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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:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML22020A4032022-02-0707 February 2022 Summary of November 17, 2021, Meeting with Florida Power and Light/Nextera on Improved Technical Specification Conversion License Amendment Requests (EPIDs L-2021-LLI-0000 and L-2021-LLI-0002) ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19248C2382019-11-20020 November 2019 Issuance of Amendment No. 201 Regarding Technical Specification Changes to Eliminate Requirements of Iodine Removal System ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19113A0992019-07-0202 July 2019 Issuance of Amendments Regarding Adoption of Risk-Informed Completion Times in Technical Specifications ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents L-2016-120, License Amendment Request EDG Day Tank Fuel Volume Change2016-06-21021 June 2016 License Amendment Request EDG Day Tank Fuel Volume Change ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) ML15356A6112016-03-0707 March 2016 Issuance of Amendments Regarding Request to Standardize the Required Actions for Inoperability of Auxiliary Feedwater Pumps ML16034A0802016-03-0707 March 2016 Issuance of Amendments Regarding Technical Specification Change to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents ML15195A6552015-08-27027 August 2015 Issuance of Amendments Regarding Change to Technical Specification 6.8.4.h., Containment Leakage Rate Testing Program ML15121A1822015-06-0505 June 2015 Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML14350A0082015-06-0101 June 2015 Issuance of Amendment to Revise the Requirement Regarding the Shift Technical Advisor ML14343A9182015-02-27027 February 2015 Issuance of Amendments to Revise Limiting Condition for Operation 3.0.4 and Surveillance Requirement 4.0.4 ML14064A1292014-03-31031 March 2014 Issuance of Amendment Regarding the Use of M5 Alloy Fuel Cladding in Core Reload Applications ML13164A2652013-08-30030 August 2013 Issuance of Amendments Revising Station Battery Connection Resistances Acceptance Criteria in Technical Specifications ML13150A3372013-06-18018 June 2013 Issuance of Amendments Revision Station Battery Connection Resistances Acceptance Criteria in Technical Specifications ML12339A1092012-12-17017 December 2012 Issuance of Amendments Regarding Revision to Cyber Security Plan Milestone 6 ML12235A4632012-09-24024 September 2012 Issuance of Amendment Regarding Extended Power Uprate ML12263A2242012-09-19019 September 2012 Public - Issuance of Amendment Regarding New Fuel Vault and Spent Fuel Pool Nuclear Criticality Analysis ML12156A2082012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate ML12181A0192012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate (Redacted) ML12052A2212012-03-30030 March 2012 Issuance of Amendments Regarding TSTF-513 Change, Revision 3, Revise Pressurized Water Reactor Operability Requirements and Actions for Reactor Coolant System Leakage Instrumentation ML11196A0792011-08-31031 August 2011 Issuance of Amendments Regarding Approval of the St. Lucie Cyber Security Plan ML1034404952010-12-28028 December 2010 Issuance of Amendments Regarding Deletion of the Structural Integrity Technical Specification Update of Accident Monitoring Instrumentation Requirements and Various Administrative Changes ML1009902752010-05-31031 May 2010 Issuance of Amendment Regarding Control Element Assembly Drop Time ML0917003142009-06-30030 June 2009 Issuance of Amendments Regarding Technical Specification Requirements Associated with Refueling Water Tank Minimum Contained Volume of Borated Water (TAC Nos. MD9208 and MD9209) ML0909602702009-05-27027 May 2009 License Amendment, Implementation of TSTF-511, Revision 0, Eliminate Working Hour Restriction from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0909701742009-04-14014 April 2009 Issuance of Amendments Regarding Relocation of the Existing Surveillance Requirements Associated with Diesel Fuel Oil Testing Program (Tac MD9261 and MD9262) 2022-02-07
[Table view] Category:Safety Evaluation
MONTHYEARML23219A0032023-09-0101 September 2023 SLRA SER Rev 1 ML23200A1462023-07-21021 July 2023 Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 ML22255A1022022-09-21021 September 2022 Authorization and Safety Evaluation for Alternative Relief Request No. 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety ML22038A1872022-02-0909 February 2022 Authorization and Safety Evaluation for Relief Request No. 19 (RR19) - the Use of an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85 ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21236A1312021-09-30030 September 2021 Authorization of RR 15 Regarding Extension of ASME Requirements Related to Reactor Pressure Vessel Weld Examinations from 10 to 20 Years ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML21027A2262021-02-17017 February 2021 Approval of Alternative to ASME Code, Section XI to Use an Alternative Inservice Inspection Schedule for the Reaction Vessel Closure Head Bolting ML20329A4022021-02-0303 February 2021 Approval of Alternative to Use ASME Code Case N-513-4 for Alternative Repair of Intake Cooling Water System ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML20099A3482020-06-25025 June 2020 Safety Evaluation for Relief Request for Fifth Ten-Year Inservice Inspection (ISI) Interval - Alternative Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML20023B3782020-02-19019 February 2020 Safety Evaluation for Relief Request RR-16, Alternate Repair of 2B Boric Acid Makeup Pump Revision for the Fourth 10-Year Inservice Inspection Interval ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19254B5332019-09-30030 September 2019 Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19115A2812019-05-31031 May 2019 Safety Evaluation for Relief Request No. 6 for the Fifth 10 Year Inservice Inspection Interval ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18256A0982018-10-30030 October 2018 Safety Evaluation for Relief Request No.5 for the Fifth 10-Year Inservice Inspection Interval ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML18018A0332018-01-26026 January 2018 Safety Evaluation of Relief Requests for the Fifth 10-Year Inservice Testing Program (EPID L-2017-LLR-0113; L-2017-LLR-0017, L-2017-LLR-0018, L-2017-LLR-0119, L-2017-LLR-0120, L-2017-LLR-0121, and L-2017-LLR-0122) ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) ML17341A4422018-01-0404 January 2018 Relief from the Requirements of the ASME Code Relief Request No. 3 for the Fifth 10-Year Inservice Inspection Interval (CAC No. MF9288; EPID L-2017-LLR-0003) ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17219A1742017-08-31031 August 2017 Relief from the Requirements of the ASME Code Regarding Relief Request 12 for the Fourth 10-Year Inservice Inspection Interval ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16210A3742016-08-30030 August 2016 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2 ML16103A3972016-07-28028 July 2016 Issuance of Amendments Regarding Removal of Technical Specification for Cleaning Fuel Oil Storage Tank Sediment and Relocating Procedures to Licensee Controlled Documents ML16167A4732016-07-0505 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16139A5882016-05-27027 May 2016 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 10, Revision 0 ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) 2023-09-01
[Table view] |
Text
December 23, 2005 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENT REGARDING TYPE A TEST INTERVAL EXTENSION (TAC NO. MC6629)
Dear Mr. Stall:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 140 to Renewed Facility Operating License No. NPF-16 for the St. Lucie Plant, Unit No. 2. This amendment consists of changes to the Technical Specifications in response to your application dated March 31, 2005, as supplemented November 9, 2005.
This amendment extends the date for the next Appendix J, Type A test at St. Lucie Unit 2 until the end of the SL2-17 refueling outage.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosures:
- 1. Amendment No. 140 to NPF-16
- 2. Safety Evaluation cc w/enclosures: See next page
December 23, 2005 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENT REGARDING TYPE A TEST INTERVAL EXTENSION (TAC NO. MC6629)
Dear Mr. Stall:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 140 to Renewed Facility Operating License No. NPF-16 for the St. Lucie Plant, Unit No. 2. This amendment consists of changes to the Technical Specifications in response to your application dated March 31, 2005, as supplemented November 9, 2005.
This amendment extends the date for the next Appendix J, Type A test at St. Lucie Unit 2 until the end of the SL2-17 refueling outage.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosures:
- 1. Amendment No. 140 to NPF-16
- 2. Safety Evaluation cc w/enclosures: See next page DISTRIBUTION:
PUBLIC LPL II-2 r/f RidsNrrPMBMoroney RidsNrrDorlLpld BClayton(paper copy) RidsOgcRp RidsAcrsAcnwMailCenter GHill (2 paper copies)
TBoyce HAshar ZCruz-Perez RPalla JPulsipher BDesai, R2 RidsNrrDpr MRubin RDennig KManoly Package No.: ML053570129
- No Legal Objection ADAMS Accession No.: ML053190343 TS: ML053570129 NRR-058 OFFICE LPLII-2/PM LPLII- APLA/C ACVB/C EEMB/C OGC LPLII-2/C 2/LA NAME BMoroney BClayton MRubin RDennig KManoly MBupp* MMarshall by memo dated by memo dated by memo dated DATE 11/17/05 11/17/05 11/04/05 11/04/05 06/22/05 12/14 /05 12 / 22 /05
OFFICIAL RECORD COPY FLORIDA POWER & LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST. LUCIE PLANT UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 140 Renewed License No. NPF-16
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Florida Power & Light Company, et al. (the licensee), dated March 31, 2005, as supplemented November 9, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, Renewed Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Michael L. Marshall, Jr., Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 23, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 140 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment number and contain vertical lines indicating the area of change.
Remove Page Insert Page 6 - 15b 6 - 15b
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 140 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16 FLORIDA POWER AND LIGHT COMPANY, ET AL.
ST. LUCIE PLANT, UNIT NO. 2 DOCKET NO. 50-389
1.0 INTRODUCTION
By letter dated March 31, 2005, as supplemented November 9, 2005, Florida Power and Light Company, et al. (FPL, the licensee) requested to amend Renewed Operating License NPF-16 for St. Lucie Unit 2, by changing the St. Lucie Unit 2 Technical Specifications (TSs),
Section 6.8.4.h, Containment Leakage Rate Testing Program. The proposed amendment would provide an additional extension from the currently approved 15-year interval since the last containment overall integrated leakage rate test (ILRT, Type A test) performed in June 1992. The proposed amendment would extend the due date for the next Type A test from June 2007 to prior to the start-up from the fall 2007 refueling outage (SL2-17), which is currently scheduled to end in late December 2007.
The licensees supplementary submittal dated November 9, 2005, provided clarifying information that did not change the scope of the proposed amendment as described in the original notice of proposed action published in the Federal Register and did not change the initial proposed no significant hazards determination.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix J, Option B requires that a Type A test be conducted at a periodic interval based on historical performance of the overall containment system. St. Lucie Unit 2 TS 6.8.4.h, Containment Leakage Rate Testing Program, requires that leakage rate testing be performed as required by 10 CFR Part 50, Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide (RG) 1.163, Performance-Based Containment Leak-Test Program, dated September 1995, with two exceptions (one of which is pertinent to the current request and is discussed in the next paragraph). This RG endorses, with certain exceptions, Nuclear Energy Institute (NEI) report NEI 94-01, Revision 0, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, dated July 26, 1995.
A Type A test is an overall (integrated) leakage rate test of the containment structure.
NEI 94-01 specifies an initial test interval of 48 months, but allows an extended interval of 10 years, based upon two consecutive successful tests. There is also a provision for extending
the test interval an additional 15 months in certain circumstances. The most recent two Type A tests at St. Lucie (April 1989 and June 1992) have been successful, so the current interval requirement would normally be 10 years. However, by letter dated August 15, 2002, the licensee requested an extension of the test interval to 15 years. On April 10, 2003, the U.S. Nuclear Regulatory Commission (NRC) staff granted this request for St. Lucie Unit 2 via License Amendment No. 130, dated April 10, 2003.
RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, provides guidance on the use of Probabilistic Risk Assessment (PRA) findings and risk insights in support of licensee requests for changes to a plants licensing basis, as in requests for license amendments and changes to the TSs.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Change Based on License Amendment No. 130, the licensee planned to perform the next Type A test for St. Lucie Unit 2 during the SL2-16 refueling outage in April 2006. Subsequent to the approval of License Amendment No.130, the licensee determined that both the reactor vessel head and the steam generators needed to be replaced at St. Lucie Unit 2 and has scheduled this work during the SL2-17 refueling outage. Since the SL2-17 outage work includes cutting an access hole in the containment, a Type A test will be required. This would result in performing Type A tests during back-to-back outages, which the licensee wishes to avoid because of the considerable expenditure of resources and additional outage time required to perform the tests. Therefore, the licensee is requesting a change to TS 6.8.4.h that would alter the exception from the guidelines of RG 1.163 and NEI 94-01, Revision 0, by adding approximately 6 months to the 5-year extension already in place, for a total interval of approximately 15 years and 6 months.
The current St. Lucie Unit 2 TS 6.8.4.h states, The first Type A test performed after the June 1992 Type A test shall be no later than June 2007. The licensee proposed to change this to state, The first Type A test performed after the June 1992 Type A test shall be prior to startup following the SL2-17 refueling outage.
The local leakage rate tests (Type B and Type C tests), including their schedules, are not affected by this request.
The licensee justifies the proposed change to extend the ILRT surveillance interval based on the historical test results and the containment inspections program, supported by risk-informed analysis. These are addressed in the following sections.
3.2 Structural Integrity Considerations In its submittal, the licensee stated that the St. Lucie Unit 2 containment vessel is examined in accordance with the requirements of the American Society of Mechanical Engineers (ASME)
Code Section XI, Subsection IWE, the plant protective coatings program, and the Containment Leakage Rate Test Program. Historically, visual inspections were performed preceding each
Type A test, thus ensuring the inspections were performed three times in 10 years. This frequency was maintained subsequent to adoption of Appendix J, Option B and approval of the 15-year ILRT surveillance interval. The results of these inspections indicated that there have been no significant deficiencies in the structural integrity or material condition of the containment vessel except for minor coating issues.
Two conditions related to material condition of the containment boundary were identified by other inspection processes. The first condition, documented in St. Lucie Plant Condition Report 97-0890, concerned deterioration of the moisture barrier at the interface of the concrete floor and containment vessel. The licensee stated that this condition generally involved only staining or light surface corrosion, with a few instances of pitting observed. Evaluations determined that the localized areas of concern do not represent an issue with respect to the integrity of the containment vessel. The site corrective action program has been utilized to track additional inspections and plan corrective actions. One-third of the moisture barrier at the concrete floor to vessel interface on both sides of containment is inspected during each inspection period of the St. Lucie ASME Section Xl, ISI-IWE Plan. Two-thirds of the Unit 2 moisture barrier has been inspected as of the spring 2003 refueling outage, with results similar to or less significant than the originally inspected areas.
The second condition involved external corrosion, due to moisture accumulation from condensation, on the component cooling water penetrations to containment, as initially documented in Condition Report 97-1799. For the second condition, corrective actions included removal of corrosion products, inspection of components and respective thickness measurements, application of protective coatings, and installation of antisweat insulation.
Results of these evaluations at the most affected penetrations determined that the piping degradation was minor and that the remaining penetrations were in satisfactory condition.
Both of these conditions were identified prior to implementation of the IWE Inspection program at St. Lucie. Based on the inspections, repairs, and evaluation of these issues, the licensee concluded that augmented inspection was not required in accordance with IWE-1240.
St Lucie Unit 2 implemented the ASME Section Xl, Subsection IWE inspection plan on August 9, 2000. The IWE program performs inspection of the entire accessible interior surface of the containment in each of 3 periods within a 10-year surveillance interval. The licensee stated that the first-period 100-percent general surface area inspection for Unit 2 was completed in April 2000 and the second-period inspection was completed in November 2001 with no indications of significant degradation found. The Metal Containment Inservice Inspection Program (ISI/IWE-PSL-1/2-PROGRAM) provides the rules and requirements for the containment inservice inspection program at St. Lucie Unit 2. The specific areas and components scheduled for inspection in accordance with the program are provided in ISI/IWE-PSL-2-PLAN, ASME Section Xl, Subsection IWE Containment Building Metal Containment Inservice Inspection Plan for St. Lucie Unit 2. The program requirements include inspection of containment surfaces, pressure retaining welds, bolting, seals, gaskets, and moisture barriers using visual, surface, and volumetric techniques as required. The licensee also stated that examinations that detect flaws or evidence of degradation shall be documented through the site corrective action process and dispositioned in accordance with the requirements of IWE-3000.
Related to the required repair of the containment vessel coatings, ASME Section Xl,
Subsection IWE, requires visual exams to assess the condition of the vessel metal surface for evidence of flaking, blistering, peeling, discoloration, and other signs of distress. The protective coatings program at St. Lucie requires that a walkdown of the containment interior be performed each refueling outage by the FPL coatings specialist and Engineering personnel to inspect any existing areas of nonqualified coatings and to determine any other areas in need of repair. Those areas identified by inspection, which do not meet acceptance criteria, are evaluated and scheduled for repair as necessary. The licensee stated that qualified nondestructive examiners perform inspections prior to any repair to assess the condition of the base material and, following the completion of the coating repairs, to document as-left conditions. The licensee found no indications of containment vessel metal degradation on St. Lucie Unit 2 during these types of inspections.
On the basis of the above discussion, the staff concludes that the licensee has adequate procedures to examine and monitor the structural integrity of the containment of St. Lucie Unit 2. Therefore, granting an additional extension of approximately 6 months for performing the ILRT is acceptable.
3.3 Risk Considerations In License Amendment No. 130, the NRC staff approved an extension of the Type A test interval from 10 to 15 years. This test interval extension was supported by a licensee risk assessment. The NRC staffs review of the licensees risk assessment was documented in the safety evaluation (SE) for License Amendment 130, and concluded that the combined risk impact of the test interval extensions, in terms of total integrated plant risk, large early release frequency, and conditional containment failure probability, is small and supportive of the change.
In the current request, the licensee performed a risk assessment of the impact of extending the Type A test frequency from the original three tests in 10 years to one test in 16 years, and reported the risk results in their application for license amendment. The risk assessment is based on the same methodology, input, and assumptions used to support License Amendment 130, with the exception of the revised test interval and the use of an updated version of the plant-specific PRA.
Based on review of the analyses provided by the licensee, the NRC staff determined that the risk impacts and risk comparisons for the proposed change are essentially unchanged from those reported in the previous SE, and the staff conclusions remain valid. Specifically, the increase in the total integrated plant risk is small and supportive of the proposed change, the increase in the test interval results in only a small change in large early release frequency consistent with the acceptance guidelines of RG 1.174 and the defense-in-depth philosophy is maintained based on the small magnitude of the change in the conditional containment failure probability.
Based on these conclusions, the staff finds that the increase in predicted risk due to the proposed change is within the acceptance guidelines, while maintaining the defense-in-depth philosophy, of RG 1.174 and, therefore, is acceptable.
3.4 Summary
Based on the foregoing evaluation, the staff finds that the interval until the next containment Type A test at St. Lucie, Unit 2, may be extended to the end of refueling outage SL2-17 (total interval of approximately 15 years and 6 months), and that the proposed change to TS 6.8.4.h is acceptable.
4.0 STATE CONSULTATION
Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (70 FR 33215, dated June 7, 2005). Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: H. Ashar Z. Cruz-Perez R. Palla J. Pulsipher Date: December 23, 2005
Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:
Senior Resident Inspector Mr. G. L. Johnston St. Lucie Plant Plant General Manager U.S. Nuclear Regulatory Commission St. Lucie Nuclear Plant P.O. Box 6090 6351 South Ocean Drive Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Craig Fugate, Director Mr. Terry Patterson Division of Emergency Preparedness Licensing Manager Department of Community Affairs St. Lucie Nuclear Plant 2740 Centerview Drive 6351 South Ocean Drive Tallahassee, Florida 32399-2100 Jensen Beach, Florida 34957 M. S. Ross, Managing Attorney Mark Warner, Vice President Florida Power & Light Company Nuclear Operations Support P.O. Box 14000 Florida Power and Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company Mr. Rajiv S. Kundalkar 801 Pennsylvania Avenue, NW. Vice President - Nuclear Engineering Suite 220 Florida Power & Light Company Washington, DC 20004 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator Mr. J. Kammel St. Lucie County Radiological Emergency 2300 Virginia Avenue Planning Administrator Fort Pierce, Florida 34982 Department of Public Safety 6000 Southeast Tower Drive Mr. William A. Passetti, Chief Stuart, Florida 34997 Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Mr. William Jefferson, Jr.
Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000