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MONTHYEARML0226602042002-09-10010 September 2002 TS Page, for Amendment 128 Regarding Working Hour Limits and Controls Project stage: Other ML0226601682002-09-10010 September 2002 TS Page for Amendment 185 Regarding Working Hour Limits and Controls Project stage: Other ML0225303242002-09-10010 September 2002 License Amendment, Issuance of Amendments Working Hour Limits & Controls (TAC Nos. MB3910 & MB3912) Project stage: Approval 2002-09-10
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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
September 10, 2002 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 UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING WORKING HOUR LIMITS AND CONTROLS (TAC NOS. MB3910 AND MB3912)
Dear Mr. Stall:
The Commission has issued the enclosed Amendment Nos. 185 and 128 to Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Units 1 and 2. These amendments consist of changes to the Technical Specifications (TS) in response to your application dated January 18, 2002.
These amendments relocate specific working hour limits and controls contained in the TS to administrative procedures.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389
Enclosures:
- 1. Amendment No. 185 to DPR-67
- 2. Amendment No. 128 to NPF-16
- 3. Safety Evaluation cc w/enclosures: See next page
September 10, 2002 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 UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING WORKING HOUR LIMITS AND CONTROLS (TAC NOS. MB3910 AND MB3912)
Dear Mr. Stall:
The Commission has issued the enclosed Amendment Nos. 185 and 128 to Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Units 1 and 2. These amendments consist of changes to the Technical Specifications (TS) in response to your application dated January 18, 2002.
These amendments relocate specific working hour limits and controls contained in the TS to administrative procedures.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389
Enclosures:
- 1. Amendment No. 185 to DPR-67
- 2. Amendment No. 128 to NPF-16
- 3. Safety Evaluation cc w/enclosures: See next page DISTRIBUTION PUBLIC PDII-2 R/F HBerkow KJabbour BMoroney BClayton (paper copy) GHill (4 paper copies) OGC ACRS RDennig DTrimble DDesaulniers LWert, RII DOCUMENT NAME: C:\ORPCheckout\FileNET\ML022530324.wpd ADAMS Accession Number:
OFFICE PDII-2/PM PDII-2/LA IEHB/SC RORP/SC OGC PDII-2/SC NAME BMoroney BClayton DTrimble RDennig KJabbour DATE 8/14/02 8/14/02 8/15/02 9/04/02 9/04/02 9/04/02 OFFICIAL RECORD COPY
FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 185 License No. DPR-67
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Florida Power & Light Company (the licensee), dated January 18, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. , 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Kahtan N. Jabbour, Acting Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 10, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 185 TO FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Page Insert Page 6-5 6-5
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 FACILITY OPERATING LICENSE Amendment No. 128 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 January 18, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, 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 2.C.2 to read as follows:
- 2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 128, 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Kahtan N. Jabbour, Acting Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 10, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 128 TO FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix A Technical Specifications with the attached page.
The revised page is identified by amendment number and contains a marginal line indicating the area of change.
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 185 AND 128 TO FACILITY OPERATING LICENSES NOS. DPR-67 AND NPF-16 FLORIDA POWER AND LIGHT COMPANY, ET AL.
ST. LUCIE PLANT, UNITS NOS. 1 AND 2 DOCKET NOS. 50-335 AND 50-389
1.0 INTRODUCTION
By letter dated January 18, 2002, Florida Power and Light Company (the licensee) requested revision of Technical Specification (TS) 6.2.2.f for the St. Lucie Plant, Units 1 and 2. The proposed revision would replace the specific TS requirements for administrative controls on workings hours of plant staff with a general requirement for administrative procedures to establish and maintain work hour limits. The proposed change is based on the U.S. Nuclear Regulatory Commission (NRC)-approved revision to the Standard Technical Specifications (STS) contained in TSTF-258, Revision 4, of the industry TS Task Force.
2.0 REGULATORY EVALUATION
As stated in Title 10, Code of Federal Regulations (10 CFR), Section 50.59(c)(1)(i), a licensee is required to submit a license amendment pursuant to 10 CFR 50.90 if a change to the TS is required. Furthermore, the requirements of 10 CFR 50.59 necessitate that NRC approve the TS changes before the TS changes are implemented. The licensees submittal meets the requirements of 10 CFR 59(c)(1)(i) and 10 CFR 50.90. The staffs evaluation of the proposed change will be discussed in the technical evaluation section.
Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TS as part of the license. The Commissions regulatory requirements related to the content of the TS are contained in 10 CFR 50.36. The TS requirements in 10 CFR 50.36 include the following categories: (1) safety limits, limiting safety systems settings and control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls. Per 10 CFR 50.36, Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. A TS requirement to develop and implement administrative procedures is an acceptable method of satisfying the administrative controls required by 10 CFR 50.36. Specific working hour limits are not required to be included in TS.
In IE Circular 80-02 (February 1, 1980), the NRC directed licensee management to review their administrative procedures regarding working hours for plant personnel who perform safety
related functions and recommended specific guidelines for limiting overtime. In a July 31, 1980, letter to all licensees and applicants, the NRC provided interim criteria for shift staffing, including the requirement for having administrative procedures to control overtime, which included the recommendations of IE Circular 80-02. Action Item I.A.1.3.1, Limit Overtime, of NUREG-0737, Clarification of TMI [Three-Mile Island] Action Plan Requirements, required licensees to include the previous guidance in their administrative procedures, but did not require them to be included in the TS. On February 8, 1982, Generic Letter (GL) 82-02 forwarded the Policy on Factors Causing Fatigue of Operating Personnel at Nuclear Reactors, which was also published in the Federal Register on February 11, 1982 (47 FR 7352).
GL 82-02 stated that licensees would be requested to revise the Administrative Controls section of their TS to require that administrative procedures follow the policy statement guidelines. On June 15, 1982, GL 82-12 issued a revised policy statement and also a revision to NUREG-0737,Section I.A.1.3.1, which incorporated the revised policy. The need to revise the TS Administrative Controls section to require administrative procedures to follow the policy statement guidelines was included in the revised NUREG-0737. On September 20, 1982, GL 82-16 issued guidance on the TS changes required by NUREG-0737. With regard to limiting overtime, it stated, The administrative section of the technical specifications should be revised to require procedures that follow the policy statement guidelines. Thus, control of work hours through administrative procedures is consistent with Action Item I.A.1.3.1 of NUREG-0737 and other guidelines issued, and the Administrative Controls section of the TS need only contain the requirement to have such procedures.
The staff reviewed the proposed changes for agreement with the precedent as established in NUREG-1432, Standard Technical Specifications for Combustion Engineering Plants, as modified by TSTF-258. The proposed changes are consistent with NUREG-1432 and TSTF-258. However, the licensee cannot justify TS changes solely on the basis of adopting the model STS. In each case the staff makes a determination that the change maintains adequate safety. This is discussed in the technical evaluation.
3.0 TECHNICAL EVALUATION
The current St. Lucie TS are similar to the Standard TS, which, although not required, were developed with specific working-hour limits included in the Administrative Controls section. An April 9, 1997, letter from C. Grimes (NRC) to J. Davis (Nuclear Energy Institute), contained a new staff position regarding controls for working hours of personnel who perform safety-related functions. It indicated that specific controls for working hours could be described in a licensee procedure, which could be located outside the TS, and provided suggested new wording for the Administrative Controls section of the Standard TS. These recommendations were subsequently incorporated into TSTF-258. The licensees proposed changes are consistent with the recommendations in the April 9, 1997, letter and with TSTF-258.
The licensee proposes to remove specific requirements on work hours in TS 6.2.2.f and to revise the wording as follows:
Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g., licensed senior reactor operators (SROs), licensed reactor operators (ROs), health physicists, auxiliary operators, and key
maintenance personnel). The administrative procedures shall include guidelines on working hours that ensure that adequate shift coverage shall be maintained without routine heavy use of overtime. Any deviation from the above guidelines shall be authorized by the Plant General Manager or the Plant General Managers designee, in accordance with approved administrative procedures, and with documentation of the basis for granting the deviation. Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.
Routine deviation from the working hour guidelines shall not be authorized.
In addition to the requirements for administrative controls to limit the working hours of unit staff who perform safety-related functions, the proposed amendment requires advance authorization of deviations from the working hour guidelines and periodic independent reviews of overtime use to ensure that excessive hours have not been assigned. These requirements provide reasonable assurance that impaired performance caused by excessive working hours will not jeopardize safe plant operation.
The staff concludes that the specific controls for working hours of reactor plant staff can be described in a licensee procedure and that the licensees established procedure control processes will provide sufficient control for changes to that procedure. Accordingly, the staff finds that the proposed amendment to the TS to replace the specific requirement for control of workings hours of plant staff with a general requirement for administrative procedures to establish and maintain work hour limits to be acceptable.
4.0 STATE CONSULTATION
Based upon a letter dated March 8, 1991, from Mary E. Clark of the State of Florida, Department of Health and Rehabilitative Services, to Deborah A. Miller, Licensing Assistant, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment relates to changes in record keeping, reporting, or administrative procedures or requirements. 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 ( 67 FR 7418, dated February 19, 2002). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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
Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: David R. Desaulniers, NRR Date: September 10, 2002
Mr. J. A. Stall ST. LUCIE PLANT Florida Power and Light Company cc:
Senior Resident Inspector Mr. R. E. Rose St. Lucie Plant Plant General Manager U.S. Nuclear Regulatory Commission St. Lucie Nuclear Plant P.O. Box 6090 6501 South Ocean Drive Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Craig Fugate, Director Mr. J.T. Voorhees Division of Emergency Preparedness Acting Licensing Manager Department of Community Affairs St. Lucie Nuclear Plant 2740 Centerview Drive 6501 South Ocean Drive Tallahassee, Florida 32399-2100 Jensen Beach, Florida 34957 M. S. Ross, Attorney Mr. Don Mothena Florida Power & Light Company Manager, Nuclear Plant Support Services P.O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Douglas Anderson County Administrator Mr. Rajiv S. Kundalkar St. Lucie County Vice President - Nuclear Engineering 2300 Virginia Avenue Florida Power & Light Company Fort Pierce, Florida 34982 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. William A. Passetti, Chief Department of Health Mr. J. Kammel Bureau of Radiation Control Radiological Emergency 2020 Capital Circle, SE, Bin #C21 Planning Administrator Tallahassee, Florida 32399-1741 Department of Public Safety 6000 SE. Tower Drive Mr. Donald E. Jernigan, Site Vice President Stuart, Florida 34997 St. Lucie Nuclear Plant 6501 South Ocean Drive Jensen Beach, Florida 34957