Letter Sequence Approval |
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MONTHYEARRBG-46754, Revision to License Amendment Request, Application for Technical Specification (TS) Change Regarding Ventilation Filter Testing Program (Vftp), TS 5.5.7, Control Room Fresh Air System (Crfas) Heater Wattage2007-10-24024 October 2007 Revision to License Amendment Request, Application for Technical Specification (TS) Change Regarding Ventilation Filter Testing Program (Vftp), TS 5.5.7, Control Room Fresh Air System (Crfas) Heater Wattage Project stage: Request ML0801605492008-02-28028 February 2008 Issuance of Amendment No. 159, Revision of Required Wattage in Technical Specification 5.5.7.e, Ventilation Filter Testing Program for Control Room Fresh Air System Heater Project stage: Approval 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 Project stage: Other ML0812207352008-05-0808 May 2008 Correction to Amendment No. 159, Revision of Required Wattage in TS 5.5.7, Ventilation Filter Testing Program for Control Room Fresh Air System Heater Tac No. MD4961) Project stage: Other 2008-02-28
[Table View] |
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Category:Letter
MONTHYEARRBG-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 ML24164A0862024-06-12012 June 2024 Notification of Commercial Grade Dedication Inspection (05000458/2024010) and Request for Information RBG-48294, 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 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 ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024 2023 Annual Radioactive Effluent Release Report IR 05000458/20244022024-04-15015 April 2024 Security Baseline Inspection Report 05000458/2024402 (Full Report) RBG-48288, Louisiana Pollutant Discharge Elimination System Permit Renewal2024-04-15015 April 2024 Louisiana Pollutant Discharge Elimination System Permit Renewal ML24106A0432024-04-11011 April 2024 June 2024 Emergency Preparedness Exercise Inspection Request for Information RBG-48277, 2023 Annual Radiological Environmental Operating Report2024-04-10010 April 2024 2023 Annual Radiological Environmental Operating Report 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 IR 05000458/20243012024-04-0202 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 IR 05000458/20240402024-03-15015 March 2024 – 95001 Supplemental Inspection Report 05000458/2024040 and Follow-Up Assessment ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) 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)) 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 IR 05000458/20230402024-01-18018 January 2024 – 95001 Supplemental Inspection Supplemental Report 05000458/2023040 and Follow-Up Assessment Letter RBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk2024-01-12012 January 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML24011A1742024-01-11011 January 2024 Security Baseline Inspection Report (Cover Letter) ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection IR 05000458/20230102023-12-12012 December 2023 Biennial Problem Identification and Resolution Inspection Report 05000458/2023010 RBG-48267, Reply to a Notice of Violation, NRC Inspection Report 05000458/20230032023-12-0707 December 2023 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1432023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A0322023-11-13013 November 2023 Integrated Inspection Report 05000458/2023003 2024-09-24
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24185A1522024-08-13013 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 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 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 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 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 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 ML1026405472010-10-21021 October 2010 Issuance of Amendment No. 169, Change to Emergency Plan Table 13.3-17, Repair and Corrective Actions to Modify Positions of On-Shift Personnel ML1023502662010-08-31031 August 2010 Issuance of Amendment No. 168, Modify Technical Specification Surveillance Requirement Frequencies from 18- to 24-Month Fuel Cycle Intervals ML1002003142010-03-31031 March 2010 License Amendment, Revise Technical Specification 5.5.6, Inservice Testing Program, to Incorporate References to ASME Code for Operation and Maintenance of Nuclear Power Plants ML0924301452009-09-29029 September 2009 Issuance of Amendment No. 166, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), to Add Reference to Analytical Method ML0920103702009-08-11011 August 2009 License Amendment No. 165, Modify Technical Specifications to Adopt NRC-approved Generic Changes TS Task Force (TSTF)-163, TSTF-220, TSTF-230, and TSTF-306 2024-08-13
[Table view] Category:Safety Evaluation
MONTHYEARML24185A1522024-08-13013 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 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 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 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) 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) ML18212A1512018-07-31031 July 2018 License Renewal Safety Evaluation Report 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 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 ML15117A5752015-06-0202 June 2015 Issuance of Amendment No. 186 Heavy Load Movement Over Fuel Assemblies ML15114A3512015-05-0404 May 2015 Correction to Relief Request No. VRR-RBS-2014-1 Regarding the Third 10-Year Inservice Testing Interval ML15071A1412015-03-23023 March 2015 Relief Request No. VRR-RBS-2014-1 Regarding the Third 10-Year Inservice Testing Interval 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 ML13350A1612015-02-10010 February 2015 Correction to Safety Evaluation Related to Amendment No. 168 Which Modified Techical Specification Surveillance Requirement Frequencies from 18- to 24-Month Fuel Cycle Intervals; Enclosed New SE Section 3.1.7B 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 2024-08-13
[Table view] |
Text
February 28, 2008 Vice President, Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61N St. Francisville, LA 70775
SUBJECT:
RIVER BEND STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: REVISION OF REQUIRED WATTAGE IN TS 5.5.7, VENTILATION FILTER TESTING PROGRAM FOR CONTROL ROOM FRESH AIR SYSTEM HEATER (TAC NO. MD4961)
Dear Sir or Madam:
The Commission has issued the enclosed Amendment No. 159 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1 (RBS). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated March 28, 2007, as supplemented by letter dated October 24, 2007.
The amendment revises the required wattage specified in the RBS TS 5.5.7.e, Ventilation Filter Testing Program, for the Control Room Fresh Air System (CRFAS) heater for testing and an administrative change to update ANSI N510-1989 to ASME N510-1989. The required wattage for testing the CRFAS heater was revised from 23 +/- 2.3 kilowatt (kW) to "15 kW," and ANSI N510-1989 was updated to ASME N510-1989.
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.
Sincerely,
/RA/
Bhalchandra Vaidya, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1. Amendment No. 159 to NPF-47
- 2. Safety Evaluation cc w/encls: See next page
Pkg ML080160598; Amdt. ML080160549, License/TS ML080280230 NRR-058
(*) no substantial change to SE input memo (**) See previous concurrence OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/SCVB/BC OGC - No legal objection NRR/LPL4/BC NAME BVaidya:sp JBurkhardt RDennig (*) RHolmes (**) THiltz DATE 2/28/08 2/28/08 11/08/07 2/19/08 2/28/08
River Bend Station (2/25/2008) cc:
Senior Vice President Attorney General Entergy Nuclear Operations State of Louisiana P.O. Box 31995 P.O. Box 94095 Jackson, MS 39286-1995 Baton Rouge, LA 70804-9095 Vice President, Oversight President of West Feliciana Entergy Nuclear Operations Police Jury P.O. Box 31995 P.O. Box 1921 Jackson, MS 39286-1995 St. Francisville, LA 70775 Senior Manager, Nuclear Safety Mr. Brian Almon
& Licensing Public Utility Commission Entergy Nuclear Operations William B. Travis Building P.O. Box 31995 P.O. Box 13326 Jackson, MS 39286-1995 1701 North Congress Avenue Austin, Texas 78701-3326 Senior Vice President
& Chief Operating Officer Mr. Jim Calloway Entergy Operations, Inc. Public Utility P.O. Box 31995 Commission of Texas Jackson, MS 39286-1995 1701 N. Congress Avenue Austin, TX 78711-3326 Associate General Counsel Entergy Nuclear Operations Ms. H. Anne Plettinger P.O. Box 31995 3456 Villa Rose Drive Jackson, MS 39286-1995 Baton Rouge, LA 70806 Manager, Licensing Mr. Richard Penrod, Senior Environmental Entergy Operations, Inc. Scientist/State Liaison Officer River Bend Station Office of Environmental Services 5485 US Highway 61N Northwestern State University St. Francisville, LA 70775 Russell Hall, Room 201 Natchitoches, LA 71497 Louisiana Dept. of Environmental Quality Radiological Emergency Planning and Senior Resident Inspector Response Division P.O. Box 1050 P.O. Box 4312 St. Francisville, LA 70775 Baton Rouge, LA 70821-4312 Regional Administrator, Region IV Louisiana Dept. of Environmental Quality U.S. Nuclear Regulatory Commission Office of Environmental Compliance 611 Ryan Plaza Drive, Suite 400 P.O. Box 4312 Arlington, TX 76011-8064 Baton Rouge, LA 70821-4312
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. 159 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 March 8, 2007, as supplemented by letter dated October 24, 2007, 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.
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- By Amendment No. 158, issued on December 31, 2007, the Facility Operating License was transferred from Entergy Gulf States, Inc., to Entergy Gulf States Louisiana, LLC. On the date the instant license amendment request was filed, Entergy Operations, Inc. was authorized to act as agent for Entergy Gulf States, Inc., and had exclusive responsibility and control over the physical construction, operation and maintenance of the facility. As a result of the license transfer, Entergy Operations, Inc., is authorized to act as agent for Entergy Gulf States, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
- 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. 159 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.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas G. Hiltz, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License No. NPF-47 and Technical Specifications Date of Issuance: February 28, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 159 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 Insert 3 3 Technical Specifications Remove Insert 5.0-13 5.0-13
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-47 ENTERGY OPERATIONS, INC.*
RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458
1.0 INTRODUCTION
By application dated March 8, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070930338), as supplemented by letter dated October 24, 2007 (ADAMS Accession No. ML072990062), Entergy Operations, Inc.* (the licensee), requested changes to the Technical Specifications (TSs) for the River Bend Station, Unit 1 (RBS). The supplement dated October 24, 2007, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on May 8, 2007 (72 FR 26175)
The proposed change would revise the required wattage specified in the RBS TS 5.5.7.e, Ventilation Filter Testing Program, for the Control Room Fresh Air System (CRFAS) heater for testing. The proposed required wattage for testing the CRFAS heater would be revised from 23 +/- 2.3 kilowatt (kW) to "15 kW" and ANSI N510-1989 would be updated to ASME N510-1989.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.36 is the Commission's regulatory requirement that TSs are needed and that TSs are required to include items in five specific categories related to facility operation. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station 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. In this regard, the Ventilation Filter Testing Program is an administrative control for RBS.
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- By Amendment No. 158, issued on December 31, 2007, the Facility Operating License was transferred from Entergy Gulf States, Inc., to Entergy Gulf States Louisiana, LLC. On the date the instant license amendment request was filed, Entergy Operations, Inc. was authorized to act as agent for Entergy Gulf States, Inc., and had exclusive responsibility and control over the physical construction, operation and maintenance of the facility. As a result of the license transfer, Entergy Operations, Inc., is authorized to act as agent for Entergy Gulf States, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
The U.S. Nuclear Regulatory Commission (NRC) staffs review evaluated the licensees assessment of the impact of the proposed change to the RBS TS on design-basis analyses.
The NRC staff evaluation of the licensees application was based on the following regulatory requirements of 10 CFR, Part 50 and regulatory guides (RGs).
10 CFR, Part 50, Appendix A, "General Design Criteria (GDC) For Nuclear Power Plants,"
Criterion 19, Control Room, Criterion 60, Control of Release of Radioactive Materials to the Environment, and 10 CFR 50.67, Accident Source Term, as supplemented by Sections 6.4 and 9.4.1 of NUREG-0800, Standard Review Plan, and RG 1.52, Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants.
3.0 TECHNICAL EVALUATION
Removal of radioiodine from the main Control Room ventilation outside air supply during a design-basis accident (DBA) is accomplished through use of charcoal adsorber trains. In its application, as supplemented, the licensee stated that the main Control Room charcoal adsorber trains are designed in accordance with the RG 1.52, Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants. Accordingly, two 100-percent-capacity redundant charcoal adsorber trains are provided. Each Control Room charcoal adsorber train includes an electric heating coil powered from a standby bus to limit the relative humidity of the incoming air to 70 percent at design flow during post-loss-of-coolant accident (LOCA) conditions. The charcoal adsorber train air heater is automatically energized if neither the high adsorber air temperature cutout nor the low adsorber air flow cutout have been activated.
The proposed change would revise the operating license by revising the CRFAS heater wattage (in kW) testing requirement shown in TS 5.5.7, Ventilation Filter Testing Program, subsection TS 5.5.7.e. Subsection e. specifies the required power in kW for Control Room ventilation electric heaters (HVC*FLT3AH/3BH) to decrease relative humidity of the air to less than 70 percent as required for proper operation of the charcoal adsorber components when tested in accordance with American Society of Mechanical Engineers (ASME) N510-1989, Testing of Nuclear Air Treatment Systems. The requested amendment will revise the CRFAS heater wattage testing requirement from 23 +/- 2.3 kW to a new value of 15 kW, and ANSI N510-1989 updated to ASME N510-1989.
By letter dated March 28, 2007, the licensee stated that the current TS is based on the nameplate data and not the design requirement; also, this change provides a calculated value for the heater to perform its design function rather than the nameplate value. The licensee also stated that this new acceptance criterion is more representative and will provide improved operational reliability and flexibility.
It is the staffs understanding that periodic in-place test of the CRFAS heaters will continue to be conducted in accordance with ASME N510-1989 as stated in TS subsection 5.5.7.e of the RBS Ventilation Filter Testing Program. This test is conducted in accordance with the guidance of RG 1.52 for the purpose of reducing the buildup of moisture on adsorbers and high-efficiency particulate air filters, thereby demonstrating compliance with the requirement of GDC 60 as it relates to the systems capability to suitably control the releases of gaseous radioactive effluents
to the environment, and GDC 19 as it relates to providing adequate protection to permit access to and occupancy of the Control Room under accident conditions.
The licensees application, as supplemented, provided an analysis that included the required calculated Control Room charcoal adsorber unit heater capacity of 15 kW assuming the worst case conditions for moisture loading. The assumed heater capacity was based on a main Control Room ambient temperature of 75 ºF. For LOCA conditions, the required heater capacity is 12 kW at a Control Room ambient temperature of 80 ºF. Based upon the NRC staffs review and assessment of the licensees calculation, the NRC staff finds the requested change the CRFAS heater wattage testing requirement from 23 +/- 2.3 kW, to a new value of 15 kW acceptable because the calculations provided by the licensee demonstrate that the requirements of GDCs 19 and 60 will continue to be met. The NRC staff also finds the change to update ANSI N510-1989 to ASME N510-1989 acceptable because the proposed change is administrative in nature, and does not materially alter the original intent of the original TSs.
4.0 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.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change 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 amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on May 8, 2007 (72 FR 26175). Accordingly, the amendments meet 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 amendments.
6.0 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) 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.
Principal Contributor: H. Walker Date: February 28, 2008