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Category:Letter
MONTHYEARL-2024-132, 2024 Population Update Analysis2024-08-13013 August 2024 2024 Population Update Analysis IR 05000335/20240022024-08-13013 August 2024 Integrated Inspection Report 05000335-2024002 and 05000389-2024002 L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval2024-08-0707 August 2024 Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-121, Subsequent License Renewal Commitment 30 Revision2024-07-30030 July 2024 Subsequent License Renewal Commitment 30 Revision L-2024-123, Submittal of In-Service Inspection Program Owners Activity Report (OAR-1)2024-07-29029 July 2024 Submittal of In-Service Inspection Program Owners Activity Report (OAR-1) L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-110, Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake2024-07-10010 July 2024 Environmental Protection Plan Report, Unusual or Important Environmental Event - Manatee in Intake L-2024-109, Schedule for Subsequent License Renewal Environmental Review2024-07-0303 July 2024 Schedule for Subsequent License Renewal Environmental Review ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches L-2024-104, Response to Request for Additional Information, St. Luce 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 102024-06-26026 June 2024 Response to Request for Additional Information, St. Luce 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 L-2024-097, Technical Specification Special Report2024-06-20020 June 2024 Technical Specification Special Report L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-090, Revised Steam Generator Tube Inspection Reports2024-06-0404 June 2024 Revised Steam Generator Tube Inspection Reports IR 05000335/20244012024-06-0303 June 2024 Security Baseline Inspection Report 05000335/2024401 and 05000389/2024401 ML24135A0642024-05-17017 May 2024 Correction Letter - Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications L-2024-075, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-05-13013 May 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation IR 05000335/20240012024-05-10010 May 2024 Integrated Inspection Report 05000335/2024001 and 05000389/2024001 ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-053, License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis2024-04-30030 April 2024 License Amendment Request L-2024-053, Updated Spent Fuel Pool Criticality Analysis L-2024-070, Cycle 32 Core Operating Limits Report2024-04-29029 April 2024 Cycle 32 Core Operating Limits Report L-2024-071, Cycle 27 Core Operating Limits Report2024-04-29029 April 2024 Cycle 27 Core Operating Limits Report ML24108A0632024-04-18018 April 2024 – Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection L-2024-064, Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report2024-04-17017 April 2024 Florida Power & Light Company - 10 CFR 50.46 - Emergency Core Cooling System SBLOCA 30-Day Report L-2024-056, Annual Radiological Environmental Operating Report for Calendar Year 20232024-04-17017 April 2024 Annual Radiological Environmental Operating Report for Calendar Year 2023 L-2024-054, 2023 Annual Environmental Operating Report2024-04-0909 April 2024 2023 Annual Environmental Operating Report ML24093A2612024-04-0202 April 2024 – Investigation Summary, Office of Investigations Case Number 2-2023-005 IR 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 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 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 2024-08-07
[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
MONTHYEARML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML23219A0032023-09-0101 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 2024-07-16
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer NextEra Energy P.O. Box 14000 Juno Beach, Florida 33408-0420 March 31, 2014
SUBJECT:
ST. LUCIE PLANT, UNIT 1 -ISSUANCE OF AMENDMENT REGARDING THE USE OF M5 ALLOY FUEL CLADDING IN CORE RELOAD APPLICATIONS (TAC NO. MF1817)
Dear Mr. Nazar:
The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No.218 to Renewed Facility Operating License No. DPR-67 for the St. Lucie Plant, Unit No. 1. This amendment consists of changes to the Technical Specifications in response to your application dated May 1 0, 2013, as supplemented by letter dated September 30, 2013. This amendment modifies the Technical Specifications to allow the use of M5 Alloy Fuel Cladding as an approved fuel rod cladding.
This change is consistent with the NRC's allowed use of M5 cladding in topical report BAW-10227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR [Pressurized-Water Reactor] Reactor Fuel," and topical report BAW-10240(P)(A), Revision 0, "Incorporation of M5 Properties in Framatome ANP Approved Methods." The NRC staff's safety evaluation of the amendment is enclosed.
The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-335
Enclosures:
- 1. Amendment No. 21sto DPR-67 2. Safety Evaluation cc w/encls: Distribution via Listserv Lisa M. Regner, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 218 Renewed 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 May 10, 2013, as supplemented by letter dated September 30, 2013, 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 1 0 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. DPR-67 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. 218 , are hereby incorporated in the renewed license. FPL 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. FOR THE NUCLEAR REGULATORY COMMISSION ssie F. Quifhocho, Chief ant Licensing Branch 11-2 / Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance:
March 31, 2014 ATTACHMENT TO LICENSE AMENDMENT NO. 218 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace Page 3 of Renewed Operating License DPR-67 with the attached Page 3. Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. Remove Pages 5-4 6-19b Insert Pages 5-4 6-19b applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: A. Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 21sare hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.
Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage. C. Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation.
FPL shall complete these activities no later than March 1, 2016, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on March 28, 2003, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed license. Until that update is complete, FPL may make changes to the programs described in such supplement without prior Commission approval, provided that FPL evaluates each such change pursuant to the criteria set forth in 1 0 CFR 50.59 and otherwise complies with the requirements in that section. D. Sustained Core Uncoverv Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery.
Renewed License No. DPR-67 Amendment No. 218 DESIGN FEATURES 2.1.2 SHIELD BUILDING a. Minimum annular space = 4 feet b. Annulus nominal volume = 543,000 cubic feet c. Nominal outside height (measured from top of foundation base to the top of the dome) = 230.5 feet d. Nominal inside diameter=
148 feet e. Cylinder wall minimum thickness = 3 feet f. Dome minimum thickness
= 2.5 feet g. Dome inside radius= 112 feet DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment vessel is designed and shall be maintained for a maximum internal pressure of 44 psig and a temperature of 264°F. PENETRATIONS 5.2.3 Penetrations through the containment structure are designed and shall be maintained in accordance with the original design provisions contained in Sections 3.8.2.1.1 0 and 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies.
Each assembly shall consist of a matrix of Zircaloy or M5 clad fuel rods and/or poison rods, with fuel rods having an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions. 5.3.1.1 Except for special test as authorized by the NRC, all fuel assemblies under control element assemblies shall be sleeved with a sleeve design previously approved by the NRC. ST. LUCIE -UNIT 1 5-4 Amendment No. d4, 44, +9, 444, 218 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (continued)
- 20. EMF-1961 (P)(A), "Statistical Setpoint!Transient Methodology for Combustion Engineering Type Reactors" 21. EMF-231 O(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Revision 1, as supplemented by ANP-3000(P), "St. Lucie Unit 1 EPU -Information to Support License Amendment Request," Revision 0. 22. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," Revision 0, as supplemented by ANP-3000(P), "St. Lucie Unit 1 EPU-Information to Support License Amendment Request," Revision 0. 23. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 0, as supplemented by ANP-2903(P), "St. Lucie Nuclear Plant Unit 1 EPU Cycle Realistic Large Break LOCA summary Report with Zr-4 Fuel Cladding," Revision 1. 24. BAW-10240(P)(A)
Revision 0, "Incorporation of M5 Properties in Framatome ANP Approved Methods." ST. LUCIE -UNIT 1 6-19b Amendment No. +++, 218 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 218 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67
1.0 INTRODUCTION
FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT, UNIT NO. 1 DOCKET NO. 50-335 By letter to the U.S. Nuclear Regulatory Commission (NRC or the Commission) dated May 10, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13135A008), as supplemented by letter dated September 30, 2013 (ADAMS Accession No. ML 13283A002), Florida Power & Light Company (the licensee) requested to amend Renewed Operating License DPR-67 for St. Lucie Plant Unit 1, by April 2014. The licensee's supplementary submittal dated September 30, 2013 (Accession No. ML 13283A002), provided clarifying information that did not change the scope of the proposed amendment as described in the notice of proposed action published in the Federal Register (78 FR 47790) and did not change the initial proposed no significant hazards consideration determination.
The proposed change would modify Technical Specification (TS) 5.3.1, "Fuel Assemblies," by adding M5 as an acceptable fuel rod cladding material.
Currently, as stated in TS 5.3.1, the St. Lucie Plant Unit 1 fuel cladding is zircaloy; therefore, an amendment is needed in order to use M5 fuel cladding.
The proposed amendment would also revise the St. Lucie Plant Unit 1 TS 6.9.1.11.b, "Core Operating Limits Report (COLR)," to permit the addition of the new reference document of analytical methodologies for the M5 material.
M5 is an alloy comprised primarily of zirconium (about 99 percent) and niobium (about 1 percent).
The elimination of tin in M5 has resulted in superior corrosion resistance and reduced irradiation-induced growth relative to both standard zircaloy (1. 7 percent tin) and low-tin zircaloy (1.2 percent tin). The addition of niobium increases ductility, which is desirable to avoid brittle failures.
By letter dated February 4, 2000 (ADAMS Accession No. ML003681490), the NRC approved AREVA topical report BAW-10227P, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR [Pressurized-Water Reactor] Reactor Fuel," which describes AREVA M5 fuel designs and provides justification for its use in PWR cores. The AREVA topical report Enclosure BAW-1 0227P-A, was submitted to the NRC by letter dated February 11, 2000 (ADAMS Accession No. ML003685828).
The topical report is proprietary and not publicly available.
The licensee also requested an exemption from the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," and Appendix K, "ECCS [Emergency Core Cooling System] Evaluation Models," to 10 CFR Part 50, to allow the use of fuel rods clad with M5 alloy for future reload applications.
The NRC addressed this exemption in separate correspondence (ADAMS Accession No. ML 14064A 125).
2.0 REGULATORY EVALUATION
The regulatory requirements that the NRC staff applied in the review of the application include: The regulations in 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," allow a licensee to apply to amend or change the license. Further, 10 CFR 50.92, "Issuance of amendment," specifies that the staff will be guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate in determining whether an amendment will be issued to the applicant.
The licensee requests a license amendment to add M5 as an acceptable fuel rod cladding material in the TSs. The NRC staff reviewed the licensee's amendment request to ensure that operation with M5 clad fuel in the core in accordance with the proposed changes will be within the conditions of operation necessary for application of the NRC-approved AREVA topical report BAW-1 0227P-A, and that the licensee will continue to operate the plant within its design basis and will comply with applicable regulatory requirements following implementation of the proposed changes. These applicable regulatory requirements include:
- NUREG 0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition," Section 4.2, "Fuel System Design." 3.0 TECHNICAL EVALUATION The licensee proposed to revise the design features section of St. Lucie Plant Unit 1 TSs, specifically TS 5.3.1, to include the use of M5 advanced alloy as a fuel rod cladding and fuel assembly structural material.
Specifically, the licensee proposed to add two words, "or M5," to TS 5.3.1 such that the revised TS would read, "Each assembly shall consist of a matrix of Zircaloy or M5 clad fuel rods and/or poison rods, with fuel rods having an initial composition of natural or slightly enriched uranium dioxide (U02) as fuel material." 3.1 Analyses and Evaluations The NRC-approved topical reports BAW-10227P-A and BAW-10240(P)(A), "Incorporation of M5 Properties in Framatome ANP Approved Methods (approved by NRC letter dated May 5, 2004; ADAMS Accession No. ML041260560)," evaluate the material properties of the M5 alloy and conclude that M5 properties are similar or better than those of zircaloy-4.
BAW-1 0240(P)(A) listed BAW-10227P-A in the reference and was approved to 62 gigawatt-days per megaton uranium metal (GWd/MTU) in the associated NRC staff safety evaluation (SE). The licensee evaluated the performance of the M5 cladding for a loss-of-coolant accident (LOCA) scenario.
The licensee's conclusion was that the results with M5 clad fuel meet the acceptance criteria of 10 CFR 50.46 and 10 CFR 50 Appendix K and are consistent with analyses which the NRC staff approved for the 2012 power uprate for St. Lucie Plant Unit 1. This conclusion is consistent with the conclusions in AREVA topical reports BAW-10227P-A and BAW-1 0240(P)(A).
Based on the approved topical reports, the NRC staff concludes that the licensee may perform reload analyses to evaluate St. Lucie Plant, Unit 1 operation with cores including M5 fuel with its present NRC-approved models which compensate for the presence of M5 fuel cladding.
The staff SE stated that licensees referencing BAW-10240(P)(A) to implement M5 cladding fuel must ensure compliance with four conditions as specified in the NRC staff SE dated May 5, 2004. The licensee has documented its compliance with these four conditions in the May 2013 submittal.
Condition 1 The first condition states: The corrosion limit, as specified by the best-estimate model will remain below 100 microns for all locations of the fuel. The licensee stated in its submittal that the corrosion limit, as predicted by the best-estimate model, will be below 100 microns for all locations of the fuel in the AREVA fuel design processes.
In addition, the limit is verified for each reload as part of the cycle-specific reload analysis as required by TS 6.9.1.11, "Core Operating Limits Report." The NRC staff finds this condition is met by the licensee's stated action; since the core reload process is part of the current licensing basis, no additional requirer(lent needs to be imposed. Condition 2 The second condition states: All of the conditions listed in the NRC SEs for all AREVA methodologies used for M5 fuel analysis will continue to be met, except that the use of M5 cladding in addition to zircaloy-4 cladding is now approved.
The licensee stated that conditions from approved SEs are incorporated as restrictions in AREVA design procedures and guidelines that control the core reload designs for St. Lucie Plant, Unit 1. In addition, this is verified for each reload as part of the cycle-specific reload analysis as required by TS 6.9.1.11.
The NRC staff finds this condition is met by the licensee's stated action; since the core reload process is part of the current licensing basis, no additional requirement needs to be imposed. Condition 3 The third condition states: All A REV A methodologies will be used only within the range for which M5 data was acceptable and for which the verifications discussed in BA W-1 0240(P) or BA W-1 0227P-A were performed.
The licensee stated that the limitations to ensure AREVA methodologies will be used only within the range for which M5 data was acceptable, and for which the verifications discussed in BAW-10240(P) or BAW-10227P-A were performed, are incorporated as restrictions in AREVA design procedures and guidelines that control the core reload designs for St. Lucie Plant, Unit 1. In addition, this is verified for each reload as part of the cycle-specific reload analysis as required by TS 6.9.1.11.
The NRC staff finds this condition is met by the licensee's stated action; since the core reload process is part of the current licensing basis, no additional requirement needs to be imposed. Condition 4 The fourth condition states: The burn up limit for implementation of M5 is 62 GWd/MTU. The licensee stated that the maximum fuel rod burnup limit for AREVA fuel designs including MS cladding continues to be 62 GWd/MTU for St. Lucie Plant Unit 1. This limit is currently part of the St. Lucie Plant, Unit 1 core functional requirements and AREVA design processes, and is verified as part of the cycle-specific reload analysis as required by TS 6.9.1.11.
The staff considers this acceptable.
3.2 TS Revisions Section 5. 3. 1 Fuel Assemblies The licensee proposes to add MS as an acceptable fuel rod cladding material.
The new sentence states: "Each assembly shall consist of a matrix of Zircaloy or MS clad fuel rods ... " Based on the NRC-approved M5 clad fuel, the staff concludes that this revision is acceptable for St. Lucie Plant Unit 1. Section 6.9.1.11.b Core Operating Limits Report The licensee proposes to add the approved AREVA topical report BAW-10240(P)(A), "Incorporation of M5 Properties in Framatome ANP Approved Methods," to the list of references in the COLR. This approved method is consistent with the guidance stated in Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," to be used for determining cycle-specific emergency core cooling system limits. This proposed change assures that applicable cycle-specific parameter limits will be determined in accordance with NRC-approved methodologies and that safety analysis limits are met. Based on the NRC-approved topical report, the staff concludes that the revision is acceptable for St. Lucie Plant Unit 1.
4.0 CONCLUSION
The staff has reviewed the licensee's license amendment request to permit the use of AREVA's advanced zirconium-based M5 alloy for fuel design. Based on the evaluation, the staff concludes that the M5 fuel design is acceptable to a peak rod average burnup limit of 62 GWd/MTU and the TS revisions are acceptable for St. Lucie Plant Unit 1.
5.0 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 Ms. Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.
In an email dated July 25, 2012 (ADAMS Accession No. ML 12208A014), from Cynthia Becker, Florida State Bureau of Radiation Control, to Farideh Saba, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida confirmed that the May 2003 letter continues to reflect the State's position on notification of issuance of license amendments.
6.0 ENVIRONMENTAL CONSIDERATION These amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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 (78 FR 4790, dated August 6, 2013). Accordingly, these amendments meet 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 these amendments.
7.0 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) there is reasonable assurance that 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:
Tai Huang Shih-Liang Wu Date: March 31, 2014 Mr. Mane Nazar Executive Vice President and Chief Nuclear Officer NextEra Energy P.O. Box 14000 Juno Beach, Florida 33408-0420 March 31, 2014
SUBJECT:
ST. LUCIE PLANT, UNIT 1 -ISSUANCE OF AMENDMENT REGARDING THE USE OF M5 ALLOY FUEL CLADDING IN CORE RELOAD APPLICATIONS (TAC NO. MF1817)
Dear Mr. Nazar:
The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 218 to Renewed Facility Operating License No. DPR-67 for the St. Lucie Plant, Unit No. 1. This amendment consists of changes to the Technical Specifications in response to your application dated May 10, 2013, as supplemented by letter dated September 30, 2013. This amendment modifies the Technical Specifications to allow the use of M5 Alloy Fuel Cladding as an approved fuel rod cladding.
This change is consistent with the NRC's allowed use of M5 cladding in topical report BAW-1 0227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR [Pressurized-Water Reactor] Reactor Fuel," and topical report BAW-10240(P)(A), Revision 0, "Incorporation of M5 Properties in Framatome ANP Approved Methods." The NRC staff's safety evaluation of the amendment is enclosed.
The Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket No. 50-335
Enclosures:
Sincerely, IRA/ Lisa M. Regner, Senior Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation
- 1. Amendment No. 218 to DPR-67 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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