Letter Sequence Request |
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CAC:MF8894, TSTF-5, Relocate TS Parameters to Colr (Open) |
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MONTHYEARHNP-16-085, Cycle 21 Core Operating Limits Report, Revision 02016-10-19019 October 2016 Cycle 21 Core Operating Limits Report, Revision 0 Project stage: Request HNP-16-066, License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report2016-12-0202 December 2016 License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report Project stage: Request ML17109A2912017-04-19019 April 2017 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Final Request for Additional Information Concerning LAR to Adopt TSTF-339, TSTF-5 and Other Administrative Changes Project stage: RAI HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. Project stage: Response to RAI HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du Project stage: Response to RAI HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. Project stage: Supplement ML17332A6602017-12-21021 December 2017 Correction to Typographical Error Identified in License Amendment No. 161 Regarding Plant Procedure Number Removed from Technical Specifications (CAC No. MF8894; EPID L-2016-LLA-0023) Project stage: Other 2017-12-21
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Category:Letter type:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023 License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0081, License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications2023-02-0707 February 2023 License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-21-0213, License Amendment Request to Remove Limitation to Perform Certain Surveillance Requirements During Shutdown2021-09-23023 September 2021 License Amendment Request to Remove Limitation to Perform Certain Surveillance Requirements During Shutdown RA-21-0162, Supplement to License Amendment Request to Revise the 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative2021-06-0808 June 2021 Supplement to License Amendment Request to Revise the 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative RA-21-0112, License Amendment Request Regarding Administrative Change to Reflect Development of a Technical Requirements Manual2021-06-0707 June 2021 License Amendment Request Regarding Administrative Change to Reflect Development of a Technical Requirements Manual RA-21-0052, License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency2021-03-24024 March 2021 License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications2021-02-24024 February 2021 License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications RA-21-0061, Notification of NPDES Permit Renewal Application2021-02-24024 February 2021 Notification of NPDES Permit Renewal Application RA-21-0073, Notification of Permit Application for Industrial Stormwater Activities2021-02-24024 February 2021 Notification of Permit Application for Industrial Stormwater Activities RA-20-0311, License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process.2021-01-14014 January 2021 License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process. RA-20-0223, Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-07-27027 July 2020 Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-20-0148, Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications2020-05-27027 May 2020 Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications RA-19-0359, License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System2020-05-12012 May 2020 License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System RA-20-0012, License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices2020-03-12012 March 2020 License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices RA-20-0032, License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits2020-03-0606 March 2020 License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RA-19-0067, License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies2019-11-0808 November 2019 License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies RA-19-0001, License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-10-0707 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications2019-07-25025 July 2019 License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-19-0252, Supplemental Information for License Amendment Request to Modify Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-06-0606 June 2019 Supplemental Information for License Amendment Request to Modify Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type RA-19-0017, License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-04-10010 April 2019 License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type RA-19-0007, License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications2019-02-18018 February 2019 License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications RA-18-0206, Supplement for License Amendment Request to Self-Perform Core Reload Design and Safety Analyses2018-11-0606 November 2018 Supplement for License Amendment Request to Self-Perform Core Reload Design and Safety Analyses ML18230A8042018-08-18018 August 2018 Amendment No. 40 to Application for Construction Permit and Operating License RA-18-0072, License Amendment Request to Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints2018-07-30030 July 2018 License Amendment Request to Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications 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 HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-16-066, License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report2016-12-0202 December 2016 License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report ML16272A4152016-09-28028 September 2016 NPDES Permit Renewal and Prior Amendment RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process HNP-16-076, Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement2016-09-16016 September 2016 Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement HNP-16-068, Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement2016-08-26026 August 2016 Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement HNP-16-050, License Amendment Request to Relocate Technical Specifications Pertaining to the Explosive Gas and Storage Tank Radioactivity Monitoring Program2016-06-29029 June 2016 License Amendment Request to Relocate Technical Specifications Pertaining to the Explosive Gas and Storage Tank Radioactivity Monitoring Program HNP-16-026, License Amendment Request to Modify Diesel Fuel Oil Testing Surveillance Requirements2016-05-26026 May 2016 License Amendment Request to Modify Diesel Fuel Oil Testing Surveillance Requirements 2023-05-31
[Table view] Category:Technical Specification
MONTHYEARRA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023 License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0081, License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications2023-02-0707 February 2023 License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes RA-21-0213, License Amendment Request to Remove Limitation to Perform Certain Surveillance Requirements During Shutdown2021-09-23023 September 2021 License Amendment Request to Remove Limitation to Perform Certain Surveillance Requirements During Shutdown RA-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21116A2072021-05-0404 May 2021 Correction to Amendment No. 184 Regarding TSTF Traveler TSTF-505, Rev. 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications2021-02-24024 February 2021 License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations RA-20-0223, Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-07-27027 July 2020 Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-20-0148, Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications2020-05-27027 May 2020 Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications ML20147A0402020-05-15015 May 2020 Amendment 63 to Updated Final Safety Analysis Report, Administrative Procedure Non-Safety Related PLP-106 Technical Specification Equipment List Program, Revision 073 (Redacted) ML20147A0332020-05-15015 May 2020 Amendment 63 to Update Final Safety Analysis Report, Chapter 16, Preliminary Technical Specification RA-19-0359, License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System2020-05-12012 May 2020 License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System RA-20-0105, Supplement to License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies2020-04-16016 April 2020 Supplement to License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RA-19-0440, Supplement to License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications2019-11-21021 November 2019 Supplement to License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications RA-19-0067, License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies2019-11-0808 November 2019 License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies RA-19-0001, License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-10-0707 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications2019-07-25025 July 2019 License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-19-0017, License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-04-10010 April 2019 License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type RA-18-0204, Transmittal of Technical Specification Bases2018-11-12012 November 2018 Transmittal of Technical Specification Bases HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RA-17-0022, Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2017-10-19019 October 2017 Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du ML17066A2992017-03-28028 March 2017 2nd Correction to License Amendment No. 154 Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program HNP-16-066, License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report2016-12-0202 December 2016 License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process HNP-16-068, Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement2016-08-26026 August 2016 Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement HNP-16-064, Transmittal of Technical Specification Bases2016-08-10010 August 2016 Transmittal of Technical Specification Bases RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process RA-16-0005, Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 52016-02-0101 February 2016 Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 HNP-15-038, License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change2015-12-17017 December 2015 License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change HNP-15-086, License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement2015-10-29029 October 2015 License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement 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 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 2023-05-31
[Table view] Category:Bases Change
MONTHYEARRA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications2021-02-24024 February 2021 License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications ML20147A0332020-05-15015 May 2020 Amendment 63 to Update Final Safety Analysis Report, Chapter 16, Preliminary Technical Specification ML20147A0402020-05-15015 May 2020 Amendment 63 to Updated Final Safety Analysis Report, Administrative Procedure Non-Safety Related PLP-106 Technical Specification Equipment List Program, Revision 073 (Redacted) RA-19-0359, License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System2020-05-12012 May 2020 License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System RA-19-0440, Supplement to License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications2019-11-21021 November 2019 Supplement to License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications RA-19-0067, License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies2019-11-0808 November 2019 License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies RA-19-0001, License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-10-0707 October 2019 License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-19-0017, License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-04-10010 April 2019 License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type RA-18-0204, Transmittal of Technical Specification Bases2018-11-12012 November 2018 Transmittal of Technical Specification Bases HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-16-066, License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report2016-12-0202 December 2016 License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process HNP-16-068, Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement2016-08-26026 August 2016 Supplement to the License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement HNP-16-064, Transmittal of Technical Specification Bases2016-08-10010 August 2016 Transmittal of Technical Specification Bases RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process RA-16-0005, Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 52016-02-0101 February 2016 Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 HNP-15-038, License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change2015-12-17017 December 2015 License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change HNP-15-086, License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement2015-10-29029 October 2015 License Amendment Request for Temporary Changes to Technical Specifications for the 'A' Emergency Service Water Pump Replacement 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 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 HNP-15-046, Transmittal of Technical Specifications Bases2015-05-18018 May 2015 Transmittal of Technical Specifications Bases HNP-14-050, Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2014-04-24024 April 2014 Application to Revise Technical Specifications to Adopt TSTF-510-A, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process HNP-12-130, Transmittal of Technical Specifications Bases2012-12-0606 December 2012 Transmittal of Technical Specifications Bases HNP-11-097, Request for License Amendment - Measurement Uncertainty Recapture Power Uprate Supplemental Information2011-12-20020 December 2011 Request for License Amendment - Measurement Uncertainty Recapture Power Uprate Supplemental Information HNP-10-006, Request for License Amendment Proposed Revision to Technical Specification 3.6.2.2.a, Surveillance Requirement 4.6.2.2.d and Associated TS Bases to Incorporate an Expanded Range of Eductor Flow Rates2010-01-27027 January 2010 Request for License Amendment Proposed Revision to Technical Specification 3.6.2.2.a, Surveillance Requirement 4.6.2.2.d and Associated TS Bases to Incorporate an Expanded Range of Eductor Flow Rates ML0932002062009-11-16016 November 2009 Technical Specification Bases HNP-04-151, Technical Specification Bases Change: Undervoltage and Underfrequency - Reactor Coolant Pump Buses2004-10-19019 October 2004 Technical Specification Bases Change: Undervoltage and Underfrequency - Reactor Coolant Pump Buses HNP-03-015, TS Bases Change - Containment Isolation Valves2003-02-19019 February 2003 TS Bases Change - Containment Isolation Valves 2023-02-16
[Table view] |
Text
Tanya M. Hamilton Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 919.362.2502 10 CFR 50.90 Dec ember , 201 6 Serial: HNP-16-0 66 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50
-400/Renewed License No. NPF
-63
Subject:
License Amendment Request to Relocate Technical Specification Cycle
-Specific Parameters to the Core Operating Limits Report Ladies and Gentlemen:
In accordance with the provisions of 10 CFR 50.90, Duke Energy Progress, LLC (Duke Energy), hereby requests a revision to the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP).
The proposed license amendment would relocate selected figures and values from the TS to the Core Operating Limits Report (COLR), including TS Figure 2.1
-1 cited in TS 2.1.1, "Safety Limits - Reactor Core," selected portions of Table 2.2-1 Note 1 on T) cited in TS 2.2.1, "Limiting Safety System Settings - Reactor Trip System Instrumentation Setpoints,"
and Departure from Nuclea te Boiling (DNB) values cited in TS 3.2.5, "DNB Parameters
." These changes are consistent with the intent of Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Improved Standard Technical Specifications Change Traveler TSTF-339, "Relocate TS Parameters to COLR."
As a result of the above changes, TS 6.9.1.6, "Core Operating Limits Report,"
and associated TS Bases will be revised to reflect the above proposed changes. Furthermore, editorial changes are proposed throughout the HNP TS to remove all reference to plant procedure PLP-106, "Technical Specification Equipment List Program and Core Operating Limits Report,"
as it pertains to the COLR. Going forward, the COLR will no longer be contained in PLP-106, aligning with the Duke Energy fleet procedure governing core design and design deliverable documents.
This amendment request also proposes to delete requirements from HNP Administrative Control TS 6.7, Safety Limit Violation, that duplicate requirements found in regulation 10 CFR 50.36. The proposed changes are consistent with the intent of NRC
-approved TSTF
-5, "Delete Safety Limit Violation Notification Requirements," Revision 1.
The proposed changes have been evaluated in accordance with 10 CFR 50.91(a)(1) using criteria in 10 CFR 50.92(c), and it has been determined that the proposed changes involve no significant hazards consideration. Attachment 1 of this license amendment request provides Duke Energy's evaluation of the proposed changes
. Attachment 2 provides a copy of the
U.S. Nuclear Regulatory Commission Page 2 HNP-1 6-0 66 proposed TS change
- s. Attachment 3 provides a copy of the TS Bases markup based on the proposed changes.
Approval of the proposed license amendment is requested by December 1, 2017 , to support the planned refueling outage scheduled f or April 2018. The amendment shall be implemented within 90 days following approval
. In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated North Carolina State Official.
This document contains no new Regulatory Commitment
- s.
Please refer any questions regarding this submittal to Jeff Robertson, HNP Regulatory Affairs Manager, at (919) 362
-3137. I declare under penalty of perjury that the foregoing is true and correct
. Executed on December , 2016. Sincerely,
Tanya M. Hamilton
Attachments
- 1. Evaluation of the Proposed Change
- 2. Proposed Technical Specification Changes
- 3. Proposed Technical Specification Bases Changes cc: Mr. C. Jones, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N.C. D HS R Ms. M. Barillas, NRC Project Manager, HNP M s. C. Haney, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Serial HNP-1 6-0 66 Attachment 1
HNP-1 6-0 66 ATTACHMENT 1 EVALUATION OF THE PROPOSED CHANGE SHEARON HARRIS NUCLEAR POWER PLANT / UNI T 1 DOCKET NO. 50
-400 RENEWED LICENSE NUMBER NPF-063 U.S. Nuclear Regulatory Commission Page 1 of 6 Serial HNP-1 6-0 66 Attachment 1 Evaluation of the Proposed Change
Subject:
License Amendment Request to Relocate Technical Specification Cycle
-Specific Parameters to the Core Operating Limits Report 1.0
SUMMARY
DESCRIPTION In accordance with the provisions of 10 CFR 50.90, Duke Energy Progress, LLC (Duke Energy), hereby requests a revision to the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed license amendment would relocate selected figures and values from the TS to the Core Operating Limits Report (COLR), including TS Figure 2.1
-1 cited in TS 2.1.1, "Safety Limits
- Reactor Core," selected portions of Table 2.2
-1 Note 1 on Safety System Settings
- Reactor Trip System Instrumentation Setpoints," and Departure from Nucleate Boiling (DNB) values cited in TS 3.2.5, "DNB Parameters." These changes are consistent with the intent of Nuclear Regulatory Commission (NRC)
-approved Technical Specification Task Force (TSTF) Improved Standard Technical Specifications Change Traveler TSTF-339, "Relocate TS Parameters to COLR." As a result of the above changes, TS 6.9.1.6, "Core Operating Limits Report," and associated TS Bases will be revised to reflect the above proposed changes.
Furthermore, editorial changes are proposed throughout the HNP TS to remove all reference to plant procedure PLP
-106, "Technical Specification Equipment List Program and Core Operating Limits Report,"
as it pertains to the COLR. Going forward, the COLR will no longer be contained in PLP-106, aligning with the Duke Energy fleet procedure governing core design and design deliverable documents.
This amendment request also proposes to delete requirements from HNP Administrative Control TS 6.7, Safety Limit Violation, that duplicate requirements found in regulation 10 CFR 50.36. The proposed changes are consistent with the intent of NRC
-approved TS TF-5, "Delete Safety Limit Violation Notification Requirements," Revision 1.
2.0 DETAILED DESCRIPTION Duke Energy proposes changes to the HNP TS as follows:
TS Figure 2.1
-1 is deleted and relocated to the COLR
. TS Safety Limit 2.1.1 is revised to read: 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (Tavg) shall not exceed the limits specified in the COLR; and the following Safety Limits shall not be exceeded: a. The departure from nucleate boiling ratio (DNBR) shall be maintained
.
U.S. Nuclear Regulatory Commission Page 2 of 6 Serial HNP-1 6-0 66 Attachment 1
- b. The peak centerline temperature shall be maintained < [(2790 - 17.9 x P - where P is the maximum weight percent of Gadolinia (%) and B is the maximum pin burnup (GWD/MTU).
APPLICABILITY:
MODES 1 and 2.
ACTION: If Safety Limit 2.1.1 is violated, restore compliance and be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
in Table 2.1
-1 of TS 2.2.1 are deleted and relocated to the COLR
. TS 3.2.5 DNB
-related parameters are deleted and relocated to the COLR.
Administrative Control TS 6.9.1.6 is revised to reflect the above changes.
Editorial change s throughout TS to remove reference to HNP plant procedure PLP
-106 as it pertains to the COLR.
Administrative Control TS 6.7
.1 is deleted to remove duplicative reporting and restart requirements to those already contained in the regulations.
Relocation of cycle
-specific parameters from the TS to the COLR, a licensee
-controlled document subject to the requirements of TS 6.9.1.6 and the provisions of 10 CFR 50.59, would afford Duke Energy the flexibility to revise cycle
-specific parameters that are in accordance with NRC-approved methodologies without the need for license amendment
- s. The COLR is required to be submitted to the NRC for each reload cycle per TS 6.9.1.6, including any mid-cycle revisions or supplements to the NRC, unless otherwise approved by the Commission.
3.0 TECHNICAL EVALUATION
Basis for Proposed Change
NRC Generic Letter 88
-16, "Removal of Cycle
-Specific Parameter Limits From Technical Specifications," dated October 4, 1988, provides guidance to licensees for the removal of cycle
-dependent variables from the TS provided that these values are included in a COLR and are determined with NRC
-approved methodologies referenced in the TS.
Westinghouse Electric Company (Westinghouse) subsequently developed WCAP
-14483, "Generic Methodology for Expanding Core Operating Limits Report," describing how cycle-specific parameters may be relocated to the COLR. WCAP
-14483 was accepted for referencing by the NRC on January 19, 1999. The Safety Evaluation Report, contained in the January 19, 1999, NRC letter approving WCAP-14483-A, concluded that additional information contained in the TS may be relocated to the COLR. The limits on the parameters which are removed from the TS and added to the COLR must be developed and justified using NRC
-approved methodologies. All accident analyses, performed U.S. Nuclear Regulatory Commission Page 3 of 6 Serial HNP-1 6-0 66 Attachment 1 in accordance with these methodologies, must meet the applicable NRC
-approved limits of the safety analysis.
The removal of parameter limits from the TS and their addition to the COLR does not obviate the requirement to operate within these limits.
Furthermore, any changes to those limits must be performed in accordance with TS 6.9.1.6.3. If any of the applicable limits of the safety analysis are not met, prior NRC approval of the change is required, as is the case for a license amendment request.
For more routine modifications, where NRC
-approved methodologies and limits of the safety analysis remain applicable, the potentially burdensome and lengthy process of amending the TS may be avoided.
The requested changes are essentially administrative in nature; therefore, the required level of safety will be maintained.
Applicability of TSTF
-339 The following requested changes are based upon the NRC
-approved Westinghouse Owner's Group (WOG) Technical Specifications Task Force (TSTF)
-339, "Relocated TS Parameters to the COLR Consistent with WCAP
-14483," Revision 2, and Westinghouse WCAP
-14483-A: 1. Revis e TS 3.2.5 to relocate the pressurizer pressure, RCS average temperature (Tavg), and RCS total flow rate values to the COLR. The minimum limit for total flow based on that used in the reference safety analysis will be retained in the TS.
- 2. Revis e TS Table 2.2
-) values, and the breakpoint and slope 3. Revis e TS 2.1 Safety Limits, and the associated bases, to relocate Figure 2.1
-1 to the COLR and replace it with more specific requirements regarding the safety limits (i.e., the
fuel DNB design basis and the fuel centerline melt design basis). The NRC
-approved methodologies used to derive the parameters in the figure will be referenced in the Reporting Requirements section of the TS.
Duke Energy has reviewed TSTF
-339, Revision 2, and concluded that the TS changes as outlined in WCAP
-14483-A are applicable to HNP.
The above proposed changes are also consistent with Revision 4 of NUREG
-1431, "Standard Technical Specifications
- Westinghouse Plants" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12100A222), with minor format and structure differences due to HNP having not converted to Improved Technical Specifications (ITS), including the TS 2.1.1 numbering scheme (alphabetical versus numerical) and the use of TS 6.7.1 to identify Safety Limit Violation actions.
Editorial Changes related to PLP
-106 The HNP COLR is currently contained within plant procedure PLP-106 as an attachment.
To maintain consistency with the Duke Energy fleet procedure governing core design deliverable documents, the COLR will no longer be contained within PLP-106, but will rather be its own entity. As such, all reference to PLP
-106 in HNP TS pertaining to the COLR will be deleted. Reference to PLP
-106 in TS as it pertains to the Technical Specification Equipment List Program is not affected by this license amendment request, aside from those instances where the current procedure title is given
. The COLR is a licensee
-controlled document, subject to the requirements of TS 6.9.1.6 and the provisions of 10 CFR 50.59.
It will continue to be submitted to the NRC for each reload cycle, including any mid
-cycle revisions or supplements to the NRC, unless otherwise approved by the Commission
. Therefore, the deletion from TS of reference PLP-106 as it pertains to the COLR is U.S. Nuclear Regulatory Commission Page 4 of 6 Serial HNP-1 6-0 66 Attachment 1 an administrative change that aligns with the corresponding wording of NUREG
-1431, Volume 1, Revision 4
.
Applicability of TSTF
-5 The requested deletion of requirements from Administrative Control TS 6.7 , Safety Limit Violation, is based upon the NRC-approved TSTF
-5 , "Delete Safety Limit Violation Notification Requirements," Revision 1.
Duke Energy has reviewed TSTF
-5, Revision 1, and concluded that the intent of the TS changes to be applicable to HNP. The proposed change s delete administrative actions from the TS that duplicate the requirements to report safety limit violations and requirements to preclude restart after a safety limit violation without NRC approval. These requirements are also mor e restrictive than those already contained in the regulations in that they require the report to be submitted to the NRC within 14 days of the violation
. The 10 CFR 50.36 reporting requirements require the licensee to notify the NRC as required by 10 CFR 50.72 and submit a Licensee Event Report to the NRC as required by 10 CFR 50.73.
Therefore, appropriate reporting would be made to the NRC in accordance with the regulations in the event a TS safety limit was violated. In addition, 10 CFR 50.36 states that operations must not be resumed until authorized by the Commission. The removal of the duplicate reporting and restart requirements from TS is a simplification of the TS and a reduction in administrative burden to track duplicated requirements.
It also aligns with the requirements as presented in NUREG
-1431, Volume 1, Revision 4.
4.0 REGULATORY ANALYSIS
4.1 No Significant Hazards Consideration Determination
Pursuant to 10 CFR 50.90, Duke Energy Progress, LLC (Duke Energy)
, proposes a license amendment request (LAR) for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP)
Technical Specification s (TS). The proposed LAR relocates selected figures and values from the TS to the Core Operating Limits Report (COLR), including TS Figure 2.1
-1 cited in TS 2.1.1, "Safety Limits - Reactor Core," selected portions of Table 2.2
-- Reactor Trip System Instrumentation Setpoints," and Departure from Nucleate Boiling (DNB) values cited in TS 3.2.5, "DNB Parameters." These changes are consistent with the intent of Nuclear Regulatory Commission (NRC)
-approved Technical Specification Task Force (TSTF) Improved Standard Technical Specifications Change Traveler TSTF
-339, "Relocate TS Parameters to COLR." This LAR also proposes the deletion of duplicative notification, reporting, and restart requirements from the Administrative Controls section of TS, consistent with the intent of NRC-approved TSTF
-5, "Delete Safety Limit Violation Notification Requirements." Furthermore, editorial changes are proposed throughout the HNP TS to remove all reference to plant procedure PLP
-106, "Technical Specification Equipment List Program and Core Operating Limits Report," as it pertains to the COLR. As a result of the above changes, TS 6.9.1.6, "Core Operating Limits Report," and associated TS Bases will be revised to reflect the above proposed changes.
Duke Energy has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below.
U.S. Nuclear Regulatory Commission Page 5 of 6 Serial HNP-1 6-0 66 Attachment 1
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed changes are administrative in nature , facilitate improved content and presentation of Administrative controls, and alter only the format and location of cycle-specific parameter figures and limits from the TS to the COLR. This relocation does not result in the alteration of the design, material, or construction standards that were applicable prior to the change. The proposed changes will not result in modification of any system interface that would increase the likelihood of an accident since these events are independent of the proposed change.
The proposed amendment will not change, degrade, or prevent actions, or alter any assumptions previously made in evaluating the radiological consequences of an accident described in the Final Safety Analysis Report (FSAR).
Therefore, the proposed change s do not involve a significant increase in the probability or consequences of an accident previously evaluated
. 2. Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes do not involve any change to the configuration or method of operation of any plant equipment. Accordingly, no new failure modes have been defined for any plant system or component important to safety nor has any new limiting single failure been identified as a result of the proposed changes. Also, there will be no change in types or increase in the amounts of any effluents released offsite.
Therefore, the proposed change s do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety? The proposed changes do not involve a significant reduction in a margin of safety. Previously
-approved methodologies will continue to be used in determination of cycle
-specific core operating limits that are present in the COLR.
The proposed changes are administrative in nature and will not affect the plant design or system operating parameters. As such, there is no detrimental impact on any equipment design parameter and the plant will continue to be operated within prescribed limits.
Therefore, the proposed change s do not involve a significant reduction in a margin of safety. Based on the above, Duke Energy concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CF R 50.92, and, accordingly, a finding of "no significant hazards consideration" is justified.
U.S. Nuclear Regulatory Commission Page 6 of 6 Serial HNP-1 6-0 66 Attachment 1 4.2 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
Duke Energy has concluded that the proposed amendment meets the criteria provided by 10 CFR 51.22(c)(9) for categorical exclusion from the requirement for an Environmental Impact Statement. The proposed amendment do es not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
U.S. Nuclear Regulatory Commission Serial HNP-1 6-0 66 Attachment 2
HNP-16-0 66 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES SHEARON HARRIS NUCLEAR POWER PLANT / UNI T 1 DOCKET NO. 50
-400 RENEWED LICENSE NUMBER NPF-063 specifiedintheCOLR;andthefollowingSafetyLimitsshallnotbeexceeded:
ADD:INSERT1 ADD:INSERT2 INSERT 1 a. HTP DNB correlation. b. The peak centerline temperature shall be maintained < [ (2790 - - (GWD/MTU).
INSERT 2 If Safety Limit .
A DD:"ThisfigureisdeletedfromTechnicalSpecificationsandrelocated totheCOLR."
NoChangesmadetothispage
[*][*][*][*][*][*][*]ADD:"Thevaluesdenotedwith[*]arespecifiedintheCOLR."
ADD:"Thevaluesdenotedwith[*]arespecifiedintheCOLR."[*][*][*][*][*][*][*][*][*][*]
ADD:"Thevaluesdenotedwith[*]arespecifiedintheCOLR."[*][*][*][*]
ADD:"Thevaluesdenotedwith[*]arespecifiedintheCOLR."[*][*][*][*]
thelimitspecifiedintheCOLR,andthelimitspecifiedintheCOLR*,andandgreaterthanorequaltothelimitspecifiedintheCOLR.
SHEARON HARRIS - UNIT 1 3/4 3-36 Amendment No. 146 TABLE 3.3-4 (Continued) TABLE NOTATIONS
- Time constants utilized in the lead-lag controller for Steam Line Pressure--Low are 50 seconds and 5 seconds. CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values. ** The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate--High is 50 seconds. CHANNEL CALIBRATION shall ensure that this time constant is adjusted to this value.
- The indicated values are the effective, cumulative, rate-compensated pressure drops as
seen by the comparator. NOTE 1: If the as-found channel setpoint is outside its predefined as-found tolerance, the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. NOTE 2: The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Trip Setpoint in Table 3.3-4 (Nominal Trip Setpoint (NTSP))
at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine NTSPs and the as-found and the as-left tolerances are specified in EGR-NGGC-0153, "Engineering Instrument Setpoints."
The as-found and as-left tolerances are specified in PLP-106, "Technical Specification Equipment List Program and Core Operating Limits Report."
ADD:"Deleted."
ADD:INSERT3 INSERT3i.ReactorCoreSafetyLimitsFigureforSpecification2.1.1.j.Overtemperature TandOverpower TsetpointparametersandtimeconstantvaluesforSpecification2.2.1.k.ReactorCoolantSystempressure,temperature,andflowDeparturefromNucleateBoiling(DNB)limitsforSpecification3/4.2.5.
U.S. Nuclear Regulatory Commission Serial HNP-1 6-0 66 Attachment 3
HNP-16-0 66 ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES SHEARON HARRIS NUCLEAR POWER PLANT / UNI T 1 DOCKET NO. 50
-400 RENEWED LICENSE NUMBER NPF-063 TheDNBRsafetylimitforhighthermalperformancefuelis1.141fortheSiemensHTPcorrelation(Reference1).Insertnewparagraph1:Therestrictionsofthissafetylimitalsopreventfuelcenterlinemelting.FuelcenterlinemeltingoccurswhenthelocalLHR,orpowerpeaking,inaregionofthefuelishigh enoughtocausethefuelcenterlinetemperaturetoreachthemeltingpointofthefuel.
Expansionofthepelletuponcenterlinemeltingmaycausethepellettostressthe claddingtothepointoffailure,allowinganuncontrolledreleaseofactivitytothereactor
coolant. The fuel centerline temperature limit is a function of weight percent of Gadolinia and pin burnup as presented in Reference 2 and approved for use at HNP per Reference 3
.
Insertnewparagraph2:
The safety limit figure provided in the COLR shows the loci of points of Fraction of Rated Thermal power, RCS Pressure, and average temperature for which the minimum DNBR is
not less than the safety analyses limit, that fuel centerline temperature remains below
melting, that the average enthalpy in the hot leg is less than or equal to the enthalpy of
saturated liquid, and that the exit quality is within the limits defined by the DNBR correlation.
The reactor core safety limits are established to preclude violation of the following fuel design
criteria:
- a. There must be at least 95% probability at a 95% confidence level (the 95 / 95 DNB
criteria) that the hot fuel rod in the core does not experience DNB; and
- b. There must be at least a 95% probability at a 95% confidence level that the hot fuel
pellet in the core does not experience centerline fuel melting.
The reactor core safety limits are used to define the various RPS functions such that the
above criteria are satisfied during steady state operation and Condition I and II events. To
ensure that the RPS precludes the violation of the above criteria, additional criteria are
applied to the Over Temperature and Overpower T reactor trip functions. That is, it must be demonstrated that the average enthalpy in the hot leg is less than or equal to the saturation
enthalpy and that the core exit quality is within the limits defined by the DNBR correlation.
A ppropriate functioning of the RPS ensures that for variations in the THERMAL POWER, RCS Pressure, RCS average temperature, RCS flow rate, and I that the reactor core safety limits will be satisfied during steady state operation and Condition I and II events.
theCOLR.
InsertnewSection:
References1.EMF-92-153(P)(A),"HTP:DeparturefromNucleateBoilingCorrelationforHighThermalPerformanceFuel." 2. XN-NF-79-56(P)(A), Revision 1 , "Gadolinia Fuel Properties for LWR Safety Evaluation." 3. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity R esults."
adjustedformeasurementuncertaintythencomparedtotheanalyticallimitsspecifiedintheCOLR.
3/4.3 INSTRUMENTATION BASES SHEARON HARRIS - UNIT 1 B 3/4 3-2a Amendment No. 146 Note 2 requires that the as-left channel setting be reset to a value that is within the as-left tolerances about the Trip Setpoint in Table 3.3-4 or within as-left tolerances about a more conservative actual (field) setpoint. As-left channel settings outside the as-left tolerances of PLP-106 and the surveillance procedures cause the channel to be INOPERABLE. A tolerance is necessary because no device perfectly measures the process. Additionally, it is not possible to read and adjust a setting to an absolute value due to the readability and/or accuracy of the test instruments or the ability to adjust potentiometers. The as-left tolerance is considered in the setpoint calculation. Failure to set the actual plant trip setpoint to within as-left the tolerances of the NTSP or within as-left tolerances of a more conservative actual field setpoint would invalidate the assumptions in the setpoint calculation, because any subsequent instrument drift would not start from the expected as-left setpoint. The determination will consider whether the instrument is degraded or is capable of being reset and performing its specified safety function.
If the channel is determined to be functioning as required (i.e., the channel can be adjusted to within the as-left tolerance and is determined to be functioning normally based on the determination performed prior to returning the channel to service), then the channel is OPERABLE and can be restored to service. If the as-left instrument setting cannot be returned to a setting within the prescribed as-left tolerance band, the instrument would be declared inoperable. The methodologies for calculating the as-found tolerances and as-left tolerances about the Trip Setpoint or more conservative actual field setpoint are specified in EGR-NGGC-0153, "Engineering Instrument Setpoints," which is incorporated by reference into the FSAR. The actual field setpoint and the associated as-found and as-left tolerances are specified in PLP-106, "Technical Specification Equipment List Program and Core Operating Limits Report," the applicable section of which is incorporated by reference into the FSAR. Limiting Trip Setpoint (LTSP) is generic terminology for the setpoint value calculated by means of the setpoint methodology documented in EGR-NGGC-0153. HNP uses the plant-specific term NTSP in place of the generic term LTSP. The NTSP is the LTSP with margin added, and is always equal to or more conservative than the LTSP. The NTSP may use a setting value that is more conservative than the LTSP, but for Technical Specification compliance with 10 CFR 50.36, the plant-specific setpoint term NTSP is cited in Note 2. The NTSP meets the definition of a Limiting Safety System Setting per 10 CFR 50.36 and is a predetermined setting for a protective channel chosen to ensure that automatic protective actions will prevent exceeding Safety Limits during normal operation and design basis anticipated operational occurrences, and assist the Engineered Safety Features Actuation System in mitigating the consequences of accidents. The Allowable Value is the least conservative value of the as-found setpoint that the channel can have when tested, such that a channel is OPERABLE if the as-found setpoint is within the as-found tolerance and is conservative with respect to the Allowable Value during a CHANNEL CALIBRATION or CHANNEL OPERATIONAL TEST. As such, the Allowable Value differs from the NTSP by an amount greater than or equal to the expected instrument channel uncertainties, such as drift, during the surveillance interval. In this manner, the actual NTSP setting ensures that a Safety Limit is not exceeded at any given point of time as long as the channel has not drifted beyond expected tolerances during the surveillance interval. Although the channel is OPERABLE under these circumstances, the trip setpoint must be left adjusted to a value within the as-left tolerance band, in accordance with uncertainty assumptions stated in the setpoint methodology (as-left criteria), and confirmed to be operating within the statistical allowances of the uncertainty terms assigned (as-found criteria). Field setting is the term used for the actual setpoint implemented in the plant surveillance procedures, where margin has been added to the calculated field setting. The as-found and as-left tolerances apply to the field settings implemented in the surveillance procedures to confirm