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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-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-21-0254, 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-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-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 RNP-RA/10-0117, Request for Technical Specification Changes to Section 3.8.3, Diesel Fuel Oil and Starting Air, and Section 3.8.5, DC Sources - Shutdown2011-01-20020 January 2011 Request for Technical Specification Changes to Section 3.8.3, Diesel Fuel Oil and Starting Air, and Section 3.8.5, DC Sources - Shutdown RA-10-011, Request for Approval of the Carolina Power & Light Company and Florida Power Corporation Cyber Security Plan2010-07-0808 July 2010 Request for Approval of the Carolina Power & Light Company and Florida Power Corporation Cyber Security Plan 2023-08-30
[Table view] Category:Technical Specification
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-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 RNP-RA/05-0107, Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass2005-11-30030 November 2005 Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass 2023-05-25
[Table view] Category:Amendment
MONTHYEARRA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0153, 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-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 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/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/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/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 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/07-0056, 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 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/05-0107, Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass2005-11-30030 November 2005 Request for Technical Specifications Change to Section 3.8.1 for the Diesel Generator Automatic Trips Bypass ML0522003672005-08-0202 August 2005 Technical Specification Pages Re Bases Control Program (Tac No. MC3636) ML0511102212005-04-19019 April 2005 Enclosure, Amendment No. 204 on TS Revisions to Eliminate Monthly Operating and Annual Occupational Radiation Exposure Report Requirements (Tac No. MC5129) RNP-RA/05-0005, Request for Technical Specifications Change to Section 3.8.4, DC Sources - Operating2005-02-14014 February 2005 Request for Technical Specifications Change to Section 3.8.4, DC Sources - Operating ML0405707022004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.3-20 Through 3.3-28 for Amendment 176 ML0405706622004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 1.3-1 Through 1.3-13 for Amendment 176 ML0405706652004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 1.1-1 Through 1.2-3 for Amendment 176 ML0405706702004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 1.4-1 Through 1.4-4 for Amendment 176 ML0405706752004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Operating License Effective Pages Through Technical Specifications Effictive Pages ML0405706832004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Table of Contents for Amendment 176 ML0405706872004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 2.0-1 Through 2.0-2 for Amendment 176 ML0405706912004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.0.1 Through 3.0.5 for Amendment 176 ML0405706942004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.1-1 Through 3.1-21 for Amendment 176 ML0405706962004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.2-1 Through 3.2-14 for Amendment 176 ML0405706992004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.3-1 Through 3.3-19 for Amendment 176 ML0407804992004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.6-1 Through 3.6-21 for Amendment 176 ML0407805072004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 5.0-1 Through 5.0-34 for Amendment 176 ML0407805052004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 4.0-1 for Amendment 176 Through 4.0-3 for Amendment 198 ML0407805042004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.9-1 Through 3.0-12 for Amendment 176 ML0407805022004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.8-1 for Amendment 176 Through 3.8-36 for Amendment 190 ML0407805002004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.7-1 Through 3.7-33 for Amendment 176 ML0405707052004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Techncial Specification Pages 3.3-29 Through 3.3-32 for Amendment 176 ML0407804962004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.5-1 Through 3.5-11 for Amendment 176 ML0407804942004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.4-1 Through 3.4-28 for Amendment 176 ML0407804912004-02-18018 February 2004 Informational Copy of Operating License & Appendices. Technical Specification Pages 3.4-29 Through 3.4-51 for Amendment 176 2023-02-16
[Table view] |
Text
10 CFR 50.90 Progress Energy Serial: RNP-RA/07-0124 NOV 1 2007 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 CHANGE TO SECTION 3.1.7 ROD POSITION INDICATION 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 3.1.7, "Rod Position Indication." The proposed change revises the requirements related to rod position indication. The requirements for one inoperable bank demand position indicator are proposed to be modified and a new condition, associated required actions, and completion times are proposed for two demand position indicators inoperable per bank for one or more banks.
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 changes, 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.
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 as rapidly as possible to provide an appropriate condition for two inoperable demand position indicators per bank for one or more banks.
Progress Energy Carolinas, Inc.
Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550
United States Nuclear Regulatory Commission Serial: RNP-RA/07-0124 Page 2 of 2 If you have any questions concerning this matter, please contact me at (843) 857-1253.
Sincerely, C. T. Baucom Manager - Support Services - Nuclear Attachments:
I. Affirmation II. Request for Technical Specifications Changes Related to Rod Position Indication III. Markup of Technical Specifications Pages IV. Retyped Technical Specifications Pages CTB/cac c: Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)
Mr. A. Gantt, Chief, Bureau of Radiological Health (SC)
Dr. W. D. Travers, NRC, Region II Ms. M. G. Vaaler, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Attorney General (SC)
United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/07-0124 Page 1 of 1 AFFIRMATION The information contained in letter RNP-RA/07-0124 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: , O T. D. Walt Vice President, HBRSEP, Unit No. 2
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 1 of 9 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES RELATED TO ROD POSITION INDICATION Description of Current Condition Technical Specifications (TS) Limiting Condition for Operation (LCO) Section 3.1.7, "Rod Position Indication," provides the operability requirements, allowed conditions, required actions, completion times and surveillance requirements associated with the Rod Position Indication system. The TS LCO Section 3.1.7, Condition C, provides the required actions and completion times for one demand position indicator per bank inoperable for one or more banks. Required Action C. 1.1 requires verification by administrative means that all analog rod position indicators (ARPIs) for the affected banks are operable once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when one bank demand position indicator is inoperable. There is no condition provided for two demand position indicators per bank inoperable for one or more banks.
Description and Justification of the Proposed Changes The proposed changes include deletion of Required Action C. 1.1 and the addition of a new condition, required actions, and completion times for the condition of two demand position indicators per bank inoperable for one or more banks. A description of the Rod Position Indication system is provided in the bases for LCO 3.1.7. A summary of the Rod Position Indication system as described in the bases for LCO 3.1.7 is provided as follows:
"The axial position of shutdown rods and control rods are determined by two separate and independent systems: the Bank Demand Position Indication System (commonly called group step counters) and the Analog Rod Position Indication (ARPI) System.
The Bank Demand Position Indication System counts the pulses from the Rod Control System that move the rods. There is one step counter for each group of rods. Individual rods in a group all receive the same signal to move and should, therefore, all be at the same position indicated by the group step counter for that group. The Bank Demand Position Indication System is considered highly precise (+/- 1 step or +/- 5/8 inch). If a rod does not move one step for each demand pulse, the step counter will still count the pulse and incorrectly reflect the position of the rod.
The ARPI System provides a highly accurate indication of actual control rod position, but at a lower precision than the step counters. This system is based on inductive analog signals from a series of coils spaced along a hollow tube with a center to center distance of 3.75 inches, which is 6 steps. Therefore, the normal indication accuracy of the ARPI System is +/- 6 steps
(+/- 3.75 inches), and the maximum uncertainty is +/- 12 steps (+/- 7.5 inches). With an indicated deviation of 12 steps between the group step counter and ARPI, the maximum deviation between actual rod position and the demand position could be 24 steps, -or 15 inches."
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 2 of 9 The proposed deletion of Required Action C. 1.1 is needed to avoid unnecessary power reduction to 50%. As currently written, Required Action C. 1.1 prevents any inoperable ARPIs in the same bank with one inoperable demand position indicator. Therefore, power reduction to _*50% would be required for an inoperable ARPI in the same bank as an inoperable demand position indicator, in accordance with the current Required Action C.2, or Required Action D. 1 if> 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> have elapsed since entry into Condition C. The requirement to verify ARPI operability in Required Action C. 1.1 is not necessary because Condition A of LCO 3.1.7 already provides the appropriate required actions for one inoperable ARPI per group. LCO 3.1.7, Condition A, requires verification of rod position (for the rod with the inoperable ARPI) once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> by use of the movable incore detectors.
Required Actions C. 1.2 and C. 1.3 are being renumbered to C. 1.1 and C. 1.2. These two required actions provide the requirements for verification of the position of each rod in the affected bank. If an ARPI is inoperable, the requirements of LCO 3.1.7, Condition A, will provide verification of the rod position using the movable incore detectors once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, which allows the completion of the renumbered Required Actions C. 1.1 and C. 1.2 (C. 1.2 and C. 1.3 in the current TS), which are also once per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion times.
The proposed new Condition D will establish the required actions and associated completion times for two inoperable bank demand position indicators per bank in one or more banks. Required Action D.1 will require placing the rod control system in manual and suspending movement of the affected bank(s) immediately. This will prevent further changes in rod position until at least one bank demand position indicator is restored for the affected bank(s). Required Action D.2 provides 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for restoration of one of the two inoperable bank demand position indicators in the affected bank(s). The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion time is appropriate based on the remaining available ARPI that provide indication of the position of the control rods and the completion of Required Action D. 1, which keeps the control rods in the affected banks at a constant position until at least one demand position indication is restored. If the required actions and associated completion time of Condition D are not met, Condition E (previously designated Condition D) would be entered, which requires the unit to be placed in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The proposed action to place the rod control system in manual and suspension of movement of the affected bank(s) normally cannot be met during operability testing of the affected bank demand position indicator. Therefore, LCO 3.0.5 can be invoked to allow not meeting proposed Required Action D. 1 during operability testing of the affected bank demand indicator to restore the indicator to operable status.
The required actions for proposed LCO 3.1.7, Condition D, are modified by a note that identifies the surveillance requirements and required action that are not required to be met during the time that no demand position indication is available in a bank. Specifically, the proposed note states that Surveillance Requirement (SR) 3.1.4.1, SR 3.1.5.1, SR 3.1.6.2, and LCO 3.1.7, Required Action C. 1.2, are not required to be met for the affected bank(s) until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after completion of Required Action D.2. This note is necessary to provide guidance for the surveillances and the action statement that cannot be met when both demand position indicators are inoperable for a bank.
The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time after restoration of one demand position indicator allows time to conduct the required surveillances. This could allow up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for restoration of one indicator
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 3 of 9 plus 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to conduct the surveillances). This time is appropriate and is justifiable based on the inoperabilities that have occurred. This LCO and its associated actions are provided for inoperability of rod position indication. There are no circumstances or postulated malfunctions in the rod position indication system that could cause one or more control rods being out of position, provided no rod movements of the affected bank have occurred while the two bank demand position indicators were inoperable. Therefore, prevention of rod movement during this condition is appropriate and the additional time to conduct required surveillances is justified.
If the failure of two bank demand position indicators were to occur during performance of SR 3.1.4.2, then the Applicability notes provided in LCO 3.1.5 and LCO 3.1.6 that state these LCOs are not required to be met, shall remain in effect until one demand position indicator is restored.
The SR 3.1.4.2 testing is currently conducted in conjunction with SR 3.1.7.2 and SR 3.1.7.3, which require movement of the bank Ž__ 19 steps to verify position indication system response. The use of the Applicability notes in LCO 3.1.5 and 3.1.6, when Condition D is entered during rod movement testing, will allow the insertion limit LCO for the bank being tested to be not met for some additional time. This is justified based on the testing remaining in progress until the rods are restored to the required positions and that there is no TS time limit specified for the testing.
Additionally, the applicable core power distribution limits specifications (i.e., LCO 3.2.1 Heat Flux Hot Channel Factor, LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor, LCO 3.2.3 Axial Flux Difference, and LCO 3.2.4 Quadrant Power Tilt Ratio) remain in effect in accordance with the Applicability requirements for these specifications.
The actions table for LCO 3.1.7 is modified by a note that allows separate condition entry for each inoperable rod position indicator per group and each demand position indicator per bank. This note will be applicable to the proposed Condition D. Entry into Condition D will be required anytime two demand position indicators are inoperable in one or more banks. The completion time for each bank with two inoperable demand position indicators would be 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from entry into Condition D, consistent with Completion Time Example 1.3-5 in Section 1.0 of the Technical Specifications.
As previously described, there are two demand position indicators per bank. Each bank is divided into two groups of rods that move in a staggered fashion within one step of each other. This is described in the bases for TS LCO 3.1.4 as follows:
"The OPERABILITY (e.g., trippability) of the shutdown and control rods is an initial assumption in all safety analyses that assume rod insertion upon reactor trip. Maximum rod misalignment is an initial assumption in the safety analysis that directly affects core power distributions and assumptions of available SDM [Shutdown Margin].
The applicable criteria for these reactivity and power distribution design requirements are described in the UFSAR [Updated Final Safety Analysis Report] and 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Plants."
Mechanical or electrical failures may cause a control rod to become inoperable or to become misaligned from its group. Control rod inoperability or misalignment may cause
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 4 of 9 increased power peaking, due to the asymmetric reactivity distribution and a reduction in the total available rod worth for reactor shutdown. Therefore, control rod alignment and OPERABILITY are related to core operation in design power peaking limits and the core design requirement of a minimum SDM.
Limits on control rod alignment have been established, and all rod positions are monitored and controlled during power operation to ensure that the power distribution and reactivity limits defined by the design power peaking and SDM limits are preserved.
Rod cluster control assemblies (RCCAs), or rods, are moved by their control rod drive mechanisms (CRDMs). Each CRDM moves its RCCA one step (approximately 5/8 inch) at a time, but at varying rates (steps per minute) depending on the signal output from the Rod Control System.
The RCCAs are divided among control banks and shutdown banks. Each bank may be further subdivided into two groups to provide for precise reactivity control. A group consists of two or more RCCAs that are electrically paralleled to step simultaneously. A bank of RCCAs consists of two groups that are moved in a staggered fashion, but always within one step of each other. HBRSEP has four control banks and two shutdown banks.
The shutdown banks are maintained either in the fully inserted or fully withdrawn position.
The control banks are moved in an overlap pattern, using the following withdrawal sequence: When control bank A reaches a predetermined height in the core, control bank B begins to move out with control bank A. Control bank A stops at the position of maximum withdrawal, and control bank B continues to move out. When control bank B reaches a predetermined height, control bank C begins to move out with control bank B. This sequence continues for the remaining control banks. The insertion sequence is the opposite of the withdrawal sequence. The control rods are arranged in a radially symmetric pattern, so that control bank motion does not introduce radial asymmetries in the core power distributions.
The axial position of shutdown rods and control rods is indicated by two separate and independent systems, which are the Bank Demand Position Indication System (commonly called group step counters) and the Analog Rod Position Indication (ARPI) System.
The Bank Demand Position Indication System counts the pulses from the rod control system that moves the rods. There is one step counter for each group of rods. Individual rods in a group all receive the same signal to move and should, therefore, all be at the same position indicated by the group step counter for that group. The Bank Demand Position Indication System is considered highly precise (+/- 1 step or +/- 5/8 inch). If a rod does not move one step for each demand pulse, the step counter will still count the pulse and incorrectly reflect the position of the rod.
The ARPI System provides a highly accurate indication of actual control rod position, but at a lower precision than the step counters. This system is based on inductive analog signals from a series of coils spaced along a hollow tube with a center'to center distance of
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 5 of 9 3.75 inches, which is six steps. The maximum uncertainty of the ARPI System is +/-12 steps
(+/- 7.5 inches). With an indicated deviation of 12 steps between the group step counter and ARPI, the maximum deviation between actual rod position and the demand position could be 24 steps, or 15 inches."
The proposed Condition D provides required actions and completion times for two inoperable demand position indicators per bank. In this condition, there are no operable demand position indicators in the bank that can be used for comparison to the ARPIs in that bank. As previously stated, under this condition suspending movement of the affected bank reduces the likelihood that an undetected rod misalignment can occur. Although, rod misalignment could be detected using the ARPIs and the movable incore detector system, if necessary.
When one bank demand position indicator is inoperable Condition C applies. The required surveillances and applicable required actions can be met under this condition because the operable demand position indicator for the bank can be used.
The rod position indication system is not modeled in the HBRSEP, Unit No. 2, probabilistic safety assessment (PSA). The PSA model does include failure of the reactor to trip and failure of control rods due to mechanical binding, but these conditions are unaffected by the proposed TS changes.
The proposed changes will not alter the ability to detect untrippable control rods. Additionally, the proposed Required Action D. 1 would not preclude the use of the control rod system in manual mode to mitigate an Anticipated Transient Without Scram (ATWS), because failure to meet Condition D. 1 would require entry into Condition E, which requires the unit to be placed in MODE 3 with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Therefore, the PSA results associated with the ability of the operator to use manual rod control to mitigate an ATWS event are unaffected.
Placing the rod control system in manual and suspending motion of the affected bank(s) as directed by proposed Required Action D. 1 does prevent the rod control system from automatically responding to a transient condition. Although not quantified, this could cause a very small increase in the likelihood of a reactor trip while the rod control system is in manual control (see UFSAR, Section 7.7.1.1, for a description of the rod control system). This minor change in reactor trip probability is considered to be less significant than the operational concerns posed by leaving the rod control system in automatic with no operable bank demand position indicators for the affected bank(s). There is no TS limitation on operation with the rod control system in manual.
Additionally, the current requirements of the HBRSEP, Unit No. 2, TS would require entry into LCO 3.0.3 when two bank demand position indicators are inoperable in one or more banks. The proposed condition, required actions, and completion times will reduce the likelihood that a shutdown of the reactor will be required for this condition, thereby avoiding placing the unit in a transient condition while there is no demand position indication available for one or more banks.
Comparison of the HBRSEP, Unit No. 2, TS to the guidance in NUREG- 1431, "Standard Technical Specifications - Westinghouse Plants," Revision 3, showsthat the current TS requirements for HBRSEP, Unit No. 2, are different than the guidance contained in NUREG-143 1. These differences are based on justification of deviations from NUREG- 1431 that were included in the license amendment associated with the conversion to Improved Standard Technical Specifications that was approved by the NRC in letter dated October 24, 1997. The current.TS include an identical
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 6 of 9 condition to the NUREG-1431 guidance that is applicable to one demand position indicator per bank inoperable for one or more banks. The required actions are also similar. The proposed deletion of HBRSEP, Unit No. 2, TS Required Action C. 1.1 to verify by administrative means that all ARPIs for the affected bank are operable is a less restrictive change to the current TS and a deviation from the NUREG- 1431 guidance. The justification for this change (as provided previously) states that this requirement is unnecessary because Required Action A. 1 provides the requirement to verify rod position for a rod with an inoperable ARPI and at least one demand position indicator remains operable for rod position comparison if only one demand position indicator is inoperable in the affected bank.
The proposed new Condition D is also less restrictive than the current TS requirements and a deviation from NUREG- 1431 guidance. A Technical Specifications Task Force (TSTF) Improved Standard Technical Specifications Change Traveler, designated TSTF-437-T, Revision 1, is available and provides one possible approach to correct the apparent error in NUREG- 1431 for the absence of a condition associated with more than one inoperable demand position indicator in a bank for one or more banks. The change described by TSTF-437-T allows the current condition for one inoperable demand position indicator to be used for more than one demand position indicator inoperable in a bank. Based on the current HBRSEP, Unit No. 2, TS requirements, this approach is not considered appropriate. As previously described in this TS change justification, two inoperable bank demand position indicators cause several other TS requirements to be not met, and therefore specific required actions and specific allowance for these circumstances is considered necessary for HBRSEP, Unit No. 2.
The preceding justifications provide the basis for the proposed changes. This TS change is being proposed at this time due to an inoperability of three demand position indicators (Shutdown Bank A Group 2, Control Bank A Group 2, and Control Bank C Group 2) and the determination that both demand position indicators for the three control rod banks (Shutdown Bank A and Control Banks A and C) would be made inoperable for a brief period in order to correct the malfunction. Therefore, this proposed TS change would establish a condition for inoperability of two demand position indicators for one or more banks. Additionally, during the preparation of this change it was noted that Required Action C. 1..1 is not needed and it is therefore proposed to be deleted. This proposed change is requested as rapidly as possible to allow appropriate TS requirements for repair of the rod position indication system.
No Significant Hazards Consideration Determination Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. (PEC), is proposing a change to Appendix A, Technical Specifications, of Facility Operating License No. DPR-23, for the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. The proposed change revises the requirements related to Limiting Condition for Operation (LCO) Section 3.1.7, Rod Position Indication. The requirements for one inoperable bank demand position indicator is proposed to be modified and a new condition, associated required actions, and completion times are proposed for two demand position indicators inoperable per bank for one or more banks.
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 7 of 9 An evaluation of the proposed change 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:
I1. The Proposed Change Does Not Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated.
The proposed change provides revised requirements for one demand position indicator inoperable and new requirements for two demand position indicators inoperable in one or more banks. The proposed change provides appropriately limiting requirements for these conditions. Additionally, the applicable core power distribution limits specifications (i.e.,
LCO 3.2.1 Heat Flux Hot Channel Factor, LCO 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor, LCO 3.2.3 Axial Flux Difference, and LCO 3.2.4 Quadrant Power Tilt Ratio) remain in effect in accordance with the Applicability requirements for these specifications. This ensures that the core power distribution remains within TS requirements or appropriate actions shall be taken. The proposed changes do not affect the automatic shutdown capability of the reactor protection system and no accident analyses are impacted by the proposed changes.
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.
- 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 provides revised requirements for one demand position indicator inoperable and new requirements for two demand position indicators inoperable in one or more banks. The proposed change provides appropriately limiting requirements for these conditions. No new accident initiators are introduced by the proposed requirements. The proposed change does not affect the reactor protection system or the reactor control system. Hence, no new failure modes are created that would cause a new or different kind of accident from any accident previously evaluated.
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.
The Bases of TS 3.1.7 states that the operability of the rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits. The proposed change does not alter the requirement to determine rod position, but provides revised requirements for one demand position indicator inoperable and new requirements for two demand position indicators inoperable in one or more banks. The proposed change provides appropriately limiting requirements for these
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 8 of 9 conditions. As a result, the initial conditions of the accident analyses are preserved, and the consequences of previously analyzed accidents are unaffected.
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, 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 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 a change 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 change revises the requirements related to rod position indication. The requirements for one inoperable bank demand position indicator are proposed to be modified and a new condition, associated required actions, and completion times are proposed for two demand position indicators inoperable per bank for one or more banks.
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.
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0124 Page 9 of 9 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 from which the individual and cumulative radiation exposure for HBRSEP, Unit No. 2, results. 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/07-0124 4 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES RELATED TO ROD POSITION INDICATION MARKUP OF TECHNICAL SPECIFICATIONS PAGES
Rod Puziilior IridicaLion 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to s 50% RTP.
C. One demand position C.1.1 "-rif, by 9ee;-
indicator per bank -adm4i;ni-4Fit mea.. 8-ours inoperable for one or &+ . .AR.f.
s L...
more banks. aff*cted banks am C.1./ ........ NOTE .........
Only required to be met for bank positions < 200 steps.
Verify the position Once per of each rod in the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> affected bank(s) is within 7.5 inches of the average of the individual rod positions in the affected bank(s).
AND (continued)
HRRSEP Unit No. 2 3-1-16 Ampndment No. .1-K
Rod Position Indication 3.1.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C1 ........ NOTE .........
Only required to be met for bank positions a 200 steps.
Verify the position Once per of each rod in the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> affected bank(s) is within 15 inches of the bank demand position.
OR C.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to s 50% RTP.
+/-;
,W' Required Action and associated Completion Time not met.J Xf.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> HBRSEP Unit No. 2 3.1-17 Amendment No. -?T
I Insert NOTE------- --------
U. Two demand position SR 3-1-4-1. SR 3.-15-1.
indicators per bank SR 3.1.6.2. and Required inoperable for one Action C-1-2 are not or more banks. required to be met for the affected bank(s) until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after completion of Required Action D.2.
D-1 Place the control Immediately rods under manual control and suspend movement of the affected bank(s).
AND D.2 Restore one demand 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> position indicator per bank.
United States Nuclear Regulatory Commission Attachment IV to Serial: RNP-RA/07-0124 3 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGES RELATED TO ROD POSITION INDICATION RETYPED TECHNICAL SPECIFICATIONS PAGES
Rod Position Indication 3.17 ACTIONS CONDITION REQUIRED ACTION CO1PLETION TIME B. (continued) Bý2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 5 50% RTP.
C. One demand position C.1.1 --------NOTE------
indicator per bank Only required to be inoperable for one or met for bank more banks. positions < 200 steps.
Verify the position Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of each rod in the affected bank(s) is within 7.5 inches of the average of the individual rod positions in the affected bank(s)-
AND C-1.2 --------
-- NOTE------
Only required to be I
met for bank positions t 200 steps.
Verify the position Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
of each rod in the affected bank(s) is within 15 inches of the bank demand position.
OR C.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to . 50% RTP.
(continued)
HBRSEP Unit No. 2 3-1-16 Amendment No.
Rod Position Indication 3.1.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
NOTE-------
D. Two demand position SR 3.1.4.1. SR 3.1.5.1.
indicators per bank SR 3.1.6.2. and Required inoperable for one Action C.1.2 are not required or more banks. to be met for the affected bank(s) until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after completion of Required Action D.2.
D-1 Place the control rods Immediately under manual control and suspend movement of the affected bank(s).
AND D.2 Restore one demand 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> position indicator per bank.
E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
HBRSEP Unit No. 2 3-1-17 Amendment No-