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Category:Letter type:RBG
MONTHYEARRBG-48308, Notification of Readiness for Supplemental Inspection2024-07-31031 July 2024 Notification of Readiness for Supplemental Inspection RBG-48276, 2023 Annual Radioactive Effluent Release Report2024-04-23023 April 2024 2023 Annual Radioactive Effluent Release Report RBG-48288, Louisiana Pollutant Discharge Elimination System Permit Renewal2024-04-15015 April 2024 Louisiana Pollutant Discharge Elimination System Permit Renewal RBG-48277, 2023 Annual Radiological Environmental Operating Report2024-04-10010 April 2024 2023 Annual Radiological Environmental Operating Report 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 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 2024-07-31
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 “Risk-Informed Categorization and Treatment for Repair 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 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-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 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 ML18115A0722018-04-25025 April 2018 Draft Response on RAI B.1.25-1(Internal Surfaces in Miscellaneous Piping and Ducting Components) ML18115A0612018-04-25025 April 2018 Draft Response on RAI B1.21-1 Flow Accelerated Corrosion 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-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-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-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-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 2024-04-10
[Table view] |
Text
' Enteigy Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 December 8, 2015 RBG-47634 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
High-frequency SUpplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CER 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, "20112, ADAMS Accession Number M/L12053A340
- 2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "Seismic Evaluation GuidanCe: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMS Accession Number ML13106A331
- 3. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287),
dated November 27, 2012, ADAMS Accession Number ML12333A168 and ML12333A170
- 4. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance", dated February 15, 2013, ADAMS Accession Number ML12319A074
- 5. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and Screening Report (ML14091A429)
- 6. NRC Letter, Screening and Prioritization Results regarding information pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews of Insights from the Fukushima Dai-ichi accident, dated May 9, 2014, (ML14111A147)
- 7. NEI Letter, Request for NRC Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), dated July 30, 2015
- 8. NRC letter dated September 15, 2015, Endorsement of Electric Power Research Institute Final Draft Report 3002004396, "High Frequency Program: Application Guidance For Functional Confirmation And Fragility"' (ML15218A569) / p
RBG-47634 December 8, 2015 Page 2 of 3
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 years from the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRC letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.
By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) and augmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)
High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required to perform a high-frequency confirmation. As noted in the May 9, 2014 letter, River Bend Station is to conduct a limited scope high-frequency confirmation.
Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:
Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRC review and endorsement. NRC endorsement was provided by Reference 8.
The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of the control point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less than or equal to 0.2g). Therefore, no additional evaluation is necessary. The attachment to this letter provides the SSE (or IHS) and GMRS information from Reference 5.
This transmittal completes commitments from Reference 4. This letter contains no new regulatory commitments. Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177.
I declare Under penalty of perjury that the foregoing is true and correct. Executed on December 8, 2015.
Sincerely, Sergio Vazquez Director - Engineering
Attachment:
High-frequency Confirmation for RBS cc: U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4511
RBG-47634 December 8, 2015 Page 3 of 3 NRC Sr. Resident Inspector P. O. 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
- U. S. Nuclear Regulatory Commission iAttn: Steven S. Koenick
- '-Mail Stop 8BlA 11555 Rockville Pike
- -.Rockville, MD 20852-2738
Attachment to RBG-47634 Page 1 of 1 High-frequency Confirmato for R8S (Reference Figure 3-2 in EPRI 30020O43*8)
(lf!
' Enteigy Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 December 8, 2015 RBG-47634 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
High-frequency SUpplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CER 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, "20112, ADAMS Accession Number M/L12053A340
- 2.: NRC Letter, Electric Power *Research Institute Report 3002000704, "Seismic Evaluation GuidanCe: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ADAMS Accession Number ML13106A331
- 3. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287),
dated November 27, 2012, ADAMS Accession Number ML12333A168 and ML12333A170
- 4. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance", dated February 15, 2013, ADAMS Accession Number ML12319A074
- 5. Entergy letter dated March 26, 2014, Seismic Hazard Reevaluations and Screening Report (ML14091A429)
- 6. NRC Letter, Screening and Prioritization Results regarding information pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews of Insights from the Fukushima Dai-ichi accident, dated May 9, 2014, (ML14111A147)
- 7. NEI Letter, Request for NRC Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), dated July 30, 2015
- 8. NRC letter dated September 15, 2015, Endorsement of Electric Power Research Institute Final Draft Report 3002004396, "High Frequency Program: Application Guidance For Functional Confirmation And Fragility"' (ML15218A569) / p
RBG-47634 December 8, 2015 Page 2 of 3
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 indicated that licensees should provide a seismic hazard evaluation and screening report within 1 .5 years from the date of the letter for central and eastern United States (CEUS) nuclear power plants. By NRC letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.
By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for River Bend Station (RBS)(Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) and augmented approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE)
High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required to perform a high-frequency confirmation. As noted in the May 9, 2014 letter, River Bend Station is to conduct a limited scope high-frequency confirmation.
Within the May 9, 2014 letter (Reference 6), NRC acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled "High Frequency Program:
Application Guidance for Functional Confirmation and Fragility Evaluation" (EPRI 3002004396) for NRC review and endorsement. NRC endorsement was provided by Reference 8.
The high-frequency confirmation for RBS shows that the high-frequency spectral accelerations of the control point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 6 (less than or equal to 0.2g). Therefore, no additional evaluation is necessary. The attachment to this letter provides the SSE (or IHS) and GMRS information from Reference 5.
This transmittal completes commitments from Reference 4. This letter contains no new regulatory commitments. Should you have any questions regarding this submittal, please contact Joey Clark at 225-381-4177.
I declare Under penalty of perjury that the foregoing is true and correct. Executed on December 8, 2015.
Sincerely, Sergio Vazquez Director - Engineering
Attachment:
High-frequency Confirmation for RBS cc: U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4511
RBG-47634 December 8, 2015 Page 3 of 3 NRC Sr. Resident Inspector P. O. 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
- U. S. Nuclear Regulatory Commission iAttn: Steven S. Koenick
- '-Mail Stop 8BlA 11555 Rockville Pike
- -.Rockville, MD 20852-2738
Attachment to RBG-47634 Page 1 of 1 High-frequency Confirmato for R8S (Reference Figure 3-2 in EPRI 30020O43*8)
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