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Category:Letter
MONTHYEARIR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 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 IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 IR 05000261/20220022022-08-0909 August 2022 Integrated Inspection Report 05000261 2022002, 07200060 2022001 and Exercise of Enforcement Discretion ML22213A0682022-08-0505 August 2022 Request for Withholding Information from Public Disclosure for H. B. Robinson Steam Electric Plant, Unit 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves IR 05000261/20220112022-07-19019 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000261/2022011 ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22125A1942022-05-12012 May 2022 Request for Withholding Information from Public Disclosure for H.B. Robinson Steam Electric Plant, Unit 2 IR 05000261/20220012022-05-0202 May 2022 Integrated Inspection Report 05000261/2022001 IR 05000261/20224012022-04-19019 April 2022 Security Baseline Inspection Report 05000261/2022401 ML22098A2262022-04-11011 April 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22083A0032022-03-29029 March 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System IR 05000261/20210062022-03-0202 March 2022 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 (Report No. 05000261/2021006) 2024-01-08
[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:Bases Change
MONTHYEARRA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0057, Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical .2021-05-27027 May 2021 Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical . RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. RNP-RA/17-0041, Transmittal of Technical Specifications Bases Revisions2017-05-23023 May 2017 Transmittal of Technical Specifications Bases Revisions RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ML16116A0332016-04-24024 April 2016 Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Revision 2 RA-16-0005, Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 52016-02-0101 February 2016 Supplement to Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 RNP-RA/15-0086, Transmittal of Technical Specifications Bases Revisions2015-10-0808 October 2015 Transmittal of Technical Specifications Bases Revisions RNP-RA/15-0077, Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication2015-09-0101 September 2015 Submittal of Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report, 14-Day Report for the Inoperability of Pressurizer Power Operated Relief Valves Position Indication ML14188B0152014-06-20020 June 2014 Request for Technical Specifications (TS) Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion RNP-RA/14-0042, Transmittal of Technical Specifications Bases Revisions2014-04-29029 April 2014 Transmittal of Technical Specifications Bases Revisions RNP-RA/13-0038, Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication2013-04-24024 April 2013 Replacement of Technical Specification Pages to Correct Typographical Errors in Request for TS Changes Regarding TS 3.1.4 Rod Group Alignment Limits and TS 3.1.7 Rod Position Indication RNP-RA/12-0066, Transmittal of Technical Specifications Bases Revisions2012-09-17017 September 2012 Transmittal of Technical Specifications Bases Revisions RNP-RA/11-0095, Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process2012-02-10010 February 2012 Request for Technical Specifications Change Regarding Missed Surveillance Using the Consolidated Line Item Improvement Process RNP-RA/11-0002, Transmittal of Technical Specifications Bases Revisions2011-01-12012 January 2011 Transmittal of Technical Specifications Bases Revisions RNP-RA/10-0001, Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation2010-03-0505 March 2010 Request for Technical Specification Changes to Section 3.3.2, Engineered Safety Feature, Actuation System (ESFAS) Instrumentation, and Section 3.3.6, Containment Ventilation Isolation Instrumentation RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions2007-10-30030 October 2007 Transmittal of Technical Specifications Bases Revisions ML0702404832007-01-19019 January 2007 H. B. Robinson, Unit 2 - Resubmission of Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions2006-04-0606 April 2006 Transmittal of Technical Specifications Bases Revisions RNP-RA/04-0133, Transmittal of Technical Specifications Bases Revisions2004-10-21021 October 2004 Transmittal of Technical Specifications Bases Revisions RNP-RA/03-0038, Request for Technical Specifications Change Re Credit for Spent Fuel Storage Pool Dissolved Boron2003-05-28028 May 2003 Request for Technical Specifications Change Re Credit for Spent Fuel Storage Pool Dissolved Boron RNP-RA/03-0061, Transmittal of TS Bases Revisions2003-05-0202 May 2003 Transmittal of TS Bases Revisions RNP-RA/02-0118, Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term2002-08-14014 August 2002 Response to Request for Additional Information on Technical Specifications Change Re Selective Implementation of Alternative Radiological Source Term 2023-05-25
[Table view] |
Text
W R. GIDEON H. B. Robinson Steam Electric Plant Unit 2 ENERGY Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 10 CFR 50.90 Serial: RNP-RAI14-0053 JUN 2 0 2014 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 Request for Technical Specifications (TS) Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion Ladies and Gentlemen:
Pursuant to 10 CFR 50.90, Duke Energy Progress, Inc. is submitting a request for an amendment to the Technical Specifications (TS) for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2).
The proposed amendment would correct the accident-induced leakage performance criterion for the Steam Generator Program stated in TS 5.5.9.b.2.
Duke Energy Progress, Inc, has concluded that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c).The Enclosure provides an evaluation of the proposed change. Proposed TS markups and retyped page are included as attachments to the Enclosure.
There are no regulatory commitments made in this submittal.
Approval of the proposed license amendment is requested by May 15, 2015 with the amendment being implemented within 120 days of issuance.In accordance with 10 CFR 50.91, a copy of this application is being provided to the State of South Carolina.If you have any questions regarding this submittal, please contact Mr. R. Hightower at (843)857-1329.I declare under penalty of perjury that the foregoing is :true and correct.Executed On:_________
Sincer W.R.;Gideon Site Vice President
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United States Nuclear Regulatory Commission Serial: RNP-RA/14-0053 Page 2 of 2 WRG/jmw
Enclosure:
Evaluation of the Proposed Change cc: Mr. V. M. McCree, NRC, Region II Ms. Martha C. Barillas, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP, Unit No. 2 Ms. S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)
United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0053 Page 1 of 9 ENCLOSURE Evaluation of the Proposed Change
Subject:
Request for Technical Specification Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion 1.
SUMMARY
DESCRIPTION
- 2. DETAILED DESCRIPTION
- 3. TECHNICAL EVALUATION
- 4. REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria 4.2 No Significant Hazards Consideration Determination 4.3 Conclusions
- 5. ENVIRONMENTAL CONSIDERATION
- 6. REFERENCES ATTACHMENTS:
- 1. Technical Specification Page Markups 2. Retyped Technical Specification Page United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/1 4-0053 Page 2 of 9 1.0
SUMMARY
DESCRIPTION This evaluation supports a request to amend Appendix A to Renewed Operating License No.DPR-23 for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2).
The proposed change to Technical Specification (TS) 5.5.9.b.2 would correct the accident-induced leakage rate for any design basis accident other than a steam generator tube rupture. The accident-induced leakage rate value provided in TS 5.5.9.b.2 was incorrectly specified as 75 gallons per day (gpd) per steam generator and is being corrected to 150 gpd per steam generator.
Approval of the proposed license amendment is requested by May 15, 2015, with the amendment being implemented within 120 days of issuance.2.0 DETAILED DESCRIPTION The proposed change to Technical Specification (TS) 5.5.9.b.2 would correct an editorial error in the accident-induced leakage rate value for any design basis accident other than a steam generator (SG) tube rupture. During the HBRSEP2 licensing submittal of Technical Specifications Task Force (TSTF) 449, Revision 4, Steam Generator Tube Integrity, the accident-induced leakage rate value located in TS 5.5.9.b.2 was incorrectly specified as the operational leakage performance criterion (75 gpd per SG), which is indicated by reference to limiting condition for operation (LCO) 3.4.13, "RCS Operational LEAKAGE," in TS 5.5.9.b.3.
TS 5.5.9.b.2 is being corrected to specify the accident-induced leakage performance criterion value of 150 gpd per SG.NRC Generic Letter (GL) 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications, conveyed the NRC's concern that current TS requirements may not be sufficient to ensure that SG tube integrity can be maintained in accordance with current licensing and design basis. GL 2006-01 requested that addressees either submit a description of their program for ensuring SG tube integrity for the interval between inspections or adopt alternative requirements for ensuring SG tube integrity.
HBRSEP2 elected to adopt TSTF traveler 449, Rev. 4, which adequately addresses the NRC staff's concerns with the existing TS.On May 30, 2006, HBRSEP2 submitted a license amendment request (ADAMS Accession No.ML061520207) in accordance with the NRC-approved TSTF-449 model application.
The scope of this application includes, among other things, changes to the primary-to-secondary leakage requirements proposed by the TSTF as well as a HBRSEP2-specific change to the operational leakage performance criterion from 150 gpd to 75 gpd. This change was determined to be necessary to ensure there was sufficient (factor of 2) margin between the operational leakage limit and the accident-induced leakage limit, since such a margin between these limits was introduced in TSTF-449.The model application for TSTF-449, Rev. 4 contains an insert (Insert 5.5.9) that replaced HBRSEP2 TS 5.5.9, including TS 5.5.9.b.2, the last sentence of which states, "Leakage is not to exceed [lgpm] per SG." As with numerous other plant-specific values referenced in the application, the leak rate value required here is plant specific and is to be entered by the applicant in the space provided between the brackets.
HBRSEP2 inadvertently entered the incorrect value of 75 gpd for the accident-induced leakage rate in this sentence.
The correct value for the accident-induced leakage rate in this sentence is 150 gpd. The accident-induced United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0053 Page 3 of 9 leakage rate value is correctly specified throughout the remainder of the TSTF-449 submittal and no other corrections are requested.
3.0 TECHNICAL EVALUATION The requested change to TS 5.5.9.b.2 corrects an editorial error in the specified accident induced leakage performance criterion value. The technical basis for the requested change is established in the dose consequence analysis performed for Engineering Change (EC) 47161, Alternate Source Term Dose Analysis.
The calculations utilized the primary-to-secondary leakage value of 150 gpd per SG. This dose consequence analysis was incorporated into the HBRSEP2 licensing design basis via this EC. The HBRSEP2 UFSAR accident analysis (Chapter 15) was updated per Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, following the approval of the aforementioned dose consequence analysis by the Nuclear Regulatory Commission.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria The proposed TS change is a correction to an editorial error in TS 5.5.9.b.2 and does not adversely affect how the Steam Generator (SG) Program meets the associated regulatory requirements.
The associated regulatory requirements include TS 3.4.13.d, RCS Operational LEAKAGE, which states the RCS operational LEAKAGE shall be limited to 75 gpd through any one SG, and TS 5.5.9.b.2 provides the accident-induced leakage performance criterion (erroneously stated as 75 gpd per SG).4.2 No Significant Hazards Consideration Determination Duke Energy Progress, Inc. is proposing a change to Appendix A, Technical Specifications, of Facility Operating Renewed License No. DPR-23, for the H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2).
The proposed change to TS 5.5.9.b.2 is a correction to an editorial error in the specified accident-induced leakage performance criterion.
Duke Energy Progress, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No.
United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0053 Page 4 of 9 The proposed change is a correction to an editorial error in the specified accident induced leakage performance criterion of TS 5.5.9.b.2.
The error in TS 5.5.9.b.2 being addressed by this proposed change was introduced at the time of the HBRSEP2 submittal of the NRC-approved Technical Specification Task Force (TSTF) traveler 449, Rev. 4, Steam Generator Tube Integrity.
The accident-induced leakage performance criterion will continue to be within the limit assumed in the accident analysis.
As a result, neither the probability nor the consequences of any accident previously evaluated will be affected.Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No.No new or different accidents result from the proposed changes. The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation.
In addition, the changes do not impose any new or different requirements or eliminate any existing requirements.
The changes do not alter assumptions made in the safety analysis, it only corrects an editorial error in the accident-induced leakage performance criterion specified in the SG Program. The proposed changes are consistent with the safety analysis assumptions and current plant operating practice.Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?Response:
No.This change will have no effect on the margin of safety. This proposed change corrects an editorial error in the accident-induced leakage performance criterion specified in the SG Program.Therefore, the proposed change does not involve a significant reduction in a margin of safety.
United States Nuclear Regulatory Commission Enclosure to Serial: RNP-RA/14-0053 Page 5 of 9 Based on the above, Duke Energy Progress, Inc. concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.3 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.5.0 Environmental 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 of 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.
Duke Energy Progress, 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.
6.0 References
- 1. TSTF-449, Revision 4, Steam Generator Tube Integrity 2. HBRSEP2 UFSAR Section 15.6.3.2.3, Dose Analysis Assumptions
- 3. HBRSEP2 Engineering Change (EC) 47161 R3, Alternate Source Term Dose Analysis 4. HBRSEP2 Renewed Operating License, DPR-23, Appendix A, Technical Specifications Section 5.5.9, Steam Generator (SG) Program.5. HBRSEP2 License Amendment Request Submittal dated 5/30/2006, ADAMS Accession No. ML061520207 U. S. Nuclear Regulatory Commission Attachment I to Enclosure to Serial RNP-RAI14-0053 Page 1 of 2 H. B. Robinson Steam Electric Plant, Unit No. 2 Request for Technical Specifications (TS) Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion MARKUP OF TECHNICAL SPECIFICATIONS PAGE Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 Steam Generator (SG) Proqram A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained.
In addition, the Steam Generator Program shall include the following:
- a. Provisions for condition monitoring assessments.
Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes.Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.b. Performance criteria for SG tube integrity.
SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.1. Structural integrity performance criterion:
All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down) and all anticipated transients included in the design specification, and design basis accidents.
This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials.
Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse.
In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.2. Accident induced leakage performance criterion:
The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed -gallons per day per SG.3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE." (continued)
HBRSEP 5.0-12 Amendment No.
U. S. Nuclear Regulatory Commission Attachment II to Enclosure to Serial RNP-RAI14-0053 Page 1 of 2 H. B. Robinson Steam Electric Plant, Unit No. 2 Request for Technical Specifications (TS) Change Regarding Correction to TS 5.5.9.b.2, Steam Generator (SG) Program Accident-Induced Leakage Performance Criterion RETYPED TECHNICAL SPECIFICATIONS PAGE
- Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.9 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained.
In addition, the Steam Generator Program shall include the following:
- a. Provisions for condition monitoring assessments.
Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes.Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met.b. Performance criteria for SG tube integrity.
SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.1. Structural integrity performance criterion:
All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down) and all anticipated transients included in the design specification, and design basis accidents.
This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials.
Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse.
In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads.2. Accident induced leakage performance criterion:
The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 150 gallons per day per SG.3. The operational LEAKAGE performance criterion is specified in LCO 3.4.13, "RCS Operational LEAKAGE." (continued)
HBRSEP 5.0-12 Amendment No.