Letter Sequence Other |
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Results
Other: L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1, L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206, L-2015-259, ANP-3440NP, Revision 1, Response to NRC Questions SRXB-RAI-1 and Snpb RAI-2 Thru Snpb RAI-20., L-2015-279, RAI Response Clarification for SRXB-RAI-1 and Snpb RAI-2 Thru RAI-20 for the Technical Specification LAR and Exemption Request Regarding the Transitioning to Areva Fuel, ML15197A339, ML15219A184, ML15279A226, ML15356A184, ML15356A185
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MONTHYEARML15002A0912014-12-30030 December 2014 St. Lucie, Unit 2 - Application for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Request L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report Project stage: Request ML15084A0112015-03-23023 March 2015 St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Request L-2015-166, Request for Additional Information Reply for Technical Specification Changes and Exemption Request Regarding the Transitioning to Areva Fuel2015-06-0202 June 2015 Request for Additional Information Reply for Technical Specification Changes and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Request ML15181A2902015-06-18018 June 2015 St. Lucie, Unit 2 - Resubmittal of the Areva Small Break LOCA Summary Report within the Application for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Request L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 12015-06-30030 June 2015 Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1 Project stage: Other ML15188A3402015-07-13013 July 2015 Summary of Closed Meeting with Florida Power and Light Company and Areva Regarding Request for Additional Information for the License Amendment and Exemption Requests Re. the Transitioning to Areva Fuel Project stage: RAI ML15219A1842015-07-30030 July 2015 RAI Response to SNPB-RAI-1 for the Technical Specification LAR and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Other L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-2062015-07-31031 July 2015 ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206 Project stage: Other ML15197A3392015-08-31031 August 2015 Request for Withholding Proprietary Information from Public Disclosure for the License Amendment Request and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Other ML15233A0362015-09-0404 September 2015 Redacted Request for Additional Information Regarding Proposed License Amendment Request and Exemption Request to Allow the Transition to Areva Fuel Project stage: RAI ML15224B3192015-09-21021 September 2015 Request for Withholding Information from Public Disclosure for the St. Lucie Plant, Unit 2 Project stage: Withholding Request Acceptance L-2015-259, ANP-3440NP, Revision 1, Response to NRC Questions SRXB-RAI-1 and Snpb RAI-2 Thru Snpb RAI-20.2015-10-0202 October 2015 ANP-3440NP, Revision 1, Response to NRC Questions SRXB-RAI-1 and Snpb RAI-2 Thru Snpb RAI-20. Project stage: Other ML15279A2262015-10-0202 October 2015 St. Lucie, Unit 2 - RAI Response to SRXB-RAI-1 and Snpb RAI-2 Thru RAI-20 for the Technical Specification LAR and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Other L-2015-279, RAI Response Clarification for SRXB-RAI-1 and Snpb RAI-2 Thru RAI-20 for the Technical Specification LAR and Exemption Request Regarding the Transitioning to Areva Fuel2015-11-0303 November 2015 RAI Response Clarification for SRXB-RAI-1 and Snpb RAI-2 Thru RAI-20 for the Technical Specification LAR and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Other L-2015-300, ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report.2015-11-30030 November 2015 ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report. Project stage: Request ML15356A1842015-12-0808 December 2015 St. Lucie, Unit 2 - RAI Response for Snpb RAI-9 for the Technical Specification LAR and Exemption Request Regarding the Transitioning to Areva Fuel Project stage: Other ML15356A1852015-12-31031 December 2015 ANP-3456NP, Revision 0, Response to SLU2 NRC Snpb RAI-9, Licensing Report. Project stage: Other 2015-06-18
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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-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) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump 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-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 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-2023-071, 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 ML23013A2032023-01-13013 January 2023 RAI Set 4 Draft Response L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-156, Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response2022-09-19019 September 2022 Correction to Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 1a Response L-2022-143, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response2022-09-0808 September 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 1A Response L-2022-115, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment2022-08-0909 August 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 3 Response and Submittal of Superseded Response for One Set 2 RAI and One Supplement 1 Attachment L-2022-108, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response2022-07-11011 July 2022 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 2 Response L-2022-075, Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response2022-06-13013 June 2022 Subsequent License Renewal Application-Aging Management Requests for Additional Information (RAI) Set 1A Response and Request for Confirmation of Information (RCI) Set 1 Response L-2022-000, License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response2022-01-19019 January 2022 License Amendment Request for the Technical Specifications Conversion to NUREG- 1432 Revision 5 - Request for Supplemental Information (Rsi) Response L-2021-105, Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2021-05-12012 May 2021 Response to Request for Additional Information for St. Lucie License Amendment Request to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2021-065, Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years2021-04-0101 April 2021 Response to Request for Additional Information. Relief Request Number RR 15, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years L-2020-165, Supplement to Updated Final Response to NRC Generic Letter 2004-022020-12-0404 December 2020 Supplement to Updated Final Response to NRC Generic Letter 2004-02 L-2020-094, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-06-26026 June 2020 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2020-061, Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2020-04-30030 April 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements ML20015A0282020-01-14014 January 2020 NMFS to NRC, Concurrence with Interim Response to Requests for Additional Information for St. Lucie Endangered Species Act Section 7 Consultation L-2019-164, Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control2019-09-11011 September 2019 Response to Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Protection Bypass Devices Requirements to Licensee Control L-2019-166, Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response2019-08-21021 August 2019 Refueling Outage SL2-24 Steam Generator Tube Inspection Report RAI Response L-2019-153, Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-25025 July 2019 Exigent Technical Specification Amendment Request Supplemental RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-149, Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-24024 July 2019 Exigent Technical Specification Amendment Request RAI Reply One-Time Allowed Outage Time Extension for Inoperable EDG L-2019-118, Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2019-06-28028 June 2019 Response to Request for Additional Information Regarding License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2019-107, License Amendment Request - Iodine Removal System Elimination2019-05-17017 May 2019 License Amendment Request - Iodine Removal System Elimination L-2019-056, Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request2019-03-0707 March 2019 Inservice Inspection Plan RAI Reply, Fifth Ten-Year Interval Unit 1 Relief Request L-2018-205, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies2018-11-15015 November 2018 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-153, Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies2018-08-17017 August 2018 Supplemental Information for License Amendment Request to Reduce the Number of Control Element Assemblies L-16-001, Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-24024 May 2018 Units. 3 and 4, Response to Request for Supplemental Information Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations L-77-291, Attachment a to L-77-291 Response to NRC Questions of May 24, 19772018-03-29029 March 2018 Attachment a to L-77-291 Response to NRC Questions of May 24, 1977 L-2018-040, Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2018-02-14014 February 2018 Response to Request for Additional Information Regarding License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply L-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b2018-02-0101 February 2018 Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b L-2017-210, Updated Final Response to NRC Generic Letter 2004-022017-12-20020 December 2017 Updated Final Response to NRC Generic Letter 2004-02 L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 62017-12-19019 December 2017 License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6 L-2017-209, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-012017-11-30030 November 2017 Response to Request for Additional Information Regarding Fifth 10-Year Inservice Testing (IST) Program Interval Relief Request PR-01 L-2017-159, Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 02017-09-13013 September 2017 Response to Request for Additional Information Regarding Inservice Inspection Plan, Fifth Ten-Year Interval Unit 1 Relief Request No. 3, Revision 0 L-2017-116, Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.52017-07-0303 July 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise the Technical Specifications (TS) for the Reactor Protection System (RPS) Power Rate-of-Change Instrumentation and Add New TS 3.0.5 L-2016-220, License Amendment Request EDG Day Tank Fuel Volume Change2016-12-0505 December 2016 License Amendment Request EDG Day Tank Fuel Volume Change L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) L-2016-153, Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes2016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request for Biological Opinion License Changes L-2016-135, Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B2016-07-22022 July 2016 Second Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B L-2016-143, Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents2016-07-15015 July 2016 Response to Request for Additional Information for the Proposed Technical Specification Change to Remove the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank and Relocate to Licensee-Controlled Documents L-2016-114, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48.2016-07-0808 July 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 48. L-2016-102, RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes2016-05-0606 May 2016 RAI Reply - License Amendment Request, Containment Vacuum Gothic Analyses and Conforming Changes L-2016-104, RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle2016-05-0606 May 2016 RAI Reply - Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle L-2016-096, Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 02016-04-21021 April 2016 Inservice Inspection Plan, RAI Reply for Fourth Ten-Year Interval Relief Request No. 10, Revision 0 L-2016-084, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States.2016-04-20020 April 2016 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States. L-2016-040, License Renewal Commitments, Reactor Vessel Internals Aging Management Plan, Response to Request for Additional Information2016-02-26026 February 2016 License Renewal Commitments, Reactor Vessel Internals Aging Management Plan, Response to Request for Additional Information 2023-09-11
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Text
Contains Proprietary Information
-Withhold per 10 CFR 2.390 0July 30O, 2015 L-20 15-206 FPIL. 10 CFR 50.90 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 RE: St. Lucie Unit 2 Docket No. 50-389 RAI Response to SNPB-RAI-1 for the Technical Specification LAR and Exemption Recquest Regarding the Transitioning to AREVA Fuel
Reference:
- 1. FPL letter L-2014-366 dated December 30, 2014, "Application for Technical Specification Change and Exemption Request Regarding the Transitioning to ARE VA Fuel," Accession No. ML15002A091
- 2. FPL letter L-2015-091 dated March 23, 2015, "Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to ARE VA Fuel," Accession No. ML 15084A01 1 3. NRC letter dated May 12, 2015, "St. Lucie Plant, Unit No. 2 -Request for Additional Information Regarding License Amendment Request and Exemption Request Regarding the Transitioning to AREVA Fuel (TAC NOS. MF5494 AND MF5495)," Accession No.ML 15127A405 4. FPL Letter L-2015-166 dated June 2, 2015, "RAI Reply for Application for Technical Specification Change and Exemption Request Regarding the Transitioning to ARE VA Fuel," Accession No. ML 15161 A3 16 5. FPL Letter L-2015-177 dated June 18, 2015, "Resubmittal of the AREVA Small Break LOCA Summary Report Within the Application for Technical Specification Change and Exemption Request Regarding the Transitioning to ARE VA Fuel," Accession No.ML15181A290
- 6. NRC Letter dated June 24, 2015, "St. Lucie Plant, Unit 2 -. Request for Additional Information Regarding License Amendment Request and Exemption Request Regarding the Transitioning to AREVA Fuel (TAC Nos. MF5494 and MF5495)," Accession No.ML1 5166A368 Pursuant to 10 CFR 50.90, Florida Power & Light Company (FPL) submitted via Reference 1 and supplemented via Reference 2 a license amendment to the Technical Specifications (TS) for St. Lucie Unit 2 to allow the use of AREVA fuel. Reference 4 provided the response to the NRC request for additional information (RAI) of Reference
- 3. Reference 5 modified the proprietary markings contained in the SBLOCA summary report.The NRC transmitted an additional RAI in Reference 6, and this letter provides the response to the RAI in Attachment 1 to this letter. Attachment 2 provides the affidavit for withholding the supporting proprietary AREVA licensing report from the public, Attachment 3 provides the proprietary AREVA licensing report, and Attachment 4 provides the non-proprietary version of the AREVA licensing report.Attachment 3 contains proprietary information per 10 CFR 2.390, upon removal, this document is Florida Power & Light Company u nco nt ro lled 6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2015-206 Page 2 If you should have any questions, please contact Mr. Ken Frehafer at (772) 467-7748.I declare under penalty of perjury that the foregoing is true and correct.Executed on -3".,,\, , 2015.Sincerely, Christopher R. Costanzo Site Vice President St. Lucie Plant CRC/KWF Attachments
- 1. RAI Response 2. ARE VA affidavit for withholding proprietary information from the public 3. AREVA proprietary report ANP-3428P, Revision 0, St. Lucie Unit 2 Fuel Transition:
Response to SNPB-RAI-1
- 4. AREVA non-proprietary report ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition:
Response to SNPB-RAI-1 cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Nuclear Plant Ms. Cindy Becker, Florida Department of Health L-20 15-206 Attachment 1 Page 1 of 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT REQUEST AND EXEMPTION REQUEST TO ALLOW THE TRANSITION TO AREVA FUEL FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT. UNIT NO. 2 DOCKET NO. 50-389 (TAC NOS. MF5494 AND MF5495)By letter dated December 30, 2014, as supplemented by letter dated March 23, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.ML1 5002A091 and ML1 5084A01 1, respectively), Florida Power & Light Company (FPL)submitted a license amendment request to the U.S. Nuclear Regulatory Commission (NRC) for St. Lucie Plant, Unit No. 2 (SL-2). The proposed amendment would revise the TSs to allow the use of AREVA fuel at SL-2. Additionally, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.12, FPL requests an exemption from the provisions of 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems [ECCSs] for light-water nuclear power reactors," and Appendix K to 10 CFR Part 50, "ECCS Evaluation Models," to allow the use of M5 fuel rod cladding in future core reload applications for SL-2.By letter dated April 8, 2015 (ADAMS Accession No. ML15090A240), FPL was informed that the NRC staff finds the application of XN-NF-78-44 (NP) (A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors [PWRs]" (ADAMS Accession No.ML15049A093), October 1982, Exxon Nuclear Company, Inc. (ENC) to AREVA (Combustion Engineering)
CE16x16 fuel, to be an expansion of the applicability of this Topical Report. The letter also stated that the staff would follow this acceptance with a request for additional information (RAl) that asks the licensee to confirm the acceptability of the application of XN-NF-78-44 (NP)(A) to AREVA CE16x16 fuel by performing additional calculations using alternative methods.Accordingly, the U.S. Nuclear Regulatory Commission staff has reviewed the information submitted by the licensee and, based upon this review, determined that the following additional information is required to complete the evaluation.
SNPB-RAI-1 Backqround Section 4.25 of ANP-3347P, Revision 0, "St Lucie, Unit 2 Fuel Transition Chapter 15 Non-LOCA [Loss of Coolant Accident]
Summary Report," provides a description regarding "Spectrum of Control Element Assembly [CEA] Ejection Accidents (UFSAR [Updated Final Safety Analysis Report] 15.4.8)." The non-proprietary version of this document is publicly available under ADAMS Accession No. ML15002A092.
L-20 15-206 Attachment 1 Page 2 of 3 The CEA ejection accident is analyzed using the methodology described in Topical Report XN-NF-78-44 (NP)(A) for total deposited enthalpy in the fuel. Topical Report XN-NF-78-44 (NP)(A)indicates that "the ejected rod analysis presented here will be applicable to all future ENC reloads for PWR type reactors.
However, as indicated in the acceptance letter of April 8, 2015, to the licensee, the application of the above methodology to AREVA's CE 16x16 fuel is considered an expansion of the applicability of this topical report.The Phenomenon Identification and Ranking Table in Section 3 of NUREG/CR-6742,"Phenomenon Identification and Ranking Tables (PIRT) for Rod Ejection Accidents in Pressurized Water Reactors Containing High Burnup Fuel," identifies certain fuel physical, mechanical, and thermal properties of the fuel design under high burnup conditions during the PWR Rod Ejection Accident.
These parameters are fuel thermal conductivity, gap conductance, clad conductivity (including oxide layer), transient cladding-to-coolant heat transfer coefficient, heat capacities of fuel and cladding, and other applicable parameters.
It is not evident from your submittal on the control rod ejection analysis whether or not a more recent fuel performance code is used to compute the fuel and clad properties.
Upon review of the control rod ejection accident analysis submitted by the licensee in ANP-3347P, Section 4.25, the staff has determined that the margin to the centerline temperature for 20 percent and 65 percent rated thermal power has been substantially reduced for beginning of cycle (BOC).RAI Based on the above, perform a plant-specific analysis of control rod ejection accident for St.Lucie, Unit 2 using an alternate methodology as was proposed to the staff during the pre-submittal meeting on November 3, 2014. By performing the alternate analysis using the combination of latest fuel performance methodology and the proposed supplement to the ARCADIA reactor analysis system methodology, provide additional information that is necessary for determining the acceptability of the applicability of XN-NF-78-44(NP)(A) to AREVA CE 16x16 fuel design.SNPB-RAI-1 Response The response to the SNPB-RAI-1 (Reference 1), provided in the attached document ANP-3428P, is prepared based on the discussions between Florida Power and Light Company (FPL), AREVA and the NRC Staff during the meeting on June 11, 2015, and includes the following:
- 1. A comparison of the XN-NF-78-44(NP)(A) methodology rod ejection results with the results of the current fuel vendor methodology, for St. Lucie Unit 2 (16x16) fuel, using conditions consistent with the current St. Lucie Unit 2 Extended Power Uprate (EPU)analysis described in the Updated Final Safety Analysis Report (UFSAR).2. A summary of the quantitative benchmark results of the XN-NF-78-44(NP)(A) methodology (Reference
- 2) for enthalpy deposition, applied to the St. Lucie Unit 2 16x16 fuel, as compared to the recent AREVA analysis results for other fuel types, previously provided in ANP-3396P (Reference 3).
L-20 15-206 Attachment 1 Page 3 of 3 Additionally, the response provided in ANP-3428(P) also includes a discussion of how the physical, mechanical and thermal properties of the fuel design under high burnup conditions are addressed in the Rod Ejection analyses performed with the EMF-2310(P)(A)
NRC approved methodology (Reference 4). EMF-2310(P)(A) methodology is used for the rod ejection DNB and fuel centerline temperature analysis.
The discussion provided in the attached ANP-3428(P) document also addresses the conservatism in the fuel centerline temperature generated with the EMF-231 0(P)(A) methodology, which resulted in low margin to the fuel centerline melt limit.The generic issues, independent of the application to 16x16 fuel, related to the conservatism of the enthalpy deposition calculation performed with the 1D rod ejection methodology
[XN-NF 44(NP)(A)], and the comparison with the 3D methodologies, as necessary, will be discussed with the NRC Staff and addressed separate from this RAI, as discussed in the June 11, 2015 meeting (Reference 5).
References:
- 1. NRC Letter dated June 24, 2015, "St. Lucie Plant, Unit 2 -Request for Additional Information Regarding License Amendment Request and Exemption Request Regarding the Transitioning to AREVA Fuel (TAC Nos. MF5494 and MF5495). (ADAMS Accession No.ML15166A368)
- 2. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, September 1983.3. L-201 5-091, Letter from C. Costanzo (FPL) to USNRC Document Control Desk, "St. Lucie Unit 2 Docket No. 50-389 -Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to AREVA Fuel," March 23, 2015.(ADAMS Accession No. ML15084A01 1)4. EMF-2310(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurizer Water Reactors," Framatome ANP, Inc., May 2004.5. NRC Letter dated July 13, 2015, "Summary of June 11, 2015, Closed Meeting With Florida Power and Light Company and AREVA Regarding Request for Additional Information for the License Amendment and Exemption Requests Regarding the Transitioning to AREVA Fuel (TAC Nos. MF5494 and MF5495). (ADAMS Accession No. ML15188A340)
L-201 5-206 Attachment 2 Page 1 of 3 AFFIDAVIT COMMONWEALTH OF V!RGINIA)) ss, CITY OF LYNCHBURG)
- 1. My name is Nathan E. Hottle. I am Manager, Product Licensing, for AREVA Inc. (AREVA) and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary.
I am familiar with the policies established by ARE VA to ensure the proper application of these criteria.3. I am familiar with the AREVA information contained in the following document: "St. Lucie Unit2 Fuel Transition:
Response to SNPB-RAI-i," referred to herein as "Document." Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA Inc. for the control and protection of proprietary and confidential information.
- 4. This Document contains information of" a proprietary' and confidential nature and is of the type customarily held in confidence by AREVA and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure.
The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is L-2015-206 Attachment 2 Page 2 of 3 requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information.
- 6. The following criteria are customarily applied by AREVA to determine whether information should be classified as proprietary: (a) The information reveals details of AREVA's research and development plans and programs or their results.(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA.(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability.(e) The information is vital to a competitive advantage held by AREVA, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of ARE VA.The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(c) and 6(d) above.7. In accordance with AREVA's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA only as required and under suitable agreement providing for nondisclosure and limited use of the information.
8, AREVA policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
L-20 15-206 Attachment 2 Page 3 of 3 9. The foregoing statements are true and correct- to the best of my knowledge, information, and belief.SUBSCRIBED before me this 4 day of. 3iflt ,2015.Sherry L. MeFaden NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 10/31/18 Reg. # 7079129=- ..... A A -- A _ .,=, _., t SNENIW L. MeMOEN f Conim~1wum 01 Wg~a?07g12, J!y~onvnhsaIai~
Ez~Ire. Oct31, 2018