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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 Specifications
MONTHYEARML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 ML21316A2482022-01-19019 January 2022 Issuance of Amendment No. 188, Regarding Revision of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML21035A1322021-03-16016 March 2021 Issuance of Amendment No. 182 Regarding Technical Specifications Related to Accident Monitoring Instrumentation, and Refueling Operations Instrumentation RA-20-0321, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Comple2020-11-11011 November 2020 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completi ML20183A4082020-07-0909 July 2020 Correction to Amendment No. 177 Regarding Elimination of Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications ML19225C0692019-09-19019 September 2019 Issuance of Amendment No. 175 Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints RA-18-0201, Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses2018-10-15015 October 2018 Corrected Technical Specification Page Regarding License Amendment Request to Self Perform Core Reload Design and Safety Analyses ML17324B1292017-12-0606 December 2017 Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a TS Bases Control Program (CAC No. MD5802) - Corrected TS Pages ML17324B0482017-12-0606 December 2017 Correction to License Amendment No. 127 Regarding Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17074A6722017-05-25025 May 2017 Issuance of Amendment Relocation of Explosion Gas Monitoring Program Technical Specifications ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16155A1242016-07-25025 July 2016 Issuance of Amendment on Main Steam Safety Valve Lift Setting Tolerance, Nominal Reactor Trip Setpoint on Pressurizer Water Level, and Pressurizer Water Level Span in Technical Specifications RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015 Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. HNP-15-040, Transmittal of Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2015-08-18018 August 2015 Transmittal of Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML15163A0562015-06-30030 June 2015 Issuance of Amendment to Revised Technical Specifications Table 3.3-4, Engineered Safety Features Actuation System Instrumentation ML15075A2122014-11-30030 November 2014 Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data ML15075A2132014-11-30030 November 2014 Attachment 9 - DPC-NE-2005 Appendix I Harris Plant Specific Data RA-15-000, Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data2014-11-30030 November 2014 Attachment 8 - DPC-NE-2005 Appendix H Robinson Plant Specific Data ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security HNP-12-116, License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values2012-11-29029 November 2012 License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values HNP-12-098, Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2012-10-22022 October 2012 Application for Technical Specification Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process HNP-12-040, Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages2012-03-20020 March 2012 Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages ML12080A2172012-03-20020 March 2012 Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report References for M5 Cladding Revised Technical Specification Pages HNP-11-067, License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis2011-08-22022 August 2011 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis HNP-11-053, Transmittal of Technical Specifications Bases Revisions2011-05-0505 May 2011 Transmittal of Technical Specifications Bases Revisions ML1023707682010-08-16016 August 2010 Response to Second Request for Additional Information Regarding Amendment to Remove Credit for Boraflex in Boiling Water Reactor Spent Fuel Pool Storage Racks ML0926402472009-10-14014 October 2009 Issuance of Amendment Regarding Lowering the Minimum Allowed Level of the Ultimate Heat Sink Main Reservoir ML0923203862009-08-25025 August 2009 Correction to Operating License and Technical Specification Page Issued with Amendment No. 131 Issued on July 2, 2009 ML0923102232009-08-25025 August 2009 Correction to Operating License and Technical Specification Page Issued with Amendment No. 131 Issued on July 2, 2009 ML0923102862009-08-20020 August 2009 Letter & Technical Specifications - Corrections to Technical Specification Pages Issued with Amendment No. 128 Issued on January 29, 2009 HNP-08-075, Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks2008-09-29029 September 2008 Request for License Amendment Technical Specifications 5.6.1.3.a and 5.6.1.3.b - Incorporation of Updated Criticality Analyses to Reflect Removal of Credit for Boraflex in BWR Spent Fuel Pool Storage Racks ML0814301512008-06-12012 June 2008 Technical Specifications, Changes to the Inservice Inspection and Testing Requirements and Establishment of a Technical Specifications Bases Control Program HNP-08-049, Request for License Amendment Technical Specification 3.7.5a2008-04-30030 April 2008 Request for License Amendment Technical Specification 3.7.5a ML0726003592007-09-19019 September 2007 Technical Specification Page Correction Issued with Amendment No. 125 Issued on July 23, 2007 HNP-07-127, Correction to Technical Specification Page in Amendment 1252007-09-13013 September 2007 Correction to Technical Specification Page in Amendment 125 ML0724707482007-08-31031 August 2007 Technical Specification, Issuance of Amendment to Revise Steam Generator Water Level Trip Setpoint Values HNP-07-005, Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.52007-06-15015 June 2007 Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.5 ML0622003982006-08-0202 August 2006 Request for License Amendment to Revise Values Associated with the Steam Generator Water Level Trip Setpoints ML0622004022006-08-0202 August 2006 Request for License Amendment HNP Calculation HNP-I/INST-1010 HNP-06-060, License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-05-23023 May 2006 License Amendment Request Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0606803122006-03-0808 March 2006 Tech Spec Pages for Amendment 120 Regarding Temperature Limit for Dissolved Oxygen in Reactor Coolant System HNP-05-143, Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools2005-12-22022 December 2005 Supplement to Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools HNP-05-002, Supplemental Information to the Proposed License Amendment Request to Technical Specification (TS) 6.8.4.k and TS Surveillance Requirement (SR) 4.6.1.6.12005-12-0909 December 2005 Supplemental Information to the Proposed License Amendment Request to Technical Specification (TS) 6.8.4.k and TS Surveillance Requirement (SR) 4.6.1.6.1 ML0525105022005-09-0101 September 2005 Request for License Amendment to Credit Soluble Boron for Fuel Storage Pools ML0517401142005-06-21021 June 2005 TS for Shearon Harris, Units 1, Enclosure, Amd MC4794, Extend the Inspection Interval for Reactor Coolant Pump Flywheels HNP-05-062, Request for License Amendment Technical Specifications (TS) 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen2005-06-20020 June 2005 Request for License Amendment Technical Specifications (TS) 3/4.4.7 Temperature Limit for Reactor Coolant System Dissolved Oxygen 2023-08-29
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~ Progress Energy James Scarola Harris Harrs NuclaroPlan Vice President Nuclear Plant FEB 1 4 2003 Progress Energy Carolinas, Inc U.S. Nuclear Regulatory Commission Serial: HNP-03-014 ATTENTION: Dociment Control Desk 10 CFR 50.90 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 5.6.3.d Ladies and Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Part 50.90, Progress Energy Carolinas, Inc. (alternately known as Carolina Power & Light Company) requests a license amendment for the Harris Nuclear Plant (HNP) to allow an increase in the decay heat load from fuel stored in Spent Fuel Pools C and D in Technical Specification 5.6.3.d.
The attachments to this letter support the proposed license amendment.
Attachment 1 provides the description, background, and technical analysis for the proposed change to the Technical Specifications.
Attachment 2 details, in accordance with 10 CFR 50.91(a), the basis for Progress Energy Carolinas, Inc.'s determination that the proposed change to the Technical Specifications does not involve a significant hazards consideration. Progress Energy Carolinas, Inc. has determined that the proposed change to the Technical Specifications will not significantly increase the amount of any effluent that may be released offsite and there is no significant increase in individual or cumulative occupational radiation exposure.
Attachment 3 provides an environmental evaluation which demonstrates that the proposed change to the Technical Specifications meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). In addition, the proposed change to the Technical Specifications is completely consistent with the extensive environmental analyses performed by the NRC Staff and Progress Energy Carolinas, Inc. in support of Amendment 103, which the Commission and the Court of Appeals found fully compliant with all applicable environmental requirements. Pursuant to 10 CFR 51.22(b), therefore, no environmental assessment or environmental impact statement is required for approval of this application.
Attachment 4 provides the proposed Technical Specification change.
Attachment 5 provides the revised Technical Specification page.
PG Box165 , 0 New Hill, NC 27562 1> 919 362 2502 F > 919 362 2095
Document Control Desk SERIAL: HNP-03-014 Page 2 In accordance with 10 CFR 50.91(b), Progress Energy Carolinas, Inc. is providing the State of North Carolina with a copy of the proposed license amendment. Progress Energy Carolinas, Inc. requests that the proposed amendment be issued within one year of submittal, with implementation during the next available refueling outage after approval.
Please refer any question regarding this submittal to Mr. John Caves at (919) 362-3137.
Sincerely, JS/dlt Attachments:
- 1. Description, Background, and Technical Analysis
- 2. 10 CFR 50.92 Evaluation
- 3. Environmental Evaluation (10 CFR 51.22)
- 4. Proposed Technical Specification Change
- 5. Revised Technical Specification Page
Document Control Desk SERIAL: HNP-03-014 Page 3 Jim Scarola, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge, and belief and the sources of his information are employees, contractors, and agents of Progress Energy Carolinas, Inc. (alternately known as Carolina Power & Light Company).
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S*£,B \Z My commission Expires:
Mr. J. B. Brady, 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-03-014 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION 5.6.3.d DESCRIPTION, BACKGROUND, AND TECHNICAL ANALYSIS Description The license amendment request for the activation of Harris Nuclear Plant (HNP) Spent Fuel Pools (SFPs) C and D (Serial: HNP-98-188 dated December 23, 1998) resulted in the issuance of Technical Specification Amendment 103 (dated December 21, 2000). Amendment 103 revised Technical Specification 5.6.3.a, b, and c for the licensed storage capacity, which is not affected by this amendment request. Documentation provided as part of the activation license amendment request stated that the projected end of plant life heat removal capacity required in SFPs C and D is 15.63 MBTU/hr. Operating License Amendment 103, however, limits the heat load from fuel stored in SFPs C and D to 1.0 MBTU/hr. This request proposes to increase the combined total SFPs C and D heat load to 7.0 MBTU/hr.
At the time of the license amendment request for activation of SFPs C and D, the configuration of the component cooling water (CCW) system allowed only 1.0 M[BTU/hr of cooling capacity to be conservatively allocated to operation of those two SFPs. Even though the standard technical specifications do not include a limit on SFP heat load, the 1.0 MBTU/hr limit was added to the HNP Technical Specifications to protect the CCW system heat load design basis following SFP C and D operation. Subsequent to issuance of Amendment 103 to the HNP Technical Specifications, the CCW system was significantly upgraded as a part of the HNP steam generator replacement and power uprate modifications, and the 1.0 MBTU/hr limit no longer serves its intended purpose.
In order to achieve this heat load increase at HNP as presently configured, it is necessary to increase the maximum allowed SFP temperature from 140'F to 150°F under normal and emergency conditions other than a design basis Loss of Coolant Accident (LOCA). For a LOCA, the maximum allowed SFP temperature increases from 150'F to 160'F. The NRC previously specifically reviewed and approved a maximum allowed SFP temperature of 140'F in the Power Uprate license application (Serial: HNP- 00-175 dated December 14, 2000) and in the SER for Steam Generator/Power Uprate (dated October 12, 2001). However, the NRC has approved higher maximum allowed SFP temperatures at other nuclear plants, including:
License Amendment Temperature Amendment No. Date (OF)
Beaver Valley Unit 1 247 January 29, 2002 155 Byron Units 1 and 2 112 March 1, 2000 157 Virgil C. Summer 133 April 12, 1996 186 Page Al-1 of 11
Attachment 1 to SERIAL: HNP-03-014
Background
This license amendment request is a continuation of the strategy for utilization of the SFPs at HNP implemented during initial licensing, License Amendment 103 for the activation of SFPs C and D, and License Amendment 107 for Steam Generator Replacement/Power Uprate (SGR/PUR). The license amendment request for SFPs C and D activation stated that the ultimate heat load capacity for pools C and D is 15.63 MBTU/hr, but the license request limited that heat load to 1.0 MBTU/hr. As part of the SGR/PUR project, the Component Cooling Water (CCW) pumps were modified and upgraded by installing new impellers. The additional heat removal capability of the CCW system provides additional cooling capacity to the spent fuel pools. The proposed license amendment will increase the heat load limit for SFPs C and D to permit balancing of spent fuel heat among all four SFPs and to utilize the available CCW system cooling capacity.
The remainder of this subsection provides a description of the structures, systems and components that are involved in this license amendment request.
The Harris Nuclear Plant (HNP) is designed with four SFPs. The four pools are divided into two complexes. The pools are identified as follows:
"* New Fuel Pool Unit 1 (Pool A)
"* Spent Fuel Pool Unit 1 (Pool B)
"* Spent Fuel Pool Unit 2 (Pool C)
"* Spent Fuel Pool Unit 2 (Pool D)
SFPs A and B (the south pool complex), are located in the south end of the Fuel Handling Building (FHB). SFPs C and D (the north pool complex), are located on the north end of the FHB. A system of transfer canals connects the four pools and a Cask Loading Pool. During refueling, spent fuel recently discharged from HNP is stored in SFPs A and B. SFPs A, B, and C contain a combination of pressurized water reactor (PWR) and boiling water reactor (BWR) fuel storage racks. SFP D will contain PWR fuel storage racks as needed.
The Fuel Pool Cooling and Cleanup System (FPCCS) serves both pool complexes. Each pool complex has related cooling, purification and skimmer subsystems. The FPCCS subsystems for SFPs C and D were completed as part of the activation of SFPs C and D. Each pool complex has a dedicated cooling system, which are independent from each other. Each cooling system consists of two redundant cooling loops. Each loop consists of a heat exchanger, cooling pump, strainer and associated piping. Each cooling loop has a piping connection to both pools in the complex as shown in Table Al-i. Two cooling trains are provided for each complex; a single cooling train is sufficient to remove all of the decay heat in the pool complex during normal operation. The two cooling pumps for a pool complex are powered from separate safety-related electric buses; these buses are powered from an emergency diesel generator in the event of the interruption of the normal power source. The cooling systems are Safety Class 3, Seismic Category I systems.
Page A1-2 of 11
Attachment 1 to SERIAL: HNP-03-014 Table Al-1 FPCCS Pump Arrangement Pump Pools in Flow Path Safety-Related Power Supply 1&4A A and/or B A Train I&4B A and/or B B Train 2&3A C and/or D A Train 2&3B C and/or D B Train Each pool complex has a purification subsystem and skimmer subsystem. There are crossties between the purification loops. The purification subsystem for a pool complex is composed of two purification pumps, two filters, a demineralizer and associated piping with cross-ties between the purification subsystems. The skimmer subsystem consists of two trains. Each skimmer train contains a strainer, pump and filter. The two skimmer trains share a common suction and discharge header, which provides a flow path from service connections in each pool and the transfer canals. The purification and skimmer subsystems are non-safety-related.
Further description of the FPCCS is provided in FSAR Section 9.1.3.
The CCW system removes the heat from the SFP heat exchangers. The CCW system is an intermediate cooling loop, which removes heat from safety-related and non-safety-related components during all plant operating conditions. The CCW system is utilized to prevent the direct leakage of radioactivity from nuclear support systems in the plant to the environment, and to prevent the ingress of chlorides and other corrosives into components to which these chemicals could be harmful. The CCW system is used as part of the Emergency Core Cooling System (ECCS) to remove heat from water being recirculated from the Containment Building sump to the reactor, and provides cooling water to the low head safety injection pumps (Residual Heat Removal pumps).
The CCW system is designed to operate during all phases of plant operations including startup, power operation, shutdown, refueling, loss of off-site power (LOOP), and the injection and recirculation phases of ECCS operation. During normal operation, usually only one CCW pump is operating, but a second pump from the other train will automatically start on low CCW system pressure or a safety injection signal.
Page A1-3 of 11
Attachment 1 to SERIAL: HNP-03-014 The CCW system consists of two safety-related trains and a common header. Cross-connect valves between the safety-related trains allow separation of the safety-related trains during design basis events. During normal operation, the cross-connect valves are open and the operating train provides flow to a common header, which supplies the SFP heat exchangers.
CCW is normally supplied to two of the four spent fuel pool heat exchangers (one from each pool complex) during normal operation. Switching the CCW between trains of SFP cooling requires local manual operation.
Further information on the CCW system, including a description of the higher capacity CCW pump impellers installed as part of the power uprate, is provided in FSAR Section 9.2.2.
Page A1-4 of 11
Attachment 1 to SERIAL: HNP-03-014 Technical Analysis The increase in SFPs C and D heat load and the increase in the normal operating SFP temperature are discussed in four parts:
- 1. Impact of the higher SFP heat load on the CCW system performance
- 2. Impact of the higher SFP heat load on the equilibrium SFP temperature
- 3. SFP Makeup Requirements
- 4. Impacts of operating with a higher SFP temperature The higher heat loads and higher SFP temperatures are acceptable based on the satisfactory results of each of the individual analyses.
CCW System Performance The impact of the higher SFP heat load on the performance of the CCW system was analyzed using bounding heat load values in the following calculations:
"* CCW supply temperature for each mode of CCW operation
"* CCW performance during a LOCA
"* Reactor Coolant System (RCS) cooldown time when on Residual Heat Removal System (RHR or RHRS)
"* Analysis of the Ultimate Heat Sink (UHS) during a LOCA
"* CCW flow balance for each mode of CCW operation With the exception of the RCS cooldown time and the CCW flow balance, the current FSAR analyses include sufficient design margin to allow SFPs C and D heat load to be increased to 7.0 MBTU/hr. New FSAR analyses for RCS cooldown time and CCW flow balance were prepared.
A CCW input to the RCS cooldown calculation was revised. The maximum CCW supply temperature was increased from 120'F to 125°F. This CCW temperature increase reduces the time required for the RCS cooldown from 350'F to 200°F. The limiting case calculated uses the following inputs:
"* A single RCP in operation
"* A single cooldown train in operation
"* A maximum CCW supply temperature of 125'F
"* A composite SFP heat load of 27.0 MBTU/hr With these inputs, the total calculated duration of the cooldown from Hot Standby to Cold Shutdown decreased. The cooldown times used in PUR/SGR analyses remain bounding.
Page A1-5 of 11
Attachment 1 to SERIAL: HNP-03-014 Increasing the SFPs C and D heat load requires additional CCW flow to 2&3 A and 2&3 B heat exchangers. The flow balance between the spent fuel heat exchangers for SFPs A and B and SFPs C and D is being changed to provide more cooling flow to SFPs C and D and a reduction in flow to the SFPs Aand B heat exchangers. The impact of the change in the flow to components other than the spent fuel pool heat exchangers has been calculated. CCW flow is satisfactory for equipment performance as described in the following section.
It is important to note that these events were evaluated using a service water supply temperature of 950 F, which is slightly higher (thus more conservative) than the Technical Specification limit of 94°F (TS 3.7.5.b). The Technical Specification limit ensures that the maximum service water supply temperature at the beginning of design basis events remains < 95°F. No change in the service water system flow balance, therefore, is required as a result of the proposed license amendment.
The analyses of CCW supply temperature for each mode of CCW operation were used in calculating the SFP equilibrium temperature.
SFP Equilibrium Temperatures Analyses were performed to determine the impact of the higher SFP heat load on the equilibrium SFP temperatures assumed in the following conditions:
"* Incore Shuffle
"* Normal Full Core Offload
"* Post Outage Full Core Offload (Emergency Core Offload)
"* Normal Operations
"* RCS Cooldown Table A1-2 shows the previously analyzed heat loads and Table A1-3 shows the heat loads analyzed for this license amendment request.
Table A1-2 Existing Analysis Operating Condition(MThr(BUhr SFP A/B Heat Load SFP C/D Heat Load (MBTU/hr) (MBTU/hr)
Incore Shuffle 22.17 1.0 Normal Full Core Offload 40.56 1.0 Emergency Core Offload 42.46 1.0 Normal Operations 16.45 1.0 RCS Cooldown 16.45 1.0 Page A 1-6 of 11
Attachment 1 to SERIAL: HNP-03-014 Table A1-3 License Amendment Analysis Operating Condition(MBUh)MBThrSFP A/B Heat Load SFP C/D Heat Load (MBTU/hr) (MBTU/hr)
Incore Shuffle 22.17 7.0 Normal Full Core Offload 40.56 7.0 Emergency Core Offload 46.23 7.0 Normal Operations 18.31 7.0 RCS Cooldown 18.31 7.0 The SFPs A and B heat loads were calculated using a method that is consistent with NRC Standard Review Plan (SRP) 9.1.3. The analyzed heat load for SFPs A and B increased from 16.45 MBTU/hr to 18.31 MBTU/hr to allow for a refueling outage as short as 15 days and to provide additional heat storage capacity in the SFPs A and B. The heat load increase in SFPs A and B for the Emergency Core Offload case was due to a more conservative calculation of the decay heat for the discharged core used in that specific case. Table A1-4 presents the acceptance criteria previously applied to the different cases and Progress Energy Carolinas, Inc.'s (alternately known as Carolina Power & Light Company) proposed changes.
Table A1-4 Spent Fuel Pool Temperatures Existing HNP Proposed Operating Condition Acceptance Acceptance Criteria (0 F) Criteria ('F)
Incore Shuffle 140 150 Core Normal Fullffod140 150 Offload Emergency Core 150 150 Offload Normal Operations 140 150 RCS Cooldown 140 150 LOCA 150 160 Page A1-7 of 11
Attachment 1 to SERIAL: HNP-03-014 To determine the required maximum SFP operating temperature, the calculations assumed that only one train of CCW and one train of SFP Cooling were operating in all of the cases except Emergency Core Offload. SRP 9.1.3 allows the Emergency Core Offload case to assume two trains of cooling are operable.
The calculations assume that the FPCCS removes all of the decay heat. Conservatively, evaporation or transmission of heat through the FHB structure is ignored, as well as the thermal inertia of the SFP water mass, fuel rack mass and fuel mass. Neglecting thermal inertia provides additional conservatism in the calculation of the SFP bulk temperatures occurring during the RCS cooldown because the cooldown duration is approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SEP Makeup Rates Table A1-5 presents the results of calculations for the required makeup rates for the heat load cases. The makeup rates use the heat loads from Table A1-2 and use a makeup source temperature of 125°F. This assumed makeup source temperature is conservative because it bounds the Technical Specification 3.7.5.b limit for the Ultimate Heat Sink of 94 'F and the Technical Specification 3.5.4.d limit for the Refueling Water Storage Tank of 125°F. The Emergency Service Water system, which takes water from the Ultimate Heat Sink and the RWST, are two possible sources of makeup to the SFP.
Table A1-5 Required Makeup Rates SFP A/B SFP C/D Total (gpm) (gpm) (gpm)
Normal Operations 35.0 13.4 48.4 In-Core Shuffle 42.4 13.4 55.8 Normal Full Core Offload 77.6 13.4 91.0 Emergency Core Offload 88.4 13.4 101.8 The total makeup requirements conservatively assume both FPCCS cooling subsystems are simultaneously impacted. The total makeup rates listed are within the makeup capabilities of systems available to makeup water to the SFP.
Page A1-8 of 11
Attachment I to SERIAL: HNP-03-014 Operation with Higher SFP Temperatures The purpose of this section is to demonstrate that the SFP structure and liner are capable of satisfactory operation with the higher SFP temperatures. In addition, this section demonstrates that the impacts of the higher ambient conditions in the FHB are acceptable. This section is divided into the following subsections:
"* FPCCS design
"* SFP design
"* Ambient temperature
"* FHB Humidity
"* SFP cooling restoration following a design basis LOCA FPCCS Design The design temperature of the FPCCS components is 200'F. The thermal loads on piping and hangers were calculated based on a SFP temperature of 150'F. Analyses of piping and hanger stresses indicate that minor modifications are required for three FPCCS hangers prior to implementing this license amendment. The modifications involve adding material so that the stresses are within allowable values. These modifications will be accomplished before implementing the license amendment. The higher pool temperature for normal operations requires the addition of procedural controls to remove the purification demineralizers from service when pool temperatures exceed 140'F. This procedural change will be added prior to implementation of the license amendment. With these minor modifications and procedural controls, the mechanical and structural design of the FPCCS remains acceptable with the proposed license amendment.
SFP Design The Spent Fuel Pools are an integral part of the Fuel Handling Building (FHB) structure. The FHB is designed and constructed as Seismic Category I. A stainless steel liner is attached to the inside surface of the pools. The liner is a non-ASME Code boundary. The existing design temperature of the SFP structure is based on a liner temperature of 150'F. As part of the analysis for this license amendment, the SFP structure and liner were re-evaluated for a pool temperature of 160'F to account for the new LOCA acceptance criteria. The evaluation concluded that adequate design margin existed to allow for the higher liner temperature without exceeding allowable stresses.
Ambient Temperature The only FHB ambient temperature in the FSAR calculated to rise because of the higher SFP water temperature of 150'F was the SFP Pump and Heat Exchanger Room (FSAR Figure 3.1 IB 13, FH21, Zone A), which was calculated to increase from 104'F to 115.5°F. The impacts on safety-related equipment in the affected space have been evaluated and found to be acceptable with the higher temperature.
Page A1-9 of 11
Attachment 1 to SERIAL: HNP-03-014 FHB Humidity The FHB operating floor (Elev. 286' and connected spaces) is serviced by the FHB Emergency Exhaust System on detection of high radiation in the FHB. The system isolates the operating floor envelope and initiates flow through a safety-related filter train (refer to FSAR Section 6.5.1.1). This filter system is designed to limit the offsite doses in the event of a postulated fuel handling accident in the FHB.
Each filtration unit contains a safety-related electric heater to control the relative humidity through the charcoal filter section. Analysis shows that the heater capacity is satisfactory for the humidity that would exist if all the pool and transfer canal surfaces were at 150'F. A fuel handling accident concurrent with the SFP heat up following a LOCA was not analyzed because the plant licensing basis does not require consideration of the simultaneous occurrence of these two unlikely events.
Due to the ample capacity of the heater system to handle the additional humidity and since the environmental qualification of affected safety-related equipment is based on 100% humidity in the FHB; therefore, it is concluded that the humidity from operating the SFPs at a higher temperatures is acceptable.
SFP cooling restoration following a LOCA As described in FSAR Section 9.1.3.3, the CCW flow to the common header is isolated during the start of ECCS recirculation operation following a LOCA. The long-term containment analysis for the LOCA uses the assumption that the common header remains isolated until five hours after the LOCA or until the containment sump is <2000 F.
The method of restoration of the CCW flow remains unchanged from the existing practice described in FSAR Section 9.1.3.3.
Table A1-6(b) lists the analyzed time to heat up from the maximum pool bulk temperature for normal operations to 150'F, 160'F and 212'F, respectively. The pool heatup rates are based on the "Normal Operations" heat loads listed in Table A1-3. The corresponding data for the existing design is presented in Table A 1-6(a).
Table A1-6(a)
Existing Analysis Maximum Normal ora Pool Heatup Time to Time to Time to boil Pool Rate (°F/hr) 150°F(hr) 160°F (hr) (hr)
Temperature (OF)
SFP A/B 123.5 4.3 6.2 N/A 20.6 SFP C/D 105 0.33 138.5 N/A 322.3 Page Al-10 of 11
Attachment 1 to SERIAL: HNP-03-014 Table A1-6(b)
License Amendment Analysis Maximum Normal ora Pool Heatup Time to Time to Time to boil Pool Rate (°F/hr) 150°F(hr) 160°F (hr) (hr)
Temperature (OF)
SFP A/B 125.7 4.73 5.1 7.2 18.2 SFP C/D 123.1 2.53 10.6 14.5 35.1 Due to the heat load in SFPs A and B, that pool complex is the limiting location. The values presented in Tables A1-6(a) and (b) contain several conservatisms in the inputs for the calculated heatup times. In particular:
"* The SFP heat load is based on the beginning of core life
"* The CCW supply temperatures are based on a SFP composite heat load which bounds the proposed composite heat load
"* The performance of the FPCCS is conservatively modeled
"* The water volumes assumed as part of the thermal inertia are conservatively low
"* The thermal mass of the fuel, fuel rack and SFP structure is neglected The proposed heat load increase for this license amendment necessarily causes the time to boil values to decrease. However, the time to boil values for the proposed heat loads remains bounded by the Probabilistic Safety Analysis that was performed by Progress Energy Carolinas, Inc. for SFPs C and D activation.
The time available to perform the restoration of cooling to the SFPs after a LOCA is conservatively calculated and provides sufficient time for the required operator actions to be implemented. The method used to restore forced cooling of the Spent Fuel Pool has not changed. Therefore, the increase in the SFPs C and D heat load results in acceptable time available for restoration of CCW to FPCCS for LOCA.
Conclusion Based on the analyses and evaluations of the proposed changes it is acceptable to:
- 1. Increase the SFPs C and D heat load to 7.0 MBTU/hr
- 2. Establish 150'F as the maximum operating SFP temperature for non-accident scenarios and 160'F as the maximum operating SFP temperature for a LOCA Page Al-ll of 11
Attachment 2 to SERIAL: HNP-03-014 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION 5.6.3.d 10 CFR 50.92 EVALUATION A written evaluation of the significant hazards consideration of a proposed license amendment is required by 10 CFR 50.92. Progress Energy Carolinas, Inc. (alternately known as Carolina Power & Light Company) 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 as follows:
Proposed Change The change involves an increase in the maximum decay heat of spent fuel stored in Spent Fuel Pools (SFPs) C and D from 1.0 MBTU/hr to 7.0 MBTU/hr, and an increase in the allowable SFP temperatures.
Basis This change does not involve a significant hazards consideration for the following reasons:
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The license amendment only increases the heat load from the Fuel Pool Cooling and Cleanup System (FPCCS) and the maximum allowable pool temperature. The changes do not modify the design of Structures, Systems and Components (SSCs) that could initiate an accident. The FHB Emergency Exhaust System mitigates the consequences of a fuel handling accident in the Fuel Handling Building. This system has been evaluated for the conditions that would exist with the higher SFP temperatures and it was found that there would be no decrease in the charcoal efficiency. As a result, there was no increase Page A2-1 of 2
Attachment 2 to SERIAL: HNP-03-014 in the doses from the fuel handling accident in the FHB. Therefore, the change does not result in any increase in the probability or consequences in any accident previously analyzed.
- 2. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The increase in the SFP decay heat load and the SFP temperature limit does not involve new plant components or procedures. No significant impact on any postulated accident is made due to this change since the required cooling capacity is maintained to the SFPs and the FPCCS, and the SFPs will operate within design parameters.
For the activation of SFPs C and D, Progress Energy Carolinas, Inc. performed a Probabilistic Safety Analysis (PSA) of a total loss of SFP forced cooling. That analysis concluded that the probability of spent fuel rack uncovery was not credible. That analysis remains bounding for this license amendment application.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed amendment does not involve a significant reduction in the margin of safety.
The proposed changes do not affect the design or operation of the barriers to fission product release (fuel cladding, reactor coolant system pressure boundary, and containment boundary). The change in the SFPs C and D decay heat load is bounded by the heat load used in the analysis of the safety-related systems for design basis accidents.
Therefore, there is no impact in the margin of safety.
Based on these considerations, the proposed change does not involve a significant reduction on the margin of safety.
Page A2-2 of 2
Attachment 3 to SERIAL: HNP-03-014 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION 5.6.3.d ENVIRONMENTAL EVALUATION (10 CFR 51.22) 10 CFR 51.22(c)(9) provides criterion for and identification of licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment.
A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (3) result in a significant increase in individual or cumulative occupational radiation exposure. Progress Energy Carolinas, Inc. (alternately known as Carolina Power & Light Company) has reviewed this amendment request and determined the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). In addition, the proposed license amendment is completely consistent with the extensive environmental analyses performed by the NRC Staff and Progress Energy Carolinas, Inc. in support of Amendment 103, which the Commission and Court of Appeals found fully compliant with all applicable environmental requirements.
Pursuant to 10 CFR 51.22(b), therefore, no environmental assessment or environmental impact statement needs to be prepared in connection with the issuance of the amendment.
The basis for this determination is as follows:
Proposed Change The change involves an increase in the decay heat of spent fuel stored in Spent Fuel Pools (SFPs) C and D from 1.0 MBTU/hr to 7.0 MBTU/hr. However, it does not authorize an increase in the HNP SFPs A, B, C and D capacity as set forth in Technical Specification 5.6.3.a, b, and c.
Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
- 1. As demonstrated in Attachment 2, the proposed amendment does not involve a significant hazards consideration.
- 2. The proposed amendment does not result in significant change in the types or increase in the amounts of any effluents that may be released offsite.
The change does not introduce any new effluents. The routine effluents from HNP include a component from the purification and pool skimmer system that serves SFPs Page A3-1 of 2
Attachment 3 to SERIAL: HNP-03-014 C and D. The flow rate of the skimmer system is independent of the heat load in the SFPs; therefore, there is no significant increase in the effluents from the plant as a result of the change.
- 3. The proposed amendment does not result in a significant increase in individual or cumulative occupational radiation exposure.
The change does not create any physical changes in the Fuel Pool Cooling and Cleanup System (FPCCS) or SFPs C and D. Personnel are shielded from the radiation by the water over the fuel assemblies and the thick concrete floors and walls that separate a pool from accessible areas.
For the activation of SFPs C and D, Progress Energy Carolinas, Inc. performed a Probabilistic Safety Analysis (PSA) of the total loss of SFP forced cooling. That analysis concluded that the probability of spent fuel rack uncovery was not credible.
That analysis remains bounding for this license amendment application.
There are no new surveillances that require entry into radiation controlled areas.
Therefore, the amendment has no significant affect on either individual or cumulative occupational radiation exposure.
Page A3-2 of 2
Attachment 4 to SERIAL: HNP-03-014 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION 5.6.3.d PROPOSED TECHNICAL SPECIFICATION CHANGE Page A4-1 of 2
DESIGN FEATURES 5.6.3.b Pool "C" is designed to contain a combination of PWR and BWR assemblies. Pool "C" can contain two (11 x 9 cell) and nine (9 X 9 cell) PWR racks for storage of 927 PWR assemblies. Pool "C"can contain two (8 x 13 cell), two (8 x 11 cell), six (13 x 11 cell), and nine (13 x 13 cell) BWR racks for storage of 2763 BWR assemblies The (9 x 9 cell) PWR racks and the (13 x 13 cell) BWR racks are dimensioned to allow interchangeability between PWR or BWR storage rack styles as required The racks in pool "C"will be installed as needed.
5.6.3.c Pool "D"contains a variable number of PWR storage spaces These racks will be installed as needed. Pool "D" is designed for a maximum storage capacity of 1025 PWR assemblies.
_ 6.3Td he heat load from fuel stored in Pools "C"and "D"chall not exceed 5 MPtu1h CL O A 5 7 COMPONENT CYCLIC OR TPRANSIENT LIMIT ,t",
5.7 1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
$k>zI 44e SHEARON HARRIS - UNIT 1 5-7a Amendment No. E
Attachment 5 to SERIAL: HNP-03-014 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICAL SPECIFICATION 5.6.3.d REVISED TECHNICAL SPECIFICATION PAGE Page A5-1 of 2
DESIGN FEATURES 5.6.3.b Pool "C" is designed to contain a combination of PWR and BWR assemblies. Pool "C" can contain two (11 x 9 cell) and nine (9 X 9 cell) PWR racks for storage of 927 PWR assemblies. Pool "C" can contain two (8 x 13 cell), two (8 x 11 cell), six (13 x 11 cell), and nine (13 x 13 cell) BWR racks for storage of 2763 BWR assemblies. The (9 x 9 cell) PWR racks and the (13 x 13 cell) BWR racks are dimensioned to allow interchangeability between PWR or BWR storage rack styles as required. The racks in pool "C" will be installed as needed.
5.6.3.c Pool "D" contains a variable number of PWR storage spaces. These racks will be installed as needed. Pool "D"is designed for a maximum storage capacity of 1025 PWR assemblies.
5.6.3.d The heat load from fuel stored in Pools "C"and "D"shall not exceed 7.0 MBtu/hr.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
SHEARON HARRIS - UNIT 1 5-7a Amendment No.