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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
Serial: RNP-RA/07-0073
Nov 19, 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 ADMINISTRATIVE CHANGES TO THE OPERATING LICENSE AND TECHNICAL SPECIFICATIONS
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 Operating License and 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 changes make administrative improvements to various Operating License and Technical Specifications sections as listed in Attachment II.
Attachment I provides an Affirmation as required by 10 CFR 50.30(b).
Attachment II provides a description of the current conditions and proposed changes, technical justification for 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 a retyped version of the affected TS pages.
In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the State of South Carolina.
Nuclear Regulatory Commission approval of the proposed license amendment by August 27, 2008, is requested, with a 30 day implementation period.
United States Nuclear Regulatory Commission Serial: RNP-RA/07-0073 Page 2 of 2
If you have any questions concerning this matter, please contact me at (843) 857-1253.
Sincerely, Original signed by C. T. Baucom C. T. Baucom Manager - Support Services - Nuclear
Attachments:
I. Affirmation II. Request for Administrative Changes to the Operating License and Technical Specifications III. Markup of Operating License and Technical Specifications Pages IV. Retyped Operating License and Technical Specifications Pages
RAC/rac
c: Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC) Mr. A. Gantt, Chief, Bureau of Radiological Health (SC) Dr. W. D. Travers, NRC, Region II Ms. M. Vaaler, NRC, NRR NRC Resident Inspector, HBRSEP Attorney General (SC)
United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/07-0073 Page 1 of 1
AFFIRMATION
The information contained in letter RNP-RA/07-0073 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: _16 Nov 2007______ _Original signed by T. D. Walt
__ T. D. Walt Vice President, HBRSEP, Unit No. 2
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0073 Page 1 of 4 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR ADMINISTRATIVE CHANGES TO THE OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Description of Current Conditions, Proposed Changes, and Technical Justification The proposed changes are to the following sections of the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Operating License (OL) and Technical Specifications (TS):
- 1. OL Section 3.G (1): The secondary water chemistry program requirements specified in this section are redundant to the requirements of TS 5.5.10, "Secondary Water Chemistry Program." Therefore, this condition is being deleted from the OL, as it is appropriately addressed as a TS program.
- 2. OL Section 3.G (2): The leakage reduction program requirements specified in this section are redundant to the requirements of TS 5.5.2, "Primary Coolant Sources Outside Containment." Therefore, this condition is being deleted from the OL, as it is appropriately addressed as a TS program.
- 3. TS Section 1.1, "Definitions:" In the last line of the definition for "SHUTDOWN MARGIN," the word "the" prior to 547°F is being deleted. This is a grammar change.
- 4. TS Section 3.1.7, "Rod Position Indication:" The footnote at the bottom of Page 3.1-15 was only applicable during Cycle 22. HBRSEP, Un it No. 2, is now in operating Cycle 25. Therefore, the footnote is obsolete and is being deleted.
- 5. TS Section 3.4.3, "RCS Pressure and Temperature (P/T) Limits" - Figure 3.4.3-1 and Figure 3.4.3-2: When these figures were issued in Amendment No. 202 (NRC letter dated February 7, 2005 -TAC NO. MC4160), some information that was on the proposed figures (Progress Energy letter dated August 19, 2004) was inadvertently omitted or typed incorrectly. Specifically, in Figure 3.4.3-1, in the notes at the top, the Upper Shell Plate Weld ID (W10201-1) was omitted and the words "allowance" and "instrumentation" were typed with an uppercase "A" or "I" instead of lower case. In Figure 3.4.3-2, in the notes at the top, the Upper Shell Plate Weld ID (W10201-1) and the Girth Weld ID (10-273) were omitted, the limiting ART Values for 3/4T of 147°F and 172°F were omitted, and the words "allowance" and "instrumentation" were typed with an uppercase "A" or "I" instead of lower case. Additionally, in the graph, the identifier for the 60°F/Hr curve is missing the "Hr" term. These errors are being corrected.
- 6. TS Section 3.4.9, "Pressurizer:" For Condition B, the symbol is being replaced with a < symbol. The current symbol is incorrect based on the LCO requirements that specify that a pressurizer heater capacity equal to or greater than 125 kW is acceptable.
- 7. TS Section 3.7.4, "Auxiliary Feedwater (AFW) System:" On the top of the table, the words "Actions (continued)" are being added and in Condition E, the term "OR" is being moved to the right to line up properly with the text consistent with Standard TS format. These are formatting changes.
- 8. TS Section 5.5.12, "Explosive Gas and Storage Tank Radioactivity Monitoring Program:" The HBRSEP, Unit No. 2, design is such that the concentration of oxygen in the Waste Gas United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0073 Page 2 of 4 Decay Tanks is controlled to be below the concentration at which a hydrogen explosion could occur, regardless of the hydrogen concentration. Therefore, by controlling the oxygen concentration to below limits, the combination of oxygen and hydrogen in the system will not be an explosive mixture. The current TS wording can imply there are limits for both hydrogen and oxygen. The term "hydrogen and" is being deleted for clarity.
These changes are administrative and are intended to ensure the TS are accurate and up-to-date. There will be no changes to the plant design or to the procedural cont rols for the operation, surveillance, or maintenance of the plant as a result of the proposed changes.
No Significant Hazards Consideration Determination Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc., is proposing changes to the Operating License and 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 changes are administrative as they delete requirements that are obsolete or redundant, or correct and clarify the typing and formatting of other requirements. The proposed changes will not result in changes to the plant design or the procedural controls for the operation, surveillance, or maintenance of the plant.
An evaluation of the proposed changes has been performed in accordance with 10 CFR 50.91(a)(1) regarding no significant hazards considerations using the standards in 10 CFR 50.92(c). A discussion of these standards as they relate to this amendment request follows:
- 1. Do the Proposed Changes Involve a Significant Increase in the Probability or Consequences of an Accident Previously Evaluated?
No. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed changes are administrative. The changes delete obsolete or redundant requirements, clarify existing requirements, and correct typing and formatting errors. There will be no resulting changes to the plant design or procedural controls. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Do the Proposed Changes Create the Possibility of a New or Different Kind of Accident From Any Previously Evaluated?
No. The proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. There are no physical changes being made to the plant or to the manner in which the plant is operated. Therefore, the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Do the Proposed Changes Involve a Significant Reduction in the Margin of Safety?
United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0073 Page 3 of 4 No. The proposed changes do not involve a significant reduction in the margin of safety. There are no physical changes being made to the plant or to the manner in which the plant is operated. The proposed changes are administrative. The changes delete obsolete or redundant requirements, clarify existing requirements, and correct t yping and formatting errors. Therefore, the changes do not involve a significant reduction in any margin of safety for HBRSEP, Unit No. 2. Based on the preceding discussion, it has been determined that the requested changes do 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 significan t increases in the am ounts 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 has reviewed this request and determined that 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., is proposing changes to the Operating License and 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 changes are administrative as they delete requirements that are obsolete or redundant, or correct and clarify the typing and formatting of other requirements. The proposed changes will not result in changes to the plant design or the procedural controls for the operation, surveillance, or maintenance of the plant.
Basis The proposed changes meet 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 changes do not involve a significant hazards consideration.
- 2. The proposed changes will not result in changes to the plant design or the procedural controls for the operation, surveillance, or maintenance of the plant. The proposed changes do not affect the generation or control of effluents. Therefore, the proposed changes will not United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/07-0073 Page 4 of 4 result in a significant change in the types or significant in creases in the amounts of any effluents that may be released offsite.
- 3. The proposed changes will not cause a significant increase in occupational radiation exposure. There are no proposed physical changes to the facility or to the manner in which the facility is operated. Therefore, the proposed changes will not result in a significant increase in individual or cumulative occupational radiation exposure.
United States Nuclear Regulatory Commission Attachment III to Serial: RNP-RA/07-0073 10 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR ADMINISTRATIVE CHANGES TO THE OPERATING LICENSE AND TECHNICAL SPECIFICATIONS
MARKUP OF OPERATING LICENSE AND TECHNICAL SPECIFICATIONS PAGES
Definitions 1.1
1.1 Definitions
HBRSEP Unit No. 2 1.1-5 Amendment No.
176 SHUTDOWN MARGIN a. All rod cluster control assemblies (RCCAs) are (continued) fully inserted except for the single RCCA of highest reactivity worth, which is assumed to
be fully withdrawn. With any RCCA not capable
of being fully inserted, the reactivity worth
of the RCCA must be accounted for in the
determination of SDM; and
- b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the 547 o F.
SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing
each slave relay and verifying the OPERABILITY of
each slave relay. The SLAVE RELAY TEST shall
include, as a minimum, a continuity check of
associated testable actuation devices.
STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during
the interval specified by the Surveillance
Frequency, so that all systems, subsystems, channels, or other designated components are
tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated
components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat
transfer rate to the reactor coolant.
TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip
OPERATIONAL TEST actuating device and verifying the OPERABILITY of (TADOT) required alarm, interlock, display, and trip
functions. The TADOT shall include adjustment, as
necessary, of the trip actuating device so that it
actuates at the required setpoint within the
required accuracy.
AFW System
3.7.4 HBRSEP
Unit No. 2 3.7-11 Amendment No.
176 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion
Time for Condition A
or B not met.
C.1 Be in MODE 3.
AND C.2 Be in MODE 4.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />
D. Steam driven AFW pump or flow path
inoperable in MODE 1, 2, or 3.
AND One motor driven AFW pump or flow path
inoperable in MODE 1, 2, or 3.
D.1 Be in MODE 3.
AND D.2 Be in MODE 4.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />
E. Four AFW flow paths inoperable in MODE 1, 2, or 3.
OR OR Three AFW pumps inoperable in MODE 1, 2, or 3.
E.1 ---------NOTE--------
LCO 3.0.3 and all other LCO Required
Actions requiring
MODE changes are
suspended until
one AFW pump and flow
path are restored to
OPERABLE status. ---------------------
Initiate action to restore one AFW pump
and flow path to
OPERABLE status.
Immediately
F. Required AFW pump and flow path inoperable
in MODE 4.
F.1 Initiate action to restore AFW pump and
flow path to OPERABLE
status.
Immediately
United States Nuclear Regulatory Commission Attachment IV to Serial: RNP-RA/07-0073 10 Pages (including cover page)
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REQUEST FOR ADMINISTRATIVE CHANGES TO THE OPERATING LICENSE AND TECHNICAL SPECIFICATIONS
RETYPED OPERATING LICENSE AND TECHNICAL SPECIFICATIONS PAGES
Definitions 1.1
1.1 Definitions
HBRSEP Unit No. 2 1.1-5 Amendment No. SHUTDOWN MARGIN a. All rod cluster control assemblies (RCCAs) are (continued) fully inserted except for the single RCCA of highest reactivity worth, which is assumed to
be fully withdrawn. With any RCCA not capable
of being fully inserted, the reactivity worth
of the RCCA must be accounted for in the
determination of SDM; and
- b. In MODES 1 and 2, the fuel and moderator temperatures are changed to 547 o F.
SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of
each slave relay. The SLAVE RELAY TEST shall
include, as a minimum, a continuity check of
associated testable actuation devices.
STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during
the interval specified by the Surveillance
Frequency, so that all systems, subsystems, channels, or other designated components are
tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated
components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
TRIP ACTUATING DEVICE A TADOT shall consist of operating the trip OPERATIONAL TEST actuating device and verifying the OPERABILITY of (TADOT) required alarm, interlock, display, and trip functions. The TADOT shall include adjustment, as
necessary, of the trip actuating device so that it
actuates at the required setpoint within the
required accuracy.
Rod Position Indication
3.1.7 HBRSEP
Unit No. 2 3.1-15 Amendment No.
3.1 REACTIVITY
CONTROL SYSTEMS
3.1.7 Rod Position Indication
LCO 3.1.7 The Analog Rod Position Indication (ARPI) System and the Demand Position Indication System shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTIONS
NOTE-------------------------------------
Separate Condition entry is allowed for each inoperable rod position indicator
per group and each demand position indicator per bank.
CONDITION REQUIRED ACTION COMPLETION TIME A. One ARPI per group inoperable for one or more groups.
A.1 Verify the position of the rods with
inoperable position
indicators by using
movable incore
detectors.
OR A.2 Reduce THERMAL POWER to 50% RTP.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B. One or more rods with inoperable position indicators have been
moved in excess of
24 steps in one
direction since the
last determination of
the rod's position.
B.1 Verify the position of the rods with inoperable position
indicators by using
movable incore
detectors.
OR 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
(continued)
Pressurizer
3.4.9 HBRSEP
Unit No. 2 3.4-21 Amendment No.
3.4 REACTOR
COOLANT SYSTEM (RCS)
3.4.9 Pressurizer
LCO 3.4.9 The pressurizer shall be OPERABLE with:
- a. Pressurizer water level 63.3% in MODE 1;
- b. Pressurizer water level 92% in MODES 2 and 3; and
- c. Pressurizer heaters OPERABLE with a capacity of 125 kW and capable of being powered from an emergency power supply.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level not within limit. A.1 Be in MODE 3 with reactor trip breakers open. AND A.2 Be in MODE 4.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B. Capacity of required pressurizer heaters
< 125 kW. B.1 Restore required pressurizer heaters to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C. Required pressurizer heaters not capable of being powered from an
emergency power
supply. C.1 Restore capability to power the required pressurizer heaters
from an emergency
power supply.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
(continued)
AFW System
3.7.4 HBRSEP
Unit No. 2 3.7-11 Amendment No.
ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion
Time for Condition A
or B not met.
C.1 Be in MODE 3.
AND C.2 Be in MODE 4.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />
D. Steam driven AFW pump or flow path
inoperable in MODE 1, 2, or 3.
AND One motor driven AFW pump or flow path
inoperable in MODE 1, 2, or 3.
D.1 Be in MODE 3.
AND D.2 Be in MODE 4.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />
E. Four AFW flow paths inoperable in MODE 1, 2, or 3.
OR Three AFW pumps inoperable in MODE 1, 2, or 3.
E.1 ---------NOTE--------
LCO 3.0.3 and all other LCO Required
Actions requiring
MODE changes are
suspended until
one AFW pump and flow
path are restored to
OPERABLE status. ---------------------
Initiate action to restore one AFW pump
and flow path to
OPERABLE status.
Immediately
F. Required AFW pump and flow path inoperable
in MODE 4.
F.1 Initiate action to restore AFW pump and
flow path to OPERABLE
status.
Immediately