Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
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MONTHYEARRBG-47805, Response to License Renewal Application NRC Request for Additional Information Set 22017-12-12012 December 2017 Response to License Renewal Application NRC Request for Additional Information Set 2 Project stage: Request RBG-47807, Response to License Renewal Application NRC Requests for Additional Information Set 32018-01-10010 January 2018 Response to License Renewal Application NRC Requests for Additional Information Set 3 Project stage: Other RBG-47812, Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 42018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 4 Project stage: Request RBG-47813, Response to License Renewal Application (LRA) NRC Request for Additional Information Set 52018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information Set 5 Project stage: Request RBG-47830, License Renewal Application Update - Neutron Absorbing Material Monitoring Program2018-02-15015 February 2018 License Renewal Application Update - Neutron Absorbing Material Monitoring Program Project stage: Other RBG-47828, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 82018-02-20020 February 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 8 Project stage: Request RBG-47840, Request for Due Date Extension for License Renewal Application NRC Request for Additional Information from 30 Days to 45 Days2018-02-22022 February 2018 Request for Due Date Extension for License Renewal Application NRC Request for Additional Information from 30 Days to 45 Days Project stage: Request RBG-47819, Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a2018-02-26026 February 2018 Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a Project stage: Supplement RBG-47834, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 92018-03-0808 March 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 9 Project stage: Request RBG-47842, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-03-22022 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement Project stage: Supplement RBG-47848, License Renewal Application Update - Neutron Absorbing Material Monitoring Program - Supplement2018-03-22022 March 2018 License Renewal Application Update - Neutron Absorbing Material Monitoring Program - Supplement Project stage: Supplement RBG-47835, Submittal of Response to License Renewal Application NRC Request for Additional Information Set 102018-03-26026 March 2018 Submittal of Response to License Renewal Application NRC Request for Additional Information Set 10 Project stage: Request RBG-47849, Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement2018-03-27027 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement Project stage: Supplement RBG-47846, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 122018-04-0303 April 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 12 Project stage: Request RBG-47850, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-04-0404 April 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement Project stage: Supplement ML18099A2362018-04-0909 April 2018 Topics for the April 10, 2018 Public Call with Entergy on River Bend Station, Unit 1 License Renewal Application Project stage: Meeting ML18106A6152018-04-16016 April 2018 Topics for the April 18, 2018, Telephone Call - Rev 1 with Aaron'S Rewrite Project stage: Request ML18115A0612018-04-25025 April 2018 Draft Response on RAI B1.21-1 Flow Accelerated Corrosion Project stage: Request ML18115A0722018-04-25025 April 2018 Draft Response on RAI B.1.25-1(Internal Surfaces in Miscellaneous Piping and Ducting Components) Project stage: Request ML18115A1632018-04-25025 April 2018 Draft Response on RBS LRA RAI B.1.21-2 Flow Accelerated Corrosion Project stage: Request RBG-47853, Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-12018-04-26026 April 2018 Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-1 Project stage: Supplement ML18121A3022018-05-0101 May 2018 Draft Response to NRC Request for Additional Information (RAI) 4.6-2a Generated from Staff'S Review on the River Bend License Renewal Application Project stage: Draft RAI ML18121A2942018-05-0101 May 2018 Draft Response to NRC Request for Additional Information (RAI) 4.6-1a Generated from Staffs Review on the River Bend License Renewal Application Project stage: Draft RAI ML18122A1262018-05-0202 May 2018 RAI B.1.17-1 Revised - w- header-footer-watermark Project stage: Request ML18122A2312018-05-0202 May 2018 Draft Response to NRC Request for Additional Information (RAI) B.1.40-5 Service Water Integrity Generated from Staffs Review on the River Bend Station, Unit 1 License Renewal Application Project stage: Draft RAI RBG-47852, Response to License Renewal Application NRC Request for Additional Information Set 132018-05-10010 May 2018 Response to License Renewal Application NRC Request for Additional Information Set 13 Project stage: Request RBG-47860, Response to License Renewal Application NRC Request for Supplemental Information2018-05-10010 May 2018 Response to License Renewal Application NRC Request for Supplemental Information Project stage: Supplement ML18131A2412018-05-11011 May 2018 RBS 012 Item 158a Response (RAI 3.2.2.3.2-1a) Revised - Received on 05/10/2018 Project stage: Request ML18135A1072018-05-15015 May 2018 RBS Draft Response (RAI 4.3.1-2a_Class 1 Fatigue w-header-footer-watermark_received on 051318 Project stage: Request ML18136A8212018-05-16016 May 2018 Draft Response to RAI 3.6.2.2.2.2-1a High Voltage Insulators - RBS LRA Review Project stage: Request ML18136A7052018-05-16016 May 2018 RBS Draft Response to LRA Review RAI 4.7.3-1a Fluence Effects for Rv Internals Project stage: Request RBG-47867, Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement2018-05-16016 May 2018 Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement Project stage: Supplement ML18141A4882018-05-21021 May 2018 Draft Response (RAI 3.6.2.2.2.2-1a) from LRA Review Revised After the May 17, 2018 Call Project stage: Request ML18143B6862018-05-24024 May 2018 RBS Draft Response (Operating Experience) to Draft RAI 3-0-5 Received 052318 Project stage: Request RBG-47861, Response to License Renewal Application NRC Request for Additional Information Sets 14,15 and Operating Experience Review Clarification2018-05-29029 May 2018 Response to License Renewal Application NRC Request for Additional Information Sets 14,15 and Operating Experience Review Clarification Project stage: Request ML18143B7362018-05-31031 May 2018 NUREG-1437, Dfc, Supplement 58, Generic Environmental Impact Statement for License Renewal of Nuclear Plants - Supplement 58 - Regarding River Bend Station, Unit 1. Project stage: Acceptance Review RBG-47870, License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List2018-06-0606 June 2018 License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List Project stage: Supplement RBG-47873, License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List, Revised Commitment 52018-06-13013 June 2018 License Renewal Application, Revised Updated Safety Analysis Report Supplement, Appendix a, Section A.4, License Renewal Commitment List, Revised Commitment 5 Project stage: Supplement ML18212A1512018-07-31031 July 2018 License Renewal Safety Evaluation Report Project stage: Approval RBG-47883, Amendment 1 to License Renewal Application2018-08-0202 August 2018 Amendment 1 to License Renewal Application Project stage: Other ML18138A3552018-08-16016 August 2018 Safety Evaluation Report Related to the License Renewal of River Bend Station, Unit 1 Project stage: Approval ML18283A0822018-10-0909 October 2018 Supplemental Information Related to License Renewal Application NRC Request for Additional Information to Clarify Response to RAI 2.3.3.16-1 Set 11 Project stage: Response to RAI ML18346A6442018-10-19019 October 2018 Revision to River Bend SER - ML18212A151 - Section 2-3-3-16 Plant Drains Project stage: Other 2018-04-03
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Category:Letter type:RBG
MONTHYEARRBG-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 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 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 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 RBG-48254, Report of Changes and Errors to 10CFR50.462023-09-21021 September 2023 Report of Changes and Errors to 10CFR50.46 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 RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 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 RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report RBG-48221, 2022 Annual Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Radiological Environmental Operating Report RBG-48142, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-27027 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-27027 February 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RBG-48198, Report of Changes and Errors to 10CFR50.462022-09-22022 September 2022 Report of Changes and Errors to 10CFR50.46 RBG-48187, Notification of Spent Fuel Cask Use2022-08-15015 August 2022 Notification of Spent Fuel Cask Use RBG-48184, Notification of Spent Fuel Cask Use2022-07-18018 July 2022 Notification of Spent Fuel Cask Use RBG-48178, Notification of Spent Fuel Cask Use2022-06-29029 June 2022 Notification of Spent Fuel Cask Use RBG-48166, Supplement to Special Report for Tritium Discovered Onsite2022-05-12012 May 2022 Supplement to Special Report for Tritium Discovered Onsite RBG-48149, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report RBG-48148, 2021 Annual Radiological Environmental Operating Report2022-04-27027 April 2022 2021 Annual Radiological Environmental Operating Report RBG-48134, Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency2021-11-29029 November 2021 Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency RBG-48136, Additional Information for the 2020 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2020 Annual Radioactive Effluent Release Report RBG-48137, Additional Information for the 2019 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2019 Annual Radioactive Effluent Release Report RBG-48128, Reply to a Notice of Violation; EA-21-017, 030 and 0502021-10-29029 October 2021 Reply to a Notice of Violation; EA-21-017, 030 and 050 RBG-48129, Payment of a Civil Penalty2021-10-21021 October 2021 Payment of a Civil Penalty RBG-48112, Report of Changes and Errors to 10CFR50.462021-09-16016 September 2021 Report of Changes and Errors to 10CFR50.46 RBG-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 12021-08-19019 August 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 1 RBG-48104, Fitness for Duty Blind Quality Assurance Specimen Testing Error2021-06-30030 June 2021 Fitness for Duty Blind Quality Assurance Specimen Testing Error RBG-48099, Submittal of Owner'S Activity Report Form for Cycle 212021-06-16016 June 2021 Submittal of Owner'S Activity Report Form for Cycle 21 RBG-48083, Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials2021-06-15015 June 2021 Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials RBG-48093, Corrected 2020 Annual Radiological Environmental Operating Report2021-05-20020 May 2021 Corrected 2020 Annual Radiological Environmental Operating Report RBG-48082, 2020 Annual Radiological Environmental Operating Report2021-04-20020 April 2021 2020 Annual Radiological Environmental Operating Report RBG-48081, 2020 Annual Radioactive Effluent Release Report2021-04-20020 April 2021 2020 Annual Radioactive Effluent Release Report RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 02021-03-14014 March 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 0 RBG-48075, Notification of Deviation from BWRVIP Guidelines2021-02-24024 February 2021 Notification of Deviation from BWRVIP Guidelines RBG-48074, Spent Fuel Storage Radioactive Effluent Release Report for 20202021-02-22022 February 2021 Spent Fuel Storage Radioactive Effluent Release Report for 2020 RBG-48061, One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-12-0303 December 2020 One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency RBG-48054, Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program2020-11-0202 November 2020 Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program RBG-48049, Reply to a Notice of Violation; EA-20-0582020-10-26026 October 2020 Reply to a Notice of Violation; EA-20-058 RBG-48038, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic2020-10-0606 October 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic RBG-48042, Submittal of Rev. 48 to Emergency Plan2020-09-22022 September 2020 Submittal of Rev. 48 to Emergency Plan RBG-48039, Report of Changes and Errors to 10CFR50.462020-09-16016 September 2020 Report of Changes and Errors to 10CFR50.46 RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-0404 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RBG-48023, Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures2020-06-0909 June 2020 Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures RBG-48019, 2019 Annual Radioactive Effluent Release Report2020-04-30030 April 2020 2019 Annual Radioactive Effluent Release Report RBG-48020, Annual Radiological Environmental Operating Report2020-04-30030 April 2020 Annual Radiological Environmental Operating Report RBG-48018, Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date2020-04-24024 April 2020 Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date 2024-01-12
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24012A1962024-01-12012 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 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) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary RBG-47919, Response to Request for Additional Information for License Amendment Request, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-12-17017 December 2018 Response to Request for Additional Information for License Amendment Request, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) RBG-47906, Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-18018 October 2018 Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 ML18283A0822018-10-0909 October 2018 Supplemental Information Related to License Renewal Application NRC Request for Additional Information to Clarify Response to RAI 2.3.3.16-1 Set 11 RBG-47903, Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power2018-10-0404 October 2018 Response to Request for Additional Information License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4,11 -1 Minimum Temperature Required Vs, RCS Pressure by Replacing with 54 Effective Full Power RBG-47895, Supplement to the Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)2018-08-15015 August 2018 Supplement to the Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI) RBG-47876, Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI)2018-06-21021 June 2018 Response to License Amendment Request (LAR) for Review and Approval of Relocation of the Reactor Core Isolation Cooling (RCIC) Injection Point NRC Request for Additional Information (RAI) ML18143B6862018-05-24024 May 2018 RBS Draft Response (Operating Experience) to Draft RAI 3-0-5 Received 052318 ML18136A7052018-05-16016 May 2018 RBS Draft Response to LRA Review RAI 4.7.3-1a Fluence Effects for Rv Internals ML18136A8212018-05-16016 May 2018 Draft Response to RAI 3.6.2.2.2.2-1a High Voltage Insulators - RBS LRA Review RBG-47867, Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement2018-05-16016 May 2018 Response to License Renewal Application NRC Request for Additional Information RAI 3.2.2.2-1a Supplement RBG-47852, Response to License Renewal Application NRC Request for Additional Information Set 132018-05-10010 May 2018 Response to License Renewal Application NRC Request for Additional Information Set 13 RBG-47860, Response to License Renewal Application NRC Request for Supplemental Information2018-05-10010 May 2018 Response to License Renewal Application NRC Request for Supplemental Information ML18121A2942018-05-0101 May 2018 Draft Response to NRC Request for Additional Information (RAI) 4.6-1a Generated from Staffs Review on the River Bend License Renewal Application RBG-47853, Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-12018-04-26026 April 2018 Response to License Renewal Application NRC Request for Additional Information Supplement to B.1.35-1 RBG-47859, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-04-26026 April 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18115A0612018-04-25025 April 2018 Draft Response on RAI B1.21-1 Flow Accelerated Corrosion ML18115A0722018-04-25025 April 2018 Draft Response on RAI B.1.25-1(Internal Surfaces in Miscellaneous Piping and Ducting Components) RBG-47850, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-04-0404 April 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement RBG-47846, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 122018-04-0303 April 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 12 RBG-47851, Response to License Amendment Request (LAR) Technical Specification 3.7.7, Control Building Air Conditioning (Cbac) System NRC Request for Additional Information (RAI)2018-03-28028 March 2018 Response to License Amendment Request (LAR) Technical Specification 3.7.7, Control Building Air Conditioning (Cbac) System NRC Request for Additional Information (RAI) RBG-47849, Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement2018-03-27027 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 4 Supplement RBG-47835, Submittal of Response to License Renewal Application NRC Request for Additional Information Set 102018-03-26026 March 2018 Submittal of Response to License Renewal Application NRC Request for Additional Information Set 10 RBG-47842, Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement2018-03-22022 March 2018 Response to License Renewal Application NRC Request for Additional Information Set 5 Supplement ML18059A8222018-03-0808 March 2018 Summary of Public Telephone Conference Call Held on February 27, 2018 Between the U.S. Nuclear Regulatory Commission and Entergy Regarding Requests for Additional Information Pertaining to the River Bend Station Unit 1 RBG-47819, Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a2018-02-26026 February 2018 Response to License Renewal Application NRC Request for Additional Information - Set 7 Supplement to RAI B.1.11-2a RBG-47828, Response to License Renewal Application NRC Request for Additional Information (RAI) Set 82018-02-20020 February 2018 Response to License Renewal Application NRC Request for Additional Information (RAI) Set 8 RBG-47818, Response to License Renewal Application NRC Request for Additional Information - Set 72018-02-0707 February 2018 Response to License Renewal Application NRC Request for Additional Information - Set 7 RBG-47812, Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 42018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 4 RBG-47822, Response to Request for Additional Information Re License Renewal Application Concerning Severe Accident Mitigation Alternatives2018-01-24024 January 2018 Response to Request for Additional Information Re License Renewal Application Concerning Severe Accident Mitigation Alternatives RBG-47813, Response to License Renewal Application (LRA) NRC Request for Additional Information Set 52018-01-24024 January 2018 Response to License Renewal Application (LRA) NRC Request for Additional Information Set 5 RBG-47807, Response to License Renewal Application NRC Requests for Additional Information Set 32018-01-10010 January 2018 Response to License Renewal Application NRC Requests for Additional Information Set 3 RBG-47805, Response to License Renewal Application NRC Request for Additional Information Set 22017-12-12012 December 2017 Response to License Renewal Application NRC Request for Additional Information Set 2 RBG-47803, Response to License Renewal Application (LRA) NRC Request for Additional Information, Severe Accident Mitigation Alternatives2017-12-0505 December 2017 Response to License Renewal Application (LRA) NRC Request for Additional Information, Severe Accident Mitigation Alternatives ML17353A0492017-12-0505 December 2017 Response to License Renewal Application NRC Request for Additional Information Re Environmental RBG-47709, Response to Request for Additional Information on Nineteenth Fuel Cycle Core Operating Limits Report2016-09-12012 September 2016 Response to Request for Additional Information on Nineteenth Fuel Cycle Core Operating Limits Report RBG-47695, Response to Request to Additional Information Regarding RBS License Amendment Request to Extend Type a and Type C Test Frequencies2016-07-27027 July 2016 Response to Request to Additional Information Regarding RBS License Amendment Request to Extend Type a and Type C Test Frequencies RBG-47675, Response to NRC Request for Additional Information - RBS LAR to Extend Type a and Type C Test Frequencies2016-04-19019 April 2016 Response to NRC Request for Additional Information - RBS LAR to Extend Type a and Type C Test Frequencies ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, RBG-47634, High-frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10CER50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi..2015-12-0808 December 2015 High-frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10CER50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi.. CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 RBG-47582, Response to Request for Information - Change to Technical Specification 3.8.1, AC Sources - Operating2015-07-16016 July 2015 Response to Request for Information - Change to Technical Specification 3.8.1, AC Sources - Operating ML15211A3772015-07-16016 July 2015 Response to Request for Information on Change to Technical Specification 3.8.1, AC Sources - Operating. 2024-01-12
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Entergy Operations, Inc.
River Bend Station 54B5 U S Highway 61 N SI Francisville, LA 70775 T 'I 225-381 4374 William F. Maguire
'>IIE Vice President River Bend Station RBG-47812 January 24, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville , MD 20852-2738
SUBJECT:
Response to License Renewal Application (LRA) NRC Request for Additional Information (RAI) Set 4 River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47
References:
- 1) Entergy Letter: License Renewal Application (RBG-47735 dated May 25, 2017)
- 2) NRC email: River Bend Station, Unit 1, Request for Additional Information, Set 4 - RBS License Renewal Application - dated December 13, 2017 (ADAMS Accession No. ML17347B424)
- 3) Entergy Letter: Request for Due Date Extension for License Renewal Application NRC Request for Additional Information - Set 4 (RBG-47814 dated December 20, 2017)
Dear Sir or Madam:
In Reference 1, Entergy Operations, Inc (Entergy) submitted an application for renewal of the Operating License for River Bend Station (RBS) for an additional 20 years beyond the current expiration date. In an email dated December 13, 2017, (Reference 2) the NRC staff made a Request for Additional Information (RAI), needed to complete the License Renewal application review. On December 20 , 2017, (Reference 3) Entergy requested that the due date for this submittal be extended from a 30 day response to a 45 day response. The extension was requested due to decreased resources during the latter part of December 2017, Enclosure 1 provides the responses to the Set 4 RAls. Enclosure 2 provides voluntary changes to the License Renewal Application (Reference 1). Enclosure 3 describes two regulatory commitments. If you require additional information , please contact Mr. Tim Schenk at (225)-
381-4177 or tschenk@entergy.com.
In accordance with 10 CFR 50 .91 (b)(1) , Entergy is notifying the State of Louisiana and the State of Texas by transmitting a copy of this letter to the designated State Official.
RBG-47812 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on January 24, 2018.
Sincerely, WFM/RMC/alc : Set 4 RAI Responses - River Bend Station : Voluntary License Renewal Application Changes - River Bend Station : Commitments - River Bend Station cc: (with Enclosure)
- u. S. Nuclear Regulatory Commission Attn: Emmanuel Sayoc 11555 Rockville Pike Rockville, MD 20852 cc: (w/o Enclosure)
U. S. Nuclear Regulatory Commission Attn: Lisa Regner 11555 Rockville Pike Rockville, MD 20852 u.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4511 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave.
Austin, TX 78711-3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312 RBF1-17-0167
RBG-47812 Enclosure 1 Responses to Request for Additional Information Set 4
RBG-47812 Page 1 of 5 REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION RIVER BEND STATION, UNIT 1 - SET 4 DOCKET NO.: 50-458 CAC NO.: MF9757 Office of Nuclear Reactor Regulation Division of Materials and License Renewal Question TRP 040, RAI 3.1.2.4.2.1 (Lubricating Oil Analysis)
Background
The LRA states that the Oil Analysis program will be consistent with GALL Report AMP XLM39 ,
"Lubricating Oil Analysis." GALL Report AMP XLM39 recommends a verification of the effectiveness of the lubricating oil program , such as GALL Report AMP XI.M32 , "One-Time Inspection," to ensure that significant degradation is not occurring and the component's intended function is maintained during the period of extended operation.
Issue LRA Table 3.1 .2-4-2 states that nickel alloy flex hose exposed to lube oil will be managed for loss of material by the Oil Analysis program.
LRA Table 3.3.2-3 states that titanium heat exchanger tubes exposed to lube oil will be managed for loss of material by the Oil Analysis program .
The above LRA Tables 3.1.2-4-2 and 3.3.2-3 do not appear to include a plant-specific note indicating that they will be included in the One-Time Inspection program inspection sample, as recommended by GALL Report AMP XLM39 .
Request Confirm whether a one-time inspection program such as GALL Report, AMP XLM32 , "One-Time Inspection," will be used to verify the effectiveness of the Oil Analysis program for managing loss of material by including the nickel alloy flex hose and titanium heat exchanger tube in the One-Time Inspection program . Alternatively, provide justification for not including the items in question in the One-Time inspection program .
Response
The One-Time Inspection Program , described in LRA Section B.1.32, will verify the effectiveness of the Oil Analysis Program by confirming that unacceptable loss of material is not occurring.
Under this program , a representative sample of susceptible components of each material and environment crediti~g the Oil Analysis Program for aging management will ~e inspected. Thus ,
the nickel alloy flex hose exposed to lube oil in Table 3.1 .2-4-2 and the titanium heat exchanger tubes exposed to lube oil in Table 3.3.2-3 are included in the One-Time Inspection Program .
LRA Tables 3.1.2-4-2 and 3.3.2-3 have Note G for the nickel alloy flex hose and the titanium heat exchanger tubes exposed to lube oil because the lube oil environment is not in NUREG-1801 fo r these components and materials. Since the component/material/environment combinations are
RBG-47812 Page 2 of 5 not in NUREG-1801 , plant-specific notes to show consistency with NUREG-1801 are not applied.
Question TRP-6, RAI B.1.5-1 (BWR CRD Return Line Nozzle)
Background
The "scope of program" program element of GALL Report AMP XI.M6 , "Control Rod Drive Return Line Nozzle," states that the scope of the program includes the control rod drive return line (CRDRL) nozzle and its nozzle-to-reactor-vessel welds which are ASME Code Class 1 components. The program element also indicates that, if an applicant has cut the piping to the CRDRL nozzle and capped the CRDRL nozzle, the scope of the program also includes a CRDRL nozzle cap and any associated nozzle-to-cap welds.
LRA Sections B.1.5 (program description) and A.1.5 (USAR supplement for the program) and program basis document (RBS-15-00006, Revision 1) indicate the following: (a) the CRDRL was removed and the CRDRL nozzle was capped prior to the plant operation; (b) the capped nozzle design includes a carbon steel safe end between the carbon steel nozzle and the nickel alloy cap; (c) the program scope includes the CRDRL nozzle, nozzle-to-reactor vessel weld, CRDRL nozzle cap, and Inconel end cap to carbon steel safe end dissimilar metal weld ; and (d) the nozzle, cap ,
and associated welds are included in the applicant's inservice inspection and visual inspections (VT-2) are performed on these components .
NRC Information Notice (IN) 2004-08, which is referenced in GALL Report AMP XI.M6, describes the operating experience regarding stress corrosion cracking (SCC) in the CRDRL nozzle-to-cap weld (Inconel 82/182 weld) .
Issue The CRDRL nozzle design includes a safe end between the nozzle and the cap . In contrast, the LRA does not clearly indicate that the program scope includes the nozzle-to-safe-end weld.
Request
- 1. Clarify whether the program scope includes the nozzle-to-safe-end weld. If it is not included in the program scope, identify a program that is used to manage cracking for this weld.
- 2. Clarify whether the applicant performs volumetric inspections on the nozzle-to-safe-end weld and safe-end-to-cap weld (e.g. , lSI or BWRVIP-75-A inspections) . If such volumetric inspections are not performed on these welds, provide justification for why volumetric inspections are not necessary in light of the industry operating experience (IN 2004-08) and potential material susceptibility to SCC.
Response
- 1. The Control Rod Drive Return Line Nozzle Program includes the control rod drive return line 'nozzle-to-safe-end weld.
- 2. The nozzle-to-safe-end weld and dissimilar metal safe-end-to-nozzle cap weld are not selected for inspection as part of the risk-based lSI. In accordance with a new program enhancement, the safe-end-to-cap weld will be inspected once prior to the period of extended operation and once every 10 years during the period of extended operation.
RBG-47812 Page 3 of 5 The changes to LRA Sections A.1.5 , A.4, B.1 .5 and Table B.3 follow with additions underlined and deletions lined through .
LRA Section A.1.5 BWR CRD Return Line Nozzle The BWR Control Rod Drive (CRD) Return Line Nozzle Program manages cracking of the CRD return line (CRDRL) reactor pressure vessel nozzle using preventive, mitigative, and inservice inspection activities. The CRDRL nozzle, which is exposed to a reactor coolant environment, was capped during construction prior to plant operation . This examination program originated through NUREG-0619 but is now governed by ASME Code,Section XI. Therefore, augmented inspections specified by NUREG-0619 are not applicable. The CRDRL inner radius is volumetrically examined to monitor the effects of cracking in accordance with the ASME Code,Section XI as part of the lSI Program . The examination is performed at least once each lSI interval. The scope of the program includes the CRDRL nozzle, the nozzle-to-reactor vessel weld ,
the nozzle-to-safe-end weld , the CRDRL nozzle cap , and the Inconel end cap to carbon steel safe end dissimilar metal weld. An enhancement is included to volumetrically examine the safe-end-to-cap weld once prior to the period of extended operation and once every 10 years during the period of extended operation. The nozzle , cap , and associated welds are included in the visual inspection (VT-2) during the reactor pressure test performed after each refueling outage.
LRA Section A.4 LICENSE RENEWAL COMMITMENT LIST Source Program or Implementation (Letter No. Activity Commitment Schedule Number) 30 Control Rod Enhance the Control Rod Drive Prior to February 28, RBG-47812 Drive Return Return Line Nozzle Program as 2025, or the end of Line Nozzle described in LRA Section A.1.5. the last refueling Program outage prior to August 29, 2025, whichever is later.
LRA Section B.1.5 BWR CRD RETURN LINE NOZZLE The BWR Control Rod Drive (CRD) Return Line Nozzle Program manages cracking of the CRD return line (CRDRL) reactor pressure vessel nozzle using preventive, mitigative, and in service inspection activities. The CRDRL nozzle , which is exposed to a reactor coolant environment, was capped during construction prior to plant operation . This examination program originated through NUREG-0619 but is now governed by ASME Code,Section XI. Therefore, augmented inspections specified by NUREG-0619 are not applicable. The CRDRL nozzle inner radius is volumetrically examined to monitor the effects of cracking in accordance with the ASME Code,Section XI as part of the lSI Program . The examination is performed at least once each lSI interval. The scope of the program includes the CRDRL nozzle, the nozzle-to-reactor vessel weld , nozzle-to-safe-end weld , the CRDRL nozzle cap , and the Inconel end cap to carbon steel safe end dissimilar metal weld. The nozzle , cap, and associated welds are included in the visual inspection (VT-2) during the reactor pressure test performed after each refueling outage.
RBG-47812 Enclosure 1 Page 4 of 5 Enhancements NeAeThe following enhancement will be im[2lemented [2rior to the [2eriod of extended o[2eration.
Element Affected Enhancement
- 4. Detection of Aging Effects The safe-end-to-ca[2 weld will be volumetrically: examined once [2rior to the [2eriod of extended o[2eration and once every: 10 y:ears during the [2eriod of extended o[2eration.
LRA Table B-3 RBS Program Consistency with NUREG-1801 NUREG-1801 Comparison Program has Plant- Program has Exceptions to Program Name Specific Enhancements NUREG-1801 BWR CRD Return Line Nozzle [B.1.5]
X Question TRP 031, RAI B.1.15-1 (Fuel Oil Chemistry)
Background
SRP-LR Table 3.0-1, "FSAR Supplement for Aging Management of Applicable Systems,"
summary description provides an acceptable program description for the GALL Report AMP XI.M30, "Fuel Oil Chemistry," as per 10 CFR 54.21 (d) . The FSAR Supplement includes the specific ASTM Standards used for monitoring and control of fuel oil contamination to maintain fuel oil quality.
Issue LRA Section A.1 .15, "Diesel Fuel Monitoring ," USAR supplement does not appear to include the specific industry standards used for the program. The current licensing basis will not be consistent with the staff-issued guidance document during the period of extended operation if the industry standards recommended by the GALL Report are not used.
Reguest Justify the apparent absence of the above mentioned industry standards in the USAR supplement for the Diesel Fuel Monitoring program. Alternatively, state the changes to the USAR supplement necessary to include the GALL Report recommended industry standards that will be used for the program.
RBG-47812 Page 5 of 5
Response
Changes are provided to the USAR supplement to identify ASTM standards used in the monitoring and control of diesel fuel , specifically, ASTM 04057, 01796, 02274 and 02276.
The changes to LRA A.1.15 and B.1.15 follow with additions underlined and deletions lined through .
A.1.15 Diesel Fuel Monitoring The Diesel Fuel Monitori ng Program manages loss of material in piping , tanks and other components in an environment of diesel fuel oil by verifying the quality of the fuel oil source. This is performed by receipt inspection , sampling , and limiting the quantities of contaminants before allowing it to enter the fuel oil storage tanks. Parameters monitored include water and sediment content, total particulates, and levels of microbiological organisms in the fuel oil. Monitoring and control are performed in accordance with ASTM standards 04057, 01796, 02274 and 02276.
The program includes multi-level sampling of fuel oil storage tanks. Where multi-level sampling cannot be performed due to design , a representative sample is taken from the lowest part of the tank. A stabilizer/biocide is added to new fuel.
B.1.15 Diesel Fuel Monitoring Program Description The Diesel Fuel Monitoring Program manages loss of material in piping , tanks and other components in an environment of diesel fuel oil by verifying the quality of the fuel oil source. Th is is performed by receipt inspection , sampling , and limiting the quantities of contaminants before allowing it to enter the fuel oil storage tanks. Parameters monitored include water and sediment content, total particulates, and levels of microbiological organisms in the fuel oil. Monitoring and control are performed in accordance with ASTM standards 04057, 01796, 02274 and 02276.
The program includes multi-level sampling of fuel oil storage tanks. Where multi-level sampling cannot be performed due to design , a representative sample is taken from the lowest part of the tank . A stabilizer/biocide is added to new fuel.
RBG-47812 Enclosure 2 Voluntary License Renewal Application Change
R8G-47812 Page 1 of 1 TRP 34-1 Voluntary LRA Change to Address Audit Question During the review of NRC audit questions on the River 8end License Renewal Application (LRA),
an inconsistency was discovered between LRA tables and the description of the Selective Leaching Program in LRA Appendix A and Appendix 8. Specifically, LRA Tables 3.3.2-18-17 and 3.3.2-18-23 cite valve bodies exposed to waste water with an aging effect of loss of material managed by the Selective Leaching Program whereas the Selective Leaching Program description does not include waste water as an applicable environment. Waste water is an applicable environment within the Selective Leaching Program . Consequently, LRA Sections A.1.39 and 8 .1.39, Selective Leaching , are revised to include waste water as an applicable environment. LRA Section A.1.39 is also revised to correct a typographical error.
The changes to LRA Sections A.1.39 and 8 .1.39 follow with additions underlined.
A.1.39 Selective Leaching The Selective Leaching Program demonstrates the absence of selective leaching through assessment of a sample of components (i.e., 20 percent of the population with maximum of 25 components) fabricated from gray cast iron and copper alloys (except for inhibited brass) that contain greater than 15 percent zinc or greater than 8 percent aluminum in an environment of- ,
raw water, treated water, waste water, or soil. A population is defined as components with the same material and environment combination. Where practical, the sample will focus on components most susceptible to the effects of aging due to time in service, severity of operating condition, and lowest design margin. The program will include a one-time visual inspection of selected components coupled with hardness measurement or other mechanical examination techniques such as destructive testing, scraping , or chipping to determine whether loss of material is occurring due to selective leaching that may affect the ability of a component to perform its intended function through the period of extended operation .
8.1.39 SELECTIVE LEACHING Program Description The Selective Leaching Program is a new program that will demonstrate the absence of selective leaching through assessment of a sample of components (i.e., 20 percent of the population with a maximum of 25 components) fabricated from gray cast iron and copper alloys (except for inhibited brass) that contain greater than 15 percent zinc or greater than 8 percent aluminum in an envirol")ment of raw water, treated water, waste water, or soil. A population is defined as components with the same material and environment combination. Where practical , the sample will focus on components most susceptible to the effects of aging due to time in service, severity of operating condition, and lowest design margin . The program will include a one-time visual inspection of selected components coupled with hardness measurement or other mechanical examination techniques such as destructive testing , scraping, or chipping to determine whether loss of material is occurring due to selective leaching that may affect the ability of a component to perform its intended function through the period of extended operation.
RBG-47812 Enclosure 3 Responses to Request for Additional Information Set 4 Commitments
RBG-47812 Page 1 of 1 This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRC's information and are not commitments.
TYPE SCHEDULED (Check one)
COMMITMENT COMPLETION DATE ONE-TIME CONTINUING (If Required)
ACTION COMPLIANCE Prior to February 28, 2025, or the No. 30, RAI B.1.5-1 Enhance the Control end of the last Rod Drive Return Line Nozzle Program as X refueling outage described in LRA Section A.1.5 prior to August 29, 2025, whichever is later.
Once prior to the period of extended The safe-end-to-cap weld will be operation and once X
volumetrically examined. every 10 years during the period of extended operation.