Letter Sequence Other |
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TAC:MC8013, Changes to Section 5.0, Administrative Controls, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) TAC:MC8014, Changes to Section 5.0, Administrative Controls, Removal of Monthly Operating Report and Occupational Radiation Exposure Report (Open) |
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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] |
Text
January 13, 2006 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
TURKEY POINT UNITS 3 AND 4 - ISSUANCE OF AMENDMENTS TO ELIMINATE REQUIREMENTS TO PROVIDE MONTHLY OPERATING REPORTS AND ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORTS (TAC NOS. MC8013 AND MC8014)
Dear Mr. Stall:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 228 to Renewed Facility Operating License No. DPR-31 and Amendment No. 224 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 in response to your application dated July 21, 2005.
The amendments delete TS 6.9.1.2.a related to Occupational Radiation Exposure Reports and TS 6.9.1.6, "Monthly Operating Reports," as described in the Notice of Availability published in the Federal Register on June 23, 2004 (69 FR 35067).
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-250 and 50-251
Enclosures:
- 1. Amendment No. 228 to DPR-31
- 2. Amendment No. 224 to DPR-41
- 3. Safety Evaluation cc w/enclosures: See next page
ML053490250 TS: ML060190401 Package No.: ML053490255 NRR-058 OFFICE CLIIP LPM LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME WReckley B Moroney BClayton MMarshall DATE 9/21/05 1/04/06 1/04/06 1/13/06 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO. 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 228 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 July 21, 2005, 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. 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 and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 228, are hereby incorporated in the license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into the 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.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Michael L. Marshall, Jr., Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 13, 2006
FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO. 4 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 224 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 July 21, 2005, 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. 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 and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 224, are hereby incorporated in the license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(C) This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Michael L. Marshall, Jr., Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 13, 2006
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 228 RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 224 RENEWED FACILITY OPERATING LICENSE NO. DPR-41 DOCKET NOS. 50-250 AND 50-251 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 xvi xvi 6-19 6-19 6-20 6-20
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 228 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AND AMENDMENT NO. 224 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-41 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251
1.0 INTRODUCTION
By application dated July 21, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052090374), the Florida Power and Light (FPL, the licensee) proposed an amendment to the Technical Specifications (TSs) for Turkey Point Plant, Units 3 and 4. The proposed amendment would delete Technical Specification (TS) 6.9.1.2a related to Occupational Radiation Exposure Reports and TS 6.9.1.5, "Monthly Operating Reports," as described in the Notice of Availability published in the Federal Register on June 23, 2004 (69 FR 35067).
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act of 1954, as amended (the Act), requires applicants for nuclear power plant operating licenses to state TSs to be included as part of the license. The Commissions regulatory requirements related to the content of TSs are set forth in Section 50.36, "Technical specifications" of Title 10 of the Code of Federal Regulations (10 CFR). The regulation requires that TSs include items in five specific categories, including (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements; (4) design features; and (5) administrative controls. However, the regulation does not specify the particular requirements to be included in a plants TSs.
The Commission has provided guidance for the content of TSs in its "Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors" (58 FR 39132, published July 22, 1993), in which the Commission indicated that compliance with the Final Policy Statement satisfies Section 182a. of the Act. The Final Policy Statement identified four criteria to be used in determining whether a particular item should be addressed in the TSs as an LCO.
The criteria were subsequently incorporated into 10 CFR 50.36 (60 FR 36593, published July 19, 1995). While the criteria specifically apply to LCOs, the Commission indicated that the intent of these criteria may be used to identify the optimum set of administrative controls in TSs.
Addressing administrative controls, 10 CFR 50.36 states that they are "the provisions relating to
organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner." The specific content of the administrative controls section of the TSs is, therefore, related to those programs and reports that the Commission deems essential for the safe operation of the facility, which are not adequately covered by regulations or other regulatory requirements. Accordingly, the NRC staff may determine that specific requirements, such as those associated with this change, may be removed from the administrative controls in the TSs if they are not explicitly required by 10 CFR 50.36(c)(5) and are not otherwise necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety.
The impetus for the monthly operating report (MOR) came from the 1973-1974 oil embargo.
Regulatory Guide 1.16, Revision 4, "Reporting of Operating Information - Appendix A Technical Specifications," published for comment in August 1975, identifies operating statistics and shutdown experience information that was desired in the operating report at that time. In the mid-1990s, the NRC staff assessed the information that is submitted in the MOR and determined that while some of the information was no longer used by the NRC staff, the MOR was the only source of some data used in the NRC Performance Indicator (PI) Program of that time period (see NRC Generic Letter (GL) 97-02, "Revised Contents of the Monthly Operating Report"). Beginning in the late 1990s, the NRC developed and implemented a major revision to its assessment, inspection, and enforcement processes through its Reactor Oversight Process (ROP). The ROP uses both plant-level PIs and inspections performed by NRC personnel. In conjunction with the development of the ROP, the NRC developed the Industry Trends Program (ITP). The ITP provides the NRC a means to assess overall industry performance using industry level indicators and to report on industry trends to various stakeholders (e.g., Congress). Information from the ITP is used to assess the NRCs performance related to its goal of having "no statistically significant adverse industry trends in safety performance."
The ITP uses some of the same PIs as the PI Program from the mid-1990s and, therefore, the NRC has a continuing use for the data provided in MORs. The NRC also uses some data from the MORs to support the evaluation of operating experience, licensee event reports, and other assessments performed by the NRC staff and its contractors.
The reporting requirements for the MOR include challenges to the pressurizer power operated relief valves (PORVs) or pressurizer safety valves. The reporting of challenges to pressurizer PORVs or safety valves was included in TSs based on the guidance in NUREG-0694, [Three Mile Island] TMI-Related Requirements for New Operating Licensees. The industry proposed and the NRC accepted the elimination of the reporting requirements in TSs for challenges to pressurizer PORVs or safety valves in Revision 4 to TSs Task Force No. 258 (TSTF-258),
Changes to Section 5.0, Administrative Controls. The NRC staffs acceptance of TSTF-258 and subsequent approval of plant-specific adoptions of TSTF-258 is based on the fact that the information on challenges to relief and safety valves is not used in the evaluation of the MOR data, and that the information needed by the NRC is adequately addressed by the reporting requirements in 10 CFR 50.73, Licensee event report system.
Licensees are required by TSs to submit annual occupational radiation exposure reports (ORERs) to the NRC. The reports, developed in the mid-1970s, supplement the reporting requirements currently defined in 10 CFR 20.2206, "Reports of individual monitoring," by providing a tabulation of data by work areas and job functions. The NRC included data from the ORERs in its annual publication of NUREG-0713, "Occupational Radiation Exposure at
Commercial Nuclear Power Reactors and Other Facilities," through the year 1997, but no longer includes the data in that or other reports.
3.0 TECHNICAL EVALUATION
3.1 Monthly Operating Reports As previously mentioned, the administrative requirements in TSs are reserved for "the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner." The current use of the information from the MORs is not related to reporting on or confirming the safe operation of specific nuclear power plants. Instead, the data is used by the NRC to assess and communicate with stakeholders regarding the overall performance of the nuclear industry. Data related to PIs for specific plants are reported to the NRC as part of the ROP. The NRC staff has determined that the MORs do not meet the criteria defined for requirements to be included in the administrative section of TSs and the reporting requirement may, therefore, be removed.
Although the MORs do not satisfy the criteria for inclusion in TSs, the NRC staff nevertheless has a continuing need to receive the data in order to compile its reports on industry trends and to support other evaluations of operating experience. In addition, information such as plant capacity factors that are reported in the MORs are useful to the NRC staff and are frequently asked for by agency stakeholders.
The NRC staff interacted with licensees, industry organizations, and other stakeholders during the development of the Consolidated Data Entry (CDE) program (currently being developed and maintained by the Institute of Nuclear Power Operation), regarding the use of an industry database like CDE to provide data currently obtained from MORs. These discussions also involved the related Revision 1 to TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report." As described in Section 4.0 of this safety evaluation, the licensee is making a regulatory commitment to continue to provide the data identified in GL 97-02, following the removal of the TS requirement to submit MORs, and will, therefore, continue to meet the needs of the NRC staff for the ITP and other evaluations. The use of an industry database such as CDE is more efficient and cost-effective for both the NRC and licensees than would be having the NRC staff obtain the needed information from other means currently available. Should a licensee fail to satisfy the regulatory commitment to voluntarily provide the information, the NRC could obtain the information through its inspection program (similar to the process described in NRC Inspection Procedure 71150, "Discrepant or Unreported Performance Indicator Data") with the licensee being charged for the time spent by the NRC staff.
The only significant changes resulting from the adoption of TSTF-369 are that the information will be provided quarterly instead of monthly (although the operating data will still be divided by month) and the form of the reporting will be from a consolidated database such as CDE instead of in correspondence from individual licensees. The change of reporting frequency to quarterly has some advantages for both the NRC staff and licensees, since it will coincide with the collection and submission of the ROP PI data. In terms of the specific method used to transmit the data to the NRC, the licensee has committed (see Section 4.0) to provide data identified in GL 97-02 on a quarterly basis. The NRC staff believes that the most efficient process for licensees and the NRC will be for all licensees to use a system such as CDE. Such systems
have advantages in terms of improved data entry, data checking, and data verification and validation. The NRC will recognize efficiency gains by having the data from all plants reported using the same computer software and format. Although the data may be transmitted to the NRC from an industry organization maintaining a database such as CDE, the licensee provides the data for the system and remains responsible for the accuracy of the data submitted to the NRC for its plant. The public will continue to have access to the data through official agency records accessible through ADAMS. Therefore, the NRC staff finds it acceptable that TS 5.6.4 is being deleted and the MOR will no longer be submitted by the licensee.
The requirements for the MOR currently include information on challenges to pressurizer PORVs or safety valves. As discussed in the previous section, the staff has documented in its approval of TSTF-258 and related plant-specific amendments that the reporting of challenges to pressurizer PORVs or safety valves may be removed from TSs since the information needed by the NRC is adequately addressed by the reporting requirements in 10 CFR 50.73, Licensee event report system. The NRC staff finds it acceptable to remove the requirement to report challenges to pressurizer PORVs or safety valves along with the other reporting requirements associated with the MOR.
3.2 Occupational Radiation Exposure Reports The information that the NRC staff needs regarding occupational doses is provided by licensees in the reports required under 10 CFR Part 20. The data from the Part 20 reports are sufficient to support the NRC trending programs, radiation related studies, and preparation of reports such as NUREG-0713. Accordingly, the NRCs limited use of the ORER submitted pursuant to the existing TSs requirements no longer warrants the regulatory burden imposed on licensees. Therefore, the NRC staff finds it acceptable that TS 5.6.1 is being deleted and the ORER will no longer be submitted by the licensee.
4.0 VERIFICATIONS AND COMMITMENTS In order to efficiently process incoming license amendment applications, the NRC staff requested each licensee requesting the changes addressed by TSTF-369 using the consolidated line item process to address the following plant-specific regulatory commitment.
Each licensee should make a regulatory commitment to provide to the NRC using an industry database the operating data (for each calender month) that is described in Generic Letter 97-02, "Revised Contents of the Monthly Operating Report," by the last day of the month following the end of each calendar quarter. The regulatory commitment will be based on use of an industry database (e.g., the industrys Consolidated Data Entry (CDE) program, currently being developed and maintained by the Institute of Nuclear Power Operations).
The licensee, in its September 1, 2005, application has made a regulatory commitment to provide the requested data as described in GL 97-02 via an industry database (e.g., the CDE)
by the last day of the month following the end of each calendar quarter. The regulatory commitment will be included in the licensees Technical Requirements Manual.1 The NRC staff finds that reasonable controls for the implementation and for subsequent evaluation of proposed changes pertaining to the above regulatory commitment can be provided by the licensees administrative processes, including its commitment management program. The NRC staff has agreed that Nuclear Energy Institute 99-04, Revision 0, "Guidelines for Managing NRC Commitment Changes," provides reasonable guidance for the control of regulatory commitments made to the NRC staff (see Regulatory Issue Summary 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," dated September 21, 2000). The NRC staff notes that this amendment establishes a voluntary reporting system for the operating data that is similar to the system established for the ROP PI program. Should the licensee choose to incorporate a regulatory commitment into the final safety analysis report or other document with established regulatory controls, the associated regulations would define the appropriate change-control and reporting requirements.
5.0 STATE CONSULTATION
Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) 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: W. Reckley Date: January 13, 2006 1
In subsequent discussions between the NRC staff and the Institute of Nuclear Power Operation, the staff has agreed that the report may be provided within approximately 45 days instead of the 30 days described in the CLIIP model application. Licensees may revise their plant-specific regulatory commitments accordingly.
Mr. J. A. Stall TURKEY POINT PLANT Florida Power and Light Company cc:
M. S. Ross, Managing Attorney Attorney General Florida Power & Light Company Department of Legal Affairs P.O. Box 14000 The Capitol Juno Beach, FL 33408-0420 Tallahassee, Florida 32304 Marjan Mashhadi, Senior Attorney Michael O. Pearce Florida Power & Light Company Plant General Manager 801 Pennsylvania Avenue, NW. Turkey Point Nuclear Plant Suite 220 Florida Power and Light Company Washington, DC 20004 9760 SW. 344th Street Florida City, FL 33035 T. O. Jones, Site Vice President Turkey Point Nuclear Plant Walter Parker Florida Power and Light Company Licensing Manager 9760 SW. 344th Street Turkey Point Nuclear Plant Florida City, FL 33035 9760 SW 344th Street Florida City, FL 33035 County Manager Miami-Dade County Mark Warner, Vice President 111 Northwest 1 Street, 29th Floor Nuclear Operations Support Miami, Florida 33128 Florida Power and Light Company P.O. Box 14000 Senior Resident Inspector Juno Beach, FL 33408-0420 Turkey Point Nuclear Plant U.S. Nuclear Regulatory Commission Mr. Rajiv S. Kundalkar 9762 SW. 344th Street Vice President - Nuclear Engineering Florida City, Florida 33035 Florida Power & Light Company P.O. Box 14000 Mr. William A. Passetti, Chief Juno Beach, FL 33408-0420 Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Mr. Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100