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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-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable RA-23-0244, Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process2024-03-20020 March 2024 Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process RA-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-21-0073, Notification of Permit Application for Industrial Stormwater Activities2021-02-24024 February 2021 Notification of Permit Application for Industrial Stormwater Activities RA-21-0061, Notification of NPDES Permit Renewal Application2021-02-24024 February 2021 Notification of NPDES Permit Renewal Application 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-20-0311, 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 2024-05-23
[Table view] Category:Technical Specification
MONTHYEARRA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable RA-23-0244, Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process2024-03-20020 March 2024 Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process RA-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 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 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 2024-05-23
[Table view] Category:Amendment
MONTHYEARRA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, “Add Action for More than One (D)Rpi Inoperable RA-23-0244, Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process2024-03-20020 March 2024 Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, “Accumulators,” Using the Consolidated Line Item Improvement Process RA-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-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-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-20-0207, 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 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-19-0001, 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-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 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-18-039, 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-14-119, Response to Request for Additional Information 2 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints2014-11-13013 November 2014 Response to Request for Additional Information #2 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints HNP-11-038, License Amendment Request for Extension of Refueling Water Storage Tank Allowed Outage Time2011-09-0202 September 2011 License Amendment Request for Extension of Refueling Water Storage Tank Allowed Outage Time HNP-09-016, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors2009-02-26026 February 2009 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 HNP-08-019, Supplement to Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.52008-03-0606 March 2008 Supplement to Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.5 HNP-07-094, Request for License Amendment to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process2008-01-0404 January 2008 Request for License Amendment to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process ML0720705472007-07-23023 July 2007 Technical Specification 6.12, High Radiation Area (TAC MD38895) HNP-07-040, Request for License Amendment to Use Other Containment Sump Water Level Instruments2007-04-30030 April 2007 Request for License Amendment to Use Other Containment Sump Water Level Instruments ML0429506192004-10-15015 October 2004 Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process HNP-04-071, Request for License Amendment Technical Specification Surveillance Requirements (SR) 4.0.5.A and Associated Bases2004-05-0505 May 2004 Request for License Amendment Technical Specification Surveillance Requirements (SR) 4.0.5.A and Associated Bases HNP-04-008, License Amendment Request: Steam Generator Water Level Instrumentation Usage, Technical Specifications 4.4.1.3.2 and 3.4.1.4.1.b, and Administrative Update to the Index2004-02-0404 February 2004 License Amendment Request: Steam Generator Water Level Instrumentation Usage, Technical Specifications 4.4.1.3.2 and 3.4.1.4.1.b, and Administrative Update to the Index HNP-03-116, Request for License Amendment Regarding Technical Specification 4.4.5.3a2003-12-0808 December 2003 Request for License Amendment Regarding Technical Specification 4.4.5.3a HNP-02-113, Request for License Amendment, Response Time Testing Elimination2002-08-30030 August 2002 Request for License Amendment, Response Time Testing Elimination HNP-02-088, Request for License Amendment, Technical Specifications 3/4.8.1.1 and 3/4.8.1.22002-07-0808 July 2002 Request for License Amendment, Technical Specifications 3/4.8.1.1 and 3/4.8.1.2 2024-05-23
[Table view] |
Text
Co Progress Energy MAY 0 5 2004 Serial: HNP-04-071 U.S. Nuclear Regulatory Commission 10 CFR 50.90 ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS (SR) 4.0.5.A AND ASSOCIATED BASES Ladies and Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power and Light Company doing business as Progress Energy Carolinas, Inc., requests a license amendment for the Harris Nuclear Plant (HNP) to Technical Specification Surveillance Requirements (SR) 4.0.5.a, "Surveillance Requirements for inservice inspection and testing of American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components." Specifically, the proposed change adds a reference to the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) in Technical Specification SR 4.0.5.a and the associated Bases. HNP is submitting the proposed change to update the Technical Specifications to allow use of the ASME OM Code for visual examination of snubbers.
In addition to the license amendment, HNP requests approval, pursuant to 10 CFR 50.55a(g)(4)(iv), to use the 1995 Edition with 1996 Addenda of the ASME OM Code for the visual examination of snubbers. HNP will use all related requirements of the respective edition and addenda in the ASME OM Code as required by 10 CFR 50.55a(g)(4)(iv) for the visual examination of snubbers.
With respect to this proposed change, HNP has reviewed the proposed license amendment against the criteria of 10 CFR 51.22 for environmental considerations. The proposed change does not involve a significant hazards consideration. In addition, there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure. Based on the foregoing, HNP concludes that the proposed change to the Technical Specifications meets the eligibility criteria for categorical exclusion delineated in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment or environmental impact statement is required for approval of this application.
Attachment 1 provides the description, background, and technical analysis for the proposed change to the Technical Specifications.
Progress Energy Carolinas, Inc.
Harris Nuclear Plant P.O. Box 165 New Hill, NC 27562 0r-
HNP-04-071 Page 2 details, in accordance with 10 CFR 50.91(a), the basis for HNP's determination that the proposed change to the Technical Specifications does not involve a significant hazards consideration. provides the proposed Technical Specifications change. provides the revised Technical Specifications page. provides the proposed Technical Specifications Bases change (for information).
In accordance with 10 CFR 50.91(b), HNP is providing the State of North Carolina with a copy of the proposed license amendment.
HNP requests that the proposed amendment be issued prior to September 1, 2004 to support planning for HNP RFO-12 which is scheduled for October 16, 2004.
Please refer any question regarding this submittal to Mr. John Caves at (919) 362-3137.
I declare, under penalty of perjury, that the attached information is true and correct (Executed on MAY 0 5 2004 )
Siery, t.J. ln I Director - Site Operations Harris Nuclear Plant RJD/jpy Attachments:
- 1. Description, Background, and Technical Analysis
- 2. 10 CFR 50.92 Evaluation
- 3. Proposed Technical Specifications Change
- 4. Revised Technical Specifications Page
- 5. Proposed Technical Specifications Bases Change c:
Mr. R. A. Musser, NRC Senior Resident Inspector Ms. B. 0. Hall, N.C. DENR Section Chief Mr. C. P. Patel, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator
Attachment 1 to SERIAL: HNP-04-071 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS (SR) 4.0.5.A AND ASSOCIATED BASES DESCRIPTION, BACKGROUND. AND TECHNICAL ANALYSIS Introduction The proposed License Amendment Request revises Technical Specification Surveillance Requirements (SR) 4.0.5.a and the associated Technical Specification Bases. These changes are necessary to reference the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code).
Description This letter is a request to amend the Harris Nuclear Plant (HNP) Technical Specifications. The proposed change revises Technical Specification SR 4.0.5.a, Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components, to include a reference to the ASME OM Code in addition to Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g).
The proposed change to Technical Specification SR 4.0.5.a will add the words "and/or the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code)" to the fourth line between the words "Code" and "applicable."
Currently, Technical Specification SR 4.0.5.a states:
"Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g), except where specific written relief had been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i);"
The proposed change is to add a reference to Technical Specification SR 4.0.5.a as follows:
"Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and/or the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g), except where specific written relief had been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i);"
Page Al-I of 3
Attachment 1 to SERIAL: HNP-04-071
Background
Harris Nuclear Plant Technical Specification SR 4.0.5 describesSection XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as the Surveillance Requirements for inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves.
HNP requests approval of the proposed change to support adoption of the 1995 Edition with 1996 Addenda of the ASME OM Code, Subsection ISTD, for the visual examination of snubbers, which is the applicable Code of ASME OM Code Case OMN-13. HNP proposes to adopt this Code Case for the Fall 2004 refueling outage (RFO-12). This Code Case was recently approved (June 2003) in Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code.
Technical Analysis The purpose of augmented snubber visual examination program is to demonstrate that each snubber is operable. Inservice inspections shall be visual examinations performed for impaired functional ability due to physical damage, leakage, corrosion, or degradation from environmental exposures or operating conditions. Visual examinations verify that (1) there are no visible indications of damage that impair operability, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers that are found unacceptable may be tested and test results which satisfy the operability test criteria may be used to recategorize the snubber(s) as acceptable, provided the testing can resolve the unacceptable condition.
At HNP, prior to startup in May 1987, within 10 months of startup, and during each outage for the first three fuel cycles, 100% of the snubbers were inspected. Prior to RFO-4, an alternate examination schedule per NRC Generic Letter 90-09 was incorporated into the FSAR, PLP-106 , and procedures that extended snubber visual examination intervals to every other outage, based on a limited number of visual examination failures. The entire population of snubbers was subsequently inspected every other outage (RFOs-5, 7, and 9). Starting in RFO-10, the examination population was divided to approximately one-half each outage to evenly distribute the snubber visual examinations per outage.
The examination results for approximately the past 10 years have resulted in only one visual examination failure (due to personnel stepping on a small mechanical snubber during RFO-9).
The examination results are as follows:
RFO-5 0 visual failures RFO-7 0 visual failures RFO-9 1 visual failure RFO-10 0 visual failures Page A1-2 of 3
Attachment 1 to SERIAL: HNP-04-071 Technical Analysis (continued)
The current, 2nd interval HNP ISI program was developed in accordance with the 1989 Edition (no Addenda) of ASME Boiler and Pressure Vessel Code,Section XI. Subarticles IWF-1200 and IWF-5300 require the examination and testing of snubbers per the first Addenda of ASME /
ANSI OM-1987, Part 4 (published in 1988), generally referred to as "OM-4." HNP Relief Request 2RG-008, Revision 1, was authorized by the NRC by letter dated June 18, 1999. This relief performs snubber testing and examination in accordance with Technical Specification 3/4.7.8 in lieu of the ASME OM-4 Code.
The 1995 Edition with 1996 Addenda of the ASME OM Code, Subsection ISTD, is the applicable Code per Code Case OMN-13. HNP plans to utilize the 1995 Edition with 1996 Addenda of the ASME OM Code for snubber visual examinations as an approved alternative to the snubber visual examination requirements of the 1989 Edition of ASME Section XI and as modified by HNP Relief Request 2RG-008, Revision 1. Code Case OMN-13 has been evaluated and approved by the NRC in Reg Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code (June 2003).
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Conclusion:==
HNP has concluded, based on the considerations discussed above, that: (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.
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Attachment 2 to SERIAL: HNP-04-071 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS (SR) 4.0.5.A AND ASSOCIATED BASES 10 CFR 50.92 NO SIGNIFICANT HAZARDS EVALUATION A written evaluation of the significant hazards consideration of a proposed license amendment is required by 10 CFR 50.92. Harris Nuclear Plant (HNP) has evaluated the proposed amendment and determined that it involves no significant hazards consideration.
According to 10 CFR 50.92, a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3. Involve a significant reduction in a margin of safety The basis for this determination is presented below.
DETERMINATION OF SIGNIFICANT HAZARDS FOR THE PROPOSED CHANGE The proposed License Amendment Request revises Technical Specification Surveillance Requirements (SR) 4.0.5.a and the associated Technical Specification Bases. These changes are necessary to reference the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code).
In accordance with 10 CFR 50.92, HNP has reviewed the attached proposed change and has concluded that it does not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed change does not involve a SHC is as follows:
- 1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes to the Technical Specification SR 4.0.5.a and the associated Bases are requested to add a reference to the ASME OM Code and applicable Addenda for inservice inspection of ASME Code Class 1, 2, and 3 components.
The existing Technical Specifications requires inservice inspection of ASME Code Class 1, 2, and 3, components and inservice testing of ASME Code Class 1, 2 and 3 pumps and Page A2-1 of 3
Attachment 2 to SERIAL: HNP-04-071 valves as required by 10 CFR 50.55a. The purposes of the inservice inspection and inservice testing programs are to assess the operational readiness of pumps and valves, to detect degradation that might affect component operability, and to maintain safety margins with provisions for increased surveillance and corrective action. 10 CFR 50.55a defines the requirements for applying industry codes and standards to each licensed nuclear power facility. The initial HNP ISI program was developed in accordance with NRC regulations (10 CFR 50.55a(g)(4)(i)) to comply with the 1983 Edition of the ASME Boiler and Pressure Vessel Code, including Addenda through the Summer of 1983 and is reflected in the existing Technical Specifications and associated Bases sections.
The current, second ten-year interval HNP ISI program was developed in accordance with the 1989 Edition (no Addenda) of ASME Boiler and Pressure Vessel Code,Section XI. Subarticles IWF-1200 and IWF-5300 require the examination and testing of snubbers per the first Addenda of ASME / ANSI OM-1987, Part 4 (published in 1988),
generally referred to as "OM-4." HNP Relief Request 2RG-008, Revision 1, grants HNP the ability to retain the snubber testing and examination program in Technical Specification 3/4.7.8.
The 1995 Edition with 1996 Addenda of the ASME OM Code, Subsection ISTD, is the applicable Code per Code Case OMN-13. HNP plans to utilize the 1995 Edition with 1996 Addenda of the ASME OM Code for snubber visual examinations as an approved alternative to the snubber visual examination requirements of the 1989 Edition of ASME Section XI and as modified by HNP Relief Request 2RG-008, Revision 1. Code Case OMN-13 has been evaluated and approved by the NRC in Reg Guide 1.192.
The proposed change to Technical Specification SR 4.0.5.a is also administrative in nature. The proposed changes comply with approved codes and standards. As a result, there will be no affect on plant safety.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated.
The changes to Technical Specification SR 4.0.5.a and Bases section 4.0.5 and are being proposed to reference the ASME OM Code in addition to Section XI of the ASME Boiler and Pressure Vessel Code. The proposed changes are administrative in nature and do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configuration of the facility.
The use of the ASME OM Code 1995 Edition with 1996 Addenda, Subsection ISTD, with incorporation of the snubber visual examination frequency of Code Case OMN-13 will result in an improvement in personnel safety and dose reduction.
Page A2-2 of 3
Attachment 2 to SERIAL: HNP-04-071 This change will have no operational impact, therefore, the proposed change will not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Involve a significant reduction in a margin of safety.
The changes to Technical Specification SR 4.0.5.a and Bases section 4.0.5 do not involve a reduction in the margin of safety. As previously identified, the subject changes are administrative in nature and will add a reference to the ASME OM Code in Technical Specification SR 4.0.5.a. Therefore, the proposed changes to the Technical Specifications and Bases will not result in a reduction in the margin of safety.
Based on the above, HNP concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified.
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Attachment 3 to SERIAL: HNP-04-071 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS (SR) 4.0.5.A AND ASSOCIATED BASES PROPOSED TECHNICAL SPECIFICATIONS CHANGE Page A3-1 of 2
APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Reauirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
4.0.3 If it is discovered that a surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified surveillance interval. whichever is less. This delay period is permitted to allow performance of the surveillance.
If the surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable ACTION requirements must be met.
When the surveillance is performed within the delay period and the surveillance criteria are not met. the LCO must immediately be declared not met. and the applicable ACTION requirements must be met.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not <
be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1. 2, and 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1. 2, and 3 components and inservice testing of ASME Code Class 1. 2. and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Codet'and applicable Addenda as required by 10 CFR Part 50. Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50. Section 50.55a(g)(6)(i);
- ' -rg ASrAE. CoN:e FMa OPERATIoti APJD MAI'JIEJJArJCf.OF mucW:AR. POWJER PLtAsJTS C&- Cot~c-)
SHEARON HARRIS - UNIT 1 3/4 0-2 Amendment No.
- as Attachment 4 to SERIAL: HNP-04-07 1 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400ALICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS (SR) 4.0.5.A AND ASSOCIATED BASES REVISED TECHNICAL SPECIFICATIONS PAGE Page A4-1 of 2
APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.
4.0.3 If it is discovered that a surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified surveillance interval, whichever is less. This delay period is permitted to allow performance of the surveillance.
If the surveillance is not performed within the delay period. the LCO must immediately be declared not met, and the applicable ACTION requirements must be met.
When the surveillance is performed within the delay period and the surveillance criteria are not met, the LCO must immediately be declared not met, and the applicable ACTION requirements must be met.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1. 2. and 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1. 2. and 3 components and inservice testing of ASME Code Class 1. 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and/or the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i):
SHEARON HARRIS - UNIT 1 3/4 0-2 Amendment No.
Attachment 5 to SERIAL: HNP-04-071 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS (SR) 4.0.5.A AND ASSOCIATED BASES PROPOSED TECHNICAL SPECIFICATIONS BASES CHANGE (FOR INFORMATION)
Page A5-1 of 2
- r APPLICABILITY BASES 4.0.5 This specification ensures that inservice inspection of ASME Code Class 1. 2 and 3 components and inservice testing of ASME Code Class 1. 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Codetand Addenda as required by 10 CFR 50.55a. Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
Under the terms of this specification. the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to 1 week after return to normal operation. And for example. the Technical Specification definition of OPERABLE does not grant a grace period before a device that isnot capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
AWDit/op -r A/Sr-E Cmo FOR OPERA-bO^- As b tAAIWjtEJJA#.cE.F oF 40CLEAe. POWER. PL ,j'rs (OrC CotC)
SHEARON HARRIS - UNIT 1 B 3/4 0-3 Amendment No.