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MONTHYEARLR-N13-0205, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity...2013-09-10010 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity... Project stage: Response to RAI 0CAN091301, Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi..2013-09-12012 September 2013 Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi.. Project stage: Response to RAI LR-N14-0051, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. Project stage: Response to RAI 0CAN031404, ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima2014-03-28028 March 2014 ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima Da Project stage: Response to RAI ML14092A4172014-03-31031 March 2014 Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1 Project stage: Request RS-14-065, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The..2014-03-31031 March 2014 Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The.. Project stage: Response to RAI LIC-14-0047, Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi2014-03-31031 March 2014 Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Project stage: Request ML14204A6202014-07-21021 July 2014 Response to Request for Additional Information Regarding Seismic Hazard and Screening Report for Seismic Recommendation 2.1 Project stage: Response to RAI ML14204A6192014-07-21021 July 2014 Response to March 12, 2012 Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 Project stage: Request NL-14-099, Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights.2014-08-18018 August 2014 Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights. Project stage: Request 0CAN081401, Response to Request for Additional Information (RAI) Associated with Near-Term Task Force (NTTF) Recommendation 2.1, Seismic Hazard and Screening Report2014-08-21021 August 2014 Response to Request for Additional Information (RAI) Associated with Near-Term Task Force (NTTF) Recommendation 2.1, Seismic Hazard and Screening Report Project stage: Response to RAI RS-14-206, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) Project stage: Other PLA-7224, Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-72242014-08-28028 August 2014 Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-7224 Project stage: Request RS-14-230, Supplemental Information Related to the Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2, 1 of the Near-Term Task Force Review Of...2014-08-29029 August 2014 Supplemental Information Related to the Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2, 1 of the Near-Term Task Force Review Of... Project stage: Supplement ML14224A5262014-09-22022 September 2014 Screening and Prioritization Results of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Project stage: Other LIC-14-0124, Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...2014-10-22022 October 2014 Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The... Project stage: Supplement LR-N14-0227, Seismic Hazard and Screening Report - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-10-30030 October 2014 Seismic Hazard and Screening Report - Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Supplement 0CAN111401, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-11-0404 November 2014 Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Other NL-14-139, Additional Information Regarding the Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-11-0505 November 2014 Additional Information Regarding the Request for Review of Entergy Seismic Hazard and Screening Report (CEUS Sites), Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request ML14310A0222014-11-13013 November 2014 Report Regarding Individual Plant Examination of External Events Supporting Information for Seismic Screening Project stage: Other ML14246A4282014-11-21021 November 2014 Screening and Prioritization Results Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident Based on Individual Plant Examination of External Events Project stage: Approval ML14310A0332014-12-15015 December 2014 NRC Response to Licensees Notification of Revised Regulatory Commitments Associated with Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Revie Project stage: RAI ML15329A1812015-12-0808 December 2015 Staff Assessment of Information Provided Pursuant of Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f)Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights.. Project stage: Approval ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review Project stage: Other ML15344A1092015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Project stage: Other ML17123A3782016-04-27027 April 2016 Reevaluated Seismic Hazard Mitigating Strategies Assessment Report Project stage: Other LIC-16-0039, Ft. Calhoun, Unit 1 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident2016-05-25025 May 2016 Ft. Calhoun, Unit 1 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI ML16365A0322016-12-21021 December 2016 Response to March 12, 2012 Information Request, Spent Fuel Pool Seismic Evaluation for Recommendation 2.1 Project stage: Other 0CAN121602, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 32016-12-30030 December 2016 Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 3 Project stage: Other 2014-07-21
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Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
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Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Jeremy G. Browning Vice President, Operations Arkansas Nuclear One 0CAN091301 September 12, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
SUBJECT:
Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident - 1.5-Year Response for Central and Eastern United States (CEUS) Sites Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6
REFERENCES:
- 1. NRC Letter to Entergy, RFI Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (0CNA031208)
(ML12053A340)
- 2. NRC Letter, Endorsement of Electric Power Research Institute (EPRI) Final Draft Report 1025287, Seismic Evaluation Guidance, dated February 15, 2013 (ML12319A074)
- 3. EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details for the Resolution of Fukushima NTTF Recommendation 2.1: Seismic (ML12333A170)
- 4. Nuclear Energy Institute (NEI) Letter to NRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013 (ML13101A345)
- 5. NRC Letter, EPRI Final Draft Report XXXXXX, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima NTTF Recommendation 2.1: Seismic, as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 (ML13106A331)
0CAN091301 Page 2 of 3
- 6. Entergy letter to NRC, Response to NRC RFI Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated April 29, 2013 (0CAN041306)
Dear Sir or Madam:
On March 12, 2012, the NRC issued Reference 1 to all power reactor licensees. of Reference 1 requested each addressee in the CEUS to submit a written response consistent with the requested seismic hazard evaluation information (items 1 through 7) by September 12, 2013. On February 15, 2013, NRC issued Reference 2, endorsing the Reference 3 industry guidance for responding to Reference 1. Section 4 of Reference 3 identifies the detailed information to be included in the seismic hazard evaluation submittals.
On April 9, 2013, NEI submitted Reference 4 to NRC, requesting NRC agreement to delay submittal of some of the CEUS seismic hazard evaluation information so that an update to the EPRI (2004, 2006) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles (items 3a and 3b in Section 4 of Reference 3) be submitted to NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to NRC by March 31, 2014. In Reference 5, NRC agreed with this recommendation. Reference 6 contained Entergys commitment to follow the approach described in Reference 4.
The attachment to this letter contains the requested descriptions of subsurface materials and properties and base case velocity profiles for Arkansas Nuclear One (ANO). The information provided in the attachment to this letter is considered an interim product of seismic hazard development efforts being performed for the industry by EPRI. The complete and final seismic hazard reports for ANO will be provided to the NRC in the seismic hazard submittal by March 31, 2014, in accordance with Reference 5.
This letter contains no new regulatory commitments. Should you have any questions regarding this submittal, please contact Stephenie Pyle at 479.858.4704.
I declare under penalty of perjury that the foregoing is true and correct; executed on September 12, 2013.
Sincerely, Original signed by Jeremy G. Browning JGB/nbm
Attachment:
ANO Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles
0CAN091301 Page 3 of 3 cc: Mr. Steven A. Reynolds Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission Attn: Director, Office of Nuclear Reactor Regulation One White Flint North 11555 Rockville Pike Rockville, MD 20852 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam One White Flint North MS O-8 B1 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission ATTN: Robert J. Fretz Jr.
OWFN - Mailstop 4A15A 11555 Rockville Pike Rockville, MD 20852-2378 U. S. Nuclear Regulatory Commission ATTN: Robert L. Dennig OWFN - Mailstop 10E1 11555 Rockville Pike Rockville, MD 20852-2378
Attachment to 0CAN091301 Arkansas Nuclear One (ANO) Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles
Attachment to 0CAN091301 Page 1 of 5 ANO Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles The basic information used to create the site geologic profile at the Arkansas Nuclear One was taken from Reference 1, with the following description:
The reactor containment building is founded on shale of the McAlester Formation with embedment depth of around 26 ft. with tendon galleries of about 36 ft. below grade. Basement rock is estimated to be at a depth of 5,000 ft(The) site shear-wave (S-wave) velocity of 5,350 fps (was) calculated using a Poissons ratio of 0.30 and the range of values of the compressional-wave (P-wave) velocity from 10,000 to 14,500 fps for McAlester shale. The Unit 1 SAR indicates the site seismic P-wave varies from 11,000 to 14,500 fps (ref. U1 SAR Fig. 2-21 & 2-30), and per Tables 2-2 & 2-5 Poissons ratio of 0.18 for rock and 0.25 for shale at the site. The Unit 1 SAR does not specifically provide a S-wave velocity. The U2 SAR indicates site P-wave velocities form 10,000 to 14,500 fps, and S-wave (not measured but calculated P-wave of 10,000 fps and a Poissons ration of 0.30) of 5,350 fps SAR figures 2-21 (Unit 1) & 2.5-21 (Unit
- 2) shows the site seismic profiles (for practical purposes, both of these SAR figures are identical)(this description) is correct and agrees with the soil profile data in the ANO Units 1 & 2 Safety Analysis Report (SAR) Amendment 24."
The safe-shutdown earthquake Control Point is defined at the surface, and the profile was modeled up to the surface. For dynamic properties of rock layers, modulus and damping curves were represented with 2 models. The first model used rock curves taken from Reference 2, the second model assumed linear behavior. These dynamic property models were weighted equally. For dynamic properties of fill and compacted sand layers, modulus and damping curves were also represented with 2 models. The first model used soil curves taken from Reference 2; the second model used soil curves taken from Reference 3 and Reference 4. These dynamic property models were weighted equally. To model the profile, rock modulus and damping curves from Reference 2 were paired with soil modulus and damping curves from Reference 2, and linear rock modulus and damping curves were paired with soil modulus and damping curves from Reference 3 and Reference 4.
The three base-case shear-wave velocity profiles used to model amplification at the site are shown in Figure 1. Profiles 1, 2, and 3 are weighted 0.4, 0.3, and 0.3, respectively.
Thicknesses, depths, and shear-wave velocities (Vs) corresponding to each profile are shown in Table 1.
Attachment to 0CAN091301 Page 2 of 5 References
- 1. Entergy (2012), Electric Power Research Institute (EPRI) Data Request for Site Amplification Calculations, Arkansas Nuclear One-Units 1 & 2, Informal report transmitted from Entergy to EPRI in July, 2012
- 2. EPRI (1993), Guidelines for Determining Design Basis Ground Motions, Elec. Power Res. Inst., Palo Alto, CA, Rept. TR-102293, Vol. 1-5
- 3. Silva, W.J., N. A. Abrahamson, G.R. Toro, and C. Costantino (1996), Description and Validation of the Stochastic Ground Motion Model, Rept. submitted to Brookhaven Natl.
Lab., Assoc. Universities Inc., Upton NY 11973, Contract No. 770573 (ML042310562)
- 4. Walling, M.A., W.J., Silva and N.A. Abrahamson (2008), Nonlinear Site Amplification Factors for Constraining the NGA Models, Earthquake Spectra, 24 (1) 243-255 Vs profiles for Arkansas Site Vs (ft/sec) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0
500 1000 1500 2000 Profile 1 Depth (ft) 2500 Profile 2 Profile 3 3000 3500 4000 4500 5000 5500 Figure 1. Vs profiles for Arkansas site
Attachment to 0CAN091301 Page 3 of 5 Table 1 Layer thicknesses, depths, and Vs for 3 profiles, Arkansas site Profile 1 Profile 2 Profile 3 thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) 0 5302 0 3378 0 8325 10.0 10.0 5302 10.0 10.0 3378 10.0 10.0 8325 10.0 20.0 5307 10.0 20.0 3381 10.0 20.0 8332 10.0 30.0 5312 10.0 30.0 3384 10.0 30.0 8340 10.0 40.0 5317 10.0 40.0 3387 10.0 40.0 8348 10.0 50.0 5322 10.0 50.0 3390 10.0 50.0 8356 10.0 60.0 5327 10.0 60.0 3393 10.0 60.0 8364 10.0 70.0 5332 10.0 70.0 3397 10.0 70.0 8372 10.0 80.0 5337 10.0 80.0 3400 10.0 80.0 8379 10.0 90.0 5342 10.0 90.0 3403 10.0 90.0 8387 10.0 100.0 5347 10.0 100.0 3406 10.0 100.0 8395 10.0 110.0 5352 10.0 110.0 3409 10.0 110.0 8403 10.0 120.0 5357 10.0 120.0 3413 10.0 120.0 8411 10.0 130.0 5362 10.0 130.0 3416 10.0 130.0 8419 10.0 140.0 5367 10.0 140.0 3419 10.0 140.0 8427 10.0 150.0 5372 10.0 150.0 3422 10.0 150.0 8434 10.0 160.0 5377 10.0 160.0 3425 10.0 160.0 8442 10.0 170.0 5382 10.0 170.0 3428 10.0 170.0 8450 10.0 180.0 5387 10.0 180.0 3432 10.0 180.0 8458 10.0 190.0 5392 10.0 190.0 3435 10.0 190.0 8466 10.0 200.0 5397 10.0 200.0 3438 10.0 200.0 8474 10.0 210.0 5402 10.0 210.0 3441 10.0 210.0 8481 10.0 220.0 5407 10.0 220.0 3444 10.0 220.0 8489 10.0 230.0 5412 10.0 230.0 3448 10.0 230.0 8497 10.0 240.0 5417 10.0 240.0 3451 10.0 240.0 8505 10.0 250.0 5422 10.0 250.0 3454 10.0 250.0 8513 10.0 260.0 5427 10.0 260.0 3457 10.0 260.0 8521 10.0 270.0 5432 10.0 270.0 3460 10.0 270.0 8529 10.0 280.0 5437 10.0 280.0 3464 10.0 280.0 8536 10.0 290.0 5442 10.0 290.0 3467 10.0 290.0 8544 10.0 300.0 5447 10.0 300.0 3470 10.0 300.0 8552 10.0 310.0 5452 10.0 310.0 3473 10.0 310.0 8560 10.0 320.0 5457 10.0 320.0 3476 10.0 320.0 8568 10.0 330.0 5462 10.0 330.0 3479 10.0 330.0 8576 10.0 340.0 5467 10.0 340.0 3483 10.0 340.0 8584 10.0 350.0 5472 10.0 350.0 3486 10.0 350.0 8591 10.0 360.0 5477 10.0 360.0 3489 10.0 360.0 8599 10.0 370.0 5482 10.0 370.0 3492 10.0 370.0 8607
Attachment to 0CAN091301 Page 4 of 5 10.0 380.0 5487 10.0 380.0 3495 10.0 380.0 8615 10.0 390.0 5492 10.0 390.0 3499 10.0 390.0 8623 10.0 400.0 5497 10.0 400.0 3502 10.0 400.0 8631 10.0 410.0 5502 10.0 410.0 3505 10.0 410.0 8638 10.0 420.0 5507 10.0 420.0 3508 10.0 420.0 8646 10.0 430.0 5512 10.0 430.0 3511 10.0 430.0 8654 10.0 440.0 5517 10.0 440.0 3514 10.0 440.0 8662 10.0 450.0 5522 10.0 450.0 3518 10.0 450.0 8670 10.0 460.0 5527 10.0 460.0 3521 10.0 460.0 8678 10.0 470.0 5532 10.0 470.0 3524 10.0 470.0 8686 10.0 480.0 5537 10.0 480.0 3527 10.0 480.0 8693 10.0 490.0 5542 10.0 490.0 3530 10.0 490.0 8701 10.0 500.0 5547 10.0 500.0 3534 10.0 500.0 8709 100.0 600.0 5572 100.0 600.0 3550 100.0 600.0 8748 100.0 700.0 5622 100.0 700.0 3581 100.0 700.0 8827 100.0 800.0 5672 100.0 800.0 3613 100.0 800.0 8905 100.0 899.9 5722 100.0 899.9 3645 100.0 899.9 8984 100.0 999.9 5772 100.0 999.9 3677 100.0 999.9 9062 100.0 1099.9 5822 100.0 1099.9 3709 100.0 1099.9 9141 100.0 1199.9 5872 100.0 1199.9 3741 100.0 1199.9 9219 100.0 1299.9 5922 100.0 1299.9 3772 100.0 1299.9 9285 100.0 1399.9 5972 100.0 1399.9 3804 100.0 1399.9 9285 100.0 1499.9 6022 100.0 1499.9 3836 100.0 1499.9 9285 100.0 1599.9 6072 100.0 1599.9 3868 100.0 1599.9 9285 100.0 1699.9 6122 100.0 1699.9 3900 100.0 1699.9 9285 100.0 1799.9 6172 100.0 1799.9 3932 100.0 1799.9 9285 100.0 1899.9 6222 100.0 1899.9 3964 100.0 1899.9 9285 100.0 1999.9 6272 100.0 1999.9 3995 100.0 1999.9 9285 100.0 2099.9 6322 100.0 2099.9 4027 100.0 2099.9 9285 100.0 2199.9 6372 100.0 2199.9 4059 100.0 2199.9 9285 100.0 2299.9 6422 100.0 2299.9 4091 100.0 2299.9 9285 100.0 2399.9 6472 100.0 2399.9 4123 100.0 2399.9 9285 100.0 2499.9 6522 100.0 2499.9 4155 100.0 2499.9 9285 100.0 2599.9 6572 100.0 2599.9 4186 100.0 2599.9 9285 100.0 2699.9 6622 100.0 2699.9 4218 100.0 2699.9 9285 100.0 2799.8 6672 100.0 2799.8 4250 100.0 2799.8 9285 100.0 2899.8 6722 100.0 2899.8 4282 100.0 2899.8 9285 100.0 2999.8 6772 100.0 2999.8 4314 100.0 2999.8 9285 100.0 3099.8 6822 100.0 3099.8 4346 100.0 3099.8 9285 100.0 3199.8 6872 100.0 3199.8 4378 100.0 3199.8 9285 100.0 3299.8 6922 100.0 3299.8 4409 100.0 3299.8 9285 100.0 3399.8 6972 100.0 3399.8 4441 100.0 3399.8 9285
Attachment to 0CAN091301 Page 5 of 5 100.0 3499.8 7022 100.0 3499.8 4473 100.0 3499.8 9285 100.0 3599.8 7072 100.0 3599.8 4505 100.0 3599.8 9285 100.0 3699.8 7122 100.0 3699.8 4537 100.0 3699.8 9285 100.0 3799.8 7172 100.0 3799.8 4569 100.0 3799.8 9285 100.0 3899.8 7222 100.0 3899.8 4600 100.0 3899.8 9285 100.0 3999.8 7272 100.0 3999.8 4632 100.0 3999.8 9285 100.0 4099.8 7322 100.0 4099.8 4664 100.0 4099.8 9285 100.0 4199.8 7372 100.0 4199.8 4696 100.0 4199.8 9285 100.0 4299.8 7422 100.0 4299.8 4728 100.0 4299.8 9285 100.0 4399.8 7472 100.0 4399.8 4760 100.0 4399.8 9285 100.0 4499.8 7522 100.0 4499.8 4792 100.0 4499.8 9285 100.0 4599.8 7572 100.0 4599.8 4823 100.0 4599.8 9285 100.0 4699.8 7622 100.0 4699.8 4855 100.0 4699.8 9285 100.0 4799.7 7672 100.0 4799.7 4887 100.0 4799.7 9285 100.0 4899.7 7722 100.0 4899.7 4919 100.0 4899.7 9285 100.0 4999.7 7772 100.0 4999.7 4951 100.0 4999.7 9285 3280.8 8280.6 9285 3280.8 8280.6 9285 3280.8 8280.6 9285