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Category:Letter type:GNRO
MONTHYEARGNRO-2023/00014, 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 4b2023-06-0606 June 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 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021 Notification of Readiness for Supplemental Inspection GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021 Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206 GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020 Notification of Spent Fuel Cask Use GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020 Response to NRC Integrated Inspection Report 05000416/2020002 GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020 Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020 GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020 Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020 Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020 Annual Radiological Effluent Release Report GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020 Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206 GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020 License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019 Notification of Readiness of 92723 Inspection GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019 Notification of Spent Fuel Cask Use GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019 Correction to Gnro 2019-00017 Emergency Plan Revision 78 GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019 Notification of Readiness of 95001 Supplemental Inspections GNRO-2019/00031, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.2019-06-13013 June 2019 Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation. GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019 Emergency Plan, Revision 78 GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019 Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019 Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018 Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018 Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018 Submittal of 2018 Report of Changes and Errors to 10CFR50.46 GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018 Core Operating Limits Report Cycle 22, Revision 1 GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018 Revised Offsite Dose Calculation Manual GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018 2023-06-06
[Table view] Category:Report
MONTHYEARML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML22011A2982022-01-11011 January 2022 ANS Evaluation Report 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 GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 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 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1432021-03-22022 March 2021 Strategy 5 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 ML21075A2752020-12-22022 December 2020 FAQ 20-06 GGNS Scram - Final Approved ML18123A3142018-05-0707 May 2018 Staff Assessment of Flooding Focused Evaluation (CAC No. MF9897; EPID L-2017-JLD-0015) ML18085A5792018-03-26026 March 2018 Proposed Revision of Replacement of Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML17290B1372017-10-17017 October 2017 Recommendations for Future Inspection - Replacement Steam Dryer. with GE Hitachi Nuclear Energy Report 0000-0125-6316-R2-NP GNRO-2017/00042, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package2017-07-12012 July 2017 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package GNRO-2017/00038, Focused Evaluation of External Flooding2017-06-27027 June 2017 Focused Evaluation of External Flooding GNRO-2016/00053, Mitigating Strategies Assessment (MSA) for Flooding Submittal2016-12-30030 December 2016 Mitigating Strategies Assessment (MSA) for Flooding Submittal GNRO-2016/00046, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 20162016-08-23023 August 2016 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 2016 GNRO-2016/00015, Non-Proprietary Version of MP Machinery and Testing, LLC (Mpm) Proprietary Report 814779, Revs 1 & 2, Neutron Transport Analysis for Grand Gulf Nuclear Station, Previously Included in Letters GNRO-2014/0080 and GNRO-2015/000112016-03-23023 March 2016 Non-Proprietary Version of MP Machinery and Testing, LLC (Mpm) Proprietary Report 814779, Revs 1 & 2, Neutron Transport Analysis for Grand Gulf Nuclear Station, Previously Included in Letters GNRO-2014/0080 and GNRO-2015/00011 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al GNRO-2014/00072, 2014 Report of Changes and Errors to 10CFR50.462014-11-12012 November 2014 2014 Report of Changes and Errors to 10CFR50.46 GNRO-2014/00060, Entergy'S 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 Events2014-08-26026 August 2014 Entergy'S 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 ML14232A7392014-08-20020 August 2014 Report of 10CFR72.48 Evaluations - July 1, 2012 Through June 30, 2014 ML14098A1752014-05-0101 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident GNRO-2014/00027, Entergy 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 Dai-ichi.2014-03-31031 March 2014 Entergy 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 Dai-ichi. ML14007A7182014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2972014-02-12012 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Grand Gulf Nuclear Station, Unit 1, TAC No.: MF0954 ML13217A0532013-07-24024 July 2013 Summary of Root Cause Evaluation - Apparent Violation of 10CFR54.13 for Grand Gulf License Renewal GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report2013-03-11011 March 2013 Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments GNRO-2012/00150, Final Report for Replacement Steam Dryer2012-12-0606 December 2012 Final Report for Replacement Steam Dryer GNRO-2012/00140, Unit No.1 - Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from ..2012-11-26026 November 2012 Unit No.1 - Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from .. GNRO-2012/00141, Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 151 of 345 Through Page 251 of 3452012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 151 of 345 Through Page 251 of 345 ML12352A0712012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Cover Through Attachment C, Seismic Walkdown Checklists (Swcs), Page 150 of 345 ML12352A0692012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment D, Area Walk-by Checklist (Awcs), Page 1 of 167 Through End ML12352A0682012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 252 of 345 Through Page 345 of 345 GNRO-2012/00113, Vibration Data Report2012-09-18018 September 2012 Vibration Data Report GNRO-2012/00109, Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation2012-09-0606 September 2012 Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation GNRO-2012/00099, Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp2012-08-21021 August 2012 Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp ML12159A5152012-06-11011 June 2012 Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident 2023-09-27
[Table view] Category:Miscellaneous
MONTHYEARML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML22011A2982022-01-11011 January 2022 ANS Evaluation Report 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 GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy ML21075A2752020-12-22022 December 2020 FAQ 20-06 GGNS Scram - Final Approved ML18123A3142018-05-0707 May 2018 Staff Assessment of Flooding Focused Evaluation (CAC No. MF9897; EPID L-2017-JLD-0015) ML18085A5792018-03-26026 March 2018 Proposed Revision of Replacement of Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML17290B1372017-10-17017 October 2017 Recommendations for Future Inspection - Replacement Steam Dryer. with GE Hitachi Nuclear Energy Report 0000-0125-6316-R2-NP GNRO-2017/00042, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package2017-07-12012 July 2017 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package GNRO-2017/00038, Focused Evaluation of External Flooding2017-06-27027 June 2017 Focused Evaluation of External Flooding GNRO-2016/00053, Mitigating Strategies Assessment (MSA) for Flooding Submittal2016-12-30030 December 2016 Mitigating Strategies Assessment (MSA) for Flooding Submittal GNRO-2016/00046, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 20162016-08-23023 August 2016 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 2016 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al GNRO-2014/00072, 2014 Report of Changes and Errors to 10CFR50.462014-11-12012 November 2014 2014 Report of Changes and Errors to 10CFR50.46 GNRO-2014/00060, Entergy'S 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 Events2014-08-26026 August 2014 Entergy'S 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 ML14232A7392014-08-20020 August 2014 Report of 10CFR72.48 Evaluations - July 1, 2012 Through June 30, 2014 ML14098A1752014-05-0101 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident GNRO-2014/00027, Entergy 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 Dai-ichi.2014-03-31031 March 2014 Entergy 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 Dai-ichi. ML13217A0532013-07-24024 July 2013 Summary of Root Cause Evaluation - Apparent Violation of 10CFR54.13 for Grand Gulf License Renewal GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report2013-03-11011 March 2013 Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report GNRO-2012/00113, Vibration Data Report2012-09-18018 September 2012 Vibration Data Report GNRO-2012/00099, Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp2012-08-21021 August 2012 Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp ML12159A5152012-06-11011 June 2012 Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML12157A1812012-05-23023 May 2012 Attachment 8 to GNRO-2012/00039 - from Diskette Labeled: Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment K Labeled Condition Reports. ML12157A4262012-05-23023 May 2012 Attachment 38 to GNRO-2012/00039 - Ensr. 2007, Impingement Mortality and Entrainment Characterization Study (Imecs), Entergy -Waterford 3. December 2007 ML12157A1832012-05-23023 May 2012 Attachment 10 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment P Labeled Thermal Monitoring Procedural Protocols. ML12157A2462012-05-23023 May 2012 Attachment 22 to GNRO-2012/00039, Er Reference - Entergy 2010e (NPDES Crs) ML12157A2512012-05-23023 May 2012 Attachment 27 to GNRO-2012/00039, Er Reference - GGNS 2007b (2006 Wmp Report) Grand Gulf Nuclear Station 2006 Waste Minimization Certified Report ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages GNRO-2010/00058, Report of 10CFR50.59 Evaluations and Commitment Changes - July 1, 2009 Through June 30, 20102010-08-17017 August 2010 Report of 10CFR50.59 Evaluations and Commitment Changes - July 1, 2009 Through June 30, 2010 GNRO-2009/00036, Report of 10CFR50.59 Evaluations and Commitment Changes - April 1, 2008 Through June 30, 20092009-07-16016 July 2009 Report of 10CFR50.59 Evaluations and Commitment Changes - April 1, 2008 Through June 30, 2009 ML1019004062009-04-30030 April 2009 GPI Data Review, Grand Gulf Nuclear Station GNRO-2008/00052, Special Report 2008-001 - Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System2008-07-17017 July 2008 Special Report 2008-001 - Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System GNRO-2007/00068, Supplement 2 to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints2007-09-21021 September 2007 Supplement 2 to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints ML0723203352007-05-30030 May 2007 GG-05-2007-FINAL Operating Exam, Operations Training, Determine Shift Staffing to Meet Shift Requirements CNRO-2006-00043, Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-7162006-09-22022 September 2006 Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-716 CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee CNRO-2006-00023, Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests2006-04-24024 April 2006 Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests ML0607204302006-03-0101 March 2006 March 1, 2006 Public Meeting Slides for Proposed Generic Letter Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations. 2023-11-21
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~Entergy Entergy Operations, Inc.
P.o. Box 756 Port Gibson, MS 39150 Vincent Fallacara Vice President, Operations Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2016/00053 December 30,2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Mitigating Strategies Assessment (MSA) for Flooding Submittal Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
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 (GNRI-2012/00059) (ML12053A340)
- 2. Entergy letter to NRC, Response to March 12, 2012, Request for Information, Enclosure 2, Recommendation 2.1, Flooding, Required Response 1, Integrated Assessment Approach, dated January 29, 2013 (GNRO-2013/00002) (ML13029A627) .
- 3. Entergy letter to NRC, Required Response 2 for Near- Term Task Force Recommendation 2. 1: Flooding - Hazard Reevaluation Report, dated March 11, 2013 (GNRO-2013/00020) (ML13071A457)
- 4. Entergy letter to NRC, Grand Gulf Nuclear Station Request for Additional Information Regarding Flooding Hazard, dated December 11, 2013, dated January 9, 2014 (GNRO-2014/00005) (ML14014A277)
- 5. NRC Staff Requirements Memoranda to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards", dated March 30, 2015 (ML15089A236)
- 6. NRC Letter, Coordination of Requests for Information Regarding Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events, dated September 1, 2015 (ML15174A257)
- 7. Nuclear Energy Institute (NEI), Report NE112-06 [Rev 2J, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, dated December 2015 (ML15348A015)
- 8. NRC Letter to Entergy, Grand Gulf Nuclear Station, Unit 1, Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation, dated December 4, 2015 (CAC NO. MF1102)
GNRO-2016/00053 Page 2 of 3
- 9. U.S. Nuclear Regulatory Commission, JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events, dated January 22, 2016 (ML1537A163)
Dear Sir or Madam:
On March 12, 2012, the US Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Section 50.54(f)
(Reference 1). The request was issued as part of implementing lessons learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to reevaluate flood-causing mechanisms using present-day methodologies and guidance. Grand Gulf Nuclear Station (GGNS) responded to the 50.54(f) letter by References 2 and 3. Supplemental information was provided in Reference 4.
Concurrent to the flood hazard reevaluation, GGNS developed and implemented mitigating strategies in accordance with NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events". In Reference 5, the NRC affirmed that licensees need to address the reevaluated flooding hazards within their mitigating strategies assessment (MSA) for beyond-design basis (BDB) external events, including the reevaluated flood hazards. This requirement was confirmed by the NRC in Reference 6. Guidance for performing MSA for Flooding is contained in Appendix G of Reference 6, endorsed by the NRC in Reference 9. For the purpose of the MSA for Flooding and in Reference 6, the NRC termed the reevaluated flood hazard, summarized in Reference 8, as the "Mitigating Strategies Flood Hazard Information" (MSFHI). Reference 6, Appendix G, describes the MSA for Flooding.
In Reference 8, the NRC concluded that the "reevaluated flood hazards information, as summarized in the Attachment to this letter, is suitable for the assessment of mitigating strategies developed in response to Order EA-12-049" for Plant and Unit.
The use of the sandbags as discuss on page five and ten of the attachment has been identified as a nonconforming condition for the use of manual operator actions in place of a permanent plant modification and is being addressed through the Grand Gulf Corrective Action Program.
The Attachment to this letter provides the Mitigating Strategies Assessment for Flooding Report for Grand Gulf Nuclear Station, Unit 1. The assessment concluded that the existing FLEX strategy can be successfully implemented and deployed as designed for all applicable-flood causing mechanisms.
This letter contains no new Regulatory Commitments.
If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.
I declare under penalty of perjury that the foregoing is true and correct. Executed on December 30,2016.
VF/sas
Attachment:
2016 Mitigating Strategies Assessment for Flooding Documentation Requirements at Grand Gulf Nuclear Station
GNRO-2016/00053 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Jim Kim, NRR/DORL (w/2)
Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss M. Kennedy (w/2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. B. J. Smith (w/2)
Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO-2016/00053 2016 Mitigating Strategies Assessment for Flooding Documentation Requirements at Grand Gulf Nuclear Station
r------------------------------.-------.--------,
Engineering Report No. GGNS-SA-16-0000t Rev 0 Page of U ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report
Title:
2016lVUTIGATING STRATEGIES ASSESSlVlENT FOR FLOODING DOCUMENl'ATION REQUIRE1\'1ENTS AT GRAND GULF NUCLEAR STATION Engineering Report Type:
New k8J Revision 0 Cancelled 0 Superseded 0 Superseded by:
Applicable Site(s)
IPI D IP2 0 IP3 0 .IAF 0 PNPS D vv D WPO D ANOl D AN02 D ECH 0 GGNS ~ RBS D WF3 0 I'Ll' D EC No. 64741 Report Origin: 0 Entergy ~ Vendor Vendor Document No.: ENTCORP038-REPT-002 Quality- Related: DYes ~ No Date:
Design Verified: Datc:
Date: 8/1//6
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ENERCON PROJECT REPORT COVER SHEET PAGE 1 OF 11 f.7~*~i!f':,'?r;i'***-**t:...,"(~!y proj~.'<:l. ~"".':~*fY 6::'1
Title:
REPORT NO.: ENTCORP038-REPT-002 2016 MITIGATING STRATEGIES ASSESSMENT FOR FLOODING DOCUMENTATION REVISION: 0 REQUIREMENTS AT GRAND GULF NUCLEAR Client: Entergy STATION Project Identifier: ENTCORP038 Item Cover Sheet Items Yes No 1 Does this Project Report contain any open assumptions, including preliminary information that require confirmation? (If YES, identify the assumptions.) 0 [gJ 2 Does this Project Report supersede an existing Project Report? (If YES, identify the superseded Project Report.)
Superseded Project Report No.
0 IZI Scope of Revision:
Initial Issue Revision Impact on Results:
N/A Safety-Related 0 Non-Safety-Related IZI (1~ .. ;.,A Originator: Jessica Maddocks y; .... "', ~
Reviewer: Jeffrey Head VVhlW~
Approver: Jared Monroe
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£:xcc;;'(:ncp*****F.\*fry p:(~i(~:t. ~v(.'ry doy REVISION STATUS SHEET PAGE 2 OF 11 2016 MITIGATING STRATEGIES ASSESSMENT FOR REPORT NO.: ENTCORP038-REPT-002 FLOODING DOCUMENTATION REQUIREMENTS AT GRAND GULF NUCLEAR STATION REVISION: 0 PROJECT REPORT REVISION STATUS REVISION DATE DESCRIPTION 0 7/8/2016 Initial Issue ATTACHMENT REVISION STATUS ATTACHMENT NO. OF ATTACHMENT NO. OF REVISION REVISION NO. PAGES NO. PAGES N/A
ENERCON TABLE OF CONTENTS PAGE 3 OF 11 t);(e![;?o(p ***..F.v(-.".i.' p:Oji.)Cl. :;:,.:~:ry do, 2016 MITIGATING STRATEGIES ASSESSMENT FOR REPORT NO. ENTCORP038-REPT-002 FLOODING DOCUMENTATION REQUIREMENTS AT GRAND GULF NUCLEAR STATION REVISION 0 Section Page No.
- 1. Summary 4
- 2. Documentation 5 2.1 NEI 12-06, Rev. 2, Section G.2 - Characterization of the MSFHI 5 2.2 NEI 12-06, Rev. 2, Section G.3 - Comparison of the MSFHI and FLEX DB Flood 7 2.3 NEI 12-06, Rev. 2, Section G.4 - Evaluation of Mitigating Strategies for the 10 MSFHI 2.4 References 11
ENTCORP038-REPT-002 Rev. 0 2016 Mitigating Strategies Assessment Flooding Documentation Requirements Grand Gulf Nuclear Station Acronyms:
- COB - Current Design Basis
- ELAP - Extended Loss of AC Power
- FHRR - Flood Hazard Reevaluation Report
- GGNS - Grand Gulf Nuclear Station
- LIP - Local Intense Precipitation
- MSFHI- Mitigating Strategies Flood Hazard Information (from the FHRR and MSFHlietter)
- PMF - Probable Maximum Flood
- PMP - Probable Maximum Precipitation
- PMWE - Probable Maximum Water Elevation
- SSC - Structures, Systems and Components Definitions:
FLEX Design Basis: The flood hazard for which FLEX was designed.
FLEX Design Basis Flood Hazard: The controlling flood parameters used to develop the FLEX flood strategies.
- 1. Summary The GGNS FHRR (Ref. 7) has concluded that the PMF on the Mississippi River and Stream A are not bounded by the COB PMF but are bounded by the FLEX DB for storage building design and equipment staging. PMF on Stream A leads to the loss of the deployment path from the north FLEX storage building (Site 1). The deployment path from the south storage building (Site 4) remains available, so the overall strategy for the storage and deployment of FLEX equipment can still be implemented as designed.
The GGNS FHRR (Ref. 7) has concluded that the PMF on Stream B is bounded by the COB and the FLEX DB.
The FHRR, as updated by Reference 9, determined LIP exceeds the COB for flooding at the plant site but is bounded by the FLEX design basis. LIP is the only flood mechanism that results in inundation of the outdoor areas in the vicinity of SSCs important to safety, and due to the existing mitigating strategy of sandbag deployment, door seals on inactive doors, and the relatively fast recession times, the overall strategy for the storage and deployment of FLEX equipment from the south storage building (Site 4) can be implemented as designed.
Other reevaluated flood hazard mechanisms (e.g., tsunami, channel migrations/diversions, etc.)
are bounded by the FLEX design basis and COB, and therefore have no impact on the site. Details of the FLEX strategies along with the bounding flood will be discussed later in this document.
Page 4 of 11
ENTCORP038-REPT-002 Rev. 0
- 2. Documentation 2.1. NEI 12-06, Rev. 2, Section G.2 - Characterization of the MSFHI.
The FHRR (Ref. 7) identified that LIP and PMF of the Mississippi River and Stream A are not bounded by the COB flood elevation. Stream B PMF is bounded by the COB flood elevation. The FHRR also analyzed the watershed associated with the Bayou Pierre and determined that there is no impact on the GGNS plant site. Other reevaluated flood hazard mechanisms (e.g., tsunami, channel migrations/diversions, etc.) are bounded by the COB and have no impact on the site.
Mississippi River PMF The Mississippi River PMF maximum flood height of 106.2 ft. MSL is 3.2 ft. higher than the COB flood height of 103 ft. MSL. The PMWE on the Mississippi River at GGNS is 122.5 ft. This is the combination of stillwater elevation and wave setup and wave runup induced by the 2-year wind speed. Plant grade is at 132.5 ft. and any safety-related equipment or FLEX equipment is protected from this event. Therefore, this event does not challenge the FLEX strategies.
Stream A PMF Stream A PMF maximum flood height of 132.1 ft. MSL is 3.2 ft. higher than the COB flood height of 128.9 ft. MSL. The PMWE on Local Stream A is 132.5 ft. This is the combination of stillwater elevation and wave setup and wave runup induced by the 2-year wind speed. This flood level leads to loss of certain parts of one of the two deployment paths (i.e. loss of the path from the north FLEX storage building [Site 1D.
Stream B PMF Stream B PMF maximum flood height determined by the MSFH I of 131.7 ft. MSL is 1.1 ft. lower than the COB flood height of 132.8 ft. MSL. Wind wave height was not calculated because Stream B is bounded by Stream A. Plant grade is at 132.5 ft. Therefore, this event does not challenge the FLEX strategies.
Bayou Pierre The Bayou Pierre was not evaluated as part of the COB but was evaluated by the FHRR. The FHRR concluded that the maximum flood level of the Bayou Pierre is 130.7 ft., which is well below the elevation of the Bayou Pierre watershed divide elevation of about 175 ft. Therefore, this event does not challenge the FLEX strategies.
Flood Height The maximum water surface elevation due to the LIP at GGNS results from a total rainfall depth of 19.3 inches within an hour and 31.4 inches within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. In the immediate vicinity of GGNS Unit 1, predicted maximum water depths at safety related building entrances resulting from the LIP range from approximately 0.3 ft to 1.0 ft (Ref. 9) at doors protecting safety related equipment.
These flow depths correspond to water surface elevations ranging from 133.3 ft. to 133.7 ft. (Ref.
7 and 9). This is above the COB flood height of 133.25 ft., and is bounded by the FLEX DB height of 133.7 ft for the south FLEX storage building (Site 4). Sandbags up to a height of 1.5 ft. and door seals at inactive doors 10301 and OCT05 are used to protect these exterior doors from flooding. Therefore, flooding through doorways is not a concern (Ref. 7).
Page 5 of 11
ENTCORP038-REPT-002 Rev. 0 Flow velocities around doors ranges from 0.4 fps to 2.1 fps (Ref. 9). Significant debris loading/transportation is not a safety hazard due to the relatively low velocity and depth of LIP flood waters in the vicinity of safety-related SSCs at GGNS, in addition to the lack of natural debris sources on site (Ref. 7).
Flood Event Duration Flood durations were evaluated at various locations around the power block near external doors protective safety related equipment. Flood durations vary at each location, but the analyzed locations typically reach the peak flood elevation about 30 minutes after the beginning of the LIP event, dropping rapidly to below half of the peak flood depth approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the onset of the LIP event, which is before Phase 2 equipment is deployed (Ref. 7). Flood depths almost completely recede by 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> which is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before any Phase 2 portable equipment is credited. This general trend of flood recession is deemed appropriate for the South Storage Building at Site 4 and the primary deployment path(s) from Site 4 due to the proximity to the power block and because the terrain is very similar. However, these recession times may not apply to areas flooded by Stream A (specifically the area of the North Access Road that is under approximately 6 ft of water, preventing deployment of equipment from the North Storage Building at Site 1) because water is intentionally diverted to Stream A for drainage, thus increasing the recession time.
It should be noted Reference 9 reanalyzes the LIP flood depths by considering roof runoff, but this does not change the flood durations by a significant amount such that the FLEX strategy would be affected.
Relevant Associated Effects Only the south storage building at Site 4 is within the scope of the LIP reanalysis due to its location relatively close to the power block. Due to its remote location and grade elevation, Site 1 is not included in the LIP reanalysis. The LIP reanalysis supports a maximum expected depth of 0.1 ft. to 0.2 ft. at Site 1 based upon the adjacent modeled areas. The north FLEX storage building at Site 1 is located such that the top-of-slab elevation is at 163 ft., and Site 4 has a top-of-slab elevation of 133.2 ft. The foundation (slab) designs of both storage buildings include an internal spill containment curb extending 0.5 ft. above the top-of-slab. This results in an "effective" top-of-slab elevation of 163.5 ft. for Site 1 and 133.7 ft. for Site 4. The flood heights at these locations are 163.2 ft. and 133.5 ft. respectively. Therefore, given the concrete slab, curb height, grading, and drainage, the building elevations are sufficient to preclude challenges/impact to the stored equipment.
The primary deployment path between the north storage building at Site 1 and the PA runs along the North Access Road for most of its length. In one location the road dips approximately 6 feet below the LIP flood elevation (Ref. 10). Therefore, it would require deployment of the FLEX*
equipment from the south storage building at Site 4. Site 4 is located approximately 500 ft west of the PA. The primary deployment route for Site 4 is north along the Plant Access Road gaining access to the PA through the Sally Port located just south of the Administration Building. The alternate paths for Site 1 and Site 4 both run along the north access road, behind the Unit 2 warehouse, and enter the site near the ISFSI pad at the northeastern edge of the protected area.
Portions of this path are unanalyzed for all flooding scenarios so it is assumed that the alternate paths are unavailable.
Based on Figure 12 of Reference 9, the maximum LIP depth along the primary deployment path from Site 4 to the staging locations is 1.5 feet. Because of Site 4's proximity to the power block, it is expected that the recession times for the deployment path from Site 4 would be similar to the recession times for the safety related doors stated in the "Flood Event Duration" section above.
Therefore, the 1.5 ft. depth would be decreased to approximately 0.75 ft. or less after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and would be almost completely receded by 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The limiting piece of phase 2 equipment with Page 6 of 11
ENTCORP038-REPT-002 Rev. 0 respect to height off the ground is the Chevy 3500 truck which has a clearance of approximately 16" from the ground to the center of the exhaust pipe per the RBS FLEX Equipment Walkdown Report, Attachment 10.002 to EC 64548 (Ref. 11). GGNS and RBS both utilize the Chevy 3500 truck for FLEX equipment deployment. Since no equipment is required to be deployed prior to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, at which time the maximum flood depth would be approximately 0.75 ft (9 inches), there is no impact on deployment of FLEX equipment from the south storage building at Site 4 due to the LIP. It should also be noted that the FLEX electrical equipment is protected from the rain by design and will not be submersed in flood waters since the trailer heights are sufficiently above the flood levels at the time equipment is deployed (at least 7 inches of clearance). This would also preclude any significant runup due to traversing the flood waters since the trailer floors are above the flood level at the time of deployment.
For Phase 3, the NSRC's ability to transport equipment to Staging Area B (site location where equipment will be pre-staged, parked, or placed prior to movement into the final location) is discussed in the GGNS SAFER Response Plan (Ref. 2) which includes multiple means and pathways of transporting NSRC equipment to the site. Therefore, transportation of NSRC equipment to the site is deemed feasible and is not discussed further in this document. Since deployment of NSRC equipment occurs later in the event (after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), no further analysis is necessary. Note that deployment of Phase 3 equipment is not impacted by any flood mechanisms identified in the FHRR.
Warning Time A flood warning time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is used for prediction of over 12 inches (30.5 cm) of rain from the National Weather Service (Ref. 3), and site preparation is governed by the Off-Normal Event Procedure 05-1-02-VI-2, "Off-Normal Event Procedure - Hurricanes, Tornadoes, and Severe Weather - Safety Related" (Ref. 5).
2.2. NEI 12-06, Rev. 2, Section G.3 - Comparison of the MSFHI and FLEX DB Flood Table 1 reflects data from the FHRR for the LIP compared to the site's COB and FLEX design basis flood.
A table is not included for the PMF from the Mississippi River, Stream A, Stream B, and Bayou Pierre because, as stated in Section 2.1, plant grade, safety-related equipment, the south storage building at Site 4, and the Site 4 deployment path required for the FLEX strategy are well above any wind-wave water level such that this does not need to be evaluated.
Any parameters where the FLEX DB flood does not bound the MSFHI are evaluated in Section 2.3.
Page 7 of 11
ENTCORP038-REPT-002 Rev. 0 Table 1
- Flood Causing Mechanism (LIP) or Bounding Set of Parameters Flood Scenario Parameter Plant FLEX Design MSFHI Bounded (B)
Current Basis Flood or Not Design Hazard LIP Bounded Basis Flood (NB) by FLEX Hazard DB
- 1. Max Stillwater Elevation (ft. MSL) 133.25 133.7 (See 133.7 B Note 1)
Cf) t5 2. Max Wave Run-up Elevation (ft. Not Identified Not Identified See Note 2 B
~ MSL) in COB in FLEX w
"0 (1) 10 3. Max Hydrodynamic/Debris Not identified See Note 3 See Note 3 N/A
'(3 0
Loading (psf) in the COB Cf)
Cf)
-c ~. Effects of Sediment Not identified See Note 4 See Note 4 N/A "0
c Deposition/Erosion in the COB co Q5 (1)
- 5. Other Associated effects (identify N/A N/A N/A N/A
-l "0
each effect) 0 0
u::: 6. Concurrent Site Conditions Not identified See Note 6 See Note 6 B in the COB
- 7. Effects on Groundwater Not identified See Note 7 See Note 7 B in the COB
- 8. Warning Time (hours) Not identified 24 24 B in the COB.
e(1)
- 9. Period of Site Preparation (hours) Not identified 6 24 NB
> c in the COB w 0 o co 10. Period of Inundation (hours)
"0:;::; 6 6 >15 NB
_o :::J u.O 7 >14 NB
- 11. Period of Recession (hours) 8
- 12. Plant Mode of Operations Normal Normal Normal B Other Operations Operations Operations
- 13. Other Factors N/A N/A N/A N/A N/A =Not Applicable Additional notes, 'N/A' justifications (why a particular parameter is judged not to affect the site), and explanations regarding the bounded/non-bounded determination. The note numbers below correspond to the parameter number in the table.
- 1. The GGNS FIP (Ref. 1) addressed the maximum flood height elevation of 133.7 ft. MSL from the GGNS FHRR.
- 2. Consideration of wind-wave action for the LIP event is not explicitly required by NUREG/CR-7046 and is judged to be negligible because of limited fetch lengths and flow depths.
- 3. Debris loading is not considered a hazard due to the relatively low velocity and depth of LIP flood waters in the vicinity of safety-related SSCs, in addition to the lack of natural debris sources on the site.
- 4. Erosion and sedimentation are not applicable to this site, and therefore, do not need to be evaluated. (Ref. 6)
Page 8 of 11
ENTCORP038-REPT-002 Rev. 0
- 5. None
- 6. The Gumbel Distribution was applied to the 2-minute wind speed data from NCDC station at Tallulah Vicksburg Regional Airport, to determine the 2-year return period wind speed, which was calculated to be 45.2 mph.
- 7. The PMP event impact on the ground water level was discounted as a majority of the precipitation resulting from a PMP event does not infiltrate to the local ground water table but instead results in surface water runoff to streams and rivers.
- 8. None
- 9. None
- 10. Local Intense Precipitation and Associated Drainage for 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> precipitation event. This is based on the hydrograph at the door "OCT5" presented by Figure 3.1-16 in the FHRR.
- 11. Local Intense Precipitation and Associated Drainage for 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> precipitation event. This is based on the hydrograph at the door "OCT5" presented by Figure 3.1-16 in the FHRR.
- 12. None
- 13. None Page 9 of 11
ENTCORP038-REPT-002 Rev. 0 2.3. NEI 12-06, Rev. 2, Section G.4 - Evaluation of Mitigating Strategies for the MSFHI 2.3.1. NEI 12-06, Rev. 2, Section G.4.1 - Assessment of Current FLEX Strategies 2.3.1.1. Stream A PMF PMF on Stream A with coincident wind generated waves results in inundation of the primary access road, but does not result in inundation of SSCs important to safety.
Inundation of the primary access road would potentially restrict deployment of FLEX equipment from the north FLEX storage building (Site 1) located north of Stream A.
However, as Figure 2 of the Final Integration Plan shows (Ref. 1), there is a second redundant FLEX storage facility located south of Stream A, such that inundation of the access road will not restrict deployment. Therefore, the FLEX strategies are not impacted by this event. (Ref. 7) 2.3.1.2. LIP Three flooding scenario parameters for the LIP are not bounded by the FLEX strategy:
Period of Site Preparation (hours), Period of Inundation (hours), and Period of Recession (hours). To address this, protection of FLEX equipment against external flooding events was evaluated in accordance with Section 6.2.3.1.1.a of NEI 12-06 (Ref. 8) which states that the FLEX equipment is protected from floods if it is stored above the flood elevation determined in the most recent site flood analysis. Flooding due to LIP is the controlling flood event for the new flood evaluation. No other flood mechanism generates water elevations with the potential to impact safety related SSCs or equipment relied upon for FLEX. The maximum water surface elevation due to the LIP at GGNS results from a total rainfall of 19.3 inches within an hour and 31.4 inches within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. In the immediate vicinity of GGNS Unit 1, predicted maximum water depths at safety related structure doorways resulting from the LIP range from approximately 0.3 ft to 1.0 ft (Ref. 9).
Table 4.3-1 in the FHRR (Ref. 7) as revised by Section 6.4.7 of Reference 9 shows the height of modeled LIP flood water at each doorway to a safety related structure that can be potentially impacted by this event. Sandbags are used up to a height of 1.5 ft. to protect entrances to the diesel generator building, standby service water buildings and control building; and door seals at inactive doors 10301 and OCT05 also protect these exterior doors from flooding.
None of the protections in place for identified safety-related SSC or PMP sealed doors are exceeded by LIP flood water heights. Therefore, equipment in these areas are protected and the areas remain accessible for use during a FLEX event.
2.3.2. Conclusions The plant response strategies to an ELAP and loss of ultimate heat sink event using the current FLEX strategy and associated ECs have been developed in accordance with the GGNS flooding reanalysis. Inundation of the primary access road would require mobilization of FLEX equipment from the south FLEX storage facility located south of Stream A since inundation potentially restricts mobilization of the equipment from the north FLEX storage facility located north of Stream A. Therefore, the flooding re-assessment will have no impact on the GGNS FLEX strategy. Equipment and personnel will be available such that the GGNS FLEX Strategies can be implemented as described in the Final Integrated Plan (Ref. 1).
Page 10 of 11
ENTCORP038-REPT-002 Rev. 0 2.4. References
- 1. GNRO-2016-00006, Final Integrated Plan Document Grand Gulf Nuclear Station, April 2016
- 2. GNRO-SA-15-00001, Rev. 001, SAFER Response Plan for Grand Gulf Nuclear Station, September 8,2015
- 3. NEI 15-05, Rev. 6, Warning Time for Local Intense Precipitation Events, April 2015
- 4. EC 50275, Rev. 2, FLEX Basis EC
- 5. 05-1-02-VI-2, Rev. 129, Off-Normal Event Procedure - Hurricanes, Tornados, and Severe Weather, December 4,2014
- 6. Grand Gulf Nuclear Station, Unit 1 - Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-causing Mechanism Reevaluation (CAC No. MF1102), December 4, 2015
- 7. 51-9195288-000, Entergy Fleet Fukushima Program Flood Hazard Reevaluation Report for Grand Gulf Nuclear Station, ML13071A457, March 2013
- 8. NEI 12-06, Rev. 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, December 2015
- 9. 32-9195573-000, Rev. 1, Flood Hazard Re-evaluation - Local Intense Precipitation -
Generated Flood Flow and Elevations at Grand Gulf Nuclear Stations, September 24, 2014
- 10. EC 50287, Rev. 0, GGNS FLEX Storage Building
- 11. EC 64548, Rev. 0, Admin EC to Issue FLEX Flood Mitigating Strategies Assessment (MSA) Report Page 11 of 11