Letter Sequence Approval |
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MONTHYEARRBG-47350, License Amendment Request, Changes to Technical Specification 2.1.1, Reactor Core SLs2013-05-28028 May 2013 License Amendment Request, Changes to Technical Specification 2.1.1, Reactor Core SLs Project stage: Request ML13197A2622013-07-16016 July 2013 Acceptance Review Email, License Amendment Request, Revise Technical Specification 2.1.1., Reactor Core Sls, to Reduce Minimum Reactor Dome Pressure Associated with Critical Power Correlation Project stage: Acceptance Review ML14106A0002014-04-15015 April 2014 NRR E-mail Capture - River Bend Station, Unit 1, Request for Additional Information Regarding Proposed Changes to TS 2.1.1, Reactor Core SLs Project stage: RAI RBG-47464, License Amendment Request - Response to NRC RAI, Changes to Technical Specification 2.1.1, Reactor Core SLs2014-05-0808 May 2014 License Amendment Request - Response to NRC RAI, Changes to Technical Specification 2.1.1, Reactor Core SLs Project stage: Response to RAI ML14192A8312014-12-11011 December 2014 Issuance of Amendment No. 182, Revise Technical Specification 2.1.1, Reactor Core Sls, to Reduce Minimum Reactor Dome Pressure Associated with Critical Power Correlation Project stage: Approval 2014-12-11
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Category:Letter
MONTHYEARML25027A4212025-01-27027 January 2025 Entergy Operations, Inc. - Application to Revise Technical Specifications to Adopt TSTF-591, Revised Risk Informed Completion Time (RICT) Program RBG-48323, License Amendment Request to Revise the Licensing Basis and Minimum Basin Water Level for the Ultimate Heat Sink2024-12-30030 December 2024 License Amendment Request to Revise the Licensing Basis and Minimum Basin Water Level for the Ultimate Heat Sink ML24339B3042024-12-0404 December 2024 Application to Revise Technical Specifications to Use Online Monitoring Methodology ML24338A0522024-12-0303 December 2024 Entergy - 2024 Certification of Foreign Ownership and Control or Influence (FOCI) IR 05000458/20244012024-12-0202 December 2024 Material Control and Accounting Program Inspection Report 05000458/2024401 (Public Report) IR 05000458/20244032024-11-27027 November 2024 Security Baseline Inspection Report 05000458/2024403 (Public) IR 05000458/20244042024-11-21021 November 2024 Security Baseline Inspection Report 05000458/2024404 (Cover Letter Only) IR 05000458/20213012024-11-14014 November 2024 NRC Initial Operator Licensing Examination Approval 05000458/2021301 ML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) IR 05000458/20240102024-10-31031 October 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000458/2024010 IR 05000458/20240032024-10-31031 October 2024 Integrated Inspection Report 05000458/2024003 RBG-48306, Report of Changes and Errors to 10CFR50.462024-09-24024 September 2024 Report of Changes and Errors to 10CFR50.46 RBG-48315, Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement2024-09-24024 September 2024 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 Supplement ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24255A1192024-09-16016 September 2024 Notification of NRC Follow Up Inspection for One Severity Level (SL) III and Two SL IV or Three or More SL IV Violations and Request for Additional Information RBG-48311, Reply to a Notice of Violation, NRC Inspection Report 05000458/20240022024-08-28028 August 2024 Reply to a Notice of Violation, NRC Inspection Report 05000458/2024002 IR 05000458/20240052024-08-22022 August 2024 Updated Inspection Plan for River Bend Station (Report 05000458/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24214A2752024-08-0202 August 2024 Acknowledgement of Readiness for Supplemental Inspection RBG-48308, Notification of Readiness for Supplemental Inspection2024-07-31031 July 2024 Notification of Readiness for Supplemental Inspection IR 05000458/20240022024-07-30030 July 2024 Integrated Inspection Report 05000458/2024002 and Notice of Violation ML24205A0392024-07-30030 July 2024 Integrated Inspection Report 05000458/2024002 and Notice of Violation ML24164A0862024-06-12012 June 2024 Notification of Commercial Grade Dedication Inspection (05000458/2024010) and Request for Information 05000458/LER-2023-005-01, Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String2024-06-0404 June 2024 Manual Reactor Scram Due to Lowering Feedwater Temperature Following an Automatic Isolation of Feedwater Heater String ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24093A0892024-05-16016 May 2024 Issuance of Amendment No. 214 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24081A0072024-05-16016 May 2024 Issuance of Amendment No. 213 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b IR 05000458/20240012024-05-14014 May 2024 Integrated Inspection Report 05000458/2024001 ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions ML24102A2842024-05-0707 May 2024 Summary of Regulatory Audit in Support of LARs to Revise Technical Specifications to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69 RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024 2023 Annual Radioactive Effluent Release Report RBG-48288, Louisiana Pollutant Discharge Elimination System Permit Renewal2024-04-15015 April 2024 Louisiana Pollutant Discharge Elimination System Permit Renewal IR 05000458/20244022024-04-15015 April 2024 Security Baseline Inspection Report 05000458/2024402 (Full Report) ML24106A0432024-04-11011 April 2024 June 2024 Emergency Preparedness Exercise Inspection Request for Information ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair RBG-48277, 2023 Annual Radiological Environmental Operating Report2024-04-10010 April 2024 2023 Annual Radiological Environmental Operating Report ML24093A1122024-04-0202 April 2024 Notification of NRC Initial Operator Licensing Examination 05000458/2024301 ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) IR 05000458/20240402024-03-15015 March 2024 – 95001 Supplemental Inspection Report 05000458/2024040 and Follow-Up Assessment ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24066A1802024-03-0707 March 2024 Notification of NRC Follow-Up Inspection for Any Severity Level I or II Traditional Enforcement Violation IR 05000458/20230062024-02-28028 February 2024 Annual Assessment Letter for River Bend Station - Report 05000458/2023006 RBG-48278, 2023 Spent Fuel Storage Radioactive Effluent Release Report2024-02-27027 February 2024 2023 Spent Fuel Storage Radioactive Effluent Release Report RBG-48286, Revision to Owners Activity Report Form (OAR) for Cycle 222024-02-27027 February 2024 Revision to Owners Activity Report Form (OAR) for Cycle 22 ML24031A0042024-02-21021 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0052 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000458/LER-2023-006, Automatic Reactor Scram Due to a Turbine Trip Following a Disconnect Failure at Switchyard2024-02-0808 February 2024 Automatic Reactor Scram Due to a Turbine Trip Following a Disconnect Failure at Switchyard RBG-48274, Notification of Readiness for Supplemental Inspection2024-02-0505 February 2024 Notification of Readiness for Supplemental Inspection IR 05000458/20230042024-01-30030 January 2024 Integrated Inspection Report 05000458/2023004 2025-01-27
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24093A0892024-05-16016 May 2024 Issuance of Amendment No. 214 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22188A1742022-07-19019 July 2022 Issuance of Amendment No. 211 Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22026A4892022-03-22022 March 2022 Issuance of Amendment Nos. 225, 225, 227, 227, and 148, Respectively, Regarding Issues Identified in Westinghouse Documents (EPID L-2021-LLA-0066) Nonproprietary ML21162A2112021-07-0202 July 2021 Issuance of Amendment No. 208 to Adopt Generic Letter 86-10 Standard License Condition for Fire Protection ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20339A5182021-01-0606 January 2021 Issuance of Amendment No. 203 Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20244A0112020-09-28028 September 2020 Issuance of Amendment No. 202 Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- RITSTF Initiative 5b ML19357A0092019-12-31031 December 2019 Redacted - Issuance of Amendment No. 201 Change to the Neutron Absorbing Material Credited in Spent Fuel Pool for Criticality Control ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19071A2992019-06-19019 June 2019 Issuance of Amendment No. 198 Removal of Table of Contents from Renewed Operating License Technical Specifications ML19066A0082019-04-29029 April 2019 Issuance of Amendment Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18360A0252019-01-17017 January 2019 Redacted Version - Issuance of Amendment No. 195 Correction of a Non-Conservative Technical Specification for Pressure-Temperature Limits ML18345A3422018-12-21021 December 2018 Issuance of Amendment No. 194 Relocation of the Reactor Core Isolation Cooling Injection Point to the a Feedwater Line ML18284A3692018-12-20020 December 2018 Renewed Facility Operating License NPF-47 ML18267A3412018-11-0707 November 2018 Issuance of Amendment No. 193 Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18177A2362018-08-0101 August 2018 And Waterford 3 Steam Electric Station - LTR, Conforming Amendments and SE Regarding Order Approving Direct and Indirect Transfers of Licenses ML18177A3872018-07-31031 July 2018 Issuance of Amendment No. 192 Addition of New Technical Specification for Control Building Air Conditioning System ML16287A5992016-10-27027 October 2016 Issuance of Amendment No. 191, Revise Technical Specifications for Extension of Containment Leakage Tests Frequency ML16124A6882016-06-21021 June 2016 Issuance of Amendment No. 190 Cyber Security Plan Implementation Schedule ML15265A1162015-10-0101 October 2015 Issuance of Conforming Amendment to Reflect the Transfer of the Facility Operating License No. NPF-47 from Entergy Gulf States Louisiana, LLC to Entergy Louisiana, LLC ML15195A0612015-09-21021 September 2015 Issuance of Amendment No. 188 Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15187A1272015-07-30030 July 2015 Issuance of Amendment Application for Changes to Technical Specification 3.8.1, AC Sources-Operating ML15117A5752015-06-0202 June 2015 Issuance of Amendment No. 186 Heavy Load Movement Over Fuel Assemblies ML15071A4752015-03-19019 March 2015 Correction to License Amendment No. 185 Adoption of TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A ML14106A1672015-02-27027 February 2015 Issuance of Amendment No. 185, Adopt TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A Using Consolidated Line Item Improvement Process ML14225A4442014-12-12012 December 2014 Issuance of Amendment No. 183, Revise Technical Specification Surveillance Requirements Related to Ventilation Filter Testing Program for Heaters in Safety-Related Charcoal Filter Trains ML14304A1812014-12-12012 December 2014 Issuance of Amendment No. 184, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date ML14192A8312014-12-11011 December 2014 Issuance of Amendment No. 182, Revise Technical Specification 2.1.1, Reactor Core Sls, to Reduce Minimum Reactor Dome Pressure Associated with Critical Power Correlation ML14136A0082014-06-18018 June 2014 Issuance of Amendment No. 181, Revise Technical Specification 3.8.4, DC Sources - Operating SRs 3.8.4.2 and 3.8.4.5 to Add Acceptance Criteria to Address Non-conservative Conditions ML13322A4292014-03-0505 March 2014 Issuance of Amendment No. 180, Request to Adopt TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs Consolidated Line Item Improvement Process ML13060A2102013-03-29029 March 2013 Issuance of Amendment No. 179, Revise Technical Specification 3.3.8.1, Loss of Power Instrumentation, to Extend Frequency of Surveillance Requirement 3.3.8.1.3 and Revise Allowable Values of Certain Functions ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML12347A1402012-12-28028 December 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Issuance of Amendments, Revise QA Program Manual and Staff Qualification Technical Specifications ML12277A3082012-12-0505 December 2012 Issuance of Amendment No. 176, Revise Technical Specification 3.8.1, AC Sources - Operating for Testing of Automatic Transfer Function to Offsite Power for Division III Bus ML12261A4722012-12-0505 December 2012 Issuance of Amendment No. 177, Revise Physical Protection License Condition Related to Milestone No. 6 of the Cyber Security Plan Implementation ML12240A1802012-09-24024 September 2012 Issuance of Amendment No. 175, Emergency Plan Change to Relocate Alternate Emergency Operations Facility from 23 to 28 Miles from the Technical Support Center ML1210705572012-05-30030 May 2012 Issuance of Amendment No. 174, Revise Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation, for Main Steam Tunnel Temperature Function Setpoints ML1200902422012-02-0808 February 2012 Issuance of Amendment No. 173, Adopt Technical Specification Task Force (TSTF)-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML1124303342011-11-21021 November 2011 Issuance of Amendment No. 172, Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML1119402002011-07-29029 July 2011 Issuance of Amendment No. 171, Add License Condition and Approval of Cyber Security Plan and Associated Implementation Schedule ML1027901222011-01-0505 January 2011 Issuance of Amendment No. 170, Revise LCO 3.10.1, Inservice Leak and Hydrostatic Testing Operation, Consistent with TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities 2024-08-13
[Table view] Category:Safety Evaluation
MONTHYEARML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24081A0072024-05-16016 May 2024 Issuance of Amendment No. 213 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b ML24093A0892024-05-16016 May 2024 Issuance of Amendment No. 214 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22265A1802022-09-27027 September 2022 Proposed Alternative to the Requirements of ASME Code of Operation and Maintenance of Nuclear Power Plants for Pressure Isolation Valve Testing Frequency ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22026A4892022-03-22022 March 2022 Issuance of Amendment Nos. 225, 225, 227, 227, and 148, Respectively, Regarding Issues Identified in Westinghouse Documents (EPID L-2021-LLA-0066) Nonproprietary ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21258A4082021-09-21021 September 2021 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of Boiling Water Reactor Vessel and Internals Project Guidelines ML21162A2112021-07-0202 July 2021 Issuance of Amendment No. 208 to Adopt Generic Letter 86-10 Standard License Condition for Fire Protection ML21146A0182021-06-0808 June 2021 Issuance of Amendments to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML21040A2922021-03-0404 March 2021 Issuance of Amendments Adoption of TSTF 501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21011A0682021-02-0202 February 2021 Issuance of Amendments Adoption of TSTF 439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20339A5182021-01-0606 January 2021 Issuance of Amendment No. 203 Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20244A0112020-09-28028 September 2020 Issuance of Amendment No. 202 Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- RITSTF Initiative 5b ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML19357A0092019-12-31031 December 2019 Redacted - Issuance of Amendment No. 201 Change to the Neutron Absorbing Material Credited in Spent Fuel Pool for Criticality Control ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19261A1672019-09-27027 September 2019 Relief Request No. RBS-ISI-021, Proposed Alternative to 10 CFR 50.55a Examination Requirments for Third 10-Year Interval Volumetric Examinations ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19071A2992019-06-19019 June 2019 Issuance of Amendment No. 198 Removal of Table of Contents from Renewed Operating License Technical Specifications ML19066A0082019-04-29029 April 2019 Issuance of Amendment Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3 ML18360A0252019-01-17017 January 2019 Redacted Version - Issuance of Amendment No. 195 Correction of a Non-Conservative Technical Specification for Pressure-Temperature Limits ML18345A3422018-12-21021 December 2018 Issuance of Amendment No. 194 Relocation of the Reactor Core Isolation Cooling Injection Point to the a Feedwater Line ML18310A0132018-11-16016 November 2018 Relief from the Requirements of the ASME Code to Use Boiling Water Reactor Vessel Internals Guidelines as an Alternative ML18267A3412018-11-0707 November 2018 Issuance of Amendment No. 193 Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18299A2732018-11-0707 November 2018 Request for Relief from Requirements of Asme Code RBS-ISI-016 from the Requirements of the ASME Code for Pressure Retaining Welds in Control Rod Housings (EPID-L-2018-LLR-0042) ML18177A2362018-08-0101 August 2018 And Waterford 3 Steam Electric Station - LTR, Conforming Amendments and SE Regarding Order Approving Direct and Indirect Transfers of Licenses ML18212A1512018-07-31031 July 2018 License Renewal Safety Evaluation Report ML18177A3872018-07-31031 July 2018 Issuance of Amendment No. 192 Addition of New Technical Specification for Control Building Air Conditioning System ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML18122A1522018-05-17017 May 2018 Relief RR-RBS-ISI-015 from the Requirements of the ASME Code Regarding Reactor Vessel Weld Inspections ML17303A0862017-11-0202 November 2017 Relief to Use Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML17138A1442017-05-24024 May 2017 Relief from the Requirements of the ASME Code ML16287A5992016-10-27027 October 2016 Issuance of Amendment No. 191, Revise Technical Specifications for Extension of Containment Leakage Tests Frequency ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML15292A5082016-08-11011 August 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16124A6882016-06-21021 June 2016 Issuance of Amendment No. 190 Cyber Security Plan Implementation Schedule ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML15195A0612015-09-21021 September 2015 Issuance of Amendment No. 188 Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation ML15187A1272015-07-30030 July 2015 Issuance of Amendment Application for Changes to Technical Specification 3.8.1, AC Sources-Operating ML15156A8602015-06-30030 June 2015 Safety Evaluation Input - Regarding Application for Change to Technical Specifications 3.8.1, AC Sources - Operating 2024-08-13
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21162A2112021-07-0202 July 2021 Issuance of Amendment No. 208 to Adopt Generic Letter 86-10 Standard License Condition for Fire Protection ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20244A0112020-09-28028 September 2020 Issuance of Amendment No. 202 Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- RITSTF Initiative 5b ML19357A0092019-12-31031 December 2019 Redacted - Issuance of Amendment No. 201 Change to the Neutron Absorbing Material Credited in Spent Fuel Pool for Criticality Control ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML18284A3702018-12-20020 December 2018 Renewed Facility Operating License NPF-47 Attachments and Appendices ML16224B0752016-09-19019 September 2016 NRC Response to Request for Interpretation of Technical Specifications RBG-47626, ISFSI - Correction of Technical Specification Typographical Errors2015-10-27027 October 2015 ISFSI - Correction of Technical Specification Typographical Errors ML15195A0612015-09-21021 September 2015 Issuance of Amendment No. 188 Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation RBG-47600, Request for Interpretation of Technical Specifications2015-08-0404 August 2015 Request for Interpretation of Technical Specifications ML15187A1272015-07-30030 July 2015 Issuance of Amendment Application for Changes to Technical Specification 3.8.1, AC Sources-Operating ML15117A5752015-06-0202 June 2015 Issuance of Amendment No. 186 Heavy Load Movement Over Fuel Assemblies ML14106A1672015-02-27027 February 2015 Issuance of Amendment No. 185, Adopt TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A Using Consolidated Line Item Improvement Process ML14192A8312014-12-11011 December 2014 Issuance of Amendment No. 182, Revise Technical Specification 2.1.1, Reactor Core Sls, to Reduce Minimum Reactor Dome Pressure Associated with Critical Power Correlation ML14136A0082014-06-18018 June 2014 Issuance of Amendment No. 181, Revise Technical Specification 3.8.4, DC Sources - Operating SRs 3.8.4.2 and 3.8.4.5 to Add Acceptance Criteria to Address Non-conservative Conditions ML13322A4292014-03-0505 March 2014 Issuance of Amendment No. 180, Request to Adopt TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs Consolidated Line Item Improvement Process RBG-47380, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases2013-07-25025 July 2013 Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases RBG-47350, License Amendment Request, Changes to Technical Specification 2.1.1, Reactor Core SLs2013-05-28028 May 2013 License Amendment Request, Changes to Technical Specification 2.1.1, Reactor Core SLs RBG-47345, Supplement to License Amendment Request 2011-052013-03-0808 March 2013 Supplement to License Amendment Request 2011-05 CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications RBG-47191, Changes to Technical Specification 3.8.1; AC Sources - Operating2011-12-0808 December 2011 Changes to Technical Specification 3.8.1; AC Sources - Operating RBG-47163, Supplement to License Amendment Request Application for Technical Specification Changes Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-427, Allowance For..2011-07-27027 July 2011 Supplement to License Amendment Request Application for Technical Specification Changes Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-427, Allowance For.. RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation2011-07-27027 July 2011 License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation RBG-47062, Unit 1, Response to Request for Additional Information on License Amendment Request 2009-05, 24-Month Fuel Cycles2010-08-17017 August 2010 Unit 1, Response to Request for Additional Information on License Amendment Request 2009-05, 24-Month Fuel Cycles ML0933605812009-12-14014 December 2009 Correction of Errors in Amendment Nos. 165 and 166 RBG-46981, Correction of Technical Specification Typographical Errors2009-11-30030 November 2009 Correction of Technical Specification Typographical Errors ML0901301612009-01-23023 January 2009 Issuance of Amendment No. 161, Revise Technical Specification Surveillance Requirements Consistent with TSTF-475, Revision 1, Control Rod Notch Surveillance Frequency ML0802802302008-02-28028 February 2008 License and Technical Specification Pgs, Amendment No. 159, Revision of Required Wattage in TS 5.5.7.e, Ventilation Filter Testing Program for Control Room Fresh Air System Heater ML0804402932008-01-25025 January 2008 License Amendment Request, Main Turbine Bypass System ML0722200262007-08-30030 August 2007 Tech Spec Page for Amendment 153 Changes to the Analytical Methods Referenced in Technical Specification 5.6.5, Core Operating Limits Report (Colr) ML0709204582007-05-0303 May 2007 Tech Spec Page for Amendment 152 Leakage Rate Testing Containment Purge Valves RBG-46552, License Amendment Request, Leakage Rate Testing of Containment Purge Valves2006-09-19019 September 2006 License Amendment Request, Leakage Rate Testing of Containment Purge Valves ML0613802362006-05-17017 May 2006 Technical Specifications, Removal of Temp Note to Loss of Power ML0606004262006-02-0909 February 2006 Technical Specifications Pages Re Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval RBG-46510, License Amendment Request Removal of Temporary Note to Loss of Power Instrumentation Requirements2005-12-19019 December 2005 License Amendment Request Removal of Temporary Note to Loss of Power Instrumentation Requirements ML0529800692005-10-0707 October 2005 Tech Spec Pages for Amendment 148 Regarding Technical Specifications 3.8.4 Actions for Inoperable Battery Charger ML0527303232005-09-15015 September 2005 Tech Spec Page for Amendment 147 Regarding Corrections to Loss of Power Instrumentation Requirements RBG-46474, License Amendment Request Re Corrections to Loss of Power Instrumentation Requirements2005-08-31031 August 2005 License Amendment Request Re Corrections to Loss of Power Instrumentation Requirements ML0526303962005-08-25025 August 2005 Tech Spec Pages for Amendment 146 Regarding End-of-Cycle Recirculation Pump Trip Instrumentation ML0515200962005-05-25025 May 2005 Technical Specifications, Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports RBG-46404, License Amendment Request LAR 2005-01, One-time Extension of the Integrated Leak Rate Test Interval2005-03-0808 March 2005 License Amendment Request LAR 2005-01, One-time Extension of the Integrated Leak Rate Test Interval ML0432101302004-10-15015 October 2004 Technical Specifications, Delete Shield Building Annulus Mixing System Technical Specification ML0432101402004-10-15015 October 2004 Technical Specification Pages Re One-Time Extension of Drywell Bypass Leakage Rate Test Interval ML0427902222004-10-0404 October 2004 Technical Specification Pages, Amendment Elimination of Requirements for Hydrogen Recombiners and Change of Requirements for Hydrogen and Oxygen Monitors 2023-12-14
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61 N St. Francisville, LA 70775 December 11, 2014
SUBJECT:
RIVER BEND STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE:
TECHNICAL SPECIFICATION 2.1.1, "REACTOR CORE SLS" (TAC NO. MF1948)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 182 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 28, 2013, as supplemented by letter dated May 8, 2014.
The amendment revises TS 2.1.1, "Reactor Core SLs [Safety Limits]," to reduce the reactor dome pressure from 785 pounds per square inch gauge (psig) to 685 psig. General Electric Nuclear Energy reported a calculational "defect" under Title 10 of the Code of Federal Regulations (1 0 CFR) Part 21. As a result of improved calculation methods, a "defect" was found concerning a potential to momentarily violate the reactor safety limits in TSs 2.1.1.1 and 2.1.1.2 during a Pressure Regulator Failure-Open transient.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Docket No. 50-458
Enclosures:
- 1. Amendment No. 182 to NPF-47
- 2. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, C
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Alan B. Wang, Projecaanager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Ltcensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY GULF STATES LOUISIANA. LLC AND ENTERGY OPERATIONS, INC.
DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 182 License No. NPF-47
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee), dated May 28, 2013, as supplemented by letter dated May 8, 2014, 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 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment 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 license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 182 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
Attachment:
Changes to the Facility Operating License No. NPF-47 and Technical Specifications FOR THE NUCLEAR REGULA TORY COMMISSION Douglas A. Broaddus, Chief Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Dateoflssuance: December 11, 2014
ATTACHMENT TO LICENSE AMENDMENT NO. 182 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Facility Operating License No. NPF-47 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
Facility Operating License Remove Technical Specifications Remove 2.0-1 2.0-1 (3)
EO I, pursuant to the Act and 10 CFR Part 70, to receive, possess and to use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 0 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level EOI is authorized to operate the facility at reactor core power levels not in excess of 3091 megawatts thermal (100% rated power) in accordance with the conditions specified herein. The items identified in Attachment 1 to this license shall be completed as specified. is hereby incorporated into this license.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 182 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 182
2.0 SAFETY LIMITS (Sls) 2.1 Sls 2.1.1 Reactor Core Sls Sls 2.0 2.1.1.1 With the reactor steam dome pressure < 685 psig or core flow < 10%
rated core flow:
THERMAL POWER shall be~ 23.8% RTP.
2.1.1.2 With the reactor steam dome pressure ~ 685 psig and core flow
~ 1 0% rated core flow:
MCPR shall be ~ 1.08 for two recirculation loop operation or~ 1.10 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be~ 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all Sls; and 2.2.2.2 Insert all insertable control rods.
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager and the corporate executive responsible for overall plant nuclear safety.
(continued)
RIVER BEND 2.0-1 Amendment No. ~. 99, W, +Ga, 444' 4-2-2, 182
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 182 TO FACILITY OPERATING LICENSE NO. NPF-47
1.0 INTRODUCTION
ENTERGY OPERATIONS, INC.
RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458 By application dated May 28, 2013 (Reference 1 ), as supplemented by letter dated May 8, 2014 (Reference 2), Entergy Operations, Inc. (Entergy, the licensee), requested changes to the Technical Specifications (TSs) for the River Bend Station, Unit 1 (RBS). The supplemental letter dated May 8, 2014, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published in the Federal Register on August 6, 2013 (78 FR 47788).
The license amendment request (LAR) proposed to revise TS 2.1.1, "Reactor Core SLs [Safety Limits]," and associated Bases. General Electric (GE) Nuclear Energy reported a calculational "defect" under Title 10 of the Code of Federal Regulations (1 0 CFR) Part 21. As a result of improved calculation methods, a "defect" was found concerning a potential to momentarily violate the reactor safety limits in TSs 2.1.1.1 and 2.1.1.2 during a Pressure Regulator Failure-Open transient if the reactor steam dome pressure were to drop below 785 pounds per square inch gauge (psig).
These changes resolve this 10 CFR Part 21 defect by providing analysis to demonstrate that the reactor dome pressure can be as low as 700 pounds per square inch atmospheric (psia), or approximately 685 psig. The reduction in reactor dome pressure alleviates the potential to momentarily violate the reactor safety limits (SLs) in TSs 2.1.1.1 and 2.1.1.2 during a Pressure Regulator Failure-Open (PRFO) transient.
2.0 REGULATORY EVALUATION
The purpose of the SLs is to ensure that specified acceptable fuel design limits (SAFDLs) are not exceeded during steady-state operation and analyzed transients. The fuel cladding is one of the physical barriers that separate the radioactive materials from the environment. The integrity of this cladding barrier is related to its relative freedom from perforations or cracking.
Fuel cladding perforations can result from thermal stresses, which can occur from reactor operation significantly above design conditions. Since the parameters that result in fuel damage are not directly observable during reactor operation, the thermal and hydraulic conditions that result in the onset of transition boiling (OTB) have been used to mark the beginning of the region in which fuel cladding damage could occur.
The LAR includes changes to the TS, the contents of which are controlled by requirements in 10 CFR Section 50.36, "Technical specifications." TSs are required to include items in the following five categories related to plant operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
Criterion 10, "Reactor design," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR, Part 50 states, in part, that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that SAFDLs are not exceeded.
NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," provides guidance on the acceptability of the reactivity control systems, the reactor core, and fuel system design. Specifically, Section 4.2, "Fuel System Design" (Reference 3), specifies all fuel damage criteria for evaluation of whether fuel designs meet the SAFDLs. Section 4.4, "Thermal Hydraulic Design" (Reference 4), provides guidance on the review of thermal-hydraulic design in meeting the requirement of Criterion 10 and the fuel design criteria established in Section 4.2.
3.0 TECHNICAL EVALUATION
3.1 Background
This TS change resolves a defect reported under 10 CFR Part 21 concerning a potential to momentarily violate reactor SLs in TSs 2.1.1.1 and 2.1.1.2 during a PRFO. On March 29, 2005, GE submitted a 10 CFR Part 21 notification, SC05-03, "Potential to Exceed Low Pressure Technical Specification Safety Limit" to the NRC (Reference 5). This Part 21 notification identified that applying newer computer analysis codes has resulted in a PRFO transient condition where the reactor steam dome pressure could potentially, momentarily, decrease below 785 psig while rated thermal power (RTP) was above the plant-specific thermal power limit specified in the TS 2.1.1.1 (23.8 percent RTP), violating reactor SLs in TS 2.1.1. On July 18, 2006, the Technical Specifications Task Force (TSTF) and the Boiling Water Reactor Owners' Group (BWROG) submitted TSTF-495, Revision 0, "Bases Change to Address GE Part 21 SC05-03" (Reference 6), proposing a modification to the "Applicable Safety Analysis" portion of the Reactor Core Safety Limit TS Bases (B 2.1.1 ). This change proposed to clarify that the SL was considered not to apply to momentary depressurization transients. In the NRC staff's safety evaluation (SE) for TSTF-495, dated August 27, 2007 (Reference 7), it was stated that although the technical arguments presented in TSTF-495 had some merit, the NRC staff found the proposed change is unacceptable because it would set a precedent which could lead to erosion of safety margins protected by SLs. The NRC staff further stated in the SE to the TSTF that from a regulatory standpoint, the proposed change to the TS Bases was not acceptable. Consequently, the BWROG discontinued the effort to resolve the issue generically and recommended that plants lower their Low Pressure Safety Limit to meet the lower range of its critical power correlation on plant-specific basis.
Some advanced fuel designs have an NRC approved critical power correlation with a lower-bound pressure that is significantly below the 785 psig reactor steam dome pressure specified in TSs 2.1.1.1 and 2.1.1.2. In particular, GE14 and GNF2 fuels, which make up the RBS core use the GEXL 14 and GEXL 17 critical power correlations, respectively. References 8, 9, and 10 are approved topical reports with an approved pressure range from 700 to 1400 psia or 685 to 1385 psig for GEXL 14 and GNF2 fuels. This amendment will approve a newTS limit of 685 psig for the reactor steam dome pressure consistent with the approved lower-bound pressures for the critical power correlations for the GE14 and GNF2 fuels. Revising the reactor steam dome pressure specified in TSs 2.1.1.1 and 2.1.1.2 to 685 psig resolves the 10 CFR Part 21 defect concerning the potential to violate an SL during a PRFO transient.
3.2 Proposed TS Changes
Current TS 2.1.1.1 states, in part, that:
With the reactor steam dome pressure < 785 psig or core flow < 1 0% rated core flow:
Revised TS 2.1.1.1 would state, in part, that:
With the reactor steam dome pressure < 685 psig or core flow < 1 0% rated core flow:
Current TS 2.1.1.2 states, in part, that:
With the reactor steam dome pressure ~ 785 psig or core flow ~ 1 0% rated core flow:
Revised TS 2.1.1.2 would state, in part, that:
With the reactor steam dome pressure ~ 685 psig or core flow ~ 1 0% rated core flow:
3.3 NRC Technical Evaluation During the PRFO transient both pressure regulators fail open, calling for Turbine Control Valves to open wider. This causes rapid depressurization. When reactor pressure reaches 810 psig, the Low Pressure Isolation Set point, Main Steam Isolation Valves (MSIVs) begin to close.
When MSIVs are approximately 10 percent closed (90 percent open), a position-driven Reactor Scram occurs, which terminates the event. The proposed changes to lower the Low Pressure TS limit to 685 psig offer a greater range for pressure to reduce further while MSIVs are closing.
MSIVs close in the next 3 to 5 seconds, which terminates pressure reduction.
In its letter dated March 29, 2005, 10 CFR Part 21 notification (Reference 3), GE concluded that during the PRFO event, the calculated critical power ratio (CPR) increases during depressurization. However, the initial calculated CPR value is the maximum calculated CPR value for the entire transient. As such the conditions that the low pressure TS SL can be exceeded exist for only a few seconds, and fuel cladding integrity is not threatened.
Nevertheless, GE considers the PRFO to be a known anticipated operational occurrence (AOO) that could contribute to the exceeding of a safety limit. While this condition was determined to not involve an actual safety hazard, the potential for violation of a reactor core SL was identified, and restoration to comply with the SL is required for the PRFO event. As a result, the licensee is revising the reactor steam dome pressure TS SL to be consistent with the NRC approved pressure range of critical power correlations for the current GE14 and GNF2 fuels designs.
Lowering the reactor steam dome pressure specification in this fashion provides margin to ensure that the reactor core Sls in TS.2.1.1 are not violated.
The NRC staff concludes that revising the reactor core Sls in TSs 2.1.1.1 and 2.1.1.2 for the reactor steam dome pressure from 785 to 685 psig resolves the reported defect under 10 CFR Part 21 concerning the potential to violate reactor core Sls in TS 2.1.1 during a PRFO transient.
TS Sls are specified to ensure that SAFDLS are not exceeded during steady-state operation, normal operational transients, and AOOs. The reactor core Sls are set such that fuel cladding integrity is maintained and no significant fuel damage is calculated to occur due to OTB if the Sls are not exceeded.
In an SEdated August 3, 2007 (Reference 8), the NRC staff approved the use of the GEXL 14 critical power correlation for to GE14 fuel. As described in the associated licensing topical report and the NRC staff's SE, the pressure range over which the GEXL 14 correlation is approved for performance of critical power calculations is from 700 psia to 1400 psia. The reactor steam dome pressure of 685 psig (approximately 700 psia) is established from the lower bound pressure. As such, the proposed change to the reactor core Sls will ensure that a valid CPR calculation is performed for the AOOs described in the Updated Final Safety Analysis Report (UFSAR), including the PRFO transient, and that the value of 685 psig proposed for the reactor steam dome pressure should not result in a violation of Reactor Core Safety Limit 2.1 during a PRFO transient. In addition, the GEXL 17 correlation for the GNF2 fuel was approved for use per NEDE-24011-PA "General Electric Standard Application for Reactor Fuel (GESTAR II)." This approach follows, and is consistent with, the way the reactor steam dome pressure has been established, and as such, valid CPR calculations will continue to be performed and the NRC has concluded that it is a safe and appropriate method to address the defect reported under 10 CFR Part 21.
As noted earlier, the NRC staff concluded that reactor depressurization transients, such as PRFO, are non-limiting for fuel cladding integrity because CPR increases during the PRFO event. Although this condition does not involve an actual safety hazard, the potential for violation of a TS reactor core Sls was identified in accordance with Part 21, and restoration of the TS to comply with the requirements of 10 CFR 50.36 is required. Therefore, the licensee proposed the amendment to address the Part 21 defect.
The proposed TS changes were analyzed based on the following NRC-approved methods with databases covering the pressure range from 700 to 1400 psia for GEXL critical power correlation for GE14 and GNF2 fuel:
( 1) the data used for development and verification of the GEXL 14 and GEXL 17 critical power correlation for GE14 fuel and GNF2 fuel, respectively, have a pressure range extended from 700 to 1400 psia using Stern Laboratory test data and documented in NEDC-32851 P-A and NEDC-33292P (References 9 and 10, respectively); and (2) the GEXL 14 and GEXL 17 correlations provides the validity of Minimum Critical Power Ratio (MCPR) calculations since the PRFO event causes the MCPR to increase due to the pressure reduction effect on the greater latent heat of vaporization and the large voids causing negative reactivity and lower power comparing with the higher pressure condition (References 1 and 2).
The NRC staff evaluated the proposed TS changes against the applicable regulatory requirements and acceptance criteria. The staff concludes that as long as the core pressure and flow are within the range of validity of the specified CPR correlation (GEXL 14 and GEXL 17 correlations), the proposed reactor steam dome pressure change to TSs 2.1.1.1 and 2.1.1.2 will ensure that 99.9 percent of the fuel rods in the core are not expected to experience OTB. This satisfies the regulatory requirements regarding acceptable fuel design limits and continues to assure that the underlying criteria of the Sls are met and therefore, the NRC staff concludes that the proposed changes in TSs 2.1.1.1 and 2.1.1.2 are acceptable.
4.0 CHANGES TOTS BASES AND REGULA TORY COMMITMENTS In Attachments 3 and 4 to the LAR, respectively, the licensee identified changes to (1) the TS Bases to reflect the proposed amendment and (2) a regulatory commitment. In identifying changes to the TS Bases, the licensee is not requesting that the NRC approve these changes.
As stated in 10 CFR 50.36(a) bases are not part of the TSs. The changes to the TS Bases and the regulatory commitment are for information purposes for the NRC staff. Bases changes are controlled by the licensee's program under TS 5.5.11, "Technical Specifications (TS) Bases Control Program," which states, in part, that Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
- 1.
A change in the TS incorporated in the license; or
- 2.
A change to the USAR [Updated Safety Analysis Report] that involves an unreviewed safety question as defined in 10 CFR 50.59.
However, the NRC staff notes that the NRC-approved methodologies in References 9, 10, and 11, which were used to justify the TS change to reduce the reactor dome pressure from 785 psig to 685 psig are not included in the TS Bases. The methodologies are discussed in the LAR and its addition to the TS Bases would clarify the bases for the change.
In the LAR, the licensee provided the following commitment:
- 1)
TS BASES changes will be incorporated into TS upon receipt of the NRC approved License Amendment in accordance with TS [5.5.11], "Bases Control Program."
The above items are not evaluated in this safety evaluation.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents 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 finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on August 6, 2013 (78 FR 47788). 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) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
8.0 REFERENCES
- 1.
Olson, E. W., Entergy Operations, Inc., letter to U.S. Nuclear Regulatory Commission, "License Amendment Request, Changes to Technical Specification 2.1.1, 'Reactor Core SLs,' River Bend Station, Unit 1, Docket No. 50-458, License No. NPF-47," dated May 28, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13155A138).
- 2.
Olson, E. W., Entergy Operations, Inc., letter to U.S. Nuclear Regulatory Commission, "License Amendment Request-Response to NRC RAI, Changes to Technical Specification 2.1.1, 'Reactor Core SLs,' River Bend Station, Unit 1, Docket No. 50-458, License No. NPF-47," dated May 8, 2014 (ADAMS Accession No. ML14140A345).
- 3.
U.S. Nuclear Regulatory Commission, NUREG-0800, "Standard Review Plant for the Review of Safety Analysis Reports for Nuclear Power Plants," Section 4.2, "Fuel System Design" (ADAMS Accession No. ML070740002).
- 4.
U.S. Nuclear Regulatory Commission, NUREG-0800, "Standard Review Plant for the Review of Safety Analysis Reports for Nuclear Power Plants," Section 4.4, "Thermal Hydraulic Design" (ADAMS Accession No. ML070550060).
- 5.
Post, J. S., GE Energy-Nuclear, letter to U.S. Nuclear Regulatory Commission, "10 CFR 21 Reportable Condition Notification: Potential to Exceed Low Pressure Technical Specification Safety Limit," dated March 29, 2005 (ADAMS Accession No. ML050950428).
- 6.
Sparkman, W., Crowthers, M., Woods, B., and lnfanger, P., Technical Specifications Task Force, letter to U.S. Nuclear Regulatory Commission, "TSTF-495, Revision 0,
'Bases Change to Address GE Part 21 SC05-03,"' dated July 18, 2006 (ADAMS Accession No. ML061990227).
- 7.
Kobetz, T., U.S. Nuclear Regulatory Commission, letter to Technical Specifications Task Force, "Denial of TSTF-495, Revision 0, "Bases Change to Address GE Part 21 SC05-03." Docket No: PROJ0753 (TAC MD2672)," dated August 27, 2007 (ADAMS Accession No. ML072340113).
- 8.
Nieh, H. K., U.S. Nuclear Regulatory Commission, letter to Andrew A. Lingenfelter, Global Nuclear Fuel-Americas, LLC, "Final Safety Evaluation for Global Nuclear Fuel (GNF) Topical Report (TR) NEDC-32851 P, Revision 2, "GEXL 14 Correlation for GE14 Fuel" (TAC No. MD5486)," dated August 3, 2007 (ADAMS Accession No. ML072080365).
- 9.
Global Nuclear Fuel-Americas, LLC, NEDC-32851 P-A, "GEXL 14 Correlation for GEXL Fuel14," Rev. 4 (Table 2, Page 6), September 2007 (proprietary).
- 10.
Global Nuclear Fuel-Americas, LLC, NEDC-33292P, "GEXL 17 Correlation for GNF2 Fuel," Rev. 3 (Table 3-1, Page 3-4), June 2009 (proprietary).
- 11.
Global Nuclear Fuel-Americas, LLC, NEDC-33270P, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Rev. 4, October 2011 Principal Contributor: T. Huang Date:December 11, 2014
Vice President, Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61 N St. Francisville, LA 70775 December 11, 2014
SUBJECT:
RIVER BEND STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE:
TECHNICAL SPECIFICATION 2.1.1, "REACTOR CORE SLS" (TAC NO. MF1948)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 182 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 28, 2013, as supplemented by letter dated May 8, 2014.
The amendment revises TS 2.1.1, "Reactor Core SLs [Safety Limits]," to reduce the reactor dome pressure from 785 pounds per square inch gauge (psig) to 685 psig. General Electric Nuclear Energy reported a calculational "defect" under Title 1 0 of the Code of Federal Regulations (1 0 CFR) Part 21. As a result of improved calculation methods, a "defect" was found concerning a potential to momentarily violate the reactor safety limits in TSs 2.1.1.1 and 2.1.1.2 during a Pressure Regulator Failure-Open transient.
A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Docket No. 50-458
Enclosures:
Sincerely, IRA/
Alan B. Wang, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 1. Amendment No. 182 to NPF-47
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4-2 r/f RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsNrrDoriLpl4-2 Resource RidsNrrDssSrxb Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMRiverBend Resource RidsRgn4MaiiCenter Resource THuang, NRR/DSS/SRXB MRazzaque, NRR/DSS/SRXB ADAMS Accession No ML14192A831 OFFICE NRRIDORL/LPL4-2/PM NRR/DORLILPL4-2/LA NRR/DSS/STSB/BC NRR/DSS/SXRB/BC NAME ABWang JBurkhardt REIIiott CJackson DATE 7/29/14 7/24/14 8/5/14 7/19/14 OFFICE OGC NRR/DORLILPL4-2/BC NRR/DORLILPL4-2/PM NAME MYoung DBroaddus ABWang DATE 8/19/14 12/10/14 12/11/14 OFFICIAL AGENCY RECORD