shearon Harris, Units 1, Enclosure, Amd MC4794, Extend the Inspection Interval for Reactor Coolant Pump Flywheels HNP-05-062, Request for License Amendment Technical Specifications (TS) 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen2005-06-20020 June 2005 Request for License Amendment Technical Specifications (TS) 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen 2023-08-29
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ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
- d. XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Bowing," approved version as specified in the COLR. Rod (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
- e. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs,"
approved version as specified in the COLR.
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 -
Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Hot Channel Factor). Rise
- f. EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Applications," approved version as specified Model for PWR LBLOCA in the COLR.
(Methodology for Specification 3.2.1 - Axial Flux 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Difference, Nuclear Enthalpy I Rise Hot Channel Factor).
- 9. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," approved version as specified in the COLR.
(Methodology for Specification 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).
SHEARON HARRIS - UNIT 1 6-24a Amendment No. 114
ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
- h. ANF-88-054(P)(A), "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors Application of PDC-3 to H. B. Robinson Unit 2," approved and as specified in the COLR. version (Methodology for Specification 3.2.1 -
3.2.2 - Heat Flux Hot Channel Factor). Axial Flux Difference, and
- i. EMF-92-081(P)(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified COLR. in the (Methodology for Specification 3.1.1.3 - Moderator Coefficient, 3.1.3.5 - Shutdown Bank Insertion Temperature Control Bank Insertion Limits, 3.2.1 - Axial FluxLimits, 3.1.3.6 -
3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Difference, Rise Hot Channel Factor). Nuclear Enthalpy
- j. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," approved as specified in the COLR. version (Methodology for Specification 3.2.3 - Nuclear Enthalpy Channel Factor). Rise Hot
- k. XN-NF-82-49(P)(A), "Exxon Nuclear Company Evaluation PWR Small Break Model," approved version as specified Model EXEM in the COLR.
(Methodology for S ecification 3.2.1 - Axial Flux 3.2.2 - Heat Flux Hot Channel Factor, and Difference, Rise Hot Channel Factor). 3.2.3 - Nuclear Enthalpy
- 1. EMF-96-029(P)(A), "Reactor Analysis Systems for PWRs,"
version as specified in the COLR. approved (Methodology for Specification 3.1.1.2 - SHUTDOWN MARGIN - MODES 3, 4 and 5, 3 .1 .1.3 - Moderator Temperature Coefficient, Shutdown Bank Insertion Limits, 3.1.3.6 - Control 3.1.3.5 -
Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Bank Insertion Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Flux Hot and 3.9.1 - Boron Concentration). Channel Factor,
- m. EMF-2328(P)(A) PWR Small Break LOCA Evaluation Model, Based, approved version as specified in the COLR. S-RELAP5 (Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
SHEARON HARRIS - UNIT 1 6-24b Amendment No. 114 I
ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
- n. Mechanical Design Methodologies XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," approved version as specified in the COLR.
ANF-81-58(P)(A). "RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model," approved version as specified in the COLR.
XN-NF-82-06(P)(A), "Qualification of Exxon Nuclear Fuel for Extended Burnup," approved version as specified in the COLR.
ANF-88-133(P)(A), "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU." approved version as specified in the COLR.
XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results,"
approved version as specified in the COLR.
EMF-92-116(P)(A). "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.
(Methodologies for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
6.9.1.6.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient accident analysis limits) of the safety analysis are met. and 6.9.1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance cycle, to the NRC Document Control Desk, with copies to the for each reload Regional Administrator and Resident Inspector.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC in accordance with 10CFR50.4 within the time period specified for each report.
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SHEARON HARRIS - UNIT 1 6-24c Amendment No.114