Letter Sequence Request |
---|
|
|
MONTHYEARRNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation Project stage: Request ML1010500902010-04-15015 April 2010 Acceptance of Progress Energy Application Dated March 5, 2010 on H. B. Robinson Steam Electric Plant Unit No. 2 Technical Specification 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation and Section 3.3.6, TAC No. ME3 Project stage: Acceptance Review ML1018806972010-07-20020 July 2010 RAI, Regarding Changes to Technical Specification Section 3.3.2, Engineered Safety Feature Actuation System Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation Project stage: RAI ML1013801412010-07-21021 July 2010 G20100201/LTR-10-0160/EDATS: SECY-2010-0194 - Anthony R. Pietrangelo Ltr. Generic Safety Issue (GSI) 191, PWR Containment Sump Performance Project stage: Other RNP-RA/10-0108, H. B. Robinson,Response to Request for Additional Information Regarding Changes to Technical Specification Section 3.3.2, Engineered Safety Feature Actuation System Instrumentation, and Section 3.3.6, Containment Ventilation Isolation2010-11-0101 November 2010 H. B. Robinson,Response to Request for Additional Information Regarding Changes to Technical Specification Section 3.3.2, Engineered Safety Feature Actuation System Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instr Project stage: Response to RAI ML1104700022011-03-0707 March 2011 Issuance of an Amendment Regarding 3.3.2 Engineered Safety Features Actuation System Instrumentation and Section 3.3.6 Containment Ventilation Isolation Instrumentation Project stage: Approval 2010-04-15
[Table View] |
|
---|
Category:Letter type:RNP
MONTHYEARRNP-RA/21-0035, Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-18018 February 2021 Duke Energy Progress, Inc - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/20-0234, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2020-07-23023 July 2020 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RNP-RA/20-0199, Registration of Use of Spent Fuel Casks2020-06-25025 June 2020 Registration of Use of Spent Fuel Casks RNP-RA/18-0063, Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal2018-11-29029 November 2018 Request for Extension of Due Date for Seismic Probabilistic Risk Assessment Submittal RNP-RA/18-0060, Transmittal of Core Operating Limits Report2018-10-17017 October 2018 Transmittal of Core Operating Limits Report RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change2018-08-0101 August 2018 Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/18-0039, Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis2018-06-27027 June 2018 Transmittal of Emergency Procedure Revisions and 10 CFR 50.54(q) Summary of Analysis RNP-RA/18-0041, Independent Spent Fuel Storage Installation - Register as User for Cask2018-06-13013 June 2018 Independent Spent Fuel Storage Installation - Register as User for Cask RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ...2018-05-16016 May 2018 Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... RNP-RA/18-0029, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-0808 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report RNP-RA/18-0031, (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 352018-04-23023 April 2018 (Hbrsep), Unit 2 - 2017 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Revision 35 RNP-RA/18-0015, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program2018-04-16016 April 2018 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018 Report of Changes Pursuant to 10 CFR 50.59(d)(2) RNP-RA/18-0020, Notification of Change in Licensed Operator Status2018-02-20020 February 2018 Notification of Change in Licensed Operator Status RNP-RA/18-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-01-23023 January 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2018-01-0808 January 2018 Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0086, Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses2017-12-14014 December 2017 Transmittal of Emergency Procedure Revision and 10 CFR 50.54(q) Summary of Analyses RNP-RA/17-0081, Submittal of Change in Licensed Operators Medical Status2017-12-11011 December 2017 Submittal of Change in Licensed Operators Medical Status RNP-RA/17-0079, Operator License Renewal Application2017-12-0707 December 2017 Operator License Renewal Application RNP-RA/17-0071, Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks2017-10-19019 October 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License Spent Fuel Casks RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-09-28028 September 2017 Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0037, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers2017-09-27027 September 2017 License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RNP-RA/17-0043, Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-42017-09-22022 September 2017 Relief Request (RR)-12 for Relief from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 RNP-RA/17-0065, Refueling Outage 30 Steam Generator Tube Inspection Report2017-09-18018 September 2017 Refueling Outage 30 Steam Generator Tube Inspection Report RNP-RA/17-0060, Notification of Change in Licensed Operator Status2017-08-10010 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0058, Notification of Change in Licensed Operator Status2017-08-0303 August 2017 Notification of Change in Licensed Operator Status RNP-RA/17-0055, Transmittal of Core Operating Limits Report for Cycle 312017-07-26026 July 2017 Transmittal of Core Operating Limits Report for Cycle 31 RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2017-06-29029 June 2017 Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/17-0051, Submittal of Nine Day Inservice Inspection Summary Report2017-06-29029 June 2017 Submittal of Nine Day Inservice Inspection Summary Report RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0038, (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report2017-05-0909 May 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radiological Environmental Operating Report RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) RNP-RA/17-0036, (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 342017-04-25025 April 2017 (Hbrsep), Unit No. 2 - 2016 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual, Current Revision 34 RNP-RA/17-0031, Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 02017-04-20020 April 2017 Provides Additional Information Regarding License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler 522, Revision 0 RNP-RA/17-0033, Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal2017-04-12012 April 2017 Flood Hazard Mitigating Strategies Assessment (MSA) Report Submittal RNP-RA/17-0014, Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0028, Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Submittal of Engineering Calculation in Support of a Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/17-0021, Transmittal of Core Operating Limits Report2017-03-13013 March 2017 Transmittal of Core Operating Limits Report RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RNP-RA/17-0015, Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 Independent Spent Fuel Storage Installations - Letter Regarding Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/17-0016, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2017-02-22022 February 2017 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RNP-RA/17-0015, H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.482017-02-22022 February 2017 H.B. Robinson Steam Electric Plant & ISFSIs - Report of Changes Pursuant to 10 CFR 72.48 RNP-RA/16-0100, Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-2272017-01-24024 January 2017 Response to Apparent Violation in NRC Inspection Report 05000261/2016404, EA-16-227 RNP-RA/16-0097, Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/20154052016-12-15015 December 2016 Transmittal Letter for Response to Inspection Report Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestones 1-7, Inspection Report 05000261/2015405 RNP-RA/16-0089, Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2016-11-10010 November 2016 Request for Withdrawal of License Amendment Request for Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/16-0090, Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise2016-11-10010 November 2016 Notification of Rescheduled Date for 2017 Emergency Preparedness Graded Exercise RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016 Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. 2021-02-18
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-24-0173, Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld2024-06-28028 June 2024 Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld RA-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-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology 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-22-0118, 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-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) 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-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 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-21-0076, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-12-0909 December 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0254, Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/ Temperature Limit Cooldown Curves2021-12-0909 December 2021 Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/ Temperature Limit Cooldown Curves RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML20093J0982020-08-21021 August 2020 Issuance of Amendment No. 269 Regarding Technical Specification Change Incorporating Three New Feedwater Bypass Isolation Valves RA-20-0007, Request to Correct Administrative Renewed Facility Operating License Error2020-01-21021 January 2020 Request to Correct Administrative Renewed Facility Operating License Error RA-19-0183, License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.32019-07-29029 July 2019 License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 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-18-0206, 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 RA-18-0048, Corrected Technical Specification Pages for TSTF-425 License Amendment Request2018-09-25025 September 2018 Corrected Technical Specification Pages for TSTF-425 License Amendment Request 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-18-000, 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 RNP-RA/18-0015, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program2018-04-16016 April 2018 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequently Requirements to a Licensee Controlled Program ML18099A1302018-04-0505 April 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. ML18038B2892018-02-0707 February 2018 License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits 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 ML17205A2332017-09-29029 September 2017 Issuance of Amendment Regarding Request to Modify the Licensing Basis Alternate Source Term RNP-RA/17-0037, License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers2017-09-27027 September 2017 License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specifications 3.8.1, AC Sources-Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers 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 RNP-RA/17-0014, Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-04-0303 April 2017 Resubmittal of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles 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 RNP-RA/16-0044, Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2016-09-16016 September 2016 Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RNP-RA/16-0057, License Amendment Request to Modify the Licensing Basis Alternate Source Term2016-09-14014 September 2016 License Amendment Request to Modify the Licensing Basis Alternate Source Term ML16116A0332016-04-24024 April 2016 Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RA-16-0003, Application to Revise Technical Specifications to Adopt Methodology Reports DPC-NF-2010, Revision 3, Nuclear Physics Methodology for Reload Design, and DPC-NE-2011-P, Revision 2, Nuclear Design Methodology Report...2016-02-0303 February 2016 Application to Revise Technical Specifications to Adopt Methodology Reports DPC-NF-2010, Revision 3, Nuclear Physics Methodology for Reload Design, and DPC-NE-2011-P, Revision 2, Nuclear Design Methodology Report... RA-15-0040, License Amendment Request, Change in Corporate Form of Duke Energy Progress2016-02-0101 February 2016 License Amendment Request, Change in Corporate Form of Duke Energy Progress RNP-RA/15-0117, Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-12-22022 December 2015 Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits RNP-RA/15-0090, Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test Interval And..2015-11-19019 November 2015 Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test Interval And.. 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. RNP-RA/13-0117, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation2014-02-10010 February 2014 License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation RA-13-1001, License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 82013-12-19019 December 2013 License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 8 RNP-RA/13-0002, License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements2013-06-0707 June 2013 License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements BSEP 13-0013, License Amendment Request to Facility Operating Licenses for Change of Licensee Name2013-04-20020 April 2013 License Amendment Request to Facility Operating Licenses for Change of Licensee Name RA-12-031, Carolina Power & Light Company and Florida Power Corporation'S License Amendment Request - Cyber Security Plan Implementation Schedule Milestones2012-09-12012 September 2012 Carolina Power & Light Company and Florida Power Corporation'S License Amendment Request - Cyber Security Plan Implementation Schedule Milestones ML12263A4242012-09-0606 September 2012 License Amendment Request to Delete Technical Specification Reactor Protection System Trip on Steam Generator Water Level Low Coincident with Steam Flow/Feedwater Flow Mismatch RNP-RA/12-0057, License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*)2012-08-29029 August 2012 License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) RNP-RA/12-0033, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2012-08-0606 August 2012 Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RNP-RA/12-0028, Request for Technical Specification Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication2012-06-0808 June 2012 Request for Technical Specification Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication RA-11-010, Progress Energy Carolinas, Inc., & Progress Energy Florida, Inc., Submittal of Application for Approval of Indirect Transfers of Control of License Pursuant to 10 CFR 50.80 and 10 CFR ,72.502011-03-30030 March 2011 Progress Energy Carolinas, Inc., & Progress Energy Florida, Inc., Submittal of Application for Approval of Indirect Transfers of Control of License Pursuant to 10 CFR 50.80 and 10 CFR ,72.50 2024-06-28
[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-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality 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-22-0118, 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-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) 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-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0057, Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical .2021-05-27027 May 2021 Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical . RA-19-0183, License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.32019-07-29029 July 2019 License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 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 RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers 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 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-18-000, 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 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 RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) 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 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 ML16116A0332016-04-24024 April 2016 Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 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 RNP-RA/15-0083, Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-11-0202 November 2015 Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits RNP-RA/15-0086, Transmittal of Technical Specifications Bases Revisions2015-10-0808 October 2015 Transmittal of Technical Specifications Bases Revisions RNP-RA/15-0077, Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication2015-09-0101 September 2015 Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication ML14188B0152014-06-20020 June 2014 Request for Technical Specifications (TS) Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion RNP-RA/14-0042, Transmittal of Technical Specifications Bases Revisions2014-04-29029 April 2014 Transmittal of Technical Specifications Bases Revisions RNP-RA/13-0077, License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications2013-09-30030 September 2013 License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications RNP-RA/13-0038, Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication2013-04-24024 April 2013 Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication RNP-RA/12-0066, Transmittal of Technical Specifications Bases Revisions2012-09-17017 September 2012 Transmittal of Technical Specifications Bases Revisions RNP-RA/12-0033, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2012-08-0606 August 2012 Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process RNP-RA/11-0095, Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2012-02-10010 February 2012 Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process RNP-RA/11-0002, Transmittal of Technical Specifications Bases Revisions2011-01-12012 January 2011 Transmittal of Technical Specifications Bases Revisions RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 RNP-RA/08-0006, Request for Technical Specifications Changes Related to Control Room Habitability - Supplement2008-04-0101 April 2008 Request for Technical Specifications Changes Related to Control Room Habitability - Supplement RNP-RA/08-0016, Supplement to the Request for Administrative Changes to the Technical Specifications2008-02-0404 February 2008 Supplement to the Request for Administrative Changes to the Technical Specifications RNP-RA/07-0126, Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System2007-11-29029 November 2007 Request for Technical Specifications Change to Section 3.6.8 Isolation Valve Seal Water System RNP-RA/07-0073, Request for Administrative Changes to the Operating License and Technical Specifications2007-11-19019 November 2007 Request for Administrative Changes to the Operating License and Technical Specifications RNP-RA/07-0124, Request for Technical Specifications Change to Section 3.1.7 Rod Position Indication2007-11-15015 November 2007 Request for Technical Specifications Change to Section 3.1.7 Rod Position Indication RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions2007-10-30030 October 2007 Transmittal of Technical Specifications Bases Revisions RNP-RA/07-0056, Request for Technical Specifications Changes Related to Control Room Habitability2007-07-17017 July 2007 Request for Technical Specifications Changes Related to Control Room Habitability RNP-RA/06-0095, Request for Technical Specifications Change to Section 3.3.3, Post Accident Monitoring2007-02-0202 February 2007 Request for Technical Specifications Change to Section 3.3.3, Post Accident Monitoring ML0702404832007-01-19019 January 2007 H. B. Robinson, Unit 2 - Resubmission of Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria ML0634104702006-11-29029 November 2006 Technical Specification Pages Re Core Operating Limit Report References, ML0628900812006-10-12012 October 2006 Submittal of H. B. Robinson, Unit 2 - Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions2006-04-0606 April 2006 Transmittal of Technical Specifications Bases Revisions 2024-05-23
[Table view] Category:Bases Change
MONTHYEARRA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality 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-22-0118, 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-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-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0057, Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical .2021-05-27027 May 2021 Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical . RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions 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 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 ML16116A0332016-04-24024 April 2016 Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 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 RNP-RA/15-0086, Transmittal of Technical Specifications Bases Revisions2015-10-0808 October 2015 Transmittal of Technical Specifications Bases Revisions RNP-RA/15-0077, Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication2015-09-0101 September 2015 Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication ML14188B0152014-06-20020 June 2014 Request for Technical Specifications (TS) Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion RNP-RA/14-0042, Transmittal of Technical Specifications Bases Revisions2014-04-29029 April 2014 Transmittal of Technical Specifications Bases Revisions RNP-RA/13-0038, Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication2013-04-24024 April 2013 Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication RNP-RA/12-0066, Transmittal of Technical Specifications Bases Revisions2012-09-17017 September 2012 Transmittal of Technical Specifications Bases Revisions RNP-RA/11-0095, Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2012-02-10010 February 2012 Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process RNP-RA/11-0002, Transmittal of Technical Specifications Bases Revisions2011-01-12012 January 2011 Transmittal of Technical Specifications Bases Revisions RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions2007-10-30030 October 2007 Transmittal of Technical Specifications Bases Revisions ML0702404832007-01-19019 January 2007 H. B. Robinson, Unit 2 - Resubmission of Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions2006-04-0606 April 2006 Transmittal of Technical Specifications Bases Revisions RNP-RA/04-0133, Transmittal of Technical Specifications Bases Revisions2004-10-21021 October 2004 Transmittal of Technical Specifications Bases Revisions RNP-RA/03-0038, Request for Technical Specifications Change Re Credit for Spent Fuel Storage Pool Dissolved Boron2003-05-28028 May 2003 Request for Technical Specifications Change Re Credit for Spent Fuel Storage Pool Dissolved Boron RNP-RA/03-0061, Transmittal of TS Bases Revisions2003-05-0202 May 2003 Transmittal of TS Bases Revisions RNP-RA/02-0118, Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term2002-08-14014 August 2002 Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term 2023-05-25
[Table view] Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML19158A3072019-08-15015 August 2019 Issuance of Amendment No. 265, Regarding Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 32019-07-16016 July 2019 Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3 ML18200A0422018-08-16016 August 2018 Issuance of Amendment No. 260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles 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 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) RNP-RA/17-0019, Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 22017-03-0808 March 2017 Supplemental Submittal to Correct Marked Up Technical Specifications (TS) Pages Transmitted with Application for Technical Specification Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 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. ML15222B1752015-09-0808 September 2015 Issuance of Amendment to Modify Technical Specification 3.8.1, Diesel Generator Testing Requirements 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. RNP-RA/15-0026, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication2015-04-0101 April 2015 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication RNP-RA/13-0117, License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation2014-02-10010 February 2014 License Amendment Request to Modify Technical Specification 3.3.1, Reactor Protection System (RPS) Instrumentation ML13198A3672013-08-29029 August 2013 Issuance of an Amendment to Revise the Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) RNP-RA/13-0089, Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria2013-08-22022 August 2013 Supplemental Submittal to Correct TS Pages Re Request for Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection & Application of Permanent Alternate Repair Criteria RNP-RA/13-0002, License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements2013-06-0707 June 2013 License Amendment Request to Modify Technical Specification 3.1.7 to Delete the Monthly Rod Position Indication Surveillance Requirements ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security RNP-RA/12-0057, License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*)2012-08-29029 August 2012 License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) ML11342A1652011-12-29029 December 2011 Issuance of an Amendment on Technical Specifications Related to Use of Areva'S M5 Advanced Alloy in Fuel Cladding and Fuel Assembly Components RNP-RA/10-0096, Request for Technical Specifications Change Regarding Use of M5 Alloy Fuel2010-10-20020 October 2010 Request for Technical Specifications Change Regarding Use of M5 Alloy Fuel ML1008303302010-03-25025 March 2010 Issuance of Amendment Regarding Technical Specifications Changes Related to the Chemical and Volume Control System RNP-RA/10-0024, Request for Emergency Technical Specifications Change to Section 3.4.17, Chemical and Volume Control System (CVCS)2010-03-22022 March 2010 Request for Emergency Technical Specifications Change to Section 3.4.17, Chemical and Volume Control System (CVCS) RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation ML0936312122009-12-16016 December 2009 Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/09-0024, Transmittal of Technical Specifications Bases Revisions2009-04-16016 April 2009 Transmittal of Technical Specifications Bases Revisions ML0813403232008-07-23023 July 2008 Issuance of Amendment Regarding the Incorporation of Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-448, Revision 3, Control Room Habitability. ML0815402792008-06-19019 June 2008 Tech Spec Pages for Amendment 218 Regarding Administrative Changes to the Operating License and Technical Specifications ML0803300542008-01-29029 January 2008 Tech Spec Pages for Amendment 217 to Make a One-time Change to Technical Specification (TS) 3.1.7 Rod Position Indication. ML0726102012007-09-19019 September 2007 Technical Specification, Correction to Technical Specification Page Issued with Amendment No. 215 Issued on June 15, 2007 ML0725706282007-09-18018 September 2007 Correction to Technical Specification Pages Issued with Amendment No. 216 Issued on July 16, 2007 RNP-RA/07-0095, Correction to Technical Specifications Page in Amendment 2162007-09-12012 September 2007 Correction to Technical Specifications Page in Amendment 216 ML0720102362007-07-16016 July 2007 Tech Spec Pages for Amendment 216 to Adopt Technical Specifications Task Force (TSTF) Standard TS Change Traveler, TSTF-447, Using the Consolidated Line Item Improvement Process ML0717202542007-06-15015 June 2007 Technical Specifications Changes Related to Containment Peak Pressure ML0709900232007-04-0404 April 2007 Technical Specifications, Changes Surveillance Requirement (SR) 3.5.2.6 RNP-RA/07-0032, Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria2007-03-22022 March 2007 Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria RNP-RA/07-0023, Response to NRC Request for Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria2007-03-13013 March 2007 Response to NRC Request for Additional Information Pertaining to Proposed Technical Specifications Changes Regarding Steam Generator Tube Repair Criteria ML0628404592006-10-0404 October 2006 Tech Spec Pages for Amendment 208 Regarding Emergency Diesel Generator or Automatic Trips Bypass TS 3.8.1 ML0627100222006-09-22022 September 2006 Technical Specification Amendment No. 210 - H.B. Robinson, Unit 2 - Issuance of Amendment and Partial Denial Reactor Protection System and Engineered Safety Feature Actuation System Instrumentation Tables ML0627005192006-09-20020 September 2006 Technical Specifications, Amendment, Methodology for Large Break Loss-of-Coolant Accident RNP-RA/06-0048, Request for Technical Specifications, Change Related to Containment Peak Pressure2006-07-17017 July 2006 Request for Technical Specifications, Change Related to Containment Peak Pressure ML0621900412006-07-11011 July 2006 Technical Specifications, Alternate Source Term for the loss-of-coolant RNP-RA/06-0046, Request for Technical Specifications Change to Section 3.5.2. Emergency Core Cooling System2006-06-0101 June 2006 Request for Technical Specifications Change to Section 3.5.2. Emergency Core Cooling System RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-05-30030 May 2006 Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process ML0610805222006-04-11011 April 2006 H. B. Robinson, Unit 2 - Request for Technical Specification Change to Core Operating Limits Report References RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.2006-03-31031 March 2006 ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis. ML0524205242005-08-25025 August 2005 Tech Spec Pages for Amendment 206 DC Sources - Operation and Shutdown RNP-RA/05-0062, Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating2005-07-13013 July 2005 Response to Request for Additional Information Regarding Technical Specifications Change Request to Section 3.8.4 DC Sources - Operating 2023-08-29
[Table view] |
Text
10 CFR 50.90 Progress Energy Serial: RNP-RA/10-0001 MAR 0 5 201[
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES TO SECTION 3.3.2, ENGINEERED SAFETY FEATURE. ACTUATION SYSTEM (ESFAS)
INSTRUMENTATION, AND SECTION 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION Ladies and Gentlemen:
In accordance with the provisions of the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. (PEC), is submitting a request for an amendment to the Technical Specifications (TS) contained in Appendix A of the Operating License for H. B. Robinson Steam Electric Plant (HBRSEP),
Unit No. 2.
The proposed amendment will revise TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," and TS 3.3.6, "Containment Ventilation Isolation System." The proposed change to TS 3.3.2 adds notes to allow for the performance of maintenance activities for an inoperable Containment Pressure - High High channel. The proposed change to TS 3.3.6 corrects an error related to table references.
Attachment I provides an Affirmation as required by 10 CFR 50.30(b).
Attachment II provides a description of the current condition, a description and justification of the proposed change, a No Significant Hazards Consideration Determination, and an Environmental Impact Consideration.
Attachment III provides a markup of the affected TS pages. Attachment IV provides the retyped TS pages. Attachment V provides a retyped version of the proposed Bases changes to Section 3.3.2. The Bases changes provide amplifying information related to the TS change.
Progress Energy Carolinas, Inc.
Hobinson Nuclear Plant 3581 West Entrance Road A670(
Hartsville, SC 29550 0U P..
United States Nuclear Regulatory Commission Serial: RNP-RA/10-0001 Page 2 of 2 In accordance with 10 CFR 50.91(b), Progress Energy Carolinas, Inc., is providing the State of South Carolina with a copy of this license amendment request.
Nuclear Regulatory Commission approval of the proposed license amendment is requested by November 30, 2010.
If you have any questions concerning this matter, please contact me at (843) 857-1253.
Sincerely, BeMnjin C. White Manager - Support Services - Nuclear Attachments:
I. Affirmation II. Request for Technical Specifications Changes related to Section 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," and Section 3.3.6, "Containment Ventilation Isolation Instrumentation" III. Markup of Technical Specifications Pages IV. Retyped Technical Specifications Pages V. Retyped Technical Specifications Bases Pages RAC/rac c: Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)
Mr. A. Gantt, Chief, Bureau of Radiological Health (SC)
Mr. L. A. Reyes, NRC, Region II Mr. T. Orf, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Attorney General (SC) ,
United States Nuclear Regulatory Commission Attachment Ito Serial: RNP-RA/10-0001 Page 1 of 1 AFFIRMATION The information contained in letter RNP-RA/10-0001 is true and correct to the best of my information, knowledge, and belief; and the sources of my information are officers, employees, contractors, and agents of Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. I declare under penalty of perjury that the foregoing is true and correct.
Executed On: I Ito L" Benjamin C. White Manager - Support Services -Nuclear HBRSEP, Unit No. 2
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/10-0001 Page 1 of 5 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES TO SECTION 3.3.2, "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS)
INSTRUMENTATION," AND SECTION 3.3.6, "CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION" Description of Current Condition Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," provides the operability requirements, allowed conditions, required actions, completion times, and surveillance requirements for the ESFAS instrumentation. Conditions D and E include a required action to place an inoperable channel in the trip condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or else initiate a reactor shutdown. Condition D would require a shutdown to Mode 4 and Condition E would require a shutdown to Mode 5. Function 4.c of Table 3.3.2-1 invokes Condition D for the inoperability of a Containment Pressure - High High channel to initiate Main Steam Line isolation. Functions 2.c and 3.b.(3) of Table 3.3.2-1 invoke Condition E for the inoperability of a Containment Pressure - High High channel to initiate Containment Spray and Phase B Containment Isolation, respectively.
Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.3.6, "Containment Ventilation Isolation System," provides the operability requirements, allowed conditions, required actions, completion times, and surveillance requirements for the Containment Ventilation Isolation instrumentation. Function 4, the initiation of Safety Injection, as listed in Table 3.3.6-1, includes the following note: "Refer to LCO 3.3.2, 'ESFAS Instrumentation,' Functions l.a-f for all initiation functions and requirements."
Description and Justification of the Proposed Change The proposed change to TS 3.3.2 will add a note to the Required Action for both Condition D and Condition E. The proposed Note for Condition D states, "For Function 4.c, a channel may be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance." The proposed Note for Condition E states, "For Functions 2.c and 3.b.(3), a channel may be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance."
The three specified functions are limited to the Containment Pressure - High High channels. The three safety functions of the Containment Pressure - High High channels are to isolate the main steam lines, initiate Containment Spray, and initiate Containment Phase B Isolation.
The Containment Pressure - High High channels are uniquely designed in that they are required to be energized to be in the trip condition. This design feature was chosen to ensure a loss of power would not result in an inadvertent initiation of containment spray, as the adverse consequences of initiating containment spray could be significant. Maintenance activities that may be required to return an inoperable channel to service often require that power to the channel be interrupted.
Extraordinary measures can be taken to maintain the trip signal with power to the channel
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/10-0001 Page 2 of 5 interrupted; however, these measures involve some risk to the plant. In order to remove a module without defeating the protection function, jumpers have to be installed in the rear of the respective instrument rack to bypass the module. These jumper installations would have to be installed "hot" directly on the terminations for the Vital AC Instrument Bus power supply to the rack. Therefore, even proper installation could cause arcing/spiking of the Vital AC power, which in turn could cause a loss of the Instrument Bus power. The consequences include the potential for plant perturbations, including the potential for unintended reactivity events or plant trips. These risks can be eliminated by allowing the trip function to be defeated during the performance of such maintenance activities. Current TS require initiation of a plant shutdown if the channel trip function is defeated after the initial 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action time has passed. The proposed notes would allow continued plant operation with the trip function defeated for maintenance purposes for a total of six hours, not including the initial six hour action time. The proposed Bases clarify that this six hours can consist of multiple shorter periods of time.
There are six Containment Pressure - High High channels. They are divided into two groups of three. The logic for actuation of the Emergency Safety Features for the three specified functions is two-out-of-three on two sets of three channels. Therefore, with one channel's trip function defeated, the safety functions will still actuate when required, assuming there is no failure of another channel in the inoperable channel's grouping of three channels.
For Function 4, Steam Line Isolation, if the Containment Pressure - High High actuation did fail, the steam lines will still automatically isolate on either High Steam Flow in Two Steam Lines Coincident with Tavg - Low, or High Steam Flow in Two Steam Lines Coincident with Steam Line Pressure - Low. Manual isolation is also available. For Function 2, Containment Spray, and Function 3b, Containment Phase B Isolation, if the Containment Pressure - High High actuation did fail, manual actuation is available.
Therefore, the six hour allowance is acceptable based on the low probability of an accident or transient occurring during that time period, the high probability that the Containment Pressure -
High High channels will still perform their actuation function, and the availability of other means to actuate the safety features. In most cases, six hours should provide sufficient time to perform maintenance activities required to return a channel to service.
The proposed change to TS 3.3.6 revises the Note for Function 4, the initiation of Safety Injection, as listed in Table 3.3.6-1, as follows: "Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1 for all initiation functions and requirements." The current TS note is inaccurate as it references Functions 1. a-f, but fails to include Function 1.g, which should be included. The proposed note, by referencing the function in general, captures each sub-function. This change to TS 3.3.6 represents an administrative correction, as there will be no actual changes to plant design or operation.
No Significant Hazards Consideration Determination Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. (PEC), is proposing changes to Appendix A, Technical Specifications (TS), of Facility Operating License No. DPR-23, for the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. The proposed changes will revise TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/10-0001 Page 3 of 5 Instrumentation," and TS 3.3.6, "Containment Ventilation Isolation System." The proposed change to TS 3.3.2 adds notes to allow for the performance of maintenance activities for an inoperable Containment Pressure - High High channel. The proposed change to TS 3.3.6 corrects an error related to table references.
An evaluation of the proposed changes has been performed in accordance with 10 CFR 50.91(a)(1) regarding no significant hazards considerations, using the standards in 10 CFR 50.92(c). A discussion of these standards as they relate to this amendment request 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 TS 3.3.2 are intended to allow for the performance of maintenance activities required to return an inoperable channel to service with the instrumentation and plant in a condition that reduces the probability of an inadvertent transient or the need for a plant shutdown., Therefore, the proposed change reduces the probability of an accident because the likelihood of accident initiation is decreased.
The emergency safety features that are actuated by the Containment Pressure - High High channels are Main Steam Line Isolation, Containment Spray, and Containment Phase B isolation. These safety features are intended to reduce the consequences of design basis accident scenarios. These safety features are still expected to function as designed.
Actuation from containment pressure exceeding the High High trip setpoint will still occur with one trip signal bypassed based on the input from the other five channels. Should an additional failure result in the inability to actuate based on Containment Pressure High High, there are other means to actuate these safety features in a timely manner. Main Steam Line Isolation based on High High containment pressure is only important for the assumed main steam line break inside containment. For such an accident, main steam line isolation will still automatically occur from either High Steam Flow in Two Steam Lines Coincident with Tavg - Low, or High Steam Flow in Two Steam Lines Coincident with Steam Line Pressure
- Low. In regard to Containment Spray and Containment Phase B Isolation, the operator can manually initiate these functions if automatic actuation did not occur and containment conditions warranted actuation. Therefore, there will not be a significant increase in the consequences of analyzed accidents.
The proposed change to TS 3.3.6 is an administrative correction and there will be no actual changes to plant design or operation.
Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/10-0001 Page 4 of 5
- 2. The Proposed Change Does Not Create the Possibility of a New or Different Kind of Accident From Any Previously Evaluated.
As described above, the proposed change to TS 3.3.2 would allow a single Containment Pressure - High High channel to not be in the trip condition for maintenance purposes for a limited period of time (up to six hours). This is a condition that is already allowed during the first six hours of the action statement. Therefore, no new accident initiators or precursors are introduced by the proposed change.
The proposed change to TS 3.3.6 is an administrative correction and there will be no actual changes to plant design or operation.
Therefore, operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. The Proposed Change Does Not Involve a Significant Reduction in the Margin of Safety.
As described above, the proposed change to TS 3.3.2 would allow a single Containment Pressure - High High channel to not be in the trip condition for a limited period of time (up to six hours) to allow an effective means of maintenance to return an inoperable channel to service. It is expected that safety systems will continue to function as designed with a single channel not in trip and therefore there will be no impact on the accident analyses or a reduction in the margin of safety.
The proposed change to TS 3.3.6 is an administrative correction and there will be no actual changes to plant design or operation.
Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant reduction in the margin of safety.
Based on the above discussion, Carolina Power and Light Company has determined that the requested change does not involve a significant hazards consideration.
Environmental Impact Consideration 10 CFR 51.22(c)(9) provides criteria for identification of licensing and regulatory actions for categorical exclusion from performing an environmental assessment. A proposed change for an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed change would not (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increases in the amounts of any effluents that may be released offsite; (3) result in a significant increase in individual or cumulative occupational radiation exposure. Carolina Power and Light Company, also known as Progress Energy Carolinas (PEC), Inc., has reviewed this request and determined the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/10-0001 Page 5 of 5 prepared in connection with the issuance of the amendment. The basis for this determination follows.
Proposed Change Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. (PEC), is proposing changes to Appendix A, Technical Specifications (TS), of Facility Operating License No. DPR-23, for the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. The proposed changes will revise TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)
Instrumentation," and TS 3.3.6, "Containment Ventilation Isolation System." The proposed change to TS 3.3.2 adds notes to allow for the performance of maintenance activities for an inoperable Containment Pressure - High-High channel. The proposed change to TS 3.3.6 corrects an error related to table references.
Basis The proposed 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 the No Significant Hazards Consideration Determination, the proposed change does not involve a significant hazards consideration.
- 2. As demonstrated in the No Significant Hazards Consideration Determination, the proposed change does not result in a significant increase in the consequences of an accident previously evaluated and does not result in the possibility of a new or different kind of accident. The proposed change is unrelated and hence has no impact on plant effluents from normal operation. Therefore, the proposed change does not result in a significant change in the types or significant increases in the amounts of any effluents that may be released offsite.
- 3. The proposed change does not alter any parameters that impact the individual and cumulative radiation exposure for HBRSEP, Unit No. 2. Therefore, the proposed change does not result in a significant increase in individual or cumulative occupational radiation exposures.
United States Nuclear Regulatory Commission Attachment III to Serial: RNP-RA/10-0001 3 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES TO SECTION 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS)
INSTRUMENTATION, AND SECTION 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION MARKUP OF TECHNICAL SPECIFICATIONS PAGES
ESFAS Instrumentation 3.3.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. C.1 Restore train to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OPERABLE status.
OR C.2.1 Be in MODE 3. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> AND C.2.2 Be in MODE 5. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> D. One channel NOTE -------------
inoperable. For Function 4.c, a channel may be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance.
D.1 Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> trip.
OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND D.2.2 Be in MODE 4. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> E. One Containment ------------ NOTE -------------
Pressure channel For Functions 2.c and 3.b.(3),
inoperable, a channel may be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance.
E.1 Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> trip.
OR E.2.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND E.2.2 Be in MODE 4. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> AND E.2.3 Be in MODE 5. 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> (continued)
HBRSEP Unit No. 2 3.3-21 Amendment No. 17-6
Containment Ventil ation Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Containment Ventilation Isolation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP MODES OR OTHER CHANNELS REQUIREMENTS SETPOINT SPECIFIED CONDITIONS
- 1. Manual Initiation 1,2.3,4,(a) 2 SR 3.3.6.6 NA
- 2. Automatic Actuation Logic and 2 trains SR 3.3.6.2 NA Actuation Relays 1,2,3,4,(a) SR 3.3.6.3 SR 3.3.6.5
- 3. Containment Radiation
- a. Gaseous 1,2,3,4,(a) 1 SR 3.3.6.1 (b)
SR 3.3.6.4 SR 3.3.6.7
- b. Particulate 1,2,3,4,(a) 1 SR 3.3.6.1 (b)
SR 3.3.6.4 SR 3.3.6.7
- 4. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1.-a-4, for all initiation functions and requirements.
(a) During movement of recently irradiated fuel assemblies within the containment.
(b) Trip Setpoint shall be in accordance with the methodology in the Offsite Dose Calculation Manual.
HBRSEP Unit No. 2 3.3-39 Amendment No. 196
United States Nuclear Regulatory Commission Attachment IV to Serial: RNP-RA/10-0001 3 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES TO SECTION 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS)
INSTRUMENTATION, AND SECTION 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION RETYPED TECHNICAL SPECIFICATIONS PAGES
ESFAS Instrumentation 3.3.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. C.1 Restore train to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OPERABLE status.
OR C.2.1 Be in MODE 3. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> AND C.2.2 Be in MODE 5. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> D. One channel - NOTE----------
inoperable. For Function 4.c, a channel may be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance.
D.1 Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> trip.
OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND D.2.2 Be in MODE 4. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> E. One Containment ------------NOTE .............
Pressure channel For Functions 2.c and 3.b.(3),
inoperable, a channel may be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance.
E.1 Place channel in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> trip.
OR E.2.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND E.2.2 Be in MODE 4. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> AND E.2.3 Be in MODE 5. 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> (continued)
HBRSEP Unit No. 2 3.3-21 Amendment No.
Containment Ventilation Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Containment Ventil ation Isol ation Instrumentation FUNCTION APPLICABLE REQUIRED SURVEILLANCE TRIP MODES OR OTHER CHANNELS REQUIREMENTS SETPOINT SPECIFIED CONDITIONS
- 1. Manual Initiation 1,2,3,4,(a) 2 SR 3.3.6.6 NA
- 2. Automatic Actuation Logic and 2 trains SR 3.3.6.2 NA Actuation Relays 1,2,3,4, (a) SR 3.3.6.3 SR 3.3.6.5
- 3. Containment Radiation
- a. Gaseous 1,2,3,4(a) 1 SR 3.3.6.1 (b)
SR 3.3.6.4 SR 3.3.6.7
- b. Particulate 1,2,3,4,(a) 1 SR 3.3.6.1 (b)
SR 3.3.6.4 SR 3.3.6.7
- 4. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.
(a) During movement of recently irradiated fuel assemblies within the containment.
(b) Trip Setpoint shall be in accordance with the methodology in the Offsite Dose Calculation Manual.
HBRSEP Unit No. 2 3.3-39 Amendment No.
United States Nuclear Regulatory Commission Attachment V to Serial: RNP-RA/10-0001 4 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES TO SECTION 3.3.2, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS)
INSTRUMENTATION, AND SECTION 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION RETYPED TECHNICAL SPECIFICATIONS BASES PAGES
ESFAS Instrumentation B 3.3.2 BASES ACTIONS C.1, C.2.1, and C.2.2 (continued) from full power conditions in an orderly manner and without challenging unit systems.
D.1, D.2.1, and D.2.2 Condition D applies to:
" Pressurizer Pressure-Low;
- Steam Line Differential Pressure-High;
- High Steam Flow in Two Steam Lines Coincident With Tavg
-Low or Coincident With Steam Line Pressure-Low; and
- Steam Line Isolation Containment Pressure - High High.
If one channel is inoperable, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> are allowed to restore the channel to OPERABLE status or to place it in the tripped condition. Generally this Condition applies to functions that operate on two-out-of-three logic. Therefore, failure of one channel places the Function in a two-out-of-two configuration. One channel must be tripped to place the Function in a one-out-of-two configuration that satisfies redundancy requirements.
Failure to restore the inoperable channel to OPERABLE status or place it in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> requires the unit be placed in MODE 3 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 4, these Functions are no longer required OPERABLE.
The Action for Condition D is modified by a Note that allows a channel for Function 4.c, Steam Line Isolation -
Containment Pressure - High High, to be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance purposes. The channel may be taken out of the trip condition multiple times provided the total time out of trip does not exceed 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (not including the initial 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action time). The (continued)
HBRSEP Unit No. 2 B 3.3-81 Revision No.
ESFAS Instrumentation B 3.3.2 BASES ACTIONS D.1, D.2.1, and D.2.2 (continued)
Containment Pressure - High High channels are uniquely designed in that they are required to be energized to be in the trip condition. Maintenance activities that interrupt power to the channel, such as, replacement of the comparator module, cause the channel to be taken out of the trip condition. Therefore, the note allows conducting these activities without being required to implement extraordinary measures to maintain the channel in the tripped condition.
The 6-hour allowance is considered acceptable based on the low probability of an accident during this time, another channel of Containment Pressure - High High must fail to prevent the isolation of the steam line from Containment Pressure - High High, and other ESFAS functions provide an automatic steam line isolation function.
E.1, E.2.1, and E.2.2 Condition E applies to:
- Safety Injection Containment Pressure-High; and
None of these signals has input to a control function.
Thus, two-out-of-three logic is necessary to meet acceptable protective requirements. However, a two-out-of-three design would require tripping a failed channel. This is undesirable because a single failure would then cause spurious containment spray initiation. Spurious spray actuation is undesirable because of the cleanup problems presented. Therefore, these channels are designed with two-out-of-three on two sets of three logic. One channel per set may be placed in trip and still maintain adequate margin to spurious spray actuation.
To avoid the inadvertent actuation of containment spray and Phase B containment isolation, no more than one channel per set may be placed in trip. Restoring the channel to OPERABLE status, or placing the inoperable channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, is sufficient to assure that the Function remains OPERABLE and minimizes the time that the Function may be in a partial trip condition (assuming the inoperable channel has failed high). The Completion Time is further (continued)
HBRSEP Unit No. 2 B 3.3-82 Revision No.
ESFAS Instrumentation B 3.3.2 BASES ACTIONS E.1, E.2.1, and E.2.2 (continued) justified based on the low probability of an event occurring during this interval. Failure to restore the inoperable channel to OPERABLE status, or place it in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, requires the unit be placed in MODE 3 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, MODE 4 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and MODE 5 within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 5, these Functions are no longer required OPERABLE.
The Action for Condition E is modified by a Note that allows a channel for Function 2.c, Containment Spray - Containment Pressure - High High, and Function 3.b.(3), Containment Phase B Isolation - Containment Pressure - High High, to be taken out of the trip condition for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for maintenance purposes. The channel may be taken out of the trip condition multiple times provided the total time out of trip does not exceed 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (not including the initial 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action time). The Containment Pressure - High High channels are uniquely designed in that they are required to be energized to be in the trip condition. Maintenance activities that interrupt power to the channel, such as, replacement of the comparator module, cause the channel to be taken out of the trip condition. Therefore, the note allows conducting these activities without being required to implement extraordinary measures to maintain the channel in the tripped condition. The 6-hour allowance is considered acceptable based on the low probability of an accident during this time, another channel of Containment Pressure -
High High must fail to prevent the initiation of containment spray or containment Phase B isolation from Containment Pressure - High High, and containment spray or containment Phase B isolation can be initiated manually.
F.1, F.2.1, and F.2.2 Condition F applies to:
- Manual Initiation of Steam Line Isolation.
For the Manual Initiation Function, this action addresses the train orientation of the relay logic. If a train or channel is inoperable, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> are allowed to return it to OPERABLE status. The specified Completion Time is (continued)
HBRSEP Unit No. 2 B 3.3-82a Revision No.