|
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Category:Letter
MONTHYEARIR 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 IR 05000458/20230032023-11-13013 November 2023 Integrated Inspection Report 05000458/2023003 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23311A4322023-11-0909 November 2023 Notification of NRC Supplemental Inspection (95001) and Request for Information RBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 12023-11-0606 November 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 1 RBG-48260, Notification of Readiness for Supplemental Inspection2023-10-12012 October 2023 Notification of Readiness for Supplemental Inspection ML23278A2402023-10-0606 October 2023 Regulatory Audit Plan in Support of License Amendment Requests to Revise TSs to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69 RBG-48258, Notification of Readiness for Supplemental Inspection2023-10-0505 October 2023 Notification of Readiness for Supplemental Inspection RBG-48259, Revision to Reply to Notice of Violation; EA-23-0552023-10-0303 October 2023 Revision to Reply to Notice of Violation; EA-23-055 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 ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000458/20234012023-09-26026 September 2023 Cyber Security Inspection Report 05000458/2023401 IR 05000458/20230012023-09-21021 September 2023 NRC Inspection Report 05000458/2023001, Disputed Non-Cited Violation Rescinded RBG-48254, Report of Changes and Errors to 10CFR50.462023-09-21021 September 2023 Report of Changes and Errors to 10CFR50.46 IR 05000458/20234032023-09-21021 September 2023 NRC Security Inspection Report 05000458/2023403 (Cover Letter) RBG-48249, Reply to a Notice of Violation, EA-23-0712023-09-14014 September 2023 Reply to a Notice of Violation, EA-23-071 RBG-48253, Submittal of Owner'S Activity Report Form for Cycle 222023-09-12012 September 2023 Submittal of Owner'S Activity Report Form for Cycle 22 IR 05000458/20230122023-09-0101 September 2023 Comprehensive Engineering Team Inspection Report 05000458/2023012 IR 05000458/20230052023-08-21021 August 2023 Updated Inspection Plan for River Bend Station (Report 05000458/2023005) - Mid Cycle Letter RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 IR 05000458/20230922023-08-15015 August 2023 Final Significance Determination of a White Finding, Notice of Violation, and Follow-Up Assessment Letter; NRC Inspection Report 05000458/2023092 IR 05000458/20230022023-08-0909 August 2023 Integrated Inspection Report 05000458/2023002 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23195A0692023-07-24024 July 2023 2023 River Bend Station Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000458/20230912023-07-20020 July 2023 Final Significance Determination of a White Finding, Notice of Violation, and Follow-Up Assessment Letter; NRC Inspection Report 05000458/2023091 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23195A0222023-07-11011 July 2023 4-2022-012 Letter - OI Closure to Licensee IR 05000458/20234042023-07-11011 July 2023 NRC Security Inspection Report 05000458/2023404 (Cover Letter Only) IR 05000458/20230902023-06-26026 June 2023 NRC Inspection Report 05000458/2023090 and Preliminary White Finding ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RBG-48226, Core Operating Limits Report (COLR) - Cycle 23, Revision 02023-05-31031 May 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 0 RBG-48237, Response to NRC Integrated Inspection Report 05000458/20230012023-05-25025 May 2023 Response to NRC Integrated Inspection Report 05000458/2023001 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23116A2352023-05-0101 May 2023 Integrated Inspection Report 05000458/2023001 RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report 2024-01-18
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML22342B2802022-12-28028 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 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 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 ML0915405702009-06-24024 June 2009 Issuance of Amendment No. 163, Revise Technical Specification 3.7.5, Main Turbine Bypass System ML0812304932008-06-0202 June 2008 Issuance of Amendment No. 160, Adoption of TSTF-2, Proposed Change to Relocate Surveillance Requirement 3.8.3.6, from the Technical Specifications to a Licensee-Controlled Document 2022-07-19
[Table view] Category:Safety Evaluation
MONTHYEARML23270B9932023-09-29029 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 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 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 ML14183A0862014-11-13013 November 2014 Correction to Relief Request RBS-ISI-019, Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements Issued 5/30/14 to Change Fourth 10-Year Inservice Inspection Interval to Third-10-Year Interval 2023-09-29
[Table view] |
Text
October 7, 2005 Mr. Paul D. Hinnenkamp 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:
TECHNICAL SPECIFICATIONS 3.8.4 ACTIONS FOR INOPERABLE BATTERY CHARGER (TAC NO. MC5423)
Dear Mr. Hinnenkamp:
The Commission has issued the enclosed Amendment No. 148 to Facility Operating License No. NPF-47 for the River Bend Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 17, 2004, as supplemented by letters dated June 29 and August 12, 2005.
The amendment revises the TS requirements for direct current (DC) sources. The current TS only includes ACTION Statements for an inoperable DC Power subsystem. The change adds a new ACTION Statement to TS 3.8.4, DC Sources - Operating, to specifically address an inoperable battery charger.
A copy of the related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1. Amendment No.148 to NPF-47
- 2. Safety Evaluation cc w/encls: See next page
Mr. Paul D. Hinnenkamp October 7, 2005 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:
TECHNICAL SPECIFICATIONS 3.8.4 ACTIONS FOR INOPERABLE BATTERY CHARGER (TAC NO. MC5423)
Dear Mr. Hinnenkamp:
The Commission has issued the enclosed Amendment No. 148 to Facility Operating License No. NPF-47 for the River Bend Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 17, 2004, as supplemented by letters dated June 29 and August 12, 2005.
The amendment revises the TS requirements for direct current (DC) sources. The current TS only includes ACTION Statements for an inoperable DC Power subsystem. The change adds a new ACTION Statement to TS 3.8.4, DC Sources - Operating, to specifically address an inoperable battery charger.
A copy of the related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosures:
- 1. Amendment No.148 to NPF-47
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION :
PUBLIC PDIV-1 Reading RidsNrrDlpmLpiv (HBerkow)
RidsNrrDlpmLpdiv (DTerao) RidsNrrLADJohnson RidsNrrPMNKalyanam RidsOgcRp RidsAcrsAcnwMailCenter GHill (2)
RJenkins GMorris RidsNrrDlpmDpr RidsRgn4MailCenter (KKennedy) RidsNrrDeDpr TBoyce Accession No.:ML052790535 *No significant change to SE Input OFFICE PDIV-1/PM PDIV-1/LA DE/EEIB/B DIPM/IROB OGC PDIV-1/SC NAME BVaidya for DJohnson RJenkins* TBoyce MSpencer DTerao NKalyanam (NLO)
DATE 9/21/05 9/19/05 8/24/05 9/22/05 10/09/05 10/06/05 OFFICIAL RECORD COPY
ENTERGY GULF STATES, INC. **
AND ENTERGY OPERATIONS, INC.
DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.148 License No. NPF-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Gulf States, Inc.* (the licensee) dated December 17, 2004, as supplemented by letters dated June 29 and August 12, 2005, 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
__________________
- 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.
- Entergy Gulf States, Inc., has merged with a wholly owned subsidiary of Entergy Corporation.
Entergy Gulf States, Inc., was the surviving company in the merger.
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. 148 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 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
David Terao, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 7, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 148 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by Amendment number and contains marginal lines indicating the areas of change.
Remove Insert 3.8-24 3.8-24
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 148 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 December 17, 2004, Agencywide Documents Access and Management System (ADAMS) Accession Number ML043640284, as supplemented by letters dated June 29 and August 12, 2005, ADAMS Accession Numbers ML051870228 and ML052290282, respectively, Entergy Operations, Inc. (the licensee), requested changes to the Technical Specifications (TSs) for the River Bend Station, Unit 1 (RBS). The supplements dated June 29 and August 12, 2005, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register on January 4, 2005 (70 FR 401).
The proposed change will revise the Operating License by modifying the TS requirements for direct current (DC) sources through revision of TS 3.8.4, "DC Sources - Operating". The current RBS TS only includes Action Statements for the inoperable DC Power subsystem.
The proposed change incorporates a new Action Statement to specifically address an inoperable battery charger. The proposed changes are related to the TS Actions for Division I and II battery chargers and DC electrical power subsystems.
2.0 REGULATORY EVALUATION
The regulatory requirements which the staff applied in its review of the application includes:
General Design Criterion (GDC) 17, Electric power systems, of Appendix A, General Design Criteria for Nuclear Power Plants, to Title 10 of the Code of Federal Regulations (CFR), Part 50, requires, in part, that nuclear power plants have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important to safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure. The offsite power system is required to be supplied by two physically independent circuits that are designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. In addition, this criterion
requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies.
GDC-18, Inspection and testing of electric power systems, requires that electric power systems that are important to safety must be designed to permit appropriate periodic inspection and testing.
Pursuant to 10 CFR 50.36(c)(3), Technical specifications, a licensees TSs must establish surveillance requirements relating to test, calibration, or inspection to assure that the necessary quality of the systems and components is maintained, that the facility will be within safety limits, and that the limiting conditions for operation (LCO) will be met.
Pursuant to 10 CFR 50.65(a)(3), preventive maintenance activities should be designed to maximize the availability of systems, structures, and components, as appropriately balanced against the objective of preventing failures of systems, structures, and components.
Regulatory Guide 1.93, Availability of Electric Power Sources, provides guidance with respect to operating restrictions (i.e., Completion Times (CTs)/allowed outage times) if the number of available DC sources is less than that required by the TS LCO. In particular, this guide prescribes a maximum CT of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for an inoperable DC source.
The onsite power system at RBS includes three independent Class 1E 125 volt (V) DC electrical power subsystems, Division I, II, and III. The DC electrical power distribution system provides the alternating current (AC) emergency power distribution system with control power. It also provides both motive and control power to selected safety-related equipment. The Division I, II, and III batteries supply the Engineered Safeguards Feature (ESF) Division I, II, and III load requirements, respectively. The Divisions are electrically isolated and physically separated so that any failure involving one division cannot jeopardize the function of another division.
3.0 TECHNICAL EVALUATION
The RBS Class 1E 125V DC battery systems supply power to Class 1E loads without interruption during normal operation or during design basis accident conditions. Each Class 1E 125V DC system consists of one battery, one main distribution bus, one static battery charger, and local distribution panels. Redundancy and independence of components precludes the loss of both systems as a result of a single failure. There is no sharing between redundant Class 1E trains of equipment such as batteries, battery chargers, or distribution panels.
Each Class 1E 125 V DC charger system has the capacity to continuously supply the normally connected running loads while maintaining its respective battery in a fully charged condition. Each battery was sized based upon supplying the design duty cycle in the event of loss of offsite AC power concurrent with a loss of coolant accident (LOCA) and a single failure of a diesel generator.
The primary sources of Class 1E DC power systems are the battery chargers. Each battery charger is capable of floating the battery on the bus or recharging a completely discharged
battery while supplying the largest combined demands of the various steady state loads under all plant operating conditions. Each battery charger is fed from a 480V AC ESF switchgear bus of the same division.
Each RBS battery system is sized in conformance with principles set out in the Institute of Electrical and Electronics Engineers (IEEE) Standard - 308, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations, and IEEE Standard - 485, IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications.
RBS has a separate backup battery charger procured and qualified to IEEE Standard - 323, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations.
This backup battery charger can receive power from either a nonsafety-related power source or a portable diesel generator and is provided as a backup battery charger for the Division I, II, and III safety-related battery chargers and three of the nonsafety-related battery chargers.
The backup battery charger's rating is equal to the largest capacity battery charger which it must replace. When the backup battery charger is to be used, the breaker of the battery charger being removed from service is relocated to the backup charger position. The backup charger breaker is taken from its storage position and placed in the position on its bus which feeds the bus of the battery charger removed from service. Manual closing of the two charger breakers completes the charging circuit. The backup battery charger breaker's position is monitored in the main control room, and is tripped upon receipt of a LOCA signal.
The licensee stated that the operation of the backup battery charger is under strict administrative control.
Where there is an electrical interface between safety-related switchgear and nonsafety-related equipment, such as chargers and switchgear, automatic breaker tripping by a LOCA signal at the safety-related switchgear is provided.
3.1 LCO 3.8.4: The licensee proposed the following:
- Provide a specific action and increased CT for an inoperable battery charger.
The proposed change to LCO 3.8.4 addresses the condition where one battery charger on Division I or II is inoperable. The licensee has proposed increasing the battery charger CT from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 7 days, provided that the licensee is able to restore battery terminal voltage to greater than or equal to the minimum established float voltage within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and is able to verify that battery float current is # 2 amps, once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
In the supplemental letter dated August 12, 2005, the licensee confirmed that the discharge of the battery during the allowable two-hour period to connect the backup battery charger would be limited by procedure. Furthermore, in its application dated December 17, 2004, the licensee provided a regulatory commitment to include the TS support function of the spare battery charger in the scope of the maintenance rule (10 CFR 50.65). Having the backup battery charger in the scope of the maintenance rule would provide added assurance that the nonsafety-related backup battery charger is capable of performing the safety design function of the safety-related battery charger that it replaces.
The licensee also provided several regulatory commitments in its August 12, 2005, supplemental letter in response to staff concerns cited in a January 26, 2005, request for additional information. The following paragraphs detail the staff concerns and the regulatory commitments that the licensee provided in response to those concerns.
The first regulatory commitment involves changing the alarm setpoint for loss of AC power to the battery charger. A loss of AC power to the battery charger would result in loss of the battery charger function and immediate loading of the respective division battery. The current alarm setpoint is 123V DC, which corresponds to the nominal open-circuit voltage of the battery. The staffs concern was that this setpoint did not provide enough margin between identifying the failed or failing battery charger and minimizing the discharge on the safety-related batteries. The licensee has addressed the staffs concern by committing to revise this alarm setpoint by setting it closer to the minimum float voltage, which is 130.2V DC.
The licensees second regulatory commitment relates to TS Surveillance Requirement (SR) 3.8.4.1 which directs the licensee to check the battery float voltage every 7 days. The licensees proposed TS Bases state that the current TS SR for checking the battery float voltage every 7 days is consistent when compared with the battery manufacturers recommendations and IEEE Standard - 450, Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications. Since the battery manufacurer for the licensees batteries, GNB Industrial Battery Company, does not prescribe a float voltage verification frequency and IEEE Standard - 450 recommends a monthly float voltage verification interval, the licensee has resolved the staffs concern by providing a regulatory committment to revise the TS Bases for SR 3.8.4.3 to clarify that the 7-day check is conservative with respect to the recommendations.
The licensees third regulatory commitment resolves the staffs concern with the backup battery charger not being credited for accident mitigation. In Section 8.3.2 of the RBS Updated Safety Analysis Report (USAR), it is currently stated that operation of the backup battery charger is under strict administrative control and that no credit was taken for a battery charger in mitigating the consequences of an accident. To resolve the staffs concern, the licensee has provided a regulatory commitment stating that it will revise the USAR prior to the implementation of the proposed change to indicate that, when used as a substitute for a safety-related battery charger, the backup battery charger will be credited for accident mitigation.
Given that the battery discharge can be terminated and that the DC bus remains energized, there is reasonable basis for extending the restoration time for an inoperable battery charger beyond the current 2-hour limit. Therefore, based on the information and regulatory commitments provided above and the availability of a spare battery charger that is capable of being supplied by a backup power source, the staff finds the proposed change acceptable.
The changes made to the other conditions of LCO 3.8.4 are administrative to accommodate the addition of the new conditions. The staff finds these administrative changes acceptable.
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 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 January 4, 2005 (70 FR 401). 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.
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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: G. Morris Date: October 7, 2005
River Bend Station cc:
Winston & Strawn General Manager - Plant Operations 1700 K Street, N.W. Entergy Operations, Inc.
Washington, DC 20006-3817 River Bend Station 5485 US Highway 61N Manager - Licensing St. Francisville, LA 70775 Entergy Operations, Inc.
River Bend Station Director - Nuclear Safety 5485 US Highway 61N Entergy Operations, Inc.
St. Francisville, LA 70775 River Bend Station 5485 US Highway 61N Senior Resident Inspector St. Francisville, LA 70775 P. O. Box 1050 St. Francisville, LA 70775 Vice President - Operations Support Entergy Operations, Inc.
President of West Feliciana P. O. Box 31995 Police Jury Jackson, MS 39286-1995 P. O. Box 1921 St. Francisville, LA 70775 Attorney General State of Louisiana Regional Administrator, Region IV P. O. Box 94095 U.S. Nuclear Regulatory Commission Baton Rouge, LA 70804-9095 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Brian Almon Public Utility Commission Ms. H. Anne Plettinger William B. Travis Building 3456 Villa Rose Drive P. O. Box 13326 Baton Rouge, LA 70806 1701 North Congress Avenue Austin, Texas 78701-3326 Mr. Michael E. Henry, State Liaison Officer Department of Environmental Quality Permits Division P.O. Box 4313 Baton Rouge, Louisiana 70821-4313 Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205 Executive Vice President and Chief Operating Officer Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 May 2005