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Category:Letter
MONTHYEARML24023A0342024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0038 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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) ML23341A2102024-01-22022 January 2024 LTR-23-0216-1 - Closure Letter - 2.206 Petition for License Renewal Plant Reactor Pressure Vessel Embrittlement ML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report ML23340A0332023-12-0101 December 2023 FPL to Fws, Comments Submitted by Florida Power and Light on the Species Status Assessment Accompanying the September 20, 2023 Proposed Threatened Species Status with Section 4(d) Rule for the Miami Cave Crayfish L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, ML23333A0152023-11-27027 November 2023 Attachment G - Arcadis Memo Re FPL Year 4 Raasr Final (June 2, 2023, Appended to Derm letter)-1 ML23333A0102023-11-27027 November 2023 Attachment B - 11/07/2022 - Waterkeeper Scoping Comments-1 L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles IR 05000250/20230032023-11-0909 November 2023 Integrated Inspection Report 05000250/2023003 and 05000251/2023003 ML23310A1342023-11-0404 November 2023 10 CFR 2.206 Petition - LTR-23-0216-1 Petition Amendment; Turkey Point Subsequent Renewal with Petitioner 11/04/2023 ML24016A2622023-10-25025 October 2023 Subsequent License Renewal Updated List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected Project L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis 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 IR 05000250/20230102023-09-29029 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000250/2023010 and 05000251/2023010 ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23265A5492023-09-22022 September 2023 Transmittal of WCAP-18830-P/NP Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles to Support a License Amendment Request from FPL - License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis ML23243A9522023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9542023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9532023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML23243A9552023-09-0808 September 2023 Notice of Availability of the Draft Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application - Tribe- Section 106 Letters ML23199A2352023-09-0505 September 2023 Letter to EPA-Turkey Point Nuclear Generating Station, Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal ML23199A2482023-09-0505 September 2023 Ltr to Florida Power and Light Co - Turkey Point Nuclear Generating Units 3 and 4 - Notice of Availability of Draft Site-Specific Environmental Impact Statement for Subsequent License Renewal L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project IR 05000250/20230052023-08-21021 August 2023 Updated Inspection Plan for Turkey Point, Units 3 & 4 (Report 05000250/2023005 and 05000251/2023005) L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000250/20230022023-08-14014 August 2023 Integrated Inspection Report 05000250/2023002 and 05000251/2023002 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 ML23242A0922023-08-0606 August 2023 Request for Withholding Information from Public Disclosure for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23198A2702023-08-0303 August 2023 Issuance of the Site-Specific Environmental Impact Statement Scoping Process Summary Report Associated with the Turkey Point Nuclear Generating Unit Numbers 3 and 4, Subsequent License Renewal Application, Environmental Report Supplement 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23178A1872023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspections During Refueling Outage No. 33 ML23188A1242023-07-20020 July 2023 Acknowledgment of Temporary Suspension Request for License Request for License Amendment Request Reactor Protection System, Engineered Safety Features System, and Nuclear Instrumentation System ML23200A0672023-07-18018 July 2023 Tp 2023 RQ Inspection Notification Letter ML23173A0812023-07-17017 July 2023 Supplement to Regulatory Audit Plan in Support of Review of License Amendment Request Supporting Digital Instrumentation & Control Modernization Project (EPID L-2022-LLA-0105) - Non-Proprietary 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) 2024-02-05
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23249A2412023-09-25025 September 2023 Regulatory Audit Summary for the Review of License Amendment Request to Revise the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23082A0402023-04-0505 April 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment Nos. 260 and 255 ML22028A0662022-05-24024 May 2022 Issuance of Amendment Nos. 296 and 289 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology (EPID L-2021-LLA-0070)- Non-Proprietary ML22098A0902022-04-13013 April 2022 Nextera/Fpl Non-Proprietary Presentation for April 13, 2022 Public Meeting Re Planned Turkey Point Digital Instrumentation and Controls License Amendment Request (EPID L-2021-LRM-0007) (Slides) ML22020A4032022-02-0707 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) ML21279A0432021-10-15015 October 2021 Summary of Pre-Application Meetings with Florida Power and Light Concerning a Proposed Digital Instrumentation and Control Upgrade for Turkey Point, Units 3 and 4 ML21119A3552021-05-26026 May 2021 Correction to Amendment Concerning Extension of Containment Leak Rate Testing Frequency Amendments ML21032A0202021-02-26026 February 2021 Issuance of Amendment Nos. 295 and 268 Concerning Extension of Containment Leak Rate Testing Frequency ML20198M4982021-01-27027 January 2021 Issuance of Amendment Nos. 294 and 267 Regarding Emergency Action Level Scheme Upgrade (EPID L-2019-LLA-0271) (L-2019-203) ML20237F3852020-10-20020 October 2020 Issuance of Amendment Nos. 293 and 286 Regarding Containment Atmospheric Radioactivity Ventilation Isolation and Leakage Detection System ML20104B5272020-04-16016 April 2020 Issuance of Exigent Amendment No. 291 Concerning the Deferral of Steam Generator Inspections ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML19266A5852019-12-17017 December 2019 Issuance of Amendment Nos. 289 and 283 Technical Specification Applicability to Equipment Shared Between Units and Exception to Technical Specification 4.0.4 ML19310D7772019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 3 Subsequent Renewed Facility Operating License ML19305C8792019-12-0404 December 2019 LTR - Issuance of Subsequent Renewed Facility Operating License Nos. DPR-31 and DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4 ML19310D7782019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 4 Subsequent Renewed Facility Operating License ML19031C8912019-08-15015 August 2019 Issuance of Amendment Nos. 288 and 282 Regarding Revised Reactor Core Safety Limit to Reflect WCAP-17642-PA Revision 1 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 L-2019-088, Subsequent License Renewal Application FPL Comments Regarding the NRC Biological Assessment2019-04-18018 April 2019 Subsequent License Renewal Application FPL Comments Regarding the NRC Biological Assessment ML19064A9032019-03-27027 March 2019 Issuance of Amendments Regarding Transition License Conditions for Reactor Coolant Pump Seals ML18354A6732019-03-18018 March 2019 Issuance of Amendments Regarding Technical Specifications Changes to Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement ML18270A4292018-12-0303 December 2018 Issuance of Amendments Nos. 284 and 278 Regarding Adoption of Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5455 and MF5456; EPID L-2014-LLA-0002) ML18255A3602018-11-14014 November 2018 Issuance of Amendments Regarding Technical Specifications Changes to Address Non-Conservative Actions for Containment and Control Room Ventilation Functions ML18019A0782018-03-19019 March 2018 Issuance of Amendments Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID L-2017-LLA-0213) ML18018A5592018-02-20020 February 2018 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML17228A5632017-10-26026 October 2017 Issuance of Amendments Regarding Technical Specifications for High-Range Noble Gas Effluent Monitors ML17209A3192017-09-28028 September 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Actuation ML17172A1152017-08-0303 August 2017 Turkey Point Nuclear Plant Generating Unit Nos. 3 and 4 - Issuance of Amendments Regarding Technical Specifications for Control Room Emergency Ventilation System (CAC Nos. MF8221 and MF8222) ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers ML16120A4732016-06-20020 June 2016 Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements ML16004A0192016-04-26026 April 2016 Issuance of Amendments Regarding Technical Specification Figure for the Boric Acid Tank Minimum Volume ML16040A3732016-03-29029 March 2016 Issuance of Amendments Regarding Technical Specifications for Communications and the Manipulator Crane ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15205A1742015-08-14014 August 2015 Issuance of Amendments Regarding Removal of Reactor Coolant System Chemistry Requirements from the Technical Specifications and Relocation of Requirements in Licensee-Controlled Documents ML15181A1792015-07-27027 July 2015 Issuance of Amendments Regarding Adoption of Technical Specification Task Force Traveler 523 (TSTF-523), Revision 2 ML13329A0922014-06-13013 June 2014 Issuance of Amendments Regarding Operating License Conditions and Technical Specifications ML13329A1392014-02-21021 February 2014 Issuance of Amendments Regarding the Use of Optimized Zirlo Fuel Rod Cladding Material ML13207A0952013-09-10010 September 2013 Issuance of Amendment No. 258 Regarding a One-Time Extension of Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d ML13059A2242013-04-0202 April 2013 Issuance of Amendments Regarding the Recirculation Ph Control System and Sodium Tetraborate Basket Loading ML12339A1122012-12-17017 December 2012 Issuance of Amendments Regarding Revision of Cyber Security ML12297A2402012-11-0606 November 2012 Issuance of Amendments Regarding Adoption of TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection ML12291A7302012-11-0505 November 2012 Issuance of Amendments Regarding Revision to Technical Specifications 3.7.5 Control Room Emergency Ventilation System ML12292A3422012-11-0505 November 2012 Issuance of Amendments Regarding Permanent Alternate Repair Criteria for Steam Generator Tubes ML12208A2982012-08-0808 August 2012 Issuance of Amendments Regarding Change to Direct Current Source Surveillance Requirements ML12130A0892012-06-21021 June 2012 Issuance of Amendments Regarding Section 5.0 Design Features 2024-01-22
[Table view] Category:Safety Evaluation
MONTHYEARML23320A3062024-01-22022 January 2024 Issuance of Amendment Nos. 298 and 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML22307A1152022-11-28028 November 2022 Authorization of Relief Request No. 10 Part II Related to Repair of Intake Cooling Water Discharge Piping (EPID L-2022-LLR-0032) (Non-Proprietary) ML22028A0662022-05-24024 May 2022 Issuance of Amendment Nos. 296 and 289 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology (EPID L-2021-LLA-0070)- Non-Proprietary ML22123A1922022-05-10010 May 2022 Authorization of Relief Request Nos. 8 and 9 Regarding Extension of Inspection Interval for Reactor Pressure Vessel Welds ML22069A7112022-03-16016 March 2022 Authorization of Relief Request No. 10 Regarding Use of ASME Code Case N-513-4 for Extended Period for Intake Cooling Water Discharge Piping ML21032A0202021-02-26026 February 2021 Issuance of Amendment Nos. 295 and 268 Concerning Extension of Containment Leak Rate Testing Frequency ML20198M4982021-01-27027 January 2021 Issuance of Amendment Nos. 294 and 267 Regarding Emergency Action Level Scheme Upgrade (EPID L-2019-LLA-0271) (L-2019-203) ML20287A5512020-11-0606 November 2020 Approval of Alternative to Use ASME Code Section XI IWA-4340 - for Repairs of Component Cooling Water System Piping ML20237F3852020-10-20020 October 2020 Issuance of Amendment Nos. 293 and 286 Regarding Containment Atmospheric Radioactivity Ventilation Isolation and Leakage Detection System ML20104B5272020-04-16016 April 2020 Issuance of Exigent Amendment No. 291 Concerning the Deferral of Steam Generator Inspections ML19357A1952020-02-10010 February 2020 Unit No.1; & Turkey Point Nuclear Generating Unit Nos. 3 & 4 - Issuance of Amendments Nos. 265, 268, 164, 290, and 284 Revise Technical Specifications to Adopt TSTF-563 ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A5852019-12-17017 December 2019 Issuance of Amendment Nos. 289 and 283 Technical Specification Applicability to Equipment Shared Between Units and Exception to Technical Specification 4.0.4 ML19031C8912019-08-15015 August 2019 Issuance of Amendment Nos. 288 and 282 Regarding Revised Reactor Core Safety Limit to Reflect WCAP-17642-PA Revision 1 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 ML19064A9032019-03-27027 March 2019 Issuance of Amendments Regarding Transition License Conditions for Reactor Coolant Pump Seals ML18354A6732019-03-18018 March 2019 Issuance of Amendments Regarding Technical Specifications Changes to Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement ML18270A4292018-12-0303 December 2018 Issuance of Amendments Nos. 284 and 278 Regarding Adoption of Risk-Informed Completion Times in Technical Specifications (CAC Nos. MF5455 and MF5456; EPID L-2014-LLA-0002) ML18255A3602018-11-14014 November 2018 Issuance of Amendments Regarding Technical Specifications Changes to Address Non-Conservative Actions for Containment and Control Room Ventilation Functions ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18071A0802018-04-0606 April 2018 Correction to Safety Evaluation for Amendment Nos. 278 and 273 Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML18019A0782018-03-19019 March 2018 Issuance of Amendments Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID L-2017-LLA-0213) ML18018A5592018-02-20020 February 2018 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations (CAC Nos. MF9903 and MF9904; EPID L-2017-LLA-0254) ML17228A5632017-10-26026 October 2017 Issuance of Amendments Regarding Technical Specifications for High-Range Noble Gas Effluent Monitors ML17209A3192017-09-28028 September 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Actuation ML17213A8632017-08-29029 August 2017 Safety Evaluation for Relief Request No. PR-03, for the Fifth 10 Year Inservice Testing Interval Regarding Boric Acid Transfer Pump Testing Instrumentation ML17172A1152017-08-0303 August 2017 Turkey Point Nuclear Plant Generating Unit Nos. 3 and 4 - Issuance of Amendments Regarding Technical Specifications for Control Room Emergency Ventilation System (CAC Nos. MF8221 and MF8222) ML17122A1402017-05-10010 May 2017 Safety Evaluation for Relief Request No. 5 for Fifth 10-Year Inservice Inspection Interval ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML16335A1952017-02-14014 February 2017 Issuance of Amendments Regarding Technical Specifications for Auxiliary Feedwater Pumps ML17004A2922017-02-0909 February 2017 Issuance of Amendments Regarding Technical Specifications for Snubbers 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) ML16279A4552016-10-28028 October 2016 Turkey Point Nuclear Generating Station Units 3 & 4 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16293A7782016-10-26026 October 2016 Turkey Point Nuclear Generating, Unit Nos. 3 and 4 - Safety Evaluation for Relief Request No. 4 for Fifth 10 Year Inservice Inspection Interval - Risk-Informed Inservice Inspection Program (CAC Nos. MF7277 and MF7278) ML16120A4732016-06-20020 June 2016 Issuance of Amendments Regarding Technical Specifications for Moderator Temperature Coefficient Measurements ML16004A0192016-04-26026 April 2016 Issuance of Amendments Regarding Technical Specification Figure for the Boric Acid Tank Minimum Volume ML16040A3732016-03-29029 March 2016 Issuance of Amendments Regarding Technical Specifications for Communications and the Manipulator Crane ML16047A1182016-03-0909 March 2016 Safety Evaluation for Relief Request No. 3 for Fifth 10-Year Inservice Inspection Interval - Alternative for Examination of Snubbers (CAC Nos. MF6386 and MF6387) ML16008B0722016-02-25025 February 2016 Issuance of Amendments Regarding Technical Specifications for Facility Staff Qualifications for Licensed Operators ML16011A4402016-02-0101 February 2016 Safety Evaluation for Relief Request No. 2 for the Fifth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations of the Regenerative Heat Exchanger Welds (MF6384-MF6385) ML16011A2052016-01-22022 January 2016 Safety Evaluation for Relief Request No. PR-02, for the Fifth 10-Year Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Residual Heat Removal Pumps (CAC Nos. MF6388 & MF6389) ML15350A2032015-12-23023 December 2015 Safety Evaluation for Relief Request No. 16, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15352A1622015-12-23023 December 2015 Safety Evaluation for Relief Request No. 17, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A2402015-12-11011 December 2015 Safety Evaluation for Relief Request No. 15, for the Fourth 10-Year Inservice Inspection Interval Regarding the Amount of Coverage Obtained During Specific Examinations ML15328A1082015-12-0909 December 2015 Safety Evaluation for Relief Request No. PR-01, for the Fifth 10-Yeaer Inservice Testing Interval Regarding Requirements for the Quarterly Testing of the Boric Acid Transfer Pumps ML15294A4432015-11-0909 November 2015 Issuance of Amendments Regarding Emergency Core Cooling System Technical Specifications ML15271A3252015-10-14014 October 2015 Safety Evaluation for Relief Request No. 1, Revision 1 for Fifth 10-Year Inservice Inspection Interval - Repair of Pressurizer Stainless Steel Heater Sleeve Without Flaw Removal ML15233A3792015-09-28028 September 2015 Issuance of Amendments Regarding Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses 2024-01-22
[Table view] Category:Technical Specifications
MONTHYEARML23234A1922023-09-27027 September 2023 Issuance of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications ML23151A4362023-05-24024 May 2023 License Amendment Request Revision 3 for the Technical Specifications Conversion to NUREG - 1431 Revision 5 ML23151A4462023-05-24024 May 2023 Enclosure 2, Volume 8: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 3 ML23151A4442023-05-24024 May 2023 Enclosure 2, Volume 6: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 ML23151A4432023-05-24024 May 2023 Enclosure 2, Volume 5: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3, LCO and SR Applicability, Revision 2 ML23151A4412023-05-24024 May 2023 Enclosure 2, Volume 3, Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Revision 2, Chapter 1 - Use and Application, Revision 2 ML23151A4532023-05-24024 May 2023 Enclosure 2, Volume 15: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Chapter 4, Design Features, Revision 1 ML23151A4542023-05-24024 May 2023 Enclosure 2, Volume 16: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Chapter 5, Administrative Controls, Revision 2 ML23151A4422023-05-24024 May 2023 Enclosure 2, Volume 4: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Chapter 2, Safety Limits, Revision 1 L-2023-063, Enclosure 2, Volume 1: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Application of Selection Criteria to Technical Specifications, Revision 2, Volume 12023-05-24024 May 2023 Enclosure 2, Volume 1: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Application of Selection Criteria to Technical Specifications, Revision 2, Volume 1 ML23151A4402023-05-24024 May 2023 Enclosure 2, Volume 2: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Generic Determination of No Significant Hazards Consideration and Environmental Assessment, Revision 2, Volume 2 ML23151A4382023-05-24024 May 2023 Enclosure 1: Contents of the Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Submittal ML23151A4452023-05-24024 May 2023 Enclosure 2, Volume 7:Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 ML23151A4472023-05-24024 May 2023 Enclosure 2, Volume 9: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 3 ML23151A4372023-05-24024 May 2023 Attachment 3: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database ML23151A4482023-05-24024 May 2023 Enclosure 2, Volume 10: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 ML23151A4522023-05-24024 May 2023 Enclosure 2, Volume 14: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 ML23151A4512023-05-24024 May 2023 Enclosure 2, Volume 13: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.8, Electrical Power Systems, Revision 3 ML23151A4502023-05-24024 May 2023 Enclosure 2, Volume 12: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 ML23151A4492023-05-24024 May 2023 Enclosure 2, Volume 11:Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 3 ML23095A0152023-04-0404 April 2023 Enclosure 2 - ITS Section 3.2 Power Distribution Limits, Revision 2, Volume 7 ML23095A0182023-04-0404 April 2023 Enclosure 2 - ITS Section 3.6 Containment Systems, Revision 2, Volume 11 ML23095A0172023-04-0404 April 2023 Enclosure 2 - ITS Section 3.5 Emergency Core Cooling Systems (Eccs), Revision 2, Volume 10 ML23095A0192023-04-0404 April 2023 Enclosure 2 - ITS Section 3.7 Plant Systems, Revision 2, Volume 12 ML23095A0202023-04-0404 April 2023 Enclosure 2 - ITS Section 3.8 Electrical Power Systems, Revision 2, Volume 13 ML23095A0222023-04-0404 April 2023 Enclosure 2 - ITS Chapter 5.0 Administrative Controls, Revision 2, Volume 16 ML23095A0212023-04-0404 April 2023 Enclosure 2 - ITS Section 3.9 Refueling Operations, Revision 2, Volume 14 ML23095A0142023-04-0404 April 2023 Enclosure 2 - ITS Section 3.1 Reactivity Control Systems, Revision 2, Volume 6 ML23095A0162023-04-0404 April 2023 Enclosure 2 - ITS Section 3.4 Reactor Coolant System (Rcs), Revision 2, Volume 9 ML23095A0092023-04-0404 April 2023 Enclosure 1 - Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (ITS) Submittal ML23095A0132023-04-0404 April 2023 Enclosure 2 - ITS Section 3.0 LCO and SR Applicability, Revision 2, Volume 5 ML23095A0122023-04-0404 April 2023 Enclosure 2 - ITS Chapter 1.0 Use and Application, Revision 2, Volume 3 L-2023-043, Enclosure 2 - Application of Selection Criteria to the Turkey Point Nuclear Generating Station Units 3 and 4 Technical Specifications, Revision 2, Volume 12023-04-0404 April 2023 Enclosure 2 - Application of Selection Criteria to the Turkey Point Nuclear Generating Station Units 3 and 4 Technical Specifications, Revision 2, Volume 1 ML22089A2102022-03-30030 March 2022 Enclosure 2 - Volume 12, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.7, Plant Systems Revision 1 L-2022-040, Enclosure 2 - Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications (ITS) Revision 1 Submittal, Volumes 1 Through 162022-03-30030 March 2022 Enclosure 2 - Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications (ITS) Revision 1 Submittal, Volumes 1 Through 16 ML22089A2072022-03-30030 March 2022 Enclosure 2 - Volume 9, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.4, Reactor Coolant System (Rcs), Revision 1 ML22089A2002022-03-30030 March 2022 Enclosure 2 - Volume 2, Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion Generic Determination of No Significant Hazards Consideration and Environmental Assessment, Revision 1 ML22089A2012022-03-30030 March 2022 Enclosure 2 - Volume 3, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Chapter 1.0 Use and Application, Revision 1 ML22089A2022022-03-30030 March 2022 Enclosure 2 - Volume 4, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion ITS Chapter 2.0 Safety Limits (Sls), Revision 1 ML22089A1972022-03-30030 March 2022 Attachment 1 - Contents of the Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications (ITS) Revision 1 Submittal ML22089A1982022-03-30030 March 2022 Enclosure 1 - Contents of the Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications (ITS) Submittal ML22089A2032022-03-30030 March 2022 Enclosure 2 - Volume 5, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.0 LCO and SR Applicability, Revision 1 ML22089A2042022-03-30030 March 2022 Enclosure 2 - Volume 6, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.1, Reactivity Control Systems, Revision 1 ML22089A2052022-03-30030 March 2022 Enclosure 2 - Volume 7, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.2, Power Distribution Limits, Revision 1 ML22089A2062022-03-30030 March 2022 Enclosure 2 - Volume 8, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.3, Instrumentation, Revision 1 ML22089A2082022-03-30030 March 2022 Enclosure 2 - Volume 10, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.5, Emergency Core Cooling Systems (Eccs), Revision 1 ML22089A2092022-03-30030 March 2022 Enclosure 2 - Volume 11, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.6 Containment Systems, Revision 1 ML22089A2112022-03-30030 March 2022 Enclosure 2 - Volume 13, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.8, Electrical Power Systems, Revision 1 ML22089A2122022-03-30030 March 2022 Enclosure 2 - Volume 14, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Section 3.9, Refueling Operations, Revision 1 ML22089A2132022-03-30030 March 2022 Enclosure 2 - Volume 15, Turkey Point Nuclear Generating Station, Units 3 and 4, Improved Technical Specifications Conversion, ITS Chapter 4.0 Design Features, Revision 1 2023-09-27
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UNITED STATES WASHINGTON, D.C. 20555-0001 August 15, 2019 Mr. Mano Nazar President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company 700 Universe Blvd., Mail Stop EX/JB Juno Beach, FL 33408
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - ISSUANCE OF AMENDMENT NOS. 288 AND 282 REGARDING REVISED REACTOR CORE SAFETY LIMIT TO REFLECT TOPICAL REPORT WCAP-17642-P-A, REVISION 1 (EPID L-2018-LLA-0120)
Dear Mr. Nazar:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 288 to Renewed Facility Operating License No. DPR-31 and Amendment No. 282 to Renewed Facility Operating License No. DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4, respectively. The amendments change the technical specifications in response to the application from Florida Power & Light Company dated May 3, 2018, as supplemented by letter August 14, 2019.
The amendments revise the technical specifications by revising the Reactor Core Safety Limit 2.1.1.b peak fuel centerline temperature to reflect the fuel centerline melt temperature
- specified in Topical Report WCAP-17642-P-A, Revision 1, "Westinghouse Performance Analysis and Design Model (PADS)."
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Perry H. ckberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosures:
- 1. Amendment No. 288 to DPR-31
- 2. Amendment No. 282 to DPR-41
- 3. Safety Evaluation cc: Listserv
UNITED STATES WASHINGTON, D.C. 20555.0001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 288 Renewed License No. DPR-31
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Florida Power & Light Company (the licensee) dated May 3, 2018, as supplemented by a letter August 14, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compljance 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.
Enclosure 1
- 2. Accordingly, the license is amended by changes to the Renewed Facility Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-31 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 288, are hereby incorporated into this renewed license.
The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented for the Unit 3 Cycle 32 reload campaign, currently scheduled for fall 2021.
FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 15, 2019
UNITED STATES WASHINGTON, D.C. 20555J.1001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 282 Renewed License No. DPR-41
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Florida Power & Light Company (the licensee) dated May 3, 2018, as supplemented by a letter August 14, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 2
- 2. Accordingly, the license is amended by changes to the Renewed Facility Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-41 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 282, are hereby incorporated into this renewed license.
The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented for the Unit 4 Cycle 32 reload campaign, currently scheduled in fall of 2020.
FOR THE NUCLEAR REGULATORY COMMISSION
~~
Undine Shoop, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nucl~ar Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: August 1 5, 201 9
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 288 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 282 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-41 TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251 Replace page 3 of Renewed Facility Operating License No. DPR-31 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace page 3 of Renewed Facility Operating License No. DPR-41 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove 2-1
3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.
- 3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all 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 below:
A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 288, are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
C. Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d ), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.
The licensee shall complete these activities no later than July 19, 2012.
The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
Unit 3 Renewed License No. DPR-31 Amendment No. 288
3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.
- 3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all 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 below:
A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 282, are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
C. Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.
The licensee shall complete these activities no later than April 10, 2013.
The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50. 71 (e )( 4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
Unit 4 Renewed License No. DPR-41 Amendment No. 282
2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T avg) shall not exceed the limits specified in the COLR, for 3 loop operation; and the following Safety Limits shall not be exceeded:
- a. The departure from nucleate boiling ratio (DNBR) shall be maintained 2: 1.17 for the WRB-1 DNB correlation.
- b. The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 9°F per 10,000 MWD/MTU of burnup.
APPLICABILITY: MODES 1 and 2.
ACTION:
Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.
APPLICABILITY: MODES 1, 2, 3, 4, and 5.
ACTION:
MODES 1 and 2:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
MODES 3, 4 and 5:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.
TURKEY POINT - UNITS 3 & 4 2-1 AMENDMENT NOS. 288 AND 282
UNITED STATES WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 288 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 282 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-41 FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251
1.0 INTRODUCTION
By application dated May 3, 2018, as supplemented by letter dated August 14, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML181278714 and ML19226A366, respecitvely), Florida Power & Light Company (the licensee) submitted a license amendment request (LAR) for Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). The proposed amendments would revise the Turkey Point Technical Specification (TS) reactor core safety limit (SL) 2.1.1.b peak fuel centerline temperature to reflect the fuel centerline melt temperature specified in Topical Report (TR)
WCAP-17642-P-A, Revision 1, "Westinghouse Performance Analysis and Design Model (PADS)," dated November 2017 (ADAMS Accession No. ML17338A396 (non-proprietary version)).
The supplemental letter dated August 14, 2019, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC or the Commission) staff's original proposed no significant hazards consideration determination as published in the Federal Register on July 3, 2018, (83 FR 31185). 1
2.0 REGULATORY EVALUATION
2.1 System Description The proposed amendments are related to the Turkey Point nuclear fuel. Reactor core SL 2.1.1.b protects against overheating of the nuclear fuel and fuel cladding, which would lead to the fuel centerline temperature rising above the fuel melting point. The consequences of fuel and cladding overheating include fuel clad perforation, which leads to nuclear fission product 1
A corrected notice was published on July 10, 2018 (83 FR 31981 ), which changed the deadline for filing requests for hearing and petitions for leave to intervene from September 3, 2018, to September 4, 2018, because of the Federal holiday.
Enclosure 3
release to the reactor coolant. Clad perforation can occur when the fuel centerline temperature reaches the melting point for the fuel and the fuel pellet expands. Reactor core SL 2.1.1.b is dependent on burnup and is applicable when the reactor is critical in MODES 1 and 2.
2.2 Regulations and Guidance Turkey Point Units 3 and 4 were licensed prior to the 1971 publication of Appendix A, "General Design Criteria [GDC] for Nuclear Power Plants," to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities." As such, Turkey Point Units 3 and 4 are not licensed to the GDC of 10 CFR Part 50, Appendix A. Section 1.3 of the Turkey Point Updated Final Safety Analysis Report (ADAMS Accession No. ML18117A088) provides a summary of the 1967 draft GDC proposed by the U.S. Atomic Energy Commission, as amended by the Atomic Industrial Forum (circa October 2, 1967). The NRC staff considered the following proposed draft GDC as being applicable to the review of the proposed Turkey Point TS SL 2.1.1.b change:
- 1967 Proposed Draft GDC 6, which requires that the reactor core, with its related controls and protection systems, be designed to function throughout its design lifetime without exceeding acceptable fuel limits specified to preclude damage.
Additional statutes and regulations that are applicable to the proposed TS SL 2.1.1.b change include:
- Section 182a of the Atomic Energy Act of 1954, as amended, which requires applicants for nuclear power plant operating licenses to include TSs as part of the license to enable the Commission to find that the utilization of special nuclear material will be in accord with the common defense and security and will provide adequate protection to the health and safety of the public.
- 10 CFR 50.36, which requires that TSs include items in the following categories:
( 1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports.
- 10 CFR 50.90, which requires NRC approval for any modification to, addition to, or deletion from the TSs.
2.3 Licensee's Proposed Changes The licensee proposes to revise the TS reactor core SL 2.1.1.b peak fuel centerline temperature to reflect the fuel centerline melt temperature specified in TR WCAP-17642-P-A, Revision 1.
The current Turkey Point TS SL 2.1.1.b states:
The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 58°F per 10,000 MWD/MTU of burnup. .
The licensee requests that Turkey Point TS SL 2.1.1.b be revised to state:
The peak fuel centerline temperature shall be maintained< S080°F, decreasing by 9°F per 10,000 MWD/MTU of burnup.
3.0 TECHNICAL EVALUATION
The scope of the NRC staff's review is limited to the proposed change related to the SL for peak fuel centerline temperature. The proposed limit reflects the limit in TR WCAP-17642-P-A, Revision 1 (PADS methodology). Additionally, the licensee provided a description of the PADS methodology, which the licensee stated that it intends to implement in the future. The change in the SL is not dependent on the implementation of the PADS methodology since the SL can be used independently of the methodology, as described in the following paragraph.
The empirically derived fuel centerline melt temperature described in the PADS methodology is based on fuel properties described in open literature. The description of the fuel properties can be found in (1) S.G. Popov; J.J. Carbajo; V.K. Ivanov; and G.L. Yoder, 'Thermophysical Properties of MOX and U02 Fuels Including the Effects of Irradiation," ORNL/TM-2000/3S1 (2000) and (2) J.J. Carbajo; G.L. Yoder; S.G. Popov; and V.K. Ivanov, "A Review of the Thermophysical Properties of MOX and U02 Fuels," Journal of Nuclear Materials, 299, 181 (2001 ). Since the fuel centerline melt temperature is based on inherent fuel properties, it is not dependent on any specific calculational methodology and is, therefore, acceptable as a standalone limit. 2 3.1 TS SL 2.1.1.b Change Evaluation In the LAR, the licensee requests to change Turkey Point TS SL 2.1.1.b to reflect the fuel centerline melt temperature found in the PADS methodology. Turkey Point TS SL 2.1.1.b limits the peak fuel centerline temperature. For Conditions I and II events (i.e., normal operation and anticipated operational occurrences), the reactor protection system is designed to ensure that the peak fuel centerline temperature does not exceed the fuel melt temperature criterion. The intent of this criterion is to avoid gross fuel melting.
The NRC staff determined that the peak fuel centerline temperature is not dependent on the PADS methodology, as discussed in the previous section. The staff evaluated the peak fuel centerline temperature and determined that is it applicable to Turkey Point, since the properties of the fuel design in use at Turkey Point Units 3 and 4 are consistent with the property data used to generate the proposed SL.
The proposed SL was empirically derived and covers the lower bound of the fuel property data, which is conservative. Additionally, during the review of the PADS methodology, the NRC staff compared the fuel centerline melting temperatures in PADS to the fuel centerline melting temperature in the NRC's confirmatory calculation code, "FRAPCON." The PADS fuel centerline melting temperature is less than that in FRAPCON, which is conservative. The staff determined that its analysis and technical justification in the safety evaluation of the PADS fuel centerline melting temperature is directly applicable to Turkey Point since the SL in the PADS 2
The two identified references provide the data describing the fuel properties. The specific burnup dependence is provided in Section 6.1.5 of TR WCAP-17642-P-A based on an assessment of these data. The NRC staff determined that this burnup dependence was acceptable as described in Section 3. 7.12 of the staffs safety evaluation approving TR WCAP-17642-P-A
methodology is applicable to Turkey Point (as described in the previous paragraph). Therefore, the NRC staff determined that the proposed SL is conservative for Turkey Point.
As previously discussed, the peak fuel centerline temperature SL is independent of the PADS methodology. Therefore, the NRC staff reviewed the proposed SL to ensure that it is supported by the current licensing basis safety analyses. The current licensing basis safety analyses use the existing SL 2.1.1.b for fuel melt as an acceptance criterion as required by the current methodology. Thus, the licensee will continue to be required to meet the existing SL when using its current licensing basis safety analyses even with the implementation of the proposed SL. Since the existing SL for peak fuel centerline temperature is more restrictive than the proposed limit, the current licensing basis safety analyses will remain conservative to the proposed SL Thus, the staff determined that the proposed limit is acceptable with the Turkey Point current licensing basis.
- The licensee's requested change meets the requirements of the 1967 Proposed Draft GDC 6, Section 182a of the Atomic Energy Act; 10 CFR 50.36; and 10 CFR 50.90, since the peak fuel centerline temperature is based on a conservative evaluation of test data that is applicable to the fuel design used at Turkey Point, and since the proposed limit will ensure that fuel melt is precluded during conditions of normal operations and under anticipated operational occurrences. Therefore, the NRC staff concludes that this change is acceptable.
3.2 Consideration of WCAP-17642-P-A Limitations and Conditions The licensee stated that it intends to implement the PADS methodology and described how applicable limitations and conditions in the NRC staffs safety evaluation of the methodology would be addressed. While the proposed change to the SL is independent of the implementation of the PADS methodology, the staff reviewed this section of the LAR to ensure that the licensee's approach would support the proposed SL The staff notes that there are other limitations and conditions in the PADS safety evaluation that were not addressed in the LAR Since the licensee is not requesting in the LAR to implement the PADS methodology, its failure to address all of the limitations and conditions in the LAR is not material to the staff's
. review.
The Turkey Point LAR addressed limitations and conditions (a) and (b) in Section 4.1 of the NRC staff safety evaluation of the PADS SE. Adherence to limitation and condition (a) ensures that the proposed SL applies to Turkey Point. If limitation and condition (a) is not satisfied, then a different SL for fuel melting would be needed. In addition, limitation and condition (b) requires that, should PADS be implemented at any point, the Turkey Point specific analyses are not to be used to predict fuel conditions beyond the melting point.
Limitation and condition (a) states, in part:
The NRC staff limits the applicability of the PADS code and methodology for cladding, fuel types and reactor for the ranges that are listed ....
The NRC staff confirmed that Turkey Point uses Westinghouse fuel that meets the constraints identified in limitation and condition (a). As such, the staff is assured that the proposed SL is applicable to Turkey Point Units 3 and 4 in that it reflects an acceptable limit on the peak fuel centerline temperature that would preclude fuel melting. Based on the confirmation provided by the licensee, the staff determined that this approach to address limitation and condition (a) is acceptable to change TS SL 2.1.1.b for Turkey Point.
Limitation and condition (b) states:
The application of PADS should at no time exceed the fuel melting temperature as calculated by PADS due to the lack of properties for molten fuel in PADS and other properties such as thermal conductivity and FGR [fission gas release].
In the LAR, the licensee stated that it "will limit the peak fuel centerline temperature per this amendment request." The NRC staff determined that the licensee's statement is acceptable because the LAR specifically proposes to change the peak fuel centerline temperature SL to ensure that fuel melt is precluded during conditions for normal operation and anticipated operational occurrences, consistent with the requirements of the 1967 Proposed Draft GDC 6.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the NRC staff notified the State of Florida official (Ms. Cynthia Becker, M.P.H., Chief of the Bureau of Radiation Control, Florida Department of Health) on January 30, 2019 (ADAMS Accession No. ML190308869), of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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, which was published in the Federal Register on July 3, 2018 (83 FR 31185) (corrected July 10, 2018 (83 FR 31981 )), that the amendments involve no significant hazar:ds consideration, and there has been no public comment on such finding. Accordingly, the 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 the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) th~re 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Diana Woodyatt Date: August 15, 2019
ML19031C891 *b memorandum **b e-mail OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SRXB/BC*
NAME PBuckberg BClayton; LRonewicz JBorromeo DATE 2/11/19 2/7 /19; 8/15/19 OFFICE NRR/DSS/STSB/BC** NRR/DSS/S NPB/BC**
NAME PSnyder RLukes DATE 7/29/19 7/29/19 OFFICE NRR/DORL/LPL2-2/BC NRR/DORULPL2-2/PM NAME UShoop PBuckberg DATE 8/15 /19 8/15/19