ML18227D863
ML18227D863 | |
Person / Time | |
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Site: | Turkey Point ![]() |
Issue date: | 02/25/1976 |
From: | Robert E. Uhrig Florida Power & Light Co |
To: | Stello V Office of Nuclear Reactor Regulation |
References | |
L-76-69 | |
Download: ML18227D863 (14) | |
Similar Documents at Turkey Point | |
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Category:Legal-Affidavit
MONTHYEARML23333A0192023-11-27027 November 2023
[Table view]Att. K- Bill Powers 2023 Expert Declaration 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 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 L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 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 L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis2023-02-10010 February 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results2023-01-17017 January 2023 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results L-2022-166, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement2022-10-0505 October 2022 Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement ML22243A1622022-08-26026 August 2022 Submittal of License Amendment Request 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project ML22172A2072022-06-16016 June 2022 Affidavit Dated June 16, 2022 ML22144A3922022-05-18018 May 2022 Affidavit Dated May 18 2022, Executed by Phillip A. Opsal - Framatome (Public Available) L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-0042022-05-0303 May 2022 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004 ML22101A2042022-04-0606 April 2022 Nextera/Fpl Affidavit for Proprietary Presentation for April 13, 2022 Public Meeting Re Planned Turkey Point Digital Instrumentation and Controls License Amendment Request ML22115A1772022-03-12012 March 2022 Affidavit Dated March 12 2022, Executed by Phillip A. Opsal - Framatome ML22063A4482022-03-0202 March 2022 Nextera/Fpl Affidavit for Proprietary Presentation for March 7, 2022, Public Meeting ML22047A1342022-02-14014 February 2022 Affidavit Dated February 14, 2022, Executed by Paul S. 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Westinghouse & Areva Affidavits for Attachment 4 L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 05; Westinghouse & Areva Affidavits for Attachment 42010-12-20020 December 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 05; Westinghouse & Areva Affidavits for Attachment 4 L-2010-113, License Amendment Request for Extended Power Uprate, Attachment 13; Westinghouse Affidavit for Attachment 122010-08-11011 August 2010 License Amendment Request for Extended Power Uprate, Attachment 13; Westinghouse Affidavit for Attachment 12 L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 11; Westinghouse Affidavit for Attachment 102010-07-26026 July 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 11; Westinghouse Affidavit for Attachment 10 ML1035601872010-07-26026 July 2010 License Amendment Request for Extended Power Uprate, Attachment 11; Westinghouse Affidavit for Attachment 10 L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 09; Cameron Affidavit for Attachment 82010-07-16016 July 2010 Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 09; Cameron Affidavit for Attachment 8 ML1035601852010-07-16016 July 2010 License Amendment Request for Extended Power Uprate, Attachment 09; Cameron Affidavit for Attachment 8 ML18228A1321979-03-0909 March 1979 Licensee'S Response to Untimely Request for Hearing of Mark P. Oncavage L-78-323, Submit Supplemental Information for Proposed Amendment to Facility Operating Licenses to Operate Until Next Refueling Prior to Conducting Steam Generator Inspection1978-10-0202 October 1978 Submit Supplemental Information for Proposed Amendment to Facility Operating Licenses to Operate Until Next Refueling Prior to Conducting Steam Generator Inspection ML18227B3061978-08-25025 August 1978 Application for Extension of Time L-78-264, 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-411978-08-0909 August 1978 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-41 L-78-233, 07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses1978-07-11011 July 1978 07/11/1978 Letter Request to Amend Appendix a of Facility Operating Licenses L-78-217, 06/22/1978 Letter Proposed Modifications to Technical Specification Figure 2.1-1, Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation1978-06-22022 June 1978 06/22/1978 Letter Proposed Modifications to Technical Specification Figure 2.1-1, Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation L-78-123, 04/10/1978 Response to Request for Additional Information Proposed Inservice Inspection and Pump & Valve Test Programs1978-04-10010 April 1978 04/10/1978 Response to Request for Additional Information Proposed Inservice Inspection and Pump & Valve Test Programs ML18227D4111978-03-0707 March 1978 Transmitting Steam Generator Repair Report, Revision 2 ML18227D8091978-01-27027 January 1978 01/27/1978 Letter Request to Amend Appendix a of Facility Operating Licenses ML18227B2801978-01-27027 January 1978 Submit Proposed Facility Operating Licenses with ECCS Reanalysis 2023-09-22 Category:Letter MONTHYEARML24023A0342024-02-0505 February 2024
[Table view]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; 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[Table view]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 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 L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. 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Conversion, Volume 1, Revision 0, Application of Selection Criteria to the Turkey Point Nuclear Generating Station Unit 3 and Unit 4 Technical Specifications L-2021-158, Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal2021-09-22022 September 2021 Contents of the Turkey Point Nuclear Plant, Units 3 and 4 Improved Technical Specifications (Its) Submittal ML21265A3772021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 6, Revision 0, Section 3.1, Reactivity Control Systems ML21265A3852021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 14, Revision 0, Section 3.9, Refueling Operations ML21265A3812021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.5, Emergency Core Cooling Systems (ECCS) ML21265A3872021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 16, Revision 0, Section 5.0, Administrative Controls ML21265A3792021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 8, Revision 0, Section 3.3, Instrumentation ML21265A3802021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 9, Revision 0, Section 3.4, Reactor Coolant Systems (RCS) ML21265A3842021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 13, Revision 0, Section 3.8, Electrical Power Systems ML21265A3862021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 15, Revision 0, Section 4.0, Design Features ML21265A3782021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 7, Revision 0, Section 3.2, Power Distribution Limits ML21265A3832021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 12, Revision 0, Section 3.7, Plant Systems ML21265A3752021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 4, Revision 0, Chapter 2.0, Safety Limits (Sls) ML21265A3762021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 5, Revision 0, Section 3.0, LCO and SR Applicability ML21265A3732021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 2, Revision 0, Determination of No Significant Hazards Considerations Generic Changes ML21265A3822021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 11, Revision 0, Section 3.6, Containment Systems ML21265A3742021-09-22022 September 2021 Improved Technical Specifications Conversion, Volume 3, Revision 0, Chapter 1.0, Use and Application L-2021-071, License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology2021-04-15015 April 2021 License Amendment Request 273, Update Listing of Approved LOCA Methodologies to Adopt Full Spectrum Tm LOCA Methodology L-2020-157, Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2020-11-0505 November 2020 Supplement to License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors L-2020-053, Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program2020-04-0404 April 2020 Exigent License Amendment Request 272, One-Time Extension of TS 6.8.4 Steam Generator Inspection Program L-2020-003, License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency2020-01-27027 January 2020 License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency L-2019-203, License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2019-12-0606 December 2019 License Amendment Request 264, Adopt Emergency Action Level (EAL) Scheme Described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. L-2019-192, License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements2019-11-0404 November 2019 License Amendment Request 270, Modify Containment Atmosphere Radioactivity Monitoring, Containment Ventilation Isolation and RCS Leakage Detection System Requirements L-2019-005, License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications2019-02-14014 February 2019 License Amendment Request 266, Clarify Requirements When One Unit Is Outside the Applicability of Certain Technical Specifications L-2018-219, Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-12-0303 December 2018 Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals L-2018-203, Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-11-20020 November 2018 Supplement to License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses2018-10-17017 October 2018 Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses L-2018-170, License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals2018-10-17017 October 2018 License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals L-2018-176, Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items2018-10-17017 October 2018 Subsequent License Renewal Application, Responses to the August 2018 NRC On-Site Regulatory Audit Follow-Up Items L-2018-177, Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses2018-10-0909 October 2018 Subsequent License Renewal Application Safety Review Requests for Confirmation of Information (Rci) Responses L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation2018-10-0505 October 2018 Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation ML18130A4662018-06-12012 June 2018 Amendments Regarding Technical Specifications Pertaining to IST Program and ISI Program Requirements and Surveillance Frequency Control Program Applicability L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018 Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications L-2018-044, License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement2018-05-14014 May 2018 License Amendment Request 257, Modify Emergency Diesel Generator Partial-Load Rejection Surveillance Requirement L-2018-065, License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 12018-05-0303 May 2018 License Amendment Request 258, Revise Reactor Core Safety Limit to Reflect WCAP-17642-PA, Revision 1 L-2018-082, Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version)2018-04-10010 April 2018 Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) L-2018-082, Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version)2018-04-10010 April 2018 Enclosure 4 to L-2018-082 - Non-Proprietary Reference Documents and Redacted Versions of Proprietary Documents (Public Version) ML18113A1422018-04-10010 April 2018 Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version) ML18113A1412018-04-10010 April 2018 Enclosure 1 to L-2018-082, Subsequent License Renewal Application, Enclosure Summary ML18113A1342018-04-10010 April 2018 Transmittal of Subsequent License Renewal Application Revision 1 L-2018-086, Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information2018-04-10010 April 2018 Subsequent License Renewal Application Appendix E Environmental Report Supplemental Information 2023-06-28 Category:Safety Evaluation MONTHYEARML23320A3062024-01-22022 January 2024
[Table view]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 Category:Technical Specification MONTHYEARL-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023
[Table view]License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2021-096, 10 CFR 50.59(d)(2) Summary Report2021-05-11011 May 2021 10 CFR 50.59(d)(2) Summary Report L-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019 Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications ML18257A0312018-10-0505 October 2018 Correction to Amendment Nos. 279 and 274 Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID l-2017-LLA-0213) L-2018-100, Submittal of 10 CFR 50.59(d)(2) Summary Report2018-04-25025 April 2018 Submittal of 10 CFR 50.59(d)(2) Summary Report L-2017-100, License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ...2017-06-28028 June 2017 License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ... L-2017-006, Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b.2017-02-0909 February 2017 Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b. L-2016-128, License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2016-128, Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2014-369, License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B.2014-12-23023 December 2014 License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B. L-2014-028, LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0808 July 2014 LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process L-2014-033, License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2014-04-0909 April 2014 License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-2013-219, License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d2013-07-12012 July 2013 License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d L-2012-314, License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement2012-09-0606 September 2012 License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement ML11293A3682012-06-15015 June 2012 Technical Specification Pages - Issuance of Amendments Regarding Extended Power Uprate L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases2011-11-16016 November 2011 Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases L-2011-276, Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System2011-08-0101 August 2011 Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System ML11195A1472011-07-29029 July 2011 Issuance of Amendments Regarding Cyber Security Program L-2011-264, Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability2011-07-18018 July 2011 Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability L-2010-115, 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 20092010-06-0404 June 2010 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 2009 L-2009-177, Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results2009-07-30030 July 2009 Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results L-2009-093, Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel2009-04-15015 April 2009 Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel L-2009-033, Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels.2009-02-16016 February 2009 Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels. L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/082008-11-10010 November 2008 Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08 L-2007-175, Rod Position Indication Systems2007-11-12012 November 2007 Rod Position Indication Systems L-2007-131, Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3)2007-09-0505 September 2007 Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3) L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication2007-05-17017 May 2007 License Amendment Request (LAR 192) Inoperable Rod Position Indication L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-04-27027 April 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity L-2005-243, 10 CFR 50.59 Report2005-12-0808 December 2005 10 CFR 50.59 Report L-2005-006, Proposed License Amendment Reactor Trip System Technical Specifications Changes2005-03-22022 March 2005 Proposed License Amendment Reactor Trip System Technical Specifications Changes L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers2005-01-20020 January 2005 Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers ML0412503672004-04-23023 April 2004 Proposed License Amendments Accident Monitoring Instrumentation Technical Specification 3.3.3.3 L-77-174, 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems1977-06-0909 June 1977 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems L-77-130, 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs1977-04-28028 April 1977 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs L-77-106, 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty1977-04-0404 April 1977 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty ML18227C7331976-11-0101 November 1976 Referring to Letter of 5/20/1976 Which Proposed Tech Spec Changes Relating to Containment Building Tendon Surveillance Program, Letter Advising Changes Are Not Acceptable L-76-199, Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ...1976-05-21021 May 1976 Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ... L-76-200, 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons1976-05-20020 May 1976 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons L-76-189, 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,1976-05-13013 May 1976 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters, L-76-192, 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes1976-05-0303 May 1976 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes ML18227D8631976-02-25025 February 1976 02/25/1976 Letter Request to Amend Appendix a of Facility Operating License. Proposes Technical Specification Changes Relating to Control Rod Insertion Limits for Unit 4, Cycle 3 ML18227D6721975-01-30030 January 1975 Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a, Proposing Addition of Limiting Conditions for Operation & Surveillance Requirements 2023-10-11 Category:Amendment MONTHYEARL-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019
[Table view]Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications ML18257A0312018-10-0505 October 2018 Correction to Amendment Nos. 279 and 274 Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID l-2017-LLA-0213) L-2017-100, License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ...2017-06-28028 June 2017 License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ... L-2016-128, License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2016-128, Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2014-028, LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0808 July 2014 LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process L-2014-033, License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2014-04-0909 April 2014 License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-2013-219, License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d2013-07-12012 July 2013 License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d ML11293A3682012-06-15015 June 2012 Technical Specification Pages - Issuance of Amendments Regarding Extended Power Uprate ML11195A1472011-07-29029 July 2011 Issuance of Amendments Regarding Cyber Security Program L-2009-177, Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results2009-07-30030 July 2009 Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results L-2009-093, Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel2009-04-15015 April 2009 Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel L-2009-033, Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels.2009-02-16016 February 2009 Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels. L-2007-175, Rod Position Indication Systems2007-11-12012 November 2007 Rod Position Indication Systems L-2007-131, Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3)2007-09-0505 September 2007 Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3) L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication2007-05-17017 May 2007 License Amendment Request (LAR 192) Inoperable Rod Position Indication L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-04-27027 April 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity L-2005-006, Proposed License Amendment Reactor Trip System Technical Specifications Changes2005-03-22022 March 2005 Proposed License Amendment Reactor Trip System Technical Specifications Changes L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers2005-01-20020 January 2005 Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers ML0412503672004-04-23023 April 2004 Proposed License Amendments Accident Monitoring Instrumentation Technical Specification 3.3.3.3 L-77-174, 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems1977-06-0909 June 1977 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems L-77-130, 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs1977-04-28028 April 1977 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs L-77-106, 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty1977-04-0404 April 1977 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty ML18227C7331976-11-0101 November 1976 Referring to Letter of 5/20/1976 Which Proposed Tech Spec Changes Relating to Containment Building Tendon Surveillance Program, Letter Advising Changes Are Not Acceptable L-76-199, Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ...1976-05-21021 May 1976 Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ... L-76-200, 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons1976-05-20020 May 1976 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons L-76-189, 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,1976-05-13013 May 1976 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters, L-76-192, 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes1976-05-0303 May 1976 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes ML18227D8631976-02-25025 February 1976 02/25/1976 Letter Request to Amend Appendix a of Facility Operating License. Proposes Technical Specification Changes Relating to Control Rod Insertion Limits for Unit 4, Cycle 3 ML18227D6721975-01-30030 January 1975 Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a, Proposing Addition of Limiting Conditions for Operation & Surveillance Requirements 2019-03-26 Category:Technical Specification MONTHYEARL-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023
[Table view]License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2021-096, 10 CFR 50.59(d)(2) Summary Report2021-05-11011 May 2021 10 CFR 50.59(d)(2) Summary Report L-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019 Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications ML18257A0312018-10-0505 October 2018 Correction to Amendment Nos. 279 and 274 Regarding the Elimination of Certain Technical Specification Reporting Requirements (CAC Nos. MF9601 and MF9602; EPID l-2017-LLA-0213) L-2018-100, Submittal of 10 CFR 50.59(d)(2) Summary Report2018-04-25025 April 2018 Submittal of 10 CFR 50.59(d)(2) Summary Report L-2017-100, License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ...2017-06-28028 June 2017 License Amendment Request (LAR) 248, Changes to Technical Specifications Regarding Inservice Testing Program and Inservice Inspection Program Requirements and Surveillance Frequency Control Program ... L-2017-006, Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b.2017-02-0909 February 2017 Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b. L-2016-128, License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2016-128, Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps2016-06-30030 June 2016 Turkey Point Nuclear Plant, Units 3 and 4 - License Amendment Request 245, Change to the Technical Specifications to Address an Inoperable Steam Supply for the Auxiliary Feedwater Pumps L-2014-369, License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B.2014-12-23023 December 2014 License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B. L-2014-028, LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0808 July 2014 LAR-230, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process L-2014-033, License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2014-04-0909 April 2014 License Amendment Request LAR-229, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-2013-219, License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d2013-07-12012 July 2013 License Amendment Request No. 225 Regarding One-Time Extension for Unit 3 Technical Specification Surveillance Requirement 4.5.1.1.d L-2012-314, License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement2012-09-0606 September 2012 License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement ML11293A3682012-06-15015 June 2012 Technical Specification Pages - Issuance of Amendments Regarding Extended Power Uprate L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases2011-11-16016 November 2011 Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases L-2011-276, Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System2011-08-0101 August 2011 Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System ML11195A1472011-07-29029 July 2011 Issuance of Amendments Regarding Cyber Security Program L-2011-264, Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability2011-07-18018 July 2011 Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability L-2010-115, 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 20092010-06-0404 June 2010 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 2009 L-2009-177, Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results2009-07-30030 July 2009 Supplement to License Amendment Request 196 - Summary of Sump Ph Calculation Inputs, Assumptions, Methodology, and Results L-2009-093, Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel2009-04-15015 April 2009 Emergency License Amendment Request No. 197, Revision of Technical Specification 3.9.10: Water Level - Reactor Vessel L-2009-033, Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels.2009-02-16016 February 2009 Submittal of License Amendment Request No. 195, Application to Delete Technical Specification 3/4.4.10, & to Implement a Technical Specification Improvement to Extend Inspection Interval for Reactor Coolant Pump Flywheels. L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/082008-11-10010 November 2008 Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08 L-2007-175, Rod Position Indication Systems2007-11-12012 November 2007 Rod Position Indication Systems L-2007-131, Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3)2007-09-0505 September 2007 Administrative Changes to Technical Specifications to Remove Notes Regarding the Inoperability of Rod Position Indication for Control Rods F-8 (Unit 4) and M-6 (Unit 3) L-2007-083, License Amendment Request (LAR 192) Inoperable Rod Position Indication2007-05-17017 May 2007 License Amendment Request (LAR 192) Inoperable Rod Position Indication L-2006-074, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-04-27027 April 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity L-2005-243, 10 CFR 50.59 Report2005-12-0808 December 2005 10 CFR 50.59 Report L-2005-006, Proposed License Amendment Reactor Trip System Technical Specifications Changes2005-03-22022 March 2005 Proposed License Amendment Reactor Trip System Technical Specifications Changes L-2005-008, Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers2005-01-20020 January 2005 Proposed License Amendment Adoption of Improved Standard Technical Specification (ISTS) Travelers ML0412503672004-04-23023 April 2004 Proposed License Amendments Accident Monitoring Instrumentation Technical Specification 3.3.3.3 L-77-174, 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems1977-06-0909 June 1977 06/09/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Revised 05/03/1976 Proposal on Subject of Air Filtration Systems L-77-130, 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs1977-04-28028 April 1977 04/28/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Proposed Valve Test, Pump Test, and Inservice Inspection Programs L-77-106, 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty1977-04-0404 April 1977 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty ML18227C7331976-11-0101 November 1976 Referring to Letter of 5/20/1976 Which Proposed Tech Spec Changes Relating to Containment Building Tendon Surveillance Program, Letter Advising Changes Are Not Acceptable L-76-199, Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ...1976-05-21021 May 1976 Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ... L-76-200, 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons1976-05-20020 May 1976 05/20/1976 Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons L-76-189, 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,1976-05-13013 May 1976 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters, L-76-192, 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes1976-05-0303 May 1976 05/03/1976 Letter Request to Amend Appendix a of Facility Operating Licenses. Revises Technical Specifications to Conform as Near as Possible to Standard Technical Specifications Without Making Any Hardware Changes ML18227D8631976-02-25025 February 1976 02/25/1976 Letter Request to Amend Appendix a of Facility Operating License. Proposes Technical Specification Changes Relating to Control Rod Insertion Limits for Unit 4, Cycle 3 ML18227D6721975-01-30030 January 1975 Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a, Proposing Addition of Limiting Conditions for Operation & Surveillance Requirements 2023-10-11 Category:Bases Change MONTHYEARL-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023
[Table view]License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2021-096, 10 CFR 50.59(d)(2) Summary Report2021-05-11011 May 2021 10 CFR 50.59(d)(2) Summary Report L-2018-100, Submittal of 10 CFR 50.59(d)(2) Summary Report2018-04-25025 April 2018 Submittal of 10 CFR 50.59(d)(2) Summary Report L-2017-006, Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b.2017-02-0909 February 2017 Supplement to License Amendment Request 236, Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b. L-2014-369, License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B.2014-12-23023 December 2014 License Amendment Request No. 236 Revision to the Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B. L-2012-314, License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement2012-09-0606 September 2012 License Amendment Request No. 224 Regarding Technical Specification 3/4.6.2.3 - Recirculation Ph Control System and Natb Basket Minimum Loading Requirement L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases2011-11-16016 November 2011 Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases L-2011-276, Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System2011-08-0101 August 2011 Supplemental Response Regarding License Amendment Request No. 194, Control Room Habitability TSTF-448, and Changes to Technical Specification 3.7.5, Control Room Emergency Ventilation System L-2011-264, Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability2011-07-18018 July 2011 Response to NRC Request for Additional Information on License Amendment Request (LAR-194) Re Control Room Envelope Habitability L-2010-115, 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 20092010-06-0404 June 2010 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 2009 L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/082008-11-10010 November 2008 Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08 L-2005-243, 10 CFR 50.59 Report2005-12-0808 December 2005 10 CFR 50.59 Report L-76-189, 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters,1976-05-13013 May 1976 05/13/1976 Letter Request to Amend Appendix a of Facility Operating License. Amendment Adds New Specification 3.1.6 on Unit 4 DNB Parameters & New Bases Section to Describe One of New DNB Parameters, ML18227D8631976-02-25025 February 1976 02/25/1976 Letter Request to Amend Appendix a of Facility Operating License. Proposes Technical Specification Changes Relating to Control Rod Insertion Limits for Unit 4, Cycle 3 2023-10-11 |
Text
NRC FORM 195 U.S. NUCI.EAR REGUI.ATORV COMMISSION
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NRC DISTRIBUTION FDR PART 60 DOCKET NIATI=RIAL FILE NUMBER V. Stello FRoM:Flordia Power 8 Light Co. DATE OF DOCUMENT Miami, Flordia 2-25-76
, R.E. Uhrig DATE REC)IVEQ QLETTER $ 5NOTORIZED PROP INPUT FORM NUMBER OF COP IES 8 ECE I V ED Q ORIGINAL l3 UN C LASS I F I E 0 OCOPV DEscRIPTIDN Ltr. notari zed 2-25-76... ENCLOSURE Ltr. trans the following....... Proposed Amdt. to OL/Change to Tech. Specs:
Consisting of revisions to 'Tech. Spec, with regards to Control Rod and Power Distrubution Limits.....W/Attachments (1 Signed Cy. Received)
Turkey Point b 3 8 4 SAFETY 'OR ACTION/INFO RMATION ENVIRO SAB 3-5-76 SSIGNED AD, ASSIGNED AD:
BRANCH CHIEF: ear BRANCH CHIEF :
PROJECT MANAGER: PROJECT MANAGER .
CD Ta arras LIC ASST INTERNAL D ISTR I BUTION FIL C PDR ERNST
&E BENAROYA ALLARD SPANGLER SSICK & STAFF EN INEER IPPOLITO SITE TECH KNIGHT OPERATING REACTORS GAMILL SIHIKIL STELLO STEPP
'AMLICKI HUIPIAN OPERATING TECH PROJECT MANAGEMENT REACTOR SAFETY SENHUT SITE ANALYSIS BOYD ROSS 0 VOLIJIER P, COLLINS NOVAK ER BUNCH HOUSTON ROSZTOCZY CHWENCER J0 COLLINS PETERSON CHECK RIMES KREGER MELTZ HELTEMES AT&I SITE SAFETY & ENV R SKOVHOLT SALTZIIAN ANALYSIS RUT BERG DENTON & MULLER EXTERNAL DISTRIBUTION CONTR UMBER LPD ~ M1 am> a. NATL LAB BROOKHAVEN NATL LAB TIC REGS V-IE ULRIKSON (ORNL)
LA PDR 1933 .
A LB CONSULTANTS 16 SE iol.~a1 ~ dna i~ ias
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@ ~) g7 February 25, 1976
'- gL-76-69 pe
'o~l Office of Nuclear Reactor Regulation ATTN: Mr. Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stello:
r Re: Turkey Point Units 3 and 4 %By Docket Nos. 50-250 and 50-251 I Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 Zn accordance with 10 CFR'50.30, Florida Power 6 Light Company submits herewith three (3) signed original's and forty (40) conformed copies of a'request to amend Appendix A of Facility Operating License DPR-41.
Unit 4 is currently in its second cycle of operation. A refueling outage is scheduled for April 19, 1976 with Cycle startup planned for late May. This submittal proposes Technical Specification changes relating to the Control rod insertion limits for Unit 4, Cycle 3. The changes are minor and clarify the control rod insertion limit curves and explanatory text which will be applicable to Cycle 3.
The proposed Technical Specification changes are as des-cribed below and as shown in the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.
Page 3.2-1 Sections'3.2.1.b, 3.2.1.c, and 3.2.1.d are amended to clarify the applicability of control group insertion limit curves for Units 3 and 4. Sections 3.2.1.b and 3.2.1.c are reworded to be consistent with one insertion limit applicable for an entire fuel cycle.
Figure 3.2-1 The control group insertion limit graph for Unit 4 three loop operation is revised to be consistent with one insertion HELPING BUILD FLORIDA
Mr. Victor Stello February 25, 1976.
limit which is applicable for the entire cycle. The revised graph is identical to the dashed-li'ne portion of the Cycle 2 graph.
Fi ure 3.2-1(a)
More conservative control group insertion limits are provided for Unit 4 two loop operation.
Pa e B3.2-1 The bases for specification 3.2 are amended to be consistent with one insertion limit which is applicable for an entire fuel cycle.
The proposed amendment has been reviewed and the conclusion reached eration that it does not involve a significant hazards consid-because the proposed control group insertion limits are more conservative than current limits. Therefore, prenoticing pursuant to 10 CFR 2.105 should not be required.
Very truly yours, Robert E. Uhrig Vice President REU:MAS:nch Attachments cc: Mr. Norman C. Moseley Jack R. Newman, Esquire
STATE OF FLORIDA )
) SS COUNTY OF DADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this said document are true and correct to the best of his knowledge, information and belief; and that he is authorized to execute the document on behalf of said Licensee.
'( ~c ~
Robert E. Uhrzg Subscribed and sworn to before me I
this <.5 day of / . <,c.~<ED'i;q .", 1976
./Ug)-.r r.-J /~u.ir,., 6( / P Notary Public, in and for the County of Dade, State of Florida '"
i~ c.g ) l ~ ' C'FF'QRJQA re t,~9+5 CCt<a" ce1QN l My Commission expires: ALY E'XPIRcS 3A 2b, 1979
3.2 CONTROL ROD AND POWER DISTRIBUTION LIMITS p+ <>t 4 contxol rod insertion limits shown on Figure 3.2-1 and the Unit 3 control rod insertion limits shown on Figure'.2-1(b)"may be revised on the basis of physics calculations and physics data obtained during startup and subsequent operation.
- e. Part length rods shall not be permitted in the core except for low power physics tests and for axial offset calibration tests performed below 75% of rated power.
2/25/76 3.2-1
UNIT 4 CONTROL GROUP INSERTION LIE)ITS FOR THREE LOOP OPERATION 100 80 Bank C 60 40-Bank D 20 0
.0 20 40 POWER 6p 'p LEVEL, PERCENT RATED
]00 FIGURE 3.2-1 2/25/76
UNIT 4
- CONTROL GROUP INSERTION LIMITS FOR TWO. LOOP OPERATION 100
- 80. ~ Bank C 5
60
~g 40 Bank D t~ ~
20 0
0 ..20 40 60 80 100 POWER LEVEL, PERCENT RATED FIGURE 3.2-1(a) Q!25/76
~.
B3. 2 BASES FOR LIMITING CONDITIONS FOR OPERATION, CONTROL AND POWER DISTRIBUTION LIGHTS Reactivity chan'ges accompanying changes in reactor power are compensated by control rod motion. Reactivity changes associated with xenon, samarium, fuel depletion, and large changes in reactor coolant temperature (operating temperature to cold shutdown) are compensated by changes in the soluble boron concentration. During power operation, the shutdown groups are fully withdrawn and control of reactor power is by the control groups. .A reactor trip occurring during power operation will put the reactor into the hot shutdown condition.
The control rod insertion limits provide for achieving hot shutdown by reactor trip at any time, assuming the highest worth control rod remains fully withdrawn, with sufficient margins to meet the assumptions used in the accident analysis. (1) In addition, they provide a limit on the max-imum inserted rod worth in the unlikely event of a hypothetical rod ejection, and pr'ovide for acceptable nuclear peaking factors. Figures 3.2-1 and 3.2-1(a) meet the shutdown requirements of Unit 4. .Figures 3.2-1(b) and 3.2-1(c) meet the shutdown requirements of Unit 3. The Unit 4 and Unit 3 rod insertion limits may be determined on the basis of startup and operating data to provide a more realistic limit which will allow for more flexibility in operation and still assure com-pliance with the shutdown requirement. The maximum shutdown margin requirement occurs 'at end-of-core life and is based on the value used in analysis of the hypothetical steam break accident. Early in core life, less shutdown margin is required, and Figure 3.2-2 shows the with respect to an u'ncontrolled cooldown. 'll shutdown margin equivalent to 1.77% reactivity at end-of-core-life other accident analyses are based on 1% reactivity shutdown margin.
B3. 2-1 2/25/76
J SAFETY EVALUATION Xntroduction By letter dated February 25, 1976, Florida Power and Light. Company (FPL) proposes changes to the Technical Specifications of Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Nuclear Generating Units 3 and 4. The proposed changes clarify the control rod insertion limits, a limiting condition for oper-ation (LCO), for Unit 4 Cycle 3,.
Because Units 3 and 4 share joint Technical Specifi-cations, FPL proposes to modify the Technical Speci-fications for Unit 3 to reflect the proposed revision to the Unit 4 Technical Specifications. However, the operating limits for Unit 3 are unchanged by the Unit 4 reload for core Cycle 3.
Discussion Section 3.2 of the Technical Specifications contains graphs which define the control group insertion limits for two-loop and three-loop operation. A description of what the insertion limits provide is contained in Section B3.2. Current Sections 3.2.1 and B3.2 have provisions for adjusting the Unit 4 insertion limits after 70% burnup of Cycle 2. Cycle 3, however, will have one insertion limit which is applicable for the entire cycle. Therefore, appropriate revisions have been made t'o the text and figures applicable to the Unit 4 insertion limits. The revisions are minor and are intended to clarify the text and graphs associated with Unit. 4 to avoid confusion between Cycle 2 and Cycle 3 insertion limits.
The three loop insertion limit for all of Cycle 3 is the same as the corresponding limit for the end of Cycle 2. The two-loop insertion limit for Cycle 3 is more conservative than the corresponding limit for Cycle 2.
Conclusions The proposed amendment will not result in any physical change to plant equipment or systems and will not ef-fect previously performed applicable safety analyses.
Comparison of Cycle 2 and Cycle 3 insertion limits shows that the proposed limits are at least as conser-vative as current limits and will provide an adequate shutdown margin throughout Cycle 3 life. The proposed amendment is consistent with the plant operation neces-sary for the design and safety evaluation conclusions contained in the Unit 4 Cycle 3 Reload Submittal to remain valid.
Based on these considerations; (l) the proposed change oes not increa'se the probability or consequences of accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as de-fined in the basis for any technical specification, therefore, the change does not involve a significant hazards consideration, (2} there is reasonable assur-ance that the health and safety of the public wi nott ic will bee endangered by operation in the proposed manner er, an d
( 3 ) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common de-fense and security or to the health and safety of the public.