Letter Sequence Approval |
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TAC:MD4250, Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors (Approved, Closed) |
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MONTHYEARML0720102362007-07-16016 July 2007 Tech Spec Pages for Amendment 216 to Adopt Technical Specifications Task Force (TSTF) Standard TS Change Traveler, TSTF-447, Using the Consolidated Line Item Improvement Process Project stage: Acceptance Review ML0715400012007-07-16016 July 2007 License Amendment 216 to Adopt Technical Specifications Task Force (TSTF) Standard TS Change Traveler, TSTF-447, Using the Consolidated Line Item Improvement Process Project stage: Approval RNP-RA/07-0095, Correction to Technical Specifications Page in Amendment 2162007-09-12012 September 2007 Correction to Technical Specifications Page in Amendment 216 Project stage: Other ML0725706282007-09-18018 September 2007 Correction to Technical Specification Pages Issued with Amendment No. 216 Issued on July 16, 2007 Project stage: Approval ML0725700692007-09-18018 September 2007 Correction to Technical Specification Pages Issued with Amendment No. 216 Issued on July 16, 2007 Project stage: Approval 2007-09-12
[Table View] |
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Category:Letter
MONTHYEARIR 05000261/20244012024-09-11011 September 2024 Security Baseline Inspection Report 05000261/2024401 ML24242A2612024-08-29029 August 2024 Operator Licensing Examination Approval 05000261/2024301 IR 05000261/20240052024-08-22022 August 2024 Updated Inspection Plan for H.B. Robinson Steam Electric Plant - Report 05000261/2024005 ML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area IR 05000261/20240022024-08-0101 August 2024 Integrated Inspection Report 05000261/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000261/20240112024-06-0303 June 2024 Focused Engineering Inspection- Commercial Grade Dedication Report 05000261/2024011 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping IR 05000261/20240012024-05-0909 May 2024 Integrated Inspection Report 05000261/2024001 IR 05000261/20240102024-04-30030 April 2024 Biennial Problem Identification and Resolution Inspection Report 05000261/2024010 IR 05000261/20230062024-02-28028 February 2024 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 - Report 05000261-2023006 IR 05000261/20243012024-02-0606 February 2024 – Notification of Licensed Operator Initial Examination 05000261/2024301 ML24033A0592024-02-0202 February 2024 Response to Request for Additional Information 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 IR 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 2024-09-11
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area 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 ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 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 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 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 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 ML22083A1072022-03-30030 March 2022 Presubmittal Licensee Presentation for SR 3.8.1.16 Proposed License Amendment Request (EPID L-2022-LRM-0021) (Slides) ML21155A2132021-08-26026 August 2021 Plant ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20058E8992020-06-18018 June 2020 Issuance of Amendment No. 267 Regarding Change to Surveillance Requirement 3.8.2.1 ML19205A2892019-09-24024 September 2019 Issuance of Amendment No. 266 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19158A3072019-08-15015 August 2019 Issuance of Amendment No. 265, Regarding Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b RA-18-0245, License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.12019-06-0404 June 2019 License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18200A0422018-08-16016 August 2018 Issuance of Amendment No. 260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18115A1502018-05-25025 May 2018 Issuance of Amendment 258 Regarding Request to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (CAC No. MF9544; EPID L-2017-LLA-0206) ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17102A9232017-05-18018 May 2017 Nonproprietary Issuance of Amendments Revising Technical Specifications for Methodology Reports DPC Ne 1008 P Revision 0, DPC Nf 2010 Revision 3 and DPC Ne 2011 P Revision 2 (CAC Nos. MF6648, MF6649, MF7693/MF7694) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17039A1532017-03-23023 March 2017 H.B. Robinson, Unit 2 - Issuance of Amendment 250 to Adopt Technical Specification Task Force (TSTF) Change Traveler TSTF-339, Revision 2, "Relocate TS Parameters to the COLR," Consistent with WCAP-14483 (CAC No. MF7615) ML16337A2642017-02-0303 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard 805 ML16201A1952016-10-11011 October 2016 Issuance of Amendment to Extend Containment Leakage Test Frequencies ML16217A1182016-09-13013 September 2016 Steam Electric Plants, Shearon Harris Nuclear Power Plant,Unit 1 -Issuance of Amendments 271, 299, 152 and 246 Re Change in Corporate Form of Duke Energy Progress, Inc ML16061A4722016-04-28028 April 2016 Issuance of Amendment to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML16049A6302016-03-0808 March 2016 Issuance of Amendments Revising Technical Specifications for Methodology Report DPC-NE-2005-P Revision 5, Thermal-Hydraulic Statistical Core Design Methodology ML15222B1752015-09-0808 September 2015 Issuance of Amendment to Modify Technical Specification 3.8.1, Diesel Generator Testing Requirements ML14318A9292014-12-19019 December 2014 H. B. Robinson; Shearon Harris Nuclear Power Plant; and Crystal River, Unit 3 - Issuance of License Amendments Regarding Revision to Cyber Security Plan Implementation Schedule Completion Date (TAC Nos. MF3263 - MF3267) ML13267A2932013-10-21021 October 2013 Issuance of Amendments 263, 291, 142 and 236 Re Name Change (TAC Nos, MF1463-MF1466) ML13198A3672013-08-29029 August 2013 Issuance of an Amendment to Revise the Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*) ML13114A7142013-05-29029 May 2013 Issuance of an Amendment to Eliminate Steam Generator Water Level-Low Coincident with Steam Flow/Feedwater Flow Mismatch Function from TS Table 3.1.1-1. Reactor Protection System Instrumentation (ME9516) ML13101A3692013-05-16016 May 2013 Issuance of an Amendment on Technical Specification Changes Regarding an Additional of a Note to Limiting Conditions for Operation 3.1.4 and 3.1.7 Allowing 1-Hour Soak Time ML13017A3812013-02-26026 February 2013 Issuance of Amendments Technical Specification Change to Add Limiting Condition of Operation 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML13014A6412013-02-13013 February 2013 Issuance of an Amendment Request for Technical Specifications Change Regarding Corrections to Table 3.3.1 Note ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security ML12160A4092012-07-0606 July 2012 Issuance of an Amendment Regarding Technical Specifications Change for Missed Surveillances Requirements, Technical Specification Task Force (TSTF) - 358 Missed Surveillance Requirements ML11342A1652011-12-29029 December 2011 Issuance of an Amendment on Technical Specifications Related to Use of Areva'S M5 Advanced Alloy in Fuel Cladding and Fuel Assembly Components ML11193A0282011-07-29029 July 2011 Issuance of Amendments Approval of Cyber Security Plan ML1104700022011-03-0707 March 2011 Issuance of an Amendment Regarding 3.3.2 Engineered Safety Features Actuation System Instrumentation and Section 3.3.6 Containment Ventilation Isolation Instrumentation ML1009904052010-05-0707 May 2010 Issuance of Amendment Regarding Technical Specifications Changes Related to Steam Generator Alternate Repair Criteria ML1008303302010-03-25025 March 2010 Issuance of Amendment Regarding Technical Specifications Changes Related to the Chemical and Volume Control System ML1001200682010-03-17017 March 2010 Issuance of Amendment Regarding Changes to the Technical Specifications Related to the Turbine Trip Input to the Reactor Protection System ML0910302432009-05-0707 May 2009 Issuance of Amendment Regarding Elimination of Work Hour Controls to Support Compliance with Revised Part 26 of Title 10 of Code of Federal Regulations 2024-08-14
[Table view] Category:Safety Evaluation
MONTHYEARML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24114A0152024-06-0303 June 2024 Unit 2 – Issuance of Amendment No. 279 Regarding Application of Leak-Before-Break Methodology for Auxiliary Reactor Coolant System Piping ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 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 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 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 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 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 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 ML21259A0992021-11-0404 November 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21242A2982021-09-21021 September 2021 Proposed Alternative to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21155A2132021-08-26026 August 2021 Plant ML21214A2222021-08-10010 August 2021 Proposed Alternatives to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21209A9962021-08-0202 August 2021 Proposed Alternative Request IST-RR-8 Related to the Inservice Testing Program ML21202A3982021-07-27027 July 2021 Relief Request Proposed Alternatives to American Society of Mechanical Engineers Operation and Maintenance Code Isolation Valve Seal Water System ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20097F0882020-06-19019 June 2020 Relief Request RA-19-0106 Regarding Proposed Alternative to ASME Code Case N-729-4 Volumetric or Surface Examination Requirements EPID-L-2019-LLR-0065) ML20058E8992020-06-18018 June 2020 Issuance of Amendment No. 267 Regarding Change to Surveillance Requirement 3.8.2.1 ML20021A0132020-02-19019 February 2020 Request for Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML19205A2892019-09-24024 September 2019 Issuance of Amendment No. 266 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19158A3072019-08-15015 August 2019 Issuance of Amendment No. 265, Regarding Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19121A4822019-06-11011 June 2019 Staff Evaluation the 2017 Annual Report of Changes and Error Corrections Affecting the Large-Break Loss-of-Coolant Accident Analysis ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18200A0422018-08-16016 August 2018 Issuance of Amendment No. 260 Regarding Request to Revise Technical Specification Reactor Coolant System Pressure and Temperature Limits to Reflect 24-Month Fuel Cycles ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18115A1502018-05-25025 May 2018 Issuance of Amendment 258 Regarding Request to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (CAC No. MF9544; EPID L-2017-LLA-0206) ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17102A9232017-05-18018 May 2017 Nonproprietary Issuance of Amendments Revising Technical Specifications for Methodology Reports DPC Ne 1008 P Revision 0, DPC Nf 2010 Revision 3 and DPC Ne 2011 P Revision 2 (CAC Nos. MF6648, MF6649, MF7693/MF7694) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17039A1532017-03-23023 March 2017 H.B. Robinson, Unit 2 - Issuance of Amendment 250 to Adopt Technical Specification Task Force (TSTF) Change Traveler TSTF-339, Revision 2, "Relocate TS Parameters to the COLR," Consistent with WCAP-14483 (CAC No. MF7615) ML16337A2642017-02-0303 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard 805 2024-08-14
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July 16, 2007Mr. Thomas D. Walt, Vice PresidentH. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550-0790
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - ISSUANCE OFAMENDMENT TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE (TSTF) STANDARD TS CHANGE TRAVELER, TSTF-447, USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MD4250)
Dear Mr. Walt:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 216 to FacilityOperating License No. DPR-23 for the H.B. Robinson Steam Electric Plant, Unit No. 2 (HBR).
This amendment consists of changes to the TSs in response to your application dated February 2, 2007. The amendment adopts the TSTF-447, Elimination of Hydrogen Recombiners and Change toHydrogen and Oxygen Monitors, which deletes the TS requirements related to containmenthydrogen monitors and supports implementation of the revisions of 10 CFR 50.44, CombustibleGas Control for Nuclear Power Reactors, that became effective on October 16, 2003. A copy of our related safety evaluation is also enclosed. The Notice of Issuance will beincluded in the Commission's next biweekly Federal Register notice. Sincerely,/RA/Lisa M. Regner, Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-261
Enclosures:
- 1. Amendment No. 216 to DPR-232. Safety Evaluationcc w/encls: See next page Mr. T. D. WaltH. B. Robinson Steam Electric Plant,Carolina Power & Light Company Unit No. 2 cc:
David T. ConleyAssociate General Counsel II - Legal Department Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, North Carolina 27602-1551Ms. Margaret A. ForceAssistant Attorney General State of North Carolina Post Office Box 629 Raleigh, North Carolina 27602U. S. Nuclear Regulatory CommissionResident Inspector's Office H. B. Robinson Steam Electric Plant 2112 Old Camden Road Hartsville, South Carolina 29550Mr. Ernest J. Kapopoulos, Jr.Plant General Manager H. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550Director of Site OperationsH. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550Public Service CommissionState of South Carolina Post Office Drawer 11649 Columbia, South Carolina 29211Ms. J. F. LucasManager - Support Services - Nuclear H. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550Mr. C. T. BaucomSupervisor, Licensing/Regulatory Programs H. B. Robinson Steam Electric Plant, Unit No. 2 Carolina Power & Light Company 3581 West Entrance Road Hartsville, South Carolina 29550Ms. Beverly Hall, Section ChiefN.C. Department of Environment and Natural Resources Division of Radiation Protection 3825 Barrett Dr.
Raleigh, North Carolina 27609-7721Mr. Robert P. GruberExecutive Director Public Staff - NCUC 4326 Mail Service Center Raleigh, North Carolina 27699-4326Mr. Henry H. Porter, Assistant DirectorSouth Carolina Department of Health Bureau of Land & Waste Management 2600 Bull Street Columbia, South Carolina 29201Mr. J. Paul FulfordManager, Performance Evaluation and Regulatory Affairs PEB 5 Carolina Power & Light Company Post Office Box 1551 Raleigh, North Carolina 27602-1551Mr. John H. O'Neill, Jr.Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street NW.
Washington, DC 20037-1128
Pkg ML071540002 Amendment ML071540001TS ML072010236*No significant change from SE InputMemoOFFICELPL2-2/PMLPL2-2/PMLPL2-2/LAITSB/BCLPL2-2/BCNAMELRegnerSBaileyCSolaTKobetz*BMozafari for TBoyce DATE7/3/077/16/077/3/073/21/077/16/07 CAROLINA POWER & LIGHT COMPANYDOCKET NO. 50-261H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 216Renewed License No. DPR-231.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Carolina Power & Light Company (thelicensee), dated July 17, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations(10 CFR) Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (I) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications, asindicated in the attachment to this license amendment; and paragraph 3.B. of Renewed Facility Operating License No. DPR-23 is hereby amended to read as follows:B. Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 216, are hereby incorporated in the license.The licensee shall operate the facility in accordance with the Technical Specifications. 3.This license amendment is effective as of the date of its issuance and shall beimplemented within 60 days.FOR THE NUCLEAR REGULATORY COMMISSION/RA/ Brenda Mozafari for Thomas H. Boyce Thomas H. Boyce, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Operating License No. DPR-23 and the Technical SpecificationsDate of Issuance: July 16, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 216RENEWED FACILITY OPERATING LICENSE NO. DPR-23DOCKET NO. 50-261Replace page 3 of Operating License No. DPR-23 with the attached page 3.Replace the following pages of the Appendix A Technical Specifications with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.Remove PageInsert Pages3.3-303.3-303.3-313.3-31 3.3-323.3-32 July 16, 2007SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 216 TORENEWED FACILITY OPERATING LICENSE NO. DPR-23CAROLINA POWER & LIGHT COMPANYH. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2DOCKET NO. 50-26
11.0 INTRODUCTION
By application to the Nuclear Regulatory Commission (NRC, Commission) datedFebruary 2, 2007, Carolina Power and Light Company (CP&L, the licensee), requested a change to the technical specifications (TS) for the H.B. Robinson Steam Electric Plant, Unit 2(HBR). The proposed change would delete the TS requirements associated with containment hydrogen monitors.The NRC has revised Title 10 to the Code of Federal Regulations (10 CFR), Section 50.44,Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors. Theamended standards eliminated the requirements for hydrogen recombiners and relaxed the requirements for hydrogen and oxygen monitoring. In letters dated December 17, 2002, and May 12, 2003, the Nuclear Energy Institute (NEI) Technical Specifications Task Force (TSTF) proposed to remove requirements for hydrogen recombiners and hydrogen and oxygen monitors from the standard technical specifications (STS) (NUREGs 1430 - 1434) on behalf of the industry. This proposed change was designated TSTF-447. Hydrogen purge systems are not part of the STS, however, the Commission eliminated the hydrogen release associated with a design-basis loss of coolant accident (LOCA) from 10 CFR 50.44 and the associated requirements that necessitated the need for the backup hydrogen vent and purge systems. The NRC staff prepared this model safety evaluation (SE) for the elimination of requirementsregarding containment hydrogen recombiners and the removal of requirements from TS for containment hydrogen and oxygen monitors and solicited public comment (67 FR 50374, August 2, 2002) in accordance with the Consolidated Line Item Improvement Process (CLIIP).
The use of the CLIIP in this matter is intended to help the NRC to efficiently process amendments that propose to remove the hydrogen recombiner and hydrogen and oxygen monitor requirements from TS. Licensees of nuclear power reactors to which this model applies were informed (68 FR 55416, September 25, 2003) that they could request amendments conforming to the model, and, in such requests, should confirm the applicability of this SE to their reactors and provide the requested plant-specific verifications and
commitments. 2.0 BACKGROUNDRegulatory Issue Summary 2000-06, Consolidated Line Item Improvement Process forAdopting Standard Technical Specification Changes for Power Reactors, was issued onMarch 20, 2000. The CLIIP is intended to improve the efficiency of NRC licensing processes.
This is accomplished by processing proposed changes to the STS in a manner that supports subsequent license amendment applications. The CLIIP includes an opportunity for the public to comment on proposed changes to the STS following a preliminary assessment by the NRC staff and finding that the change will likely be offered for adoption by licensees. The NRC staff evaluates any comments received for a proposed change to the STS and either reconsiders the change or proceeds with announcing the availability of the change for proposed adoption by licensees. Those licensees opting to apply for the subject change to TS are responsible forreviewing the staff's evaluation, referencing the applicable technical justifications, and providing any necessary plant-specific information. Each amendment application made in response to the notice of availability would be processed and noticed in accordance with applicable rules and NRC procedures.The Commission's regulatory requirements related to the content of TS are set forth in10 CFR 50.36. This regulation requires that the TS include items in five specific categories.
These categories include (1) safety limits, limiting safety system settings and limiting control settings, (2) limiting conditions for operation (LCO), (3) surveillance requirements, (4) design features, and (5) administrative controls. However, the regulation does not specify the particular TSs to be included in a plant's license.Additionally, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether anLCO is required to be included in the TS. These criteria are as follows:1.Installed instrumentation that is used to detect, and indicate in the control room,a significant abnormal degradation of the reactor coolant pressure boundary.2.A process variable, design feature, or operating restriction that is an initialcondition of a design-basis accident or transient analysis that assumes either the failure of or presents a challenge to the integrity of a fission product barrier. 3.A structure, system, or component that is part of the primary success path andwhich functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.4.A structure, system or component which operating experience or probabilisticrisk assessment has shown to be significant to public health and safety.Existing LCOs and related surveillances included as TS requirements which satisfy any of thecriteria stated above must be retained in the TS. Those TS requirements which do not satisfy these criteria may be relocated to other licensee-controlled documents.As part of the rulemaking that revised 10 CFR 50.44, the Commission retained requirements forensuring a mixed atmosphere, inerting Mark I and II containments, and providing hydrogen control systems capable of accommodating an amount of hydrogen generated from ametal-water reaction involving 75 percent of the fuel cladding surrounding the active fuel region in Mark III and ice condenser containments. The Commission eliminated the design-basisLOCA hydrogen release from 10 CFR 50.44 and consolidated the requirements for hydrogen and oxygen monitoring to 10 CFR 50.44 while relaxing safety classifications and licensee commitments to certain design and qualification criteria. The Commission also relocated without change the hydrogen control requirements in 10 CFR 50.34(f) to 10 CFR 50.44 and the high point vent requirements from 10 CFR 50.44 to 10 CFR 50.46a.3.0 EVALUATIONThe ways in which the requirements and recommendations for combustible gas control wereincorporated into the licensing bases of commercial nuclear power plants varied as a function of when plants were licensed. Plants that were operating at the time of the Three Mile Island (TMI), Unit 2, accident are likely to have been the subject of confirmatory orders that imposed the combustible gas control functions described in NUREG-0737, Clarification of TMI ActionPlan Requirements, as obligations. The issuance of plant-specific amendments adopting thechanges of TSTF-447 to remove hydrogen recombiner and hydrogen and oxygen monitoring controls from TS supersede the combustible gas control specific requirements imposed by post-TMI confirmatory orders. 3.1 Hydrogen Monitoring EquipmentSection 50.44(b)(1), the STS, and plant-specific TS currently contain requirements formonitoring hydrogen. Licensees have also made commitments to design and qualification criteria for hydrogen monitors in Item II.F.1, Attachment 6 of NUREG-0737 and RegulatoryGuide (RG) 1.97, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plantand Environs Conditions During and Following an Accident. The hydrogen monitors arerequired to assess the degree of core damage during a beyond design-basis accident and confirm that random or deliberate ignition has taken place. If an explosive mixture that could threaten containment integrity exists during a beyond design-basis accident, then other severe accident management strategies, such as purging and/or venting, would need to be considered.
The hydrogen monitors are needed to implement these severe accident management strategies.With the elimination of the design-basis LOCA hydrogen release, hydrogen monitors are nolonger required to mitigate design-basis accidents and, therefore, the hydrogen monitors do not meet the definition of a safety-related component as defined in 10 CFR 50.2. RG 1.97 recommends classifying the hydrogen monitors as Category 1. RG 1.97 Category 1 is intended for key variables that most directly indicate the accomplishment of a safety function for design-basis accident events and, therefore, are items usually addressed within TS. As part of the rulemaking to revise 10 CFR 50.44, the Commission found that the hydrogen monitors no longer meet the definition of Category 1 in RG 1.97. The Commission concluded that Category 3, as defined in RG 1.97, is an appropriate categorization for the hydrogen monitors because the monitors are required to diagnose the course of beyond design-basis accidents.
Hydrogen monitoring is not the primary means of indicating a significant abnormal degradation of the reactor coolant pressure boundary. Section 4 of Attachment 2 to SECY-00-0198, StatusReport on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on Risk-Informed Changes to 10 CFR 50.44 (Combustible Gas Control), found that the hydrogen monitors were not risk-significant. Therefore, the NRCstaff finds that hydrogen monitoring equipment requirements no longer meet any of the four criteria in 10 CFR 50.36(c)(2)(ii) for retention in TS and, therefore, may be relocated to other licensee-controlled documents.However, because the monitors are required to diagnose the course of beyond design-basisaccidents, each licensee should verify that it has, and make a regulatory commitment to maintain, a hydrogen monitoring system capable of diagnosing beyond design-basis accidents.The elimination of Post-Accident Sampling System requirements from some plant-specific TS(and associated CLIIP notices) indicated that during the early phases of an accident, safety-grade hydrogen monitors provide an adequate capability for monitoring containment hydrogen concentration. The NRC staff has subsequently concluded that Category 3 hydrogen monitors also provide an adequate capability for monitoring containment hydrogen concentration during the early phases of an accident.4.0 VERIFICATIONS AND COMMITMENTSAs requested by the NRC staff in the notice of availability for this TS improvement, the licenseehas addressed the following plant-specific verifications and commitments.4.1Each licensee should verify that it has, and make a regulatory commitment tomaintain, a hydrogen monitoring system capable of diagnosing beyond design-basis accidents.The licensee has verified that it has a hydrogen monitoring system capable of diagnosingbeyond design-basis accidents. The licensee has committed in its application to maintain the hydrogen monitors within its Updated Final Safety Analysis Report. The licensee will implement this commitment as part of the implementation of the amendment.4.2For plant designs with an inerted containment, each licensee should verify that ithas, and make a regulatory commitment to maintain, an oxygen monitoring system capable of verifying the status of the inert containment.This is not applicable as the licensee does not have an inerted containment.The NRC staff finds that reasonable controls for the implementation and for subsequentevaluation of proposed changes pertaining to the above regulatory commitments are provided by the licensee's administrative processes, including its commitment management program.
The NRC staff has determined that the commitments do not warrant the creation of regulatory requirements which would require prior NRC approval of subsequent changes. The NRC staff has agreed that NEI 99-04, Revision 0, Guidelines for Managing NRC Commitment Changes
,provides reasonable guidance for the control of regulatory commitments made to the NRC staff (see Regulatory Issue Summary 2000-17, Managing Regulatory Commitments Made by PowerReactor Licensees to the NRC Staff, dated September 21, 2000). The commitments should becontrolled in accordance with the industry guidance or comparable criteria employed by a specific licensee. The NRC staff may choose to verify the implementation and maintenance of these commitments in a future inspection or audit.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South Carolina State official was notifiedof the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
This amendment changes requirements with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed findingthat the amendment involves no significant hazards consideration and there has been no public comment on such finding (72 FR 20378, April 24, 2007). Accordingly, the amendment 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 need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) thereis 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. Principal Contributor: Trent Wertz Date: July 16, 2007