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| ==REFERENCES:== | | ==REFERENCES:== |
| : 1. NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide , December 2015 (ML16005A625) | | : 1. NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide , December 2015 (ML16005A625) |
| : 2. JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events , February 2016 (ML15357A163) | | : 2. JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events , February 2016 (ML15357A163) |
| : 3. Entergy letter to NRC, Seismic Hazard and Screening Report (Central Eastern United States 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 Dai-ichi Accident , dated March 28, 2014 (ML14092A021) | | : 3. Entergy letter to NRC, Seismic Hazard and Screening Report (Central Eastern United States 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 Dai-ichi Accident , dated March 28, 2014 (ML14092A021) |
| (0CAN031404) | | (0CAN031404) |
| : 4. NRC letter to ANO, Arkansas Nuclear One, Units 1 and 2- Staff Assessment of Information Provided Pursuant to 10 CFR 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident (TAC NOS. MF3822 and MF3823), dated December 15, 2015 (ML15344A109) | | : 4. NRC letter to ANO, Arkansas Nuclear One, Units 1 and 2- Staff Assessment of Information Provided Pursuant to 10 CFR 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident (TAC NOS. MF3822 and MF3823), dated December 15, 2015 (ML15344A109) |
| (0CNA121502) | | (0CNA121502) |
| : 5. Entergy letter to NRC, Response to Request for Additional Information Associated with NTTF Recommendation 2.1, Seismic Hazard and Screening Report Arkansas Nuclear One , dated August 21, 2014 (ML14233A275) (0CAN081401) | | : 5. Entergy letter to NRC, Response to Request for Additional Information Associated with NTTF Recommendation 2.1, Seismic Hazard and Screening Report Arkansas Nuclear One , dated August 21, 2014 (ML14233A275) (0CAN081401) |
| : 6. Entergy letter to NRC, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident , dated November 4, 2014, (ML14308A212) (0CAN111401) | | : 6. Entergy letter to NRC, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident , dated November 4, 2014, (ML14308A212) (0CAN111401) |
| : 7. NRC Letter to Entergy, Request for Information Pursuant to 10 CFR 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 (ML12053A340) (0CNA031208) | | : 7. NRC Letter to Entergy, Request for Information Pursuant to 10 CFR 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 (ML12053A340) (0CNA031208) |
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| Page 5 of 5 | | Page 5 of 5 |
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| REFERENCES | | REFERENCES |
| : 1. NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide , December 2015 (ML16005A625) | | : 1. NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide , December 2015 (ML16005A625) |
| : 2. JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for BDBEEs , February 2016 (ML15357A163) | | : 2. JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for BDBEEs , February 2016 (ML15357A163) |
| : 3. Entergy letter to NRC, Seismic Hazard and Screening Report (Central Eastern United States Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai- | | : 3. Entergy letter to NRC, Seismic Hazard and Screening Report (Central Eastern United States Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai- |
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| ichi Accident , dated March 28, 2014 (ML14092A021) (0CAN031404) | | ichi Accident , dated March 28, 2014 (ML14092A021) (0CAN031404) |
| : 4. NRC letter to ANO, Staff Assessment of Information Provided Pursuant to 10 CFR 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident (TAC NOS. MF3822 and MF3823), dated December 15, 2015 (ML15344A109) (0CNA121502) | | : 4. NRC letter to ANO, Staff Assessment of Information Provided Pursuant to 10 CFR 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident (TAC NOS. MF3822 and MF3823), dated December 15, 2015 (ML15344A109) (0CNA121502) |
| : 5. U.S. NRC, NUREG-1407: Procedural and Submittal Guidance for the IPEEE for Severe Accident Vulnerabilities , Washington, D.C., June 1991 (ML063550238) | | : 5. U.S. NRC, NUREG-1407: Procedural and Submittal Guidance for the IPEEE for Severe Accident Vulnerabilities , Washington, D.C., June 1991 (ML063550238) |
| : 6. NEI, NEI 12-01 Revision 0: Guideline for Assessing Beyond-Design-Basis Accident Response Staffing and Communications Capabilities , Washington, D.C., May 2012 | | : 6. NEI, NEI 12-01 Revision 0: Guideline for Assessing Beyond-Design-Basis Accident Response Staffing and Communications Capabilities , Washington, D.C., May 2012 |
| : 7. EPRI, SPID for the Resolution of Fukushima NTTF Recommendation 2.1: Seismic, Report Number 1025287 , Palo Alto, CA, November 2012 | | : 7. EPRI, SPID for the Resolution of Fukushima NTTF Recommendation 2.1: Seismic, Report Number 1025287 , Palo Alto, CA, November 2012 |
| : 8. EPRI, High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation , Report Number 3002004396, Palo Alto, CA, July 30, 2015 | | : 8. EPRI, High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation , Report Number 3002004396, Palo Alto, CA, July 30, 2015 |
| : 9. Entergy letter to NRC, Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for BDBEEs , dated January 12, 2016 (ML16014A396) (0CAN011601) | | : 9. Entergy letter to NRC, Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for BDBEEs , dated January 12, 2016 (ML16014A396) (0CAN011601) |
| : 10. NRC letter to NEI, Endorsement of EPRI Report 3002007148, Seismic Evaluation Guidance: SFP Integrity Evaluation , dated March 17,2016 (ML15350A158) | | : 10. NRC letter to NEI, Endorsement of EPRI Report 3002007148, Seismic Evaluation Guidance: SFP Integrity Evaluation , dated March 17,2016 (ML15350A158) |
| : 11. CALC-ANOC-CS-16-00008, Mitigating Strategies Assessment for New Seismic Hazards Information ANO , Revision 000 | | : 11. CALC-ANOC-CS-16-00008, Mitigating Strategies Assessment for New Seismic Hazards Information ANO , Revision 000 |
| : 12. CALC-13-E-0005-57, HCLPF Evaluation of FLEX SFP Cooling and Instrumentation , Revision 000 | | : 12. CALC-13-E-0005-57, HCLPF Evaluation of FLEX SFP Cooling and Instrumentation , Revision 000 |
| : 13. Entergy Letter to NRC, High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi | | : 13. Entergy Letter to NRC, High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi |
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| Accident , dated December 30, 2016 (0CAN121603) | | Accident , dated December 30, 2016 (0CAN121603) |
| : 14. NRC Letter to Entergy, Request for Information Pursuant to 10 CFR 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 (ML12053A340) (0CNA031208)}} | | : 14. NRC Letter to Entergy, Request for Information Pursuant to 10 CFR 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 (ML12053A340) (0CNA031208)}} |
Letter Sequence Other |
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Results
Other: 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 Accident, 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 3, ML15344A109, 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)
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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 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-14-206, 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 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 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 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 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 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 2014-03-28
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Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024 Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24017A1582024-01-17017 January 2024 Submittal of Emergency Plan Revision 50 IR 05000313/20234202024-01-10010 January 2024 Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420 IR 05000313/20234022024-01-0202 January 2024 Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402 ML23354A0022023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment IR 05000313/20234052023-12-12012 December 2023 Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405 ML23341A0832023-12-11011 December 2023 Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter ML23305A0922023-12-0707 December 2023 Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23275A2072023-11-28028 November 2023 Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23325A1412023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000313/20230032023-11-21021 November 2023 Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001 ML23243B0452023-11-13013 November 2023 Request for Withholding Information from Public Disclosure ML23313A0962023-11-13013 November 2023 Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000313/20230112023-10-10010 October 2023 Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011 IR 05000313/20230052023-08-21021 August 2023 Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle IR 05000313/20243012023-08-14014 August 2023 Notification of NRC Initial Operator Licensing Examination 05000313/2024301 IR 05000313/20230022023-08-11011 August 2023 Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation ML23209A6022023-08-0909 August 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 ML23208A2132023-08-0303 August 2023 Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23188A1732023-07-12012 July 2023 Request for Withholding Information from Public Disclosure ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements IR 05000313/20234032023-06-28028 June 2023 Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403 ML23178A0892023-06-26026 June 2023 August 2023 Emergency Preparedness Program Inspection-Request for Information ML23166B0902023-06-21021 June 2023 Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report IR 05000313/20234012023-06-13013 June 2023 Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401 ML23130A2972023-05-17017 May 2023 Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information ML23121A3012023-05-10010 May 2023 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times ML23114A3572023-05-10010 May 2023 Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000313/20230012023-05-0909 May 2023 Integrated Inspection Report 05000313/2023001 and 05000368/2023001 ML23118A3202023-05-0808 May 2023 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010) IR 05000368/20233012023-05-0101 May 2023 NRC Examination Report 05000368/2023301 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23108A1362023-04-24024 April 2023 Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46 ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 2024-01-24
[Table view] Category:Report
MONTHYEAR1CAN062304, 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 ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version2023-06-20020 June 2023 Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version ML23088A2172022-12-31031 December 2022 Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022 2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-02-24024 February 2022 Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis2021-10-0606 October 2021 Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment 2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval2021-06-29029 June 2021 Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval 0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes2021-05-10010 May 2021 Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1392021-03-22022 March 2021 Strategy 1 ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy 1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values2020-03-19019 March 2020 Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values 0CAN121901, Summary of Lost Specimens Investigation Report2019-12-0303 December 2019 Summary of Lost Specimens Investigation Report ML18215A1782018-06-30030 June 2018 WCAP-18169-NP, Rev 1, Arkansas Nuclear One Unit 2 Heatup and Cooldown Limit Curves for Normal Operation. ML17214A0292018-02-12012 February 2018 Staff Assessment of Flooding Focused Evaluation (CAC Nos. MF9809 and MF9810) ML17291A0092017-10-26026 October 2017 Staff Assessment Regarding Program Plan for Aging Management for Reactor Vessel Internals (CAC No. MF8155; EPID L-2016-LRO-0001) ML17236A1792017-08-22022 August 2017 Arkansas, Units 1 and 2, ANO Emergency Plan On-Shift Staffing Analysis Report, Revision 2 0CAN081703, Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report2017-08-16016 August 2017 Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report ML17167A0832017-06-28028 June 2017 Arkansas Nuclear One, Unit 2 - Review of Commitment Submittal for License Renewal Regarding Nickel-Based Alloy Aging Management Program Plan (CAC No. MF8154) 0CAN061701, Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis2017-06-0707 June 2017 Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis 0CAN051704, Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One.2017-03-13013 March 2017 Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One. 2CAN011703, Submittal of Additional Protocol Report2017-01-26026 January 2017 Submittal of Additional Protocol Report ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 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 ML17003A2902016-12-20020 December 2016 Areva, Inc. - Engineering Information Record - Arkansas Nuclear One HFE-High Frequency Confirmation Report ML16365A0272016-10-31031 October 2016 ANP-3486NP, Revision 0, MRP-227-A Applicant/Licensee Action Item 6 Analysis for Arkansas Nuclear One Unit 1 (ANO-1). ML16293A5842016-09-30030 September 2016 WCAP-18166-NP, Revision 0, Analysis of Capsule 284 from the Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 Reactor Vessel Radiation Surveillance Program. 1CAN091601, Submittal of Initial Examination Completion of Post-Examination Analysis2016-09-0101 September 2016 Submittal of Initial Examination Completion of Post-Examination Analysis ML16202A1672016-07-0505 July 2016 Report 1500227.401, PWR Internals Aging Management Program Plan. ML16147A3242016-05-31031 May 2016 ANP-3417NP, Rev. 1, MRP-227-A Applicant/Licensee Action Item #7 Analysis for Arkansas Nuclear One, Unit 1. ML16004A1792015-12-31031 December 2015 Attachment 2, ANP-3418NP, Revision 0, Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2) Licensing Report. (Non-Proprietary) ML15278A0242015-09-28028 September 2015 Attachment 2, Areva Document ANP-3417NP, Revision 0, MRP-227-A Applicant / Licensee Action Item No. 7 Analysis for Arkansas Nuclear One, Unit 1 (Non-Proprietary), Attachment 3, Affidavit, and Attachment 4, List of Commitments ML15099A1522015-04-16016 April 2015 Review of Spring 2014 Steam Generator Tube Inspection Report, Inspection During Refueling Outage 2R23 ML15071A0552015-03-31031 March 2015 ANP-3300Q2NP, Revision 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1. ML15086A0242015-03-25025 March 2015 ANP-3300Q3NP, Revision 0 to Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1 (Non-Proprietary ML15043A1032015-02-10010 February 2015 Areva Document ANP-3383NP, Response to Request for Additional Information for the Reactor Pressure Vessel Internals Aging Management Program Plan for Arkansas Nuclear One Unit 1 ML15041A0742015-02-0606 February 2015 ANP-3300Q1NP, Rev. 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1, Attachment 2 to 1CAN0 2023-06-29
[Table view] Category:Miscellaneous
MONTHYEARCNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L 0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes2021-05-10010 May 2021 Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy 1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values2020-03-19019 March 2020 Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values 0CAN121901, Summary of Lost Specimens Investigation Report2019-12-0303 December 2019 Summary of Lost Specimens Investigation Report ML17214A0292018-02-12012 February 2018 Staff Assessment of Flooding Focused Evaluation (CAC Nos. MF9809 and MF9810) ML17291A0092017-10-26026 October 2017 Staff Assessment Regarding Program Plan for Aging Management for Reactor Vessel Internals (CAC No. MF8155; EPID L-2016-LRO-0001) ML17167A0832017-06-28028 June 2017 Arkansas Nuclear One, Unit 2 - Review of Commitment Submittal for License Renewal Regarding Nickel-Based Alloy Aging Management Program Plan (CAC No. MF8154) 2CAN011703, Submittal of Additional Protocol Report2017-01-26026 January 2017 Submittal of Additional Protocol Report ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 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 ML17003A2902016-12-20020 December 2016 Areva, Inc. - Engineering Information Record - Arkansas Nuclear One HFE-High Frequency Confirmation Report 1CAN091601, Submittal of Initial Examination Completion of Post-Examination Analysis2016-09-0101 September 2016 Submittal of Initial Examination Completion of Post-Examination Analysis ML16147A3242016-05-31031 May 2016 ANP-3417NP, Rev. 1, MRP-227-A Applicant/Licensee Action Item #7 Analysis for Arkansas Nuclear One, Unit 1. ML15099A1522015-04-16016 April 2015 Review of Spring 2014 Steam Generator Tube Inspection Report, Inspection During Refueling Outage 2R23 ML15086A0242015-03-25025 March 2015 ANP-3300Q3NP, Revision 0 to Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1 (Non-Proprietary ML15043A1032015-02-10010 February 2015 Areva Document ANP-3383NP, Response to Request for Additional Information for the Reactor Pressure Vessel Internals Aging Management Program Plan for Arkansas Nuclear One Unit 1 0CAN021501, Spent Fuel Storage Radioactive Effluent Release Report for 20142015-02-0303 February 2015 Spent Fuel Storage Radioactive Effluent Release Report for 2014 ML15028A4932015-01-31031 January 2015 ANP-3281Q1NP, Rev. 0, Response to NRC Request for Additional Information on Time-Limited Aging Analysis for the ANO-1 Reactor Vessel Internals, Attacment 2 ML14329A4262014-10-22022 October 2014 U.S. Nuclear Regulatory Commission, Record of Review, Arkansas Nuclear One Unit 2 (ANO-2), LAR Attachment V-Table V-1 Fire PRA Facts and Observations (F&Os). ML14223A8032014-08-12012 August 2014 Review of Steam Generator Tube Inspection Report for Refueling Outage 1R24 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 ML14051A1882014-03-18018 March 2014 Staff Assessments of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0090-MF0091) 0CAN021403, Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary Report2014-02-11011 February 2014 Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary Report ML14028A1992014-01-16016 January 2014 Units 1 and 2, Unsatisfactory Blind Quality Assurance Drug Testing Samples 2CAN091302, Updated Seismic Walkdown Report2013-09-30030 September 2013 Updated Seismic Walkdown Report 1CAN031305, Cycle 24 COLR, Revision 62013-03-13013 March 2013 Cycle 24 COLR, Revision 6 ML12159A5972012-06-18018 June 2012 Closeout of NRC Bulletin 2011-01, Mitigating Strategies 0CAN021204, Units 1 and 2, Third Five-Year Surveillance of the First Ventilated Storage Cask2012-02-29029 February 2012 Units 1 and 2, Third Five-Year Surveillance of the First Ventilated Storage Cask 2CAN011202, Additional Protocol Report2012-01-31031 January 2012 Additional Protocol Report ML1130703872011-11-0202 November 2011 Fall 2011 RFO - Steam Generator Inspection Call - Part II, Summary of the ANO1 1R23 Steam Generator Inspection 2CAN091103, CFR 50.59 Summary Report2011-09-16016 September 2011 CFR 50.59 Summary Report 1CAN041105, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-0162011-04-20020 April 2011 Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016 0CAN101003, 10 CFR 50.59 Summary Report and Commitment Change Summary Report2010-10-0707 October 2010 10 CFR 50.59 Summary Report and Commitment Change Summary Report 1CAN091001, 10 CFR 50.46 Report - Significant Change in Peak Cladding Temperature2010-09-0808 September 2010 10 CFR 50.46 Report - Significant Change in Peak Cladding Temperature 0CAN031001, Units 1 & 2, Unsatisfactory Laboratory Testing Report2010-03-18018 March 2010 Units 1 & 2, Unsatisfactory Laboratory Testing Report 2CAN011003, Submittal of Us Dept. of Commerce, Bureau of Industry and Security. Additional Protocol Report2010-01-28028 January 2010 Submittal of Us Dept. of Commerce, Bureau of Industry and Security. Additional Protocol Report 0CAN100901, Units 1 & 2, Unsatisfactory Laboratory Testing Report2009-10-13013 October 2009 Units 1 & 2, Unsatisfactory Laboratory Testing Report 0CAN050903, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes2009-05-15015 May 2009 Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes 2CAN100802, CFR 50.59 Summary Report for Period Ending October 6, 20082008-10-13013 October 2008 CFR 50.59 Summary Report for Period Ending October 6, 2008 2CAN070804, Cycle 20 Startup Report2008-07-0303 July 2008 Cycle 20 Startup Report 2021-05-10
[Table view] |
Text
0CAN121602
December 30 2016
U.S. Nuclear Regulatory Commission
ATTN: Document Control Desk
11555 Rockville Pike
Rockville, MD 20852
SUBJECT:
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
Arkansas Nuclear One - Units 1 and 2
Docket Nos. 50-313 and 50-368
License Nos. DPR-51 and NPF-6
Dear Sir or Madam:
The purpose of this letter is to provide the results of the assessment for Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2, respectively) to demonstrate that an Individual Plant
Examination of External Events (IPEEE)-based alternate mitigating strategy can be
implemented considering the impacts of the r eevaluated seismic hazard. The assessment was performed in accordance with the guidance provided in Appendix H of Reference 1, which was
endorsed by the NRC in Reference 2.
The mitigating strategies seismic hazard information (MSSHI) is the licensee's reevaluated
seismic hazard information at ANO-1 and ANO-2 which was developed using probabilistic
seismic hazard analysis. The MSSHI for Path 3 includes the performance-based ground motion
response spectrum (GMRS) at various frequencies developed at the ANO-1 and ANO-2 control
point elevations. In response to Reference 7, Entergy Operations, Inc. submitted the
reevaluated seismic hazard information including the uniform hazard response spectra, GMRS, and the hazard curves (References 3, 5, and 6). The NRC staff concluded that the MSSHI
adequately characterizes the reevaluated seismic hazard for the site (Reference 4).
Consistent with Section H.4.3 of Reference 1, the ANO-1 and ANO-2 GMRS is bounded by the
high-confidence-of-low-probability-of-failure (HCLPF) spectrum developed from evaluations for
the IPEEE between 1 and 10 Hz - referred to as the IPEEE HCLPF spectrum (IHS).
Section 6.1.2 of Reference 2 identified that the method described in Section H.4.3 of
Reference 1 is applicable to ANO-1 and ANO-2. The ANO-1 and ANO-2 GMRS are not
bounded by the IHS at frequencies greater than 10 Hz.
Based upon the mitigating strategies assessment in the attachment to this letter, the mitigating
strategies for ANO-1 and ANO-2 considering the impacts of the reevaluated seismic hazard can
be implemented as designed.
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802
Tel 479-858-3110 Richard L. Anderson A NO Site Vice President
0CAN121602 Page 2 of 3
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
December 30, 2016.
Sincerely, ORIGINAL SIGNED BY TERRY A. EVANS (ACTING VP) FOR RICHARD L. ANDERSON
RLA/nbm
Attachment:
Mitigating Strategies Assessment for Arkansas Nuclear One
REFERENCES:
- 1. NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide , December 2015 (ML16005A625)
- 2. JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events , February 2016 (ML15357A163)
- 3. Entergy letter to NRC, Seismic Hazard and Screening Report (Central Eastern United States 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 Dai-ichi Accident , dated March 28, 2014 (ML14092A021)
(0CAN031404)
- 4. NRC letter to ANO, Arkansas Nuclear One, Units 1 and 2- Staff Assessment of Information Provided Pursuant to 10 CFR 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident (TAC NOS. MF3822 and MF3823), dated December 15, 2015 (ML15344A109)
(0CNA121502)
- 5. Entergy letter to NRC, Response to Request for Additional Information Associated with NTTF Recommendation 2.1, Seismic Hazard and Screening Report Arkansas Nuclear One , dated August 21, 2014 (ML14233A275) (0CAN081401)
- 6. Entergy letter to NRC, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident , dated November 4, 2014, (ML14308A212) (0CAN111401)
- 7. NRC Letter to Entergy, Request for Information Pursuant to 10 CFR 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 (ML12053A340) (0CNA031208)
0CAN121602 Page 3 of 3
cc: Mr. Kriss Kennedy Regional Administrator
U. S. Nuclear Regulatory Commission, Region IV
1600 East Lamar Boulevard Arlington, TX 76011-4511
NRC Senior Resident Inspector
Arkansas Nuclear One
P.O. Box 310
London, AR 72847
U. S. Nuclear Regulatory Commission
Attn: Mr. Thomas J. Wengert
MS O8 B1A
One White Flint North
11555 Rockville Pike
Rockville, MD 20852
Attachment to 0CAN121602 Mitigating Strategies Assessment for Arkansas Nuclear One Attachment to 0CAN121602
Page 1 of 5
Mitigating Strategies Assessment for Arkansas Nuclear One Introduction
The purpose of this mitigating strategies assessment is to evaluate and demonstrate that
Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2, respectively) can mitigate the effects
of the reevaluated seismic hazard information developed pursuant to the 10 CFR 50.54(f) letter
dated March 12, 2012 (Reference 14). The assessment was performed in accordance with the
guidance provided in Reference 1. Reference 1 discusses a method to develop an alternate
mitigating strategy (AMS) to address the mitigating strategies seismic hazard information (MSSHI). This includes a modification of the general criteria and baseline assumptions included
in Section 3.2.1 of Reference 1 to exclude consideration of losses such as an extended loss of
alternating current power (ELAP), loss of offsite power, or loss of ultimate heat sink (LUHS)
unless caused by the seismic hazard. Reference 2 provides an NRC staff position that the
method described in Section H.4.3 of Reference 1 for an AMS is acceptable for mitigating a
beyond-design-basis external event (BDBEE).
An individual plant examination of external events (IPEEE)-based AMS relies on the seismic
evaluation of plant equipment to demonstrat e robustness of structures, systems, and components (SSCs) to the ground motion response spectrum (GMRS). The IPEEE for ANO-1
and ANO-2 relied on the results of an Electric Power Research Institute (EPRI) seismic margins
assessment (SMA) methodology to demonstrate the capability to bring the plant to a safe-
shutdown condition following a review level earthquake (RLE) as described in NUREG-1407 (Reference 5). The EPRI SMA methodology approach evaluated two safe-shutdown success
paths. The safe-shutdown success paths provide independent means of achieving a
safe-shutdown condition following a severe seismic event (e.g., core cooling by heat removal
from the steam generators and core cooling by reactor coolant system 'feed and bleed').
The IPEEE high-confidence-of-low-probability-of-failure spectrum (IHS) for ANO-1 and ANO-2
demonstrates plant seismic capacity to levels higher than the GMRS in the 1-10 Hz range (Reference 4). Seismic evaluations performed under the IPEEE included SSCs in those two
safe-shutdown success paths. Therefore, based on the results of the IPEEE, safe-shutdown of
the plant following a seismic event can be accomplished and consequences can be mitigated
for a seismic event up to the plant capacity level (i.e., the IHS) for which the SSCs in the IPEEE
were evaluated.
Indefinite Coping
A plant-specific evaluation was performed which concluded that SSCs that limit the SMA-based
IPEEE coping duration to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> are available for an indefinite period following a beyond-
design-basis seismic event at the reevaluated seismic hazard level to support continued
maintenance of the safe-shutdown condition. The ANO-1 and ANO-2 IPEEE was based on the
EPRI SMA method. This approach defined the Seismic Equipment List for evaluation of
safe-shutdown success paths to be comprised of those SSCs required to bring the plant to a
safe-shutdown condition and maintain that condition for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Therefore, the
IPEEE results have been evaluated for limitations that are based on the 72-hour coping
duration. Generally, the conclusions of the SM A are not sensitive to coping duration; however, certain consumable items, such as water and fuel oil inventories, have been evaluated based Attachment to 0CAN121602
Page 2 of 5
on a limited onsite supply. The ability to continue coping would potentially require re-supply of consumables.
Site access is assumed to be restored to a near-normal status and/or augmented transportation
resources are available within a few days as discussed in NEI 12-01 (Reference 6) to allow for
additional supplies to be delivered and allow for continuation of coping strategies and maintain
the plant in a safe-shutdown condition. A plant-specific evaluation has been performed to
identify consumables and/or SSCs that are limiting for the 72-hour coping duration assumed in
the development of the IPEEE and to identify methods of addressing any shortfalls.
The coping evaluation (Reference 11) concluded that borated and non-borated water would be
available indefinitely for all safety functions. Several water supplies are available to ANO-1 and
ANO-2 to support coping for an extended period following the beyond-design-basis seismic
event to support continued maintenance of the safe-shutdown condition. This includes multiple
large atmospheric storage tanks and the ultimate heat sink. The large atmospheric storage
tanks include the ANO-1 condensate storage tank (CST), both ANO-2 CSTs, the safety-related
condensate storage tank (QCST), the ANO-1 borated water storage tank, and the ANO-2
refueling water tank. These tanks would provide numerous days of continued operation for
reactor coolant inventory control, decay heat removal, and spent fuel pool (SFP) cooling. This
would provide ample coping time before inventory from the ultimate heat sink is required. The
ultimate heat sink is comprised of the emergency cooling pond (ECP), a large but finite source
of inventory, and Lake Dardanelle which can be considered an indefinite supply of water. The National Strategic Alliance for FLEX Emergency Response (SAFER) Response Centers (NSRC) would supply portable pumps and other equipment to support the indefinite coping
capability for both ANO-1 and ANO-2.
Although not determined to be limiting, fuel oil supplies supporting emergency diesel generator
and portable diesel-driven equipment operation were also evaluated for extended coping (Reference 11). The on-site supplies have been evaluated to last at least 3.5 days to continue the strategies evaluated under the IPEEE and the on-site FLEX strategies for SFP cooling.
Consistent with the ANO Final Integrated Plan (FIP) (Reference 9), at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of on-site
fuel is ample time to have additional fuel oil provided from offsite resources as necessary.
IPEEE Upgrade to Full Scope
The ANO-1 IPEEE was a modified full scope SMA and requires the performance of a detailed review of relay chatter. The ANO-2 IPEEE was a modified focused scope SMA and also
requires the performance a detailed review of relay chatter. ANO-2 is included in the focused
scope bin, and an upgrade to a full scope assessment is required as described in
EPRI 1025287 (Reference 7).
ANO-2 was binned as a 0.3g focused scope plant in NUREG-1407 (Reference 5). As stated in
Section 3.3.1 of the EPRI Seismic Evaluation Guidance: Screening, Prioritization, and
Implementation Details (SPID), focused-scope IPEEE submittals may be used for screening
against the GMRS provided they are enhanced to bring them in line with full scope
assessments. The enhancements include (1) a full scope detailed review of relay chatter and
(2) a full evaluation of soil failures.
Attachment to 0CAN121602
Page 3 of 5
Full Scope Relay Chatter Review Assessments of relay chatter effects in accordance with the scope and procedures described in
NUREG-1407 (Reference 5) were performed for ANO-1 and ANO-2. ANO-1 and ANO-2 were
considered A-46 plants, and the relay chatter review was conducted consistent with staff
recommendations outlined in NUREG-1407, Appendix D, Table 7.17.2, which includes
expansion of the A-46 relay scope to include IPEEE systems and evaluation of the entire
expanded scope at the IPEEE RLE.
Soil Failure Analysis As stated in NUREG 1407 (Reference 5), Section 3.2.1, a plant in the full-scope category that is
located on a rock site is not required to perform a soil failure evaluation. The ANO-1 and ANO-2
safety-related structures are founded on rock.
SFP Cooling Evaluation
The evaluation of SFP cooling for ANO was performed based on the initial conditions
established in NEI 12-06 (Reference 1) for SFP cooling coping in the event of an ELAP/LUHS.
The evaluation also used the results of SFP heatup analyses from the ELAP evaluation as input (Reference 9).
The FLEX strategy for SFP cooling utilizes SFP level monitoring and makeup capability as
described in the ANO Final Implementation Plan (Reference 9). The permanently installed plant equipment relied on for the implementation of the SFP cooling FLEX strategy includes
components associated with SFP level instrumentation and the SFP makeup riser. This equipment, portable FLEX equipment availab ility (including its storage and deployment pathways) and the permanently installed plant equipment needed to accomplish SFP cooling
have subsequently been evaluated considering t he GMRS-consistent loading conditions in accordance with NEI 12-06, Appendix H, Section 5, and/or Seismic Qualification Utility Group (SQUG) experience-based walkdowns (Reference 12). FLEX equipment availability has been
demonstrated through evaluations in accordance with NEI 12-06, Appendix H, Section 5, by evaluating the SFP makeup riser pipe supports, both ANO FLEX storage buildings, sliding and rocking of FLEX equipment stored within those buildings, the onsite FLEX equipment
deployment path, and the NSRC equipment deployment path. In addition, Seismic Qualification Utility Group (SQUG) experience-based walkdowns were conducted to demonstrate sufficient
seismic adequacy of the SFP makeup riser piping, SFP level instrumentation components, operator access pathways needed to implement the FLEX SFP cooling strategies, and local
storage of portable flexible hoses near the SFP. Through the evaluations completed in
accordance with NEI 12-06, Appendix H, Section 5, and SQUG walkdowns, the means to
provide SFP cooling following a severe seismic event has been demonstrated to be adequate
for GMRS-consistent loading conditions in accordance with NEI 12-06, Appendix H.
High Frequency Evaluation (HFE)
To address high frequency exceedance above the IHS, ANO-1 and ANO-2 have conducted an
evaluation of high frequency motion sensitive components (relays) in accordance with the
guidance in EPRI 3002004396 (Reference 8). The HFE confirmed that the applicable devices
in the EPRI SMA methodology scope are acceptable for the high frequency motions at both Attachment to 0CAN121602
Page 4 of 5
ANO-1 and ANO-2 (Reference 13). Reliance on post-event operator actions was necessary to resolve outliers. A summary of the operator actions and associated outliers is provided in
Reference 13.
Availability of FLEX Equipment
With the exception of SFP cooling, the AMS described in H.4.3 does not rely upon availability of FLEX equipment. On-site FLEX equipment may be available for deployment to support the
maintenance of core cooling, containment, and SFP cooling functions. In order to provide additional potential mitigating capability, portable FLEX equipment not being used for the AMS
is stored and reasonably protected in accordance with Section 5.3.1 of NEI 12-06.
Additionally, ANO maintains the capability to obtain additional portable FLEX equipment from
offsite sources. The use of offsite equipment for ANO is documented in Reference 9. The
industry has established two NSRCs to support utilities during BDBEEs, of which ANO has
established contracts to participate in the process for support of the NSRCs as required. Each
NSRC holds multiple sets of equipment, capable of being fully deployed when requested. In the
event of a beyond-design-basis seismic even t, equipment can be moved from an NSRC to a local assembly area established by the SAFER t eam. From there, equipment can be taken to the site and staged at the SAFER onsite Staging Area by helicopter, if ground transportation is
unavailable. Communications would be established between the site and the SAFER team via
satellite phones and required equipment moved to the site as needed. Initial equipment would
be delivered to the site within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from the initial request. The order in which equipment is
delivered is identified in the ANO SAFER Response Plan and no modifications to the sequence
are necessary following a seismic event.
Summary of Modifications
Based on the conclusions of the seismic MSA, ANO does not require any modifications to assure SFP cooling, indefinite coping, the availability of FLEX equipment, or to support
components evaluated under the HFE.
Implementation of SFP makeup following a severe seismic event would be at the discretion of
Operations. The existing site procedures direct operations to restore SFP cooling utilizing
various methods in the event of an SFP emergency, one of which includes providing emergency
makeup from the respective unit's service water system. The service water system for each unit was determined to be seismically adequate as part of IPEEE, as it is required for safe-
shutdown. While Operations would likely utiliz e the service water systems to provide SFP cooling following a loss of normal SFP cooling, the MSA shows that the FLEX SFP hose
makeup strategy is capable of being implemented, providing additional flexibility following a
severe seismic event. As such, no procedure changes are necessary because Operations would direct the use of the FLEX SFP makeup based on the condition of the unit.
Attachment to 0CAN121602
Page 5 of 5
REFERENCES
- 1. NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide , December 2015 (ML16005A625)
- 2. JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for BDBEEs , February 2016 (ML15357A163)
- 3. Entergy letter to NRC, Seismic Hazard and Screening Report (Central Eastern United States Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-
ichi Accident , dated March 28, 2014 (ML14092A021) (0CAN031404)
- 4. NRC letter to ANO, Staff Assessment of Information Provided Pursuant to 10 CFR 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi Accident (TAC NOS. MF3822 and MF3823), dated December 15, 2015 (ML15344A109) (0CNA121502)
- 5. U.S. NRC, NUREG-1407: Procedural and Submittal Guidance for the IPEEE for Severe Accident Vulnerabilities , Washington, D.C., June 1991 (ML063550238)
- 6. NEI, NEI 12-01 Revision 0: Guideline for Assessing Beyond-Design-Basis Accident Response Staffing and Communications Capabilities , Washington, D.C., May 2012
- 7. EPRI, SPID for the Resolution of Fukushima NTTF Recommendation 2.1: Seismic, Report Number 1025287 , Palo Alto, CA, November 2012
- 8. EPRI, High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation , Report Number 3002004396, Palo Alto, CA, July 30, 2015
- 9. Entergy letter to NRC, Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for BDBEEs , dated January 12, 2016 (ML16014A396) (0CAN011601)
- 10. NRC letter to NEI, Endorsement of EPRI Report 3002007148, Seismic Evaluation Guidance: SFP Integrity Evaluation , dated March 17,2016 (ML15350A158)
- 11. CALC-ANOC-CS-16-00008, Mitigating Strategies Assessment for New Seismic Hazards Information ANO , Revision 000
- 12. CALC-13-E-0005-57, HCLPF Evaluation of FLEX SFP Cooling and Instrumentation , Revision 000
- 13. Entergy Letter to NRC, High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the NTTF Review of Insights from the Fukushima Dai-ichi
Accident , dated December 30, 2016 (0CAN121603)
- 14. NRC Letter to Entergy, Request for Information Pursuant to 10 CFR 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 (ML12053A340) (0CNA031208)