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MONTHYEARGNRO-2013/00032, Entergys 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 Accident2013-04-26026 April 2013 Entergys 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 Project stage: Response to RAI ML13120A1052013-04-26026 April 2013 Response to Request for Information: Near-Term Task Force Recommendation 2.1, Seismic Reevaluation Project stage: Response to RAI L-PI-13-038, 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 Accident2013-04-29029 April 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 Project stage: Response to RAI L-2013-265, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites2013-09-0909 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites Project stage: Response to RAI ML13254A1662013-09-10010 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f). Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident... Project stage: Response to RAI GNRO-2013/00068, Response to 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 1.5 Year Response for CEUS Site2013-09-12012 September 2013 Response to 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 1.5 Year Response for CEUS Site Project stage: Response to RAI ML13259A0442013-09-12012 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 - 1.5 Year Response for CEUS Sites Project stage: Response to RAI L-PI-13-088, Nspm'S 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- 1.5 Year Response for CEU2013-09-12012 September 2013 Nspm'S 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- 1.5 Year Response for CEUS S Project stage: Response to RAI ML14051A1072014-02-12012 February 2014 Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites Project stage: Response to RAI BVY 14-019, Notification of Revised Regulatory Commitments Associated with Request for Information Per 10 CFR50.54(f) Regarding Recommendations 2.1, 2.3, & 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ...2014-03-12012 March 2014 Notification of Revised Regulatory Commitments Associated with Request for Information Per 10 CFR50.54(f) Regarding Recommendations 2.1, 2.3, & 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ... Project stage: Request RBG-47453, Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-26026 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request L-2014-085, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident Project stage: Response to RAI HNP-14-035, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.32014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 Project stage: Request L-PI-14-028, PINGP 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 Fukushima Dai-ichi Accident2014-03-27027 March 2014 PINGP 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 Fukushima Dai-ichi Accident Project stage: Response to RAI CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request LR-N14-0035, 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 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. Project stage: Response to RAI RS-14-069, 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 Near-.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 Near-. Project stage: Response to RAI NL-14-0343, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites Project stage: Request JAFP-14-0039, 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 Insights2014-03-31031 March 2014 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 NRC 2014-0024, NextEra Energy Point Beach, LLC - 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 F2014-03-31031 March 2014 NextEra Energy Point Beach, LLC - 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 Fukush Project stage: Request RS-14-072, 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) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights..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) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights.. Project stage: Response to RAI NL-14-0344, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites Project stage: Request L-2014-089, Florida Power & Light (FPL) Seismic Hazard & Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2014-03-31031 March 2014 Florida Power & Light (FPL) Seismic Hazard & Screening Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid Project stage: Request ML14092A4142014-03-31031 March 2014 Response to March 12, 2012 Information Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1 Project stage: Request ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - 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. Project stage: Response to RAI L-MT-14-035, Interim Evaluation in Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-04-0303 April 2014 Interim Evaluation in Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. Project stage: Response to RAI ML14111A1472014-05-0909 May 2014 Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights Project stage: Approval JAFP-14-0102, 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 JAFP-14-0128, Follow-up to 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 Accident2014-12-0505 December 2014 Follow-up to 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 Project stage: Request ML14323A0272014-12-31031 December 2014 Screening and Prioritization Results of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the NTTF Project stage: Other 2014-02-12
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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
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Text
~Entergy Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Kevin J. Mulligan Site Vice President Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2013/00068 September 12, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Entergy's 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 - 1.5 Year Response for CEUS Sites Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1,2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (ML12053A340, GNRI-2012/00059)
- 2. NRC Letter, Endorsement of EPRI Final Draft Report 1025287, "Seismic Evaluation Guidance, "dated February 15, 2013 (ML12319A074)
- 3. EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPIO) for the Resolution of Fukushima Near- Term Task Force Recommendation 2.1:
Seismic (ML12333A170)
- 4. NEI Letter to NRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013 (M L131 01 A345)
- 5. NRC Letter, EPRI Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Near- Term Task Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7,2013 (ML13106A331)
- 6. Entergy letter to NRC, 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, dated April 26, 2013 (ML13119A104, GNRO-2013/00032)
GNRO-2013/00068 Page 2 of 3
Dear Sir or Madam:
On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee in the Central and Eastern United States (CEUS) to submit a written response consistent with the requested seismic hazard evaluation information (items 1 through 7) by September 12, 2013. On February 15, 2013, NRC issued Reference 2, endorsing the Reference 3 industry guidance for responding to Reference 1. Section 4 of Reference 3 identifies the detailed information to be included in the seismic hazard evaluation submittals.
On April 9, 2013, the Nuclear Energy Institute (NEI) submitted Reference 4 to NRC, requesting NRC agreement to delay submittal of some of the CEUS seismic hazard evaluation information so that an update to the Electric Power Research Institute (EPRI)
(2004, 2006) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles (items 3a and 3b in Section 4 of Reference 3) be submitted to NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to NRC by March 31, 2014. In Reference 5, NRC agreed with this recommendation. Reference 6 contained Entergy Operations, Inc.'s (Entergy's) commitment to follow the approach described in Reference 4.
The attachment to this letter contains the requested descriptions of subsurface materials and properties and base case velocity profiles for Grand Gulf Nuclear Station (GGNS).
The information provided in the attachment to this letter is considered an interim product of seismic hazard development efforts being performed for the industry by EPRI. The complete and final seismic hazard report for GGNS will be provided to the NRC in our seismic hazard submittal by March 31,2014 in accordance with Reference 5.
This letter contains no new regulatory commitments. Should you have any questions regarding this submittal, please contact Mr. Christopher R. Robinson, Licensing Manager, at (601) 437-7326.
I declare under penalty of perjury that the foregoing is true and correct; executed on September 12,2013.
Sincerely,
~r r_
KJM/slw
Attachment:
Grand Gulf Nuclear Station's Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles Cc: (See next page)
GNRO-2013/00068 Page 3 of 3 cc: U. S. Nuclear Regulatory Commission ATTN: Steven A. Reynolds Acting Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission Attn: Director, Office of Nuclear Reactor Regulation Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission ATTN: Mr. Alan Wang, NRRlDORL Mail Stop OWFN/8 B1 Washington, DC 20555-0001 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment to GNRO*2013/00068 Grand Gulf Nuclear Station's Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles
Attachment to GNRO-2013/00068 Page 1 of 5 Grand Gulf Nuclear Stations Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles Grand Gulf Site Description The basic information used to create the site geologic profile at the Grand Gulf Nuclear Station is shown in Table 1. This profile was developed using information documented in Reference 1.
As indicated in Table 1, the safe shutdown earthquake (SSE) Control Point is defined at elevation -87 feet, and the profile was modeled up to this elevation. For dynamic properties of sand, silt, and clay layers, modulus and damping curves were represented with two models.
The first model used soil curves taken from Reference 2, the second model used soil curves taken from References 3 and 4. These dynamic property models were weighted equally.
The three base-case shear-wave velocity profiles used to model amplification at the site are shown in Figure 1. Profiles 1, 2, and 3 are weighted 0.4, 0.3, and 0.3, respectively.
Thicknesses, depths, and shear-wave velocities (Vs) corresponding to each profile are shown in Table 2.
References
- 1. Entergy (2012). Site Geologic Conditions for Grand Gulf Nuclear Station, Informal report transmitted to Electric Power Research Institute (EPRI) in July 2012.
- 2. EPRI (1993). Guidelines for Determining Design Basis Ground Motions, Report TR-102293, Volumes 1-5, Palo Alto, CA.
- 3. Silva, W.J., N. A. Abrahamson, G.R. Toro, and C. Costantino (1996). Description and Validation of the Stochastic Ground Motion Model, Report submitted to Brookhaven National Laboratory, Assoc. Universities Inc., Upton NY 11973, Contract No. 770573.
- 4. Walling, M.A., W.J., Silva and N.A. Abrahamson (2008). Nonlinear Site Amplification Factors for Constraining the NGA Models, Earthquake Spectra, 24 (1) 243-255.
Attachment to GNRO-2013/00068 Page 2 of 5 Table 1 - Geotechnical profile for Grand Gulf site Elev. Depth Soil Description Compression Shear Density Poissons Youngs Shear Bulk Range Wave Wave (pcf) Modulus Modulus Modulus Modulus (feet) Velocity (fps) Velocity (ksf) (ksf) (ksf) (ksf)
(fps) 197 to 70 Loess - Silt 1400 670 105 0.35 3950 1460 4390 127 127 to 20 Terrace - Silty Clay 4600 1100 119 0.47 13,200 4470 73,000 107 107 to 20 Terrace - Sand 6000 1600 125 0.46 29,000 9940 121,000 87 87 SSE Control Point at
- base mat of - - - - - - -
structures 87 to 20 Catahoula - Clay 6560 1600 120 0.47 28,000 9540 156,000 67 67 to Catahoula - Clay 17 50 and Silt with Silty 6560 1640 120 0.47 29,500 10,000 164,000 Sand Layers 17 to Catahoula - Clay
-33 50 and Silt with Silty 6400 1720 120 0.46 32,200 11,000 134,000 Sand Layers
-33 to Catahoula - Clay
-103 70 and Silt with Silty 6730 1715 120 0.47 32,200 11,000 179,000 Sand Layers
Attachment to GNRO-2013/00068 Page 3 of 5 Wm Vs profiles for Grand Gulf Site Vs (ft/sec) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0
500 1000 1500 Profile 1 W
Depth (ft) 2000 Profile 2 Profile 3 2500 3000 3500 4000 4500 Figure 1 - Vs profiles for Grand Gulf site
Attachment to GNRO-2013/00068 Page 4 of 5 Table 2 - Layer thicknesses, depths, and Vs for 3 profiles, Grand Gulf site Profile 1 Profile 2 Profile 3 thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) thickness(ft) depth (ft) Vs(ft/s) 0 1600 0 1280 0 2000 10.2 10.2 1600 10.2 10.2 1280 10.2 10.2 2000 10.2 20.3 1600 10.2 20.3 1280 10.2 20.3 2000 12.5 32.8 1640 12.5 32.8 1312 12.5 32.8 2050 12.5 45.3 1640 12.5 45.3 1312 12.5 45.3 2050 4.6 49.9 1640 4.6 49.9 1312 4.6 49.9 2050 7.9 57.7 1640 7.9 57.7 1312 7.9 57.7 2050 12.5 70.2 1640 12.5 70.2 1312 12.5 70.2 2050 12.5 82.7 1720 12.5 82.7 1376 12.5 82.7 2150 12.5 95.1 1720 12.5 95.1 1376 12.5 95.1 2150 12.5 107.6 1720 12.5 107.6 1376 12.5 107.6 2150 12.5 120.1 1720 12.5 120.1 1376 12.5 120.1 2150 14.1 134.2 1715 14.1 134.2 1372 14.1 134.2 2144 14.1 148.3 1715 14.1 148.3 1372 14.1 148.3 2144 14.1 162.4 1715 14.1 162.4 1372 14.1 162.4 2144 14.1 176.5 1715 14.1 176.5 1372 14.1 176.5 2144 14.1 190.6 1715 14.1 190.6 1372 14.1 190.6 2144 17.7 208.3 1800 17.7 208.3 1312 17.7 208.3 2826 17.7 226.0 1800 17.7 226.0 1312 17.7 226.0 2826 17.7 243.8 1800 17.7 243.8 1312 17.7 243.8 2826 6.2 250.0 1800 6.2 250.0 1312 6.2 250.0 2826 44.0 294.0 1800 44.0 294.0 1312 44.0 294.0 2826 32.8 326.8 1873 32.8 326.8 1312 32.8 326.8 2941 32.8 359.6 1873 32.8 359.6 1312 32.8 359.6 2941 32.8 392.4 1873 32.8 392.4 1312 32.8 392.4 2941 40.0 432.4 2005 40.0 432.4 1283 40.0 432.4 3147 40.0 472.4 2005 40.0 472.4 1283 40.0 472.4 3147 27.6 500.0 2005 27.6 500.0 1283 27.6 500.0 3147 52.5 552.5 2005 52.5 552.5 1283 52.5 552.5 3147 40.0 592.5 2005 40.0 592.5 1283 40.0 592.5 3147 42.7 635.2 2005 42.7 635.2 1283 42.7 635.2 3147 42.7 677.8 2005 42.7 677.8 1283 42.7 677.8 3147 42.7 720.5 2005 42.7 720.5 1283 42.7 720.5 3147 65.6 786.1 2182 65.6 786.1 1396 65.6 786.1 3425 65.6 851.7 2182 65.6 851.7 1396 65.6 851.7 3425 65.6 917.3 2182 65.6 917.3 1396 65.6 917.3 3425 65.6 982.9 2182 65.6 982.9 1396 65.6 982.9 3425 65.6 1048.6 2182 65.6 1048.6 1396 65.6 1048.6 3425 65.6 1114.2 2359 65.6 1114.2 1510 65.6 1114.2 3704 65.6 1179.8 2359 65.6 1179.8 1510 65.6 1179.8 3704
Attachment to GNRO-2013/00068 Page 5 of 5 65.6 1245.4 2359 65.6 1245.4 1510 65.6 1245.4 3704 65.6 1311.0 2359 65.6 1311.0 1510 65.6 1311.0 3704 65.6 1376.6 2359 65.6 1376.6 1510 65.6 1376.6 3704 131.2 1507.9 2552 131.2 1507.9 1634 131.2 1507.9 4007 131.2 1639.1 2552 131.2 1639.1 1634 131.2 1639.1 4007 131.2 1770.3 2552 131.2 1770.3 1634 131.2 1770.3 4007 131.2 1901.6 2552 131.2 1901.6 1634 131.2 1901.6 4007 131.2 2032.8 2552 131.2 2032.8 1634 131.2 2032.8 4007 131.2 2164.0 2871 131.2 2164.0 1837 131.2 2164.0 4507 131.2 2295.3 2871 131.2 2295.3 1837 131.2 2295.3 4507 131.2 2426.5 2871 131.2 2426.5 1837 131.2 2426.5 4507 131.2 2557.7 2871 131.2 2557.7 1837 131.2 2557.7 4507 131.2 2689.0 2871 131.2 2689.0 1837 131.2 2689.0 4507 164.0 2853.0 3054 164.0 2853.0 1955 164.0 2853.0 4795 164.0 3017.1 3054 164.0 3017.1 1955 164.0 3017.1 4795 164.0 3181.1 3054 164.0 3181.1 1955 164.0 3181.1 4795 164.0 3345.1 3054 164.0 3345.1 1955 164.0 3345.1 4795 164.0 3509.2 3054 164.0 3509.2 1955 164.0 3509.2 4795 490.5 3999.7 3054 490.5 3999.7 1955 490.5 3999.7 4795 3280.8 7280.5 9285 3280.8 7280.5 9285 3280.8 7280.5 9285