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Category:Letter
MONTHYEARML24276A2302024-10-16016 October 2024 Westinghouse Topical Report – Request for Withholding Information from Public Disclosure ML24289A2372024-10-15015 October 2024 Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles IR 05000250/20243012024-10-0303 October 2024 NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301 L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24269A1292024-09-24024 September 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24260A2262024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections 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-2024-112, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project 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 IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000250/20240012024-05-10010 May 2024 Integrated Inspection Report 05000250/2024001 and 05000251/2024001 ML24135A0942024-05-0909 May 2024 Periodic Update to the Updated Final Safety Analysis Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report ML24127A1862024-05-0909 May 2024 Request for Withholding Information from Public Disclosure ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report IR 05000250/20240102024-05-0101 May 2024 Design Basis Assurance Inspection Programs Inspection Report 05000250/2024010 and 05000251/2024010 and Notice of Violation L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-057, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications ML24096A2152024-04-0505 April 2024 Ltr. to Lewis Johnson, Principal Chief, Seminole Nation of Oklahoma, Re., Section 106 Letters for Turkey Point ML24096A2162024-04-0505 April 2024 Ltr. to Marcellus Osceola, Chairman, Seminole Tribe of Florida, Re., Section 106 Letters for Turkey Point ML24087A1982024-04-0505 April 2024 Notice of Availability of the Final Environmental Impact Statement for the Turkey Point Nuclear Generating Unit Numbers 3 and 4 Subsequent License Renewal Application ML24096A2182024-04-0505 April 2024 Ltr. to Stephanie Bryan, Tribal Chair, Poarch Band of Creek Indians, Re., Section 106 Letters for Turkey Point 2024-09-25
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24158A0072024-09-17017 September 2024 SLR License DPR-41 ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses ML24158A0062024-09-17017 September 2024 SLR License DPR-31 ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML24036A0732024-02-12012 February 2024 – Correction of Amendment Nos. 297 and 290 Regarding Conversion to Improved Standard Technical Specifications 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 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 ML19310D7782019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 4 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 ML19310D7772019-12-0404 December 2019 Florida Power & Light Company - Turkey Point Nuclear Generating Unit 3 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 2024-09-17
[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 ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project 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 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 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) 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 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 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 2024-07-16
[Table view] |
Text
September 5, 2007Mr. J. A. StallSenior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
TURKEY POINT UNITS 3 AND 4 - ISSUANCE OF AMENDMENTSREGARDING ADDITION OF A NEW TECHNICAL SPECIFICATION 3.0.6 (TAC NOS. MD5583 AND MD5584)
Dear Mr. Stall:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 235 toRenewed Facility Operating License No. DPR-31 and Amendment No. 230 to Renewed Facility Operating License No. DPR-41 for the Turkey Point Plant, Units Nos. 3 and 4, respectively.
The amendments consist of changes to the Technical Specifications (TSs) in response to yourapplication dated April 26, 2007.This amendment would revise the TSs to add new Limiting Condition for Operation 3.0.6.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in theCommission's biweekly Federal Register notice. Sincerely,/RA/Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor LicensingOffice of Nuclear Reactor RegulationDocket Nos. 50-250 and 50-251
Enclosures:
- 1. Amendment No. 235 to DPR-31 2. Amendment No. 230 to DPR-41
- 3. Safety Evaluationcc w/enclosures: See next page
ML072200269TS: ML072420209Pkg: ML072180644OFFICENSPDPLPL2-2/PMLPL2-2/LAITSB/BCOGCLPL2-2/BCNAMESAndersonMVaaler forBMozafariBClaytonTKobetzEWilliamson "NLO"TBoyceEMarinos forDATE8/23/078/13/078/10/078/22/07 (also by memo dtd 8/1/07)8/17/07 8/23/07 FLORIDA POWER AND LIGHT COMPANYTURKEY POINT PLANT, UNIT NO. 3DOCKET NO. 50-250AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 235 Renewed License No. DPR-311.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Florida Power and Light Company (thelicensee) dated April 26, 2007, 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 amendmentcan 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 andsecurity or to the health and safety of the public; andE. The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 235 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 implementedwithin 60 days within issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA Evangelos C. Marinos for/Thomas H. Boyce, ChiefPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: September 5, 2007 FLORIDA POWER AND LIGHT COMPANYTURKEY POINT PLANT, UNIT NO. 4DOCKET NO. 50-251AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 230 Renewed License No. DPR-411.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Florida Power and Light Company (thelicensee) dated April 26, 2007, 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 amendmentcan 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 andsecurity or to the health and safety of the public; andE. The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 230 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 beimplemented within 60 days within issuance.FOR THE NUCLEAR REGULATORY COMMISSIONRA Evangelos C. Marinos for/Thomas H. Boyce, ChiefPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: September 5, 2007 ATTACHMENT TO LICENSE AMENDMENTAMENDMENT NO. 235 RENEWED FACILITY OPERATING LICENSE NO. DPR-31AMENDMENT NO. 230 RENEWED FACILITY OPERATING LICENSE NO. DPR-41DOCKET NOS. 50-250 AND 50-251Replace Page 3 of Renewed Operating License DPR-31 with the attached Page 3.
Replace Page 3 of Renewed Operating License DPR-41 with the attached Page 3.
Revise the Appendix A Technical Specifications by removing the pages identified below andinserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. REMOVE INSERT3/4 0-13/4 0-13/4 0-23/4 0-2 3Unit 3Renewed License No. DPR-31Amendment No. 235E.Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use atany 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 theconditions 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 LevelThe applicant is authorized to operate the facility at reactor core power levels notin excess of 2300 megawatts (thermal).B. Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 235 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 ReportThe licensee's Final Safety Analysis Report supplement submitted pursuant to10 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.
3Unit 4Renewed License No. DPR-41Amendment No. 230 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use atany 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 theconditions 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 LevelThe applicant is authorized to operate the facility at reactor core power levels notin excess of 2300 megawatts (thermal).B. Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 230 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 ReportThe licensee's Final Safety Analysis Report supplement submitted pursuant to10 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.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 235 TORENEWED FACILITY OPERATING LICENSE NO. DPR-31 ANDAMENDMENT NO. 230 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-41FLORIDA POWER AND LIGHT COMPANYTURKEY POINT PLANT, UNIT NOS. 3 AND 4DOCKET NOS. 50-250 AND 50-25
11.0 INTRODUCTION
By application dated April 26, 2007 Florida Power and Light Company (FPL, the licensee)requested changes to the Technical Specifications (TSs) for Turkey Point Plant, Units 3 and 4 (Reference 7.1). The staff's proposed no significant hazards consideration determination was published in the Federal Register on July 3, 2007 (72 FR 36522).The proposed changes would add limiting condition for operation (LCO) 3.0.6 to allowtemporary exceptions to TS Actions that require equipment to be taken out of service.
The LCO 3.0.6 exception allows equipment to be temporarily returned to service under administrative controls for the purpose of operability testing.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plantoperating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The Commission's regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36. Thisregulation requires that the TSs include items in the following categories: (1) Safety limits, limiting safety system settings, and limiting control settings (50.36(c)(1)); (2) Limiting conditions for operation (50.36(c)(2)); (3) Surveillance requirements (50.36(c)(3)); (4) Design features (50.36(c)(4)); and (5) Administrative controls (50.36(c)(5)).In general there are two classes of changes to TSs: (1) Changes needed to reflectmodifications to the design basis (TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time. This amendment deals with the second class of changes. In determining the acceptability of adding LCO 3.0.6, the staff used the accumulation
- 2 -of generically approved guidance in NUREG-1431, Revision 3, "Standard TechnicalSpecifications for Westinghouse Plants."Section LCO 3.0, "Limiting Condition for Operation Applicability" of the TSs establishes generalrequirements applicable to all TSs unless otherwise stated. In general, these requirements state the relationships between testing, equipment operability, and operational modes. On August 28, 1990, TS amendments were issued for Turkey Point that approved the use ofthe standard TS format (Unit 3 Amendment No.137, Unit 4 Amendment 132). Since that time the applicable standard TSs have been improved in response to the evolution of policy and preferred format under NUREG-1431, "Standard Technical Specifications for Westinghouse Plants."The proposed amendment is a request to adopt the improvements provided by NUREG-1431LCO 3.0.5 to allow equipment that has been removed from service due to TS required ACTIONS to be tested. The sole purpose of this exception is to allow equipment to be returned to service under administrative controls for the purpose of performing testing to demonstrate operability for that or other equipment.This amendment is consistent with NUREG-1431, and two amendments approved for otherplants. Similar changes have been approved on June 16, 1998, for Seabrook Station (Ref. 7.2), and on April 17, 2000, for Milestone Unit 3 (Ref 7.3).
3.0 TECHNICAL EVALUATION
The Turkey Point TS ACTIONS require certain types of equipment to be taken out of service ifthat or other equipment does not meet operability requirements. TS Actions may require equipment to be de-energized, isolated, locked out, etc. It may be necessary to place that equipment back in service to perform operability testing. NUREG-1431 Revision 3, resolves this issue with LCO 3.0.5, which is a temporary relaxation of the TSs to allow equipment to be returned to service for the purpose of operability testing.The licensee's amendment adds new LCO 3.0.6 that is equivalent to LCO 3.0.5 in the currentrevision of the Standard Westinghouse TSs. Several minor changes were made to incorporate the new limiting condition into the Turkey Point TS. The new LCO 3.0.6 states:Equipment removed from service or declared inoperable to comply with ACTIONrequirements may be returned to service under administrative controls solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.1 and 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.References to the new testing exception in LCO 3.0.6 are also made in LCOs 3.0.1 and 3.0.2as part of this amendment.The new LCO 3.0.6 is consistent with the current version of Westinghouse Standard TSs, NUREG-1431 Revision 3, and may enhance overall safety by returning systems or components to operable status in a more timely manner. It also has the potential to reduce the regulatory burden associated with seeking case by case approval to perform appropriate testing notallowed by the current TS. Therefore, the proposed changes are acceptable.
4.0 STATE CONSULTATION
Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department ofHealth, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.
5.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that this 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. TheCommission has previously issued a proposed finding that the amendments involve nosignificant hazards consideration, and there has been no public comment on such finding (72 FR 36522). Accordingly, the amendments meet the eligibility criteria for categoricalexclusion 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) thereis reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
7.1Licensee submittal to incorporate new LCO 3.0.6 Requirements, April 26, 2007(Agencywide Document Access and Management System (ADAMS) Accession No. ML071280265)7.2Safety Evaluation for Amendment No.57, Seabrook Station, June 16, 1998(ADAMS Accession No. ML011840185)7.3Safety Evaluation for Amendment No.179, Millstone Unit 3, April 17, 2000 (ADAMS Accession No. ML003709001)Principal Contributor:William Cartwright Date: September 5, 2007 Florida Power and Light CompanyTURKEY POINT PLANT cc:Mr. William E. Webster Vice President, Nuclear Operations, South Region Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420
Marjan Mashhadi, Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW.
Suite 220 Washington, DC 20004William Jefferson, Jr.Site Vice President Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL 33035 County Manager Miami-Dade County 111 Northwest 1 Street, 29th Floor Miami, Florida 33128 Senior Resident InspectorTurkey Point Nuclear Plant U.S. Nuclear Regulatory Commission 9762 SW. 344 th StreetFlorida City, Florida 33035Mr. William A. Passetti, ChiefDepartment of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741Mr. Craig Fugate, DirectorDivision of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100Attorney GeneralDepartment of Legal AffairsThe CapitolTallahassee, Florida 32304Michael O. Pearce Plant General Manager Turkey Point Nuclear Plant Florida Power and Light Company 9760 SW. 344th Street Florida City, FL 33035James Connolly, Licensing ManagerFlorida Power and Light Company Turkey Point Nuclear Plant 9760 SW. 344th Street Florida City, FL 33035
Don E. Grissette Vice President, Nuclear Training and Performance Improvement Florida Power and Light Company P.O. Box 14000 Juno Beach, FL 33408-0420Mr. Rajiv S. KundalkarVice President, Nuclear Technical Services Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420