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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:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application2023-03-0303 March 2023 Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application L-2023-037, Annual Radioactive Effluent Release Report2023-03-0101 March 2023 Annual Radioactive Effluent Release Report L-2023-017, Radiological Emergency Plan Revision 73 and Revision 7 42023-02-17017 February 2023 Radiological Emergency Plan Revision 73 and Revision 7 4 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-181, Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 52022-12-0101 December 2022 Response to Request for Additional Information Regarding License Amendment Request for the Technical Specifications Conversion to NUREG-1431, Revision 5 L-2022-182, Emergency Response Data System (Eros) Changes2022-11-17017 November 2022 Emergency Response Data System (Eros) Changes L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2022-171, 10 CFR 50.59(d)(2) Summary Report2022-10-20020 October 2022 10 CFR 50.59(d)(2) Summary Report L-2022-167, Submittal of Periodic Reports2022-10-13013 October 2022 Submittal of Periodic Reports L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement L-2022-149, U4R33 Steam Generator Tube Inspection Report2022-10-0404 October 2022 U4R33 Steam Generator Tube Inspection Report L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-148, Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication2022-09-16016 September 2022 Florida Power & Light Company, Comments on NRC Inspection Procedure (IP) 71111.21 N.03, Commercial Grade Dedication L-2022-151, Evacuation Time Estimate Study2022-09-15015 September 2022 Evacuation Time Estimate Study L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-08-19019 August 2022 Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 L-2022-136, Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report2022-08-12012 August 2022 Response to Request for Additional Information Regarding Turkey Point Unit 3 Cycle 32 Steam Generator Tube Inspection Report L-2022-109, Inservice Inspection Program - Owner'S Activity Report (OAR-1)2022-06-27027 June 2022 Inservice Inspection Program - Owner'S Activity Report (OAR-1) L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 22022-06-0909 June 2022 Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2 2024-01-25
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September 9, 2013 PL L-2013-265 FPL.
U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Florida Power & Light Company's, Turkey Point Units 3 and 4 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
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
- 2. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance," dated February 15, 2013, ML12319A074
- 3. EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, November 2012, ML12333A170
- 4. NEI Letter to NRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013, ML13101A254
- 5. NRC Letter, EPRI Final Draft Report XXXXXX, "Seismic Evaluation Guidance:
Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013, ML13106A331 On March 12, 2012, the 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.
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Turkey Point Units 3 and 4 L-2013-265 Docket Nos. 50-250 and 50-251 Page 2 of 2 On February 15, 2013, NRC issued Reference 2, endorsing the Reference 3 industry guidance for responding to the request outlined in Reference 1. Section 4 of Reference 3 identifies the detailed information to be included in the seismic hazard evaluation submittals.
On April 9, 2013, NEI submitted Reference 4 to NRC, requesting NRC agreement to delay submittal of some of the CEUS seismic hazard evaluation information so that an update to the EPRI (2004, 2006) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles (items 3a and 3b in Section 4 of Reference 3) be submitted to NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to NRC by March 31, 2014. In Reference 5, NRC agreed with this recommendation.
The enclosure to this letter contains the requested descriptions of subsurface materials and properties and base case velocity profiles for Turkey Point Units 3 and 4. The information provided in the enclosure is considered an interim product of the seismic hazard development efforts being performed for the industry by EPRI. The complete and final seismic hazard reports for Turkey Point Units 3 and 4 will be provided to the NRC in the Turkey Point 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. Robert J. Tomonto, Turkey Point Licensing Manager, at (305) 246-7327.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on September _, 2013 Sincerely, Michael Kiley Site Vice President Turkey Point Nuclear Plant Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant
L-2013-265 Enclosure Florida Power & Light Company's Turkey Point Units 3 and 4 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 Page 1 of 9
L-2013-265 Enclosure The information presented in this document provides the necessary information described in items 3.a. "Description of Subsurface Materials and Properties," and 3.b. "Development of Base Case Profiles and Nonlinear Material Properties" of Section 4 of Reference 6 listed below. The basic information used to create the site geological profile at the Turkey Point Nuclear Generating Station is shown in Table 1. This profile was developed using information documented in Reference 1 below, which is a combination of data from the Turkey Point Units 3 and 4 Updated Safety Analysis Report (UFSAR), the FSAR for the COL Application for Units 6 and 7, and other related design information. The following near-surface material characteristics were used in developing the geological profiles:
The subsurface soils at the site consist of a limerock fill, sand and silt fill layer, underlain by limerock.
Description Elevation ft MLW Very dense limerock, sand, and silt fill +18 to - 5 Limestone, sand and silt fill - 5 to -10 Fossiliferous limerock (Miami Oolite) -10 to -35 The geophysical survey indicated the following two basic units for the subsurface conditions:
Description Elevation ft MLW Limerock fill +18 to -10 Miami Oolite -10 to -35 The Turkey Point SSE Control Point is defined at elevation +18 ft, so the profile was modeled to include the above description of near-surface materials. Table 2 shows the thicknesses, depths, and shear-wave velocities (Vs) for the layers, which were derived from this information.
Specifically:
" The highest geologic unit in the profile is the Limerock fill (described above), which is 28 ft in thickness (from depth 0 ft to 28 ft) and is modeled with a best-estimate Vs of 1400 fps.
" The next lower geologic unit is Miami Oolite (described above), which is 25 ft thick (from depth 28 ft to 53 ft) and is modeled with a best-estimate Vs of 2300 fps. The bottom of this unit is at elevation -35 ft (see above description).
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L-2013-265 Enclosure
" The next lower geologic unit is the Key Largo formation of Table 1, which extends from elevation -35 ft (the bottom of the Miami Oolite above) to -49.4 ft (which is the elevation of the top of Stratum 4 in Table 1). This 14 ft thick unit is modeled in Table 2 with Vs of 5800 fps (following Table 1).
" Stratum 4 in Table 1, the Ft. Thompson formation, extends from elevation -49.4 ft to -
115.1 ft, a thickness of 65.7 ft, and this is modeled in Table 2 with a best-estimate Vs of 4250 fps (following Table 1).
" Stratum 5 in Table 1, the Upper Tamiami unit, extends from elevation -115.1 ft to -159 ft, a thickness of 43.9 ft, and this is modeled in Table 2 with a best-estimate Vs of 1400 fps (following Table 1).
- Stratum 6 in Table 1, the Lower Tamiami unit, extends from elevation -159 ft to -215.2 ft, a thickness of 56.2 ft, and this is modeled in Table 2 with a best-estimate Vs of 1600 fps (following Table 1).
" Stratum 7 in Table 1, the Peace River unit, extends from elevation -215.2 ft to -452.1 ft, a thickness of 236.9 ft, and this is modeled in Table 2 with a best-estimate Vs of 1650 fps (following Table 1).
- Stratum 8 in Table 1, the Arcadia unit, begins at elevation -452.1 ft and is modeled with a thickness of 244.7 ft, down to a depth of 714.3 ft. This unit is modeled in Table 2 with a best-estimate Vs of 3600 fps (following Table 1).
" For deeper units (below 714 ft depth), the profile is modeled with layers that have monotonically increasing Vs values, down to a depth of about 4000 ft, where the profile is estimated to have Vs of 9285 fps. This interpretation of the deep Vs properties follows general estimates of Vs in Southern Florida as shown in Turkey Point Units 6 and 7 COL Application Figure 2.5.4-211 in Reference 5.
For dynamic properties of rock layers, modulus and damping curves were represented with two models. The first model used non-linear rock curves taken from Reference 2 and the second model assumed linear behavior. These dynamic property models were weighted equally.
For dynamic properties of fill and compacted sand layers, modulus and damping curves were also represented with 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. To model the profile, rock modulus and damping curves from Reference 2 were paired with soil modulus and damping curves from Reference 2, and linear rock modulus and damping curves were paired with soil modulus and damping curves from References 3 and 4.
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L-2013-265 Enclosure The 3 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. EC 279883, Engineering Evaluation PTN-ENG-SECS-13-025, Rev 0, Submittal of Subsurface Materials and Properties, in Response to the 50.54(F) Information Request Regarding NTTF 2.1: Seismic Reevaluation for PTN U3 & U4, Attachment 3, Turkey Point Nuclear Units 3 & 4 Site Geologic Conditions.
- 2. EPRI (1993). Guidelines for Determining Design Basis Ground Motions, Elec. Power Res.
Inst., Palo Alto, CA, Rept. TR-102293, Vol. 1-5.
- 3. Silva, W.J., N. A. Abrahamson, G.R. Toro, and C. Costantino (1996). Description and Validation of the Stochastic Ground Motion Model, Rept. submitted to Brookhaven Natl.
Lab., Assoc. Universities Inc., Upton NY 11973, Contract No. 770573.
- 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.
- 5. Turkey Point FSAR Units 6 and 7 COL Application FSAR, Rev. 4, Section 2.5.4.
ML13008A438
- 6. Electric Power Research Institute (EPRI) Final Report No. 1025287, February 2013, entitled, "Seismic Evaluation Guidance Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic" Page 4 of 9
L-2013-265 Enclosure Table 1 Summary of Recommended Geotechnical Engineering Parameters (COL Application Part 2-FSAR Rev. 3 Table 2.5.4-209)
StratumdI) 2 3 4 5 6 7 8 Fill Key Ft. Upper Lower Peace Description Muck Miami Largo Thompson Tamiami Tamiami River Arcadia Elevation of top of layer (ft) -1.2 -4.5 -26.7 -49.4 -115.1 -159.0 -215.2 -452.1 -
ML, GM, Limestone Limestone SM, SP- ML SM Limestone -
MH GP- SM GM, SM, SW-SM, SW, USCS symbol SP-SM Total unit weight, y (pc') 80 125 136 139 120 120 120 130 130 Natural water content, w, (%) >80 -- - - 30 - - 33 Fines content (%) >60 18 - - 28 62 16 - 15 Atterberg limits Liquid limit, LL - - - 24 - - -
Plastic limit, PL . .... 20 - - -
Plasticity index,PI . .... 4 - - -
SPT N6o-value (blows/ft) -0 20 - - 40 32 75 - 30 Undrained properties Undrained shear strength, su (ksf) . ... 4 -- -- -
Internal friction angle, ýp,(deg) ....
Drained properties Effective cohesion, c' (ksf) - -. 0 1.7 0 - -
Effective friction angle, (p,(deg) - - 35 20 40 - 33 Average Rock core recovery (%) - - 83 to 96 41 to 98 - - - 63 to 100 -
Average RQD (%) - - 54 to 81 16 to 91 - - - 32 to 90 -
Unconfined compressive strength, U (psi) - 200 1,500 2,000 -- - - 100 -
2,700 1,100 Elastic modulus (high strain), EH - 630 ksi 2,600 ksi 1,500 ksi 1,500 ksf 2,500 ksf ksf 980 ksi ksf 19,700 25,750 27,400 9,100 Elastic modulus (low strain), EL - 950 ksi 2,600 ksi 1,500 ksi ksf ksf ksf 980 ksi ksf 1,000 420 Shear modulus (high strain), GH - 230 ksi 1,000 ksi 550 ksi 550 ksf 900 ksf ksf 360 ksi ksf 10,150 3,500 Shear modulus (low strain), GL - 350 ksi 1,000 ksi 550 ksi 7,300 ksf 9,500 ksf ksf 360 ksi ksf Shear wave velocity, V,, (ft/sec) - 3,600 5,800 4,250 1,400 1,600 1,650 3,600 860 Compression wave velocity, Vc, (ft/sec) - 8,000 11,000 8,700 2,900 3,300 3,450 7,850 1,600 Coefficient of sliding - 0.6 0.7 0.7 0.4 0.3 - - 0.5 Poisson's ratio, g - 0.37 0.31 0.34 0.35 0.35 0.35 0.36 0.3 Static earth pressure coefficients Active, K. - 0.3 - - 0.27 0.5 - - 0.3 At-rest, K. - 0.5 - - 0.5 0.66 -- 0.5 (a) Properties of Stratum I (muck) are not provided as this stratum was removed prior to construction Page 5 of 9
L-2013-265 Enclosure Figure 1 Shear Wave Velocity (Vs) profiles for Turkey Point site Vs profiles for Turkey Point Site vs (ft/56c) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0
500 T IT _[
1000 -'-
1500,- Profile 1 9,2000 ___,,,,,-Profile 2
- Profile 3 a 2500 3000 3500 4000 4500 __ __
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L-20 13-265 Enclosure Table 2 Layer thicknesses, depths, and Shear Wave Velocity (Vs) for 3 profiles, Turkey Point Site Profile 1 ___ Profile 2 ___ Profile 3 ___
thickness depth Vs thickness depth Vs thickness depth Vs (f)(ft) (ft/s) (ft) (ft) (ft/s) (ft) (ft) (ft/s)
_______ 0 1400 ______ 0 896 0 2198 7.0 7.0 1400 7.0 7.0 896 7.0 7.0 2198 7.0 14.0 1400 7.0 14.0 896 7.0 14.0 2198 7.0 21.0 1400 7.0 21.0 896 7.0 21.0 2198 7.0 28.0 1400 7.0 28.0 896 7.0 28.0 2198 8.3 36.3 2300 8.3 36.3 1472 8.3 36.3 3611 8.3 44.6 2300 8.3 44.6 1472 8.3 44.6 3611 5.4 50.0 2300 5.4 50.0 1472 5.4 50.0 3611 3.0 53.0 2300 3.0 53.0 1472 3.0 53.0 3611 7.0 60.0 5800 7.0 60.0 3712 7.0 60.0 9106 7.0 67.0 5800 7.0 67.0 3712 7.0 67.0 9106 6.6 73.6 4250 6.6 73.6 2720 6.6 73.6 6672 6.6 80.1 4250 6.6 80.1 2720 6.6 80.1 6672 6.6 86.7 4250 6.6 86.7 2720 6.6 86.7 6672 6.6 93.2 4250 6.6 93.2 2720 6.6 93.2 6672 6.6 99.8 4250 6.6 99.8 2720 6.6 99.8 6672 6.6 106.4 4250 6.6 106.4 2720 6.6 106.4 6672 6.6 112.9 4250 6.6 112.9 2720 6.6 112.9 6672 6.6 119.5 4250 6.6 119.5 2720 6.6 119.5 6672 6.6 126.0 4250 6.6 126.0 2720 6.6 126.0 6672 6.6 132.6 4250 6.6 132.6 2720 6.6 132.6 6672 8.8 141.4 1400 8.8 141.4 896 8.8 141.4 2198 8.8 150.2 1400 8.8 150.2 896 8.8 150.2 2198 8.8 159.0 1400 8.8 159.0 896 8.8 159.0 2198 8.8 167.8 1400 8.8 167.8 896 8.8 167.8 2198 8.8 176.6 1400 8.8 176.6 896 8.8 176.6 2198 14.0 190.6 1600 14.0 190.6 1024 14.0 190.6 2512 14.0 204.7 1600 14.0 204.7 1024 14.0 204.7 2512 14.0 218.7 1600 14.0 218.7 1024 14.0 218.7 2512 14.0 232.7 1600 14.0 232.7 1024 14.0 232.7 2512 17.3 250.0 1650 17.3 250.0 1056 17.3 250.0 2590 30.1 280.1 1650 30.1 280.1 1056 30.1 280.1 2590 23.7 303.8 1650 23.7 303.8 1056 23.7 303.8 2590 23.7 327.5 11650 23.7 327.5 1056 23.7 327.5 2590 Page 7 of 9
L-2013-265 Enclosure Table 2 Layer thicknesses, depths, and Shear Wave Velocity (Vs) for 3 profiles, Turkey Point Site Profile 1 Profile 2 Profile 3 thickness depth Vs thickness depth Vs thickness depth Vs (f0) (ft) (ft/s) (ft) (1) (ft/s) (f0) (0) (ft/s) 23.7 351.2 1650 23.7 351.2 1056 23.7 351.2 2590 23.7 374.9 1650 23.7 374.9 1056 23.7 374.9 2590 23.7 398.6 1650 23.7 398.6 1056 23.7 398.6 2590 23.7 422.2 1650 23.7 422.2 1056 23.7 422.2 2590 23.7 445.9 1650 23.7 445.9 1056 23.7 445.9 2590 23.7 469.6 1650 23.7 469.6 1056 23.7 469.6 2590 25.0 494.6 3600 25.0 494.6 2304 25.0 494.6 5652 5.3 500.0 3600 5.3 500.0 2304 5.3 500.0 5652 39.3 539.3 3600 39.3 539.3 2304 39.3 539.3 5652 25.0 564.3 3600 25.0 564.3 2304 25.0 564.3 5652 25.0 589.3 3600 25.0 589.3 2304 25.0 589.3 5652 25.0 614.3 3600 25.0 614.3 2304 25.0 614.3 5652 25.0 639.3 3600 25.0 639.3 2304 25.0 639.3 5652 25.0 664.3 3600 25.0 664.3 2304 25.0 664.3 5652 25.0 689.3 3600 25.0 689.3 2304 25.0 689.3 5652 25.0 714.3 3600 25.0 714.3 2304 25.0 714.3 5652 25.0 739.3 4000 25.0 739.3 2560 25.0 739.3 6279 25.0 764.3 4000 25.0 764.3 2560 25.0 764.3 6279 25.0 789.3 4000 25.0 789.3 2560 25.0 789.3 6279 25.0 814.3 4000 25.0 814.3 2560 25.0 814.3 6279 25.0 839.3 4000 25.0 839.3 2560 25.0 839.3 6279 25.0 864.3 4000 25.0 864.3 2560 25.0 864.3 6279 25.0 889.3 4000 25.0 889.3 2560 25.0 889.3 6279 25.0 914.3 4000 25.0 914.3 2560 25.0 914.3 6279 25.0 939.3 4000 25.0 939.3 2560 25.0 939.3 6279 25.0 964.3 4000 25.0 964.3 2560 25.0 964.3 6279 100.0 1064.3 4500 100.0 1064.3 2880 100.0 1064.3 7064 100.0 1164.3 4500 100.0 1164.3 2880 100.0 1164.3 7064 100.0 1264.3 4500 100.0 1264.3 2880 100.0 1264.3 7064 100.0 1364.3 4500 100.0 1364.3 2880 100.0 1364.3 7064 100.0 1464.3 4500 100.0 1464.3 2880 100.0 1464.3 7064 100.0 1564.3 5500 100.0 1564.3 3520 100.0 1564.3 8634 100.0 1664.3 5500 100.0 1664.3 3520 100.0 1664.3 8634 100.0 1764.3 5500 100.0 1764.3 3520 100.0 1764.3 8634 100.0 1864.3 5500 100.0 1864.3 3520 100.0 1864.3 8634 Page 8 of 9
L-2013-265 Enclosure Table 2 Layer thicknesses, depths, and Shear Wave Velocity (Vs) for 3 profiles, Turkey Point Site Profile 1 Profile 2 Profile 3 thickness depth Vs thickness depth Vs thickness depth Vs (1t00 ) (ft/s) 10.
(50) (1/s) (100 ) (1. /s) 100.0 1964.3 5500 100.0 1964.3 3520 100.0 1964.3 8634 100.0 2064.3 5500 100.0 2064.3 3520 100.0 2064.3 8634 100.0 2164.3 5500 100.0 2164.3 3520 100.0 2164.3 8634 100.0 2264.3 5500 100.0 2264.3 3520 100.0 2264.3 8634 100.0 2364.3 5500 100.0 2364.3 3520 100.0 2364.3 8634 100.0 2464.3 5500 100.0 2464.3 3520 100.0 2464.3 8634 200.0 2664.3 8000 200.0 2664.3 5120 200.0 2664.3 9285 200.0 2864.3 8000 200.0 2864.3 5120 200.0 2864.3 9285 200.0 3064.3 8000 200.0 3064.3 5120 200.0 3064.3 9285 200.0 3264.3 8000 200.0 3264.3 5120 200.0 3264.3 9285 200.0 3464.3 8000 200.0 3464.3 5120 200.0 3464.3 9285 500.0 3964.2 8000 500.0 3964.2 5120 500.0 3964.2 9285 3280.8 7251 9285 3280.8 7245.1 9285 3280.8 7245.1 9285 Page 9 of 9