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MONTHYEARML0909106822009-03-31031 March 2009 Email Acceptance Letter License Amendment Request to Delete TS 3.4.10 and to Implement TS Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Project stage: Acceptance Review ML1002103212010-02-23023 February 2010 License Amendments, Removed Structural Integrity Requirements and Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels Project stage: Other 2009-03-31
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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 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 23, 2010 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 SUB~IECT: TURKEY POINT UNITS 3 AND 4 - ISSUANCE OF AMENDMENTS REGARDING TECHNICAL SPECIFICATION CHANGE ASSOCIATED WITH REMOVAL OF STRUCTURAL INTEGRITY REQUIREMENTS AND TECHNICAL SPECIFICATION IMPROVEMENT TO EXTEND THE INSPECTION INTERVAL FOR REACTOR COOLANT PUMP FLYWHEELS (TAC NOS. ME0701 AND ME0702)
Dear Mr. Nazar:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 242 to Renewed Facility Operating License No. DPR-31 and Amendment No. 238 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 your application dated February 16, 2009.
The amendments remove the structural integrity requirements contained in TS 3/4.4.10, and its associated Bases from the Turkey Point TSs. The proposed amendment also relocates the reactor coolant pump (RCP) motor flywheel inspection requirements in Surveillance Requirement (SR) 4.4.10 to SR 4.0.5 and revises the RCP motor flywheel inspection frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Si~rIY' t 1 ; : j e c t Manager
~:~tnL~enSing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosures:
- 1. Amendment No. 242 to DPR-31
- 2. Amendment No. 238 to DPR-41
- 3. Safety Evaluation cc w/enclosures: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT, UNIT NO.3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 242 Renewed License No. DPR-31
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Florida Power and Light Company (the licensee) dated February 16, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is amended by changes to the 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 1\10. 242 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 within 60 days within issuance.
F. 0. R~E NUCLEARr.. E EGG~U.~ATORY. COMMIS.SION
~~V~~
~renda L Mozafari, Chief (~iZ4 Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: February 23, 2010
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.4 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 238 Renewed License No. DPR-41
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Florida Power and Light Company (the licensee) dated February 16, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is amended by changes to the 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. 238 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 within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
. YJ/fM'
~;enda L Mozafari, Chief Plant Licensing Branch 11-2 (A:Jli~
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: February 23,2010
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 242 RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 238 RENEWED FACILITY OPERATING LICENSE NO. DPR-41 DOCKET NOS. 50-250 AND 50-251 Replace 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.
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove pages Insert pages Index-viii Index-viii 3/4 0-4 3/4 0-4 3/44-38
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 2300 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 242 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.
Renewed License No. DPR-31 Amendment No. 242 I
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 2300 megawatts (thermal).
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 238 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.
Renewed License No. DPR-41 AMENDMENT NO. 238 I
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.4.9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System................................................................................. 3/44-30 FIGURE 3.4-2 TURKEY POINT UNITS 3&4 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 32 EFPY 3/44-31 FIGURE 3.4.3 TURKEY POINT UNITS 3&4 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS (100°F/hr)
APPLICABLE UP TO 32 EFPY 3/44-32 TABLE 3.4.5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHEDULE 3/44-34 Pressurizer 3/44-35 Overpressure Mitigating Systems................................................................... 3/44-36 3/4.4.10 DELETED 3/4 4-38 3/4.4.11 REACTOR COOLANT SYSTEM VENTS....................................................... 3/4 4-39 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS 3/45-1 3/4/5.2 ECCS SUBSYSTEMS - Tavg GREATER THAN OR EQUAL TO 350°F.......... 3/45-3 FIGURE 3.5-1 RHR PUMP CURVE....................................................................................... 3/45-6 3/4.5.3 ECCS SUBSYSTEMS - Tavg LESS THAN 350°F 3/4 5-9 3/4.5.4 REFUELING WATER STORAGE TANK........................................................ 3/45-10 TURKEY POINT - UNITS 3 & 4 viii AMENDMENT NOS. 242 AND 238
APPLICABI L1TY SURVEILLANCE REQUIREMENTS (CONTINUED)
- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda and the ASME OM Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Code and the ASME OM Code and applicable Addenda terminology for Required frequencies for inservice inspection and testing performing inservice inspection activities and testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days
- c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
- d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
- e. Nothing in the ASME Boiler and Pressure Vessel Code or the ASME OM Code shall be construed to supersede the requirements of any Technical Specification.
- f. Each reactor coolant pump flywheel shall be inspected at least once every 20 years, by either conducting an in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius, or conduct a surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the disassembled flywheel.
4.0.6 Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in Specification 3.0.5 for individual specifications or whenever certain portions of a specification contain surveillance parameters different for each unit, which will be identified in parentheses, footnotes or body of the requirement.
TURKEY POINT - UNITS 3 & 4 3/40-4 AMENDMENT NOS. 242 AND 238
REACTOR COOLANT SYSTEM 3/4.4.10 DELETED TURKEY POINT - UNITS 3 & 4 3/44-38 AMENDMENT NOS. 242 AND 238
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 242 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AND AMENDMENT NO. 238 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-41 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT, UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251
1.0 INTRODUCTION
By application dated February 16, 2009, Florida Power and Light Company (FPL, the licensee) proposed an amendment to the Technical Specifications (TSs) for Turkey Point Plant, Units 3 and 4. The requested changes would remove the structural integrity requirements contained in TS 3/4.4.10, and its associated Bases from the Turkey Point TSs. The proposed amendment also relocates the reactor coolant pump (RCP) motor flywheel inspection requirements in Surveillance Requirement (SR) 4.4.10 to SR 4.0.5 and revises the RCP motor flywheel inspection frequency from the currently approved 1O-year inspection interval, to an interval not to exceed 20 years. The Bases for TS 3/4.4.10 will be deleted and the Bases revised to address the change in the RCP flywheel inspection interval. These Bases changes will be performed under the Turkey Point TS Bases Control Program, and are not included with the submittal.
2.0 REGULATORY EVALUATION
2.1 Removal of TS 3/4.4.10 and Associated Bases Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The Commission's regulatory requirements related to the content of the TSs are contained in Title 10, Code of Federal Regulations (10 CFR) Section 50.36. The TS requirements in 10 CFR 50.36 include the following categories: (1) safety limits, limiting safety systems settings and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls.
The licensee stated in its February 16, 2009 letter that on July 22, 1993, the Commission issued its Final Policy Statement on Technical Specifications for Nuclear Power Reactors, stating that satisfying the guidance in the policy statement also satisfies Section 182a of the Atomic Energy Act and 10 CFR 50.36. The Final Policy Statement gave guidance for evaluating the required scope of the TSs and defined the guidance criteria to be used in determining which of the limiting conditions for operation (LCOs) and associated SRs should remain in the TSs. The
- 2 Commission stated that, in allowing certain items to be relocated to licensee-controlled documents while requiring that other items be retained in the TSs, it was adopting the qualitative standard enunciated by the Atomic Safety and Licensing Appeal Board. 1 There, the Appeal Board observed:
[T]here is neither a statutory nor a regulatory requirement that every operational detail set forth in an applicant's safety analysis report (or equivalent) be subject to a technical specification, to be included in the license as an absolute condition of operation which is legally binding upon the licensee unless and until changed with specific Commission approval. Rather, as best we can discern it, the contemplation of both the Act and the regulations is that technical specifications are to be reserved for those matters as to which the imposition of rigid conditions or limitations upon reactor operation is deemed necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety.
Pursuant to 10 CFR 50.36(c)(2)(ii), a TS is required for an LCO meeting one or more of the following criteria:
(1) Installed instrumentation that is used to detect, and indicate in a control room, a significant abnormal degradation of the reactor coolant pressure boundary; (2) A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; (3) A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of, or presents a challenge to the integrity of a fission product barrier; and (4) A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
As a result, existing LCO requirements which fall within or satisfy any of the criteria in 10 CFR 50.36(c)(2)(ii) must be retained in the TS while those LCO requirements which do not fall within or satisfy these criteria may be relocated to other licensee-controlled documents.
2.2 Extension of RCP Motor Flywheel Inspection Interval The function of the RCP in the reactor coolant system (RCS) of a pressurized water reactor plant is to maintain an adequate cooling flow rate by circulating a large volume of primary coolant water at high temperature and pressure through the RCS. Following an assumed loss of power to the RCP motor, the flywheel, in conjunction with the impeller and motor assembly, provides sufficient rotational inertia to assure adequate primary coolant flow during RCP coastdown, thus 1 Portland General Electric Co. (Trojan Nuclear Plant), ALAB-531 ,9 NRC 263, 273 (1979).
-3 resulting in adequate core cooling. A concern regarding the overspeed of the RCP and its potential for failure led to the issuance of Regulatory Guide (RG) 1.14, "Reactor Coolant Pump Flywheel Integrity," Revision 1, dated AUgust 1975. RG 1.14 describes a method acceptable to the Nuclear Regulatory Commission (NRC, the Commission) staff of addressing concerns related to RCP vibration and the possible effects of missiles that might result from the failure of the RCP flywheel. The need to protect components important to safety from such missiles are addressed in General Design Criterion 4, "Environmental and Dynamic Effects Design Basis," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," which is applicable to plants that obtained their construction permits after May 21, 1971.
Specific requirements to have an RCP Flywheel Inspection Program consistent with RG 1.14 or previously-issued relaxations from the RG are included in the Administrative Controls Section of the TSs. The purpose of the testing and inspection programs defined in the TSs is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure. The RG provides criteria in terms of critical speeds that could result in the failure of an RCP flywheel during normal or accident conditions.
In addition to the guidance in RG 1.14, the NRC has more recently issued RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," which provides guidance and criteria for evaluating proposed changes that use risk-informed justifications.
A proposed justification for extending the RCP flywheel inspections from a 1O-year inspection interval to an interval not to exceed 20 years was provided by the Westinghouse Owners Group (WOG) in topical report WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination," transmitted by letter dated August 24, 2001. The topical report addressed the proposed extension for all domestic WOG plants. Turkey Point Plant, Units 3 and 4 are 3-loop Westinghouse plants. The NRC accepted the topical report for referencing in license applications by letter and Safety Evaluation (SE) dated May 5,2003 (Agencywide Documents Access and Management System Accession No. ML031250595).
The proposed changes would extend the RCP motor flywheel examination frequency from the currently approved 1O-year inspection interval to an interval not to exceed 20 years. These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-421 (Revision 0) that has been approved generically for the Westinghouse Standard Technical Specifications (STSs), NUREG-1431. A notice announcing the availability of this proposed TS change using the Consolidated Line Item Improvement Process was published in the Federal Register on October 22, 2003 (68 FR 60422).
3.0 TECHNICAL EVALUATION
3.1 Removal of TS 3/4.4.10 and Associated Bases The licensee stated that the purpose of TS 3/4.4.10, "Structural Integrity", is to specify the requirements of maintaining the structural integrity of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Class 1,2 and 3 components. This specification was originally intended to support assurance that structural integrity and operational readiness of these components are maintained at an acceptable level throughout the
- 4 life of the facility. The specification is applicable in all operational modes. However, the specification does not provide actions for plant shutdown if the LCO is not met. This is because the specification addresses the passive pressure boundary function of ASME Code Class 1, 2 and 3 components as established under the Inservice Inspection (lSI) program. The lSI program is required pursuant to 10 CFR 50.55a, Codes and standards and SR 4.0.5.
The licensee states that maintaining a program-type requirement within an LCO creates significant interpretation issues for Operations personnel. The RCS structural integrity TS was part of the original TS and, therefore no basis history is available regarding its intent. However, the TS 3/4.4.10 appears to have been included to help ensure that plant heatup and startup would not occur until all required portions of applicable systems were verified to meet lSI acceptance criteria following inspections performed during a plant outage (normally performed during refueling outages).
Meeting these acceptance criteria helps ensure the integrity of applicable systems during all modes of operation, including accident events. For instance, the RCS pressure boundary is purposefully breached during Modes 5 and 6 operations to support plant outage activities and such breaches are not historically considered a violation of TS 3/4.4.10. Furthermore, TS 3/4.4.10 contains no action suggesting it was designed to accommodate integrity concerns once plant heatup has commenced. Structural integrity lSI activities are performed only during plant outages when conditions exist that permit access to the RCS pressure boundary and are not monitored or controlled through application of the lSI program during the operational cycle.
The licensee stated other TSs are designed to monitor the structural integrity of the RCS during operation and provide actions to shut down the unit if compliance is not maintained. For example, reactor coolant heatup and cooldown rates (TSs 3.4.9.1 and 3.4.9.2) and the overpressure mitigation system (TS 3.4.9.3) protect against applying undue stresses as a result of pressure/temperature transients on RCS components and piping. The RCS leakage TSs (3.4.6.1 and 3.4.6.2) provides a means of protecting the RCS integrity by detecting and monitoring leakage. Therefore, the licensee stated it is not necessary to apply TS 3/4.4.10 when integrity issues become evident during plant operation above cold shutdown. Because TS 3/4.4.10 is redundant to other regulations, it is acceptable to remove TS 3/4.4.10 from the TSs.
Finally, removal of this specification does not reduce the controls that are necessary to ensure compliance with the ASME Code. Structural Integrity is maintained by compliance with 10 CFR 50.55a, as implemented through the Turkey Point lSI Program required by TS 4.0.5, as well as by compliance with TSs 3.4.6.1, 3.4.6.2, 3.4.9.1, 3.4.9.2 and 3.4.9.3 for the RCS.
The TS changes proposed by FPL in this license amendment request are required to be evaluated to confirm compliance with the regulatory requirements in Section 2.0 of this SE. The licensee's basis for each finding is discussed in the following paragraphs.
For Criterion 1, the licensee stated the RCS ASME Code Class 1, 2, and 3 components do not include any instrumentation. Therefore, the NRC staff finds that TS 3/4.4.10 does not meet Criterion 1.
-5 For Criterion 2, the licensee stated structural integrity is neither a process variable, design feature, or operating restriction that is an initial condition of a design-basis analysis (DBA) or transient analysis. Structural integrity is not monitored or controlled during plant operation; it is verified during periodic inspections. Therefore, the NRC staff finds that TS 3/4.4.10 does not meet Criterion 2.
For Criterion 3, the licensee stated ASME Code Class 1, 2, and 3 components that are part of the primary success path and function to mitigate DBAs or transients that either assume the failure of, or present a challenge to, the integrity/operability of these components, are included in the individual specification that cover these components. The portion of this TS that is proposed to be removed addresses only the passive pressure boundary function of these components.
Therefore, the NRC staff finds that TS 3/4.4.10 does not meet Criterion 3.
For Criterion 4, the licensee stated the requirements covered by this TS that are being removed have not been shown to be risk significant to pUblic health and safety by either operating experience or probabilistic safety assessment. In addition, failure modes of applicable structures, systems or components (SSCs) would not be identified from the requirements of this TS. Furthermore, the requirements of this TS do not affect the risk review/unavailability monitoring of applicable SSCs. Therefore, the NRC staff finds that TS 3/4.4.10 does not meet Criterion 4.
The review for the structural integrity LCO relocation was actually performed and presented in a split report from the Director of NRR, Thomas Murley, on May 8 1988. Originally, NUREG-0212, "Standard Technical Specifications for Combustion Engineering" contained provisions for the LCOs and SRs in reference to the structural integrity of ASME Code Class 1, 2, and 3 components. This split report identified Section 3/4.4.10 "Structural Integrity" as not meeting the criterion for 10 CFR 50.36 and was, therefore, removed from subsequent revisions of the STSs.
This conclusion is consistent with NUREG-1431, "Standard Technical Specifications Westinghouse Plants," Revision 3.0, dated March 2004.
Therefore, since this TS does not fulfill any of the 10 CFR 50.36(c)(2)(ii) criteria for items that TSs must be established, the staff finds that removing TS 3/4.4.10 and the associated bases is acceptable. Finally, the removal of TS 3/4.4.10 and its associated references to structural integrity eliminates the redundancy of structural integrity requirements from the TSs that are already covered under 10 CFR 50.55a. Therefore, the NRC staff finds this proposed change to be acceptable.
Normally in applying the Commission Final Policy Statement on Technical Specifications for Nuclear Power Reactors, the NRC staff would require that a licen'see identify both the licensee-controlled document receiving a relocated TS and the change control mechanism that governs that document. However, in this instance, the licensee proposes deletion without relocation of the TS. The NRC staff finds this proposed deletion without relocation to be acceptable because the ASME Code Class 1, 2, and 3 structural integrity requirements continue to be covered under 10 CFR 50.55a, with which the licensee must comply with.
-6 3.2 Extension of RCP Motor Flywheel Inspection Interval The justification for the proposed change was provided in WCAP-15666, which the NRC staff accepted for referencing in license applications by letter and SE dated May 5, 2003. The topical report addresses the three critical speeds defined in RG 1.14: (a) the critical speed for ductile failure, (b) the critical speed for non-ductile failure, and (c) the critical speed for excessive deformation of the flywheel. The NRC staff found that the topical report adequately addressed these issues and demonstrated that acceptance criteria, for normal and accident conditions defined in RG 1.14, would continue to be met for all domestic WOG plants following an extension of the inspection interval. The topical report also provided a risk assessment for extending the RCP flywheel inspection interval. The NRC staffs review, documented in the SE for the topical report, determined that the analysis methods and risk estimates are acceptable when compared to the guidance in RG 1.174.
The technical basis of the change, as described in the NRC-approved topical report WCAP-15666, remains valid for the licensee's proposal to adopt the 20-year inspection interval.
The licensee has maintained the inspection methods consistent with RG 1.14 currently in its TSs and is proposing to adopt only the increased inspection interval.
In conclusion, the NRC staff finds that the regulatory positions in RG 1.14 concerning the three critical speeds are satisfied. The potential for failure of the RCP flywheel is, and will continue to be, negligible during normal and accident conditions. The change is, therefore, acceptable.
4.0 STATE CONSULTATION
Based upon a letter dated May 2,2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.
5.0 ENVIRONMENTAL CONSIDERATION
These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The NRC staff has determined that the 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 that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (74 FR 18255). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by
-7 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.
Principal Contributor: Keith M. Hoffman Date: February 23, 2010
IVIL100210321 *via memo NRR-058 OFFICE LPL2-2/PM LPL2-2/LA ITSB/BC CPNB/BC OGC NLO LPL2-2/BC(A)
NAME JPaige BClayton RElliott TLupold* BMizuno BMozafari DATE 01/25/10 01/22/10 02/02/10 01/19/10 02/19/10 02/23/10