Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
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MONTHYEARML1011601822010-04-16016 April 2010 St. Lucie Unit 1 License Amendment Request for Extended Power Uprate Project stage: Request L-2010-181, Withdrawal of Extended Power Uprate License Amendment Request2010-08-13013 August 2010 Withdrawal of Extended Power Uprate License Amendment Request Project stage: Withdrawal ML1035604192010-11-22022 November 2010 St. Lucie, Unit 1 - Transmittal of Affidavits from Westinghouse, Areva and Caldon Ultrasonica Technology Center Re License Amendment Request for Extended Power Uprate Project stage: Request ML1107302992011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Licensing Report Project stage: Request ML1107302822011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 2; Supplemental Environmental Report Project stage: Supplement ML1107301162011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate Project stage: Request ML1113200042011-05-12012 May 2011 EPU - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Project stage: Acceptance Review ML11153A0482011-05-27027 May 2011 St. Lucie Plant, Unit 1 - Information Regarding Areva LOCA and Non-LOCA Methodologies Provided in Support of the License Amendment Request for Extended Power Uprate Project stage: Request ML11173A1042011-06-23023 June 2011 Acceptance for Review of License Amendment Request for Extended Power Uprate Project stage: Acceptance Review L-2011-273, Information Regarding Anticipated Transients Without Scram (ATWS) Provided in Support of the Extended Power Uprate License Amendment Request2011-07-22022 July 2011 Information Regarding Anticipated Transients Without Scram (ATWS) Provided in Support of the Extended Power Uprate License Amendment Request Project stage: Request L-2011-314, Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-08-12012 August 2011 Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request NRC-2011-0190, St. Lucie Nuclear Plant, Units 1 and 2 - Federal Register Notice - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI2011-08-26026 August 2011 St. Lucie Nuclear Plant, Units 1 and 2 - Federal Register Notice - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Info Project stage: Approval ML11208B6442011-08-26026 August 2011 Federal Register Notice - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Information Project stage: Other ML11208B6422011-09-0101 September 2011 Transmittal Letter - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI Information Project stage: Other ML1123602302011-09-0202 September 2011 Request for Concurrence on List of Species with Essential Fish Habitat in the Vicinity of the St. Lucie Plant, Units 1 and 2 Project stage: Other L-2011-360, Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-09-0202 September 2011 Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-383, Response to NRC Containment and Ventilation Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-09-22022 September 2011 Response to NRC Containment and Ventilation Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-389, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-09-22022 September 2011 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-404, Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-10-0505 October 2011 Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-422, Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information and Supplemental Information Regarding Extended Power Uprate License Amendment Request2011-10-10010 October 2011 Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information and Supplemental Information Regarding Extended Power Uprate License Amendment Request Project stage: Supplement L-2011-448, Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-10-31031 October 2011 Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-466, Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification 5.6, Design Features - Fuel Storage - Criticality2011-11-0404 November 2011 Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification 5.6, Design Features - Fuel Storage - Criticality Project stage: Request L-2011-467, Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-11-14014 November 2011 Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-493, Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-11-23023 November 2011 Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-524, Response to NRC Steam Generator Tube Integrity and Chemistry Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-12-27027 December 2011 Response to NRC Steam Generator Tube Integrity and Chemistry Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request ML11332A0212011-12-28028 December 2011 Federal Register Notice - Draft Environmental Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Request ML11332A0202011-12-28028 December 2011 Transmittal Letter - Draft Environmental Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Draft Other L-2011-533, Response to NRC Reactor System Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2011-12-29029 December 2011 Response to NRC Reactor System Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-566, Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-14014 January 2012 Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-532, Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-14014 January 2012 Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-565, Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-14014 January 2012 Response to NRC Instrumentation & Controls Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-534, Response to NRC Reactor System Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-18018 January 2012 Response to NRC Reactor System Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2011-441, Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-18018 January 2012 Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-012, Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-21021 January 2012 Response to NRC Reactor Systems Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-009, Response to NRC Reactor System Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-01-21021 January 2012 Response to NRC Reactor System Branch and Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-043, Comment (1) of Richard L. Anderson, on Behalf of Florida Power & Light, Regarding Draft Environmental Assessment and Draft Finding of No Significant Impact Related the Proposed Extended Power Uprate2012-01-30030 January 2012 Comment (1) of Richard L. Anderson, on Behalf of Florida Power & Light, Regarding Draft Environmental Assessment and Draft Finding of No Significant Impact Related the Proposed Extended Power Uprate Project stage: Draft Other ML12044A1272012-02-13013 February 2012 Comment (2) from Edward W. Johnson Opposing Ncr Permit Approval for St. Lucie 1 & 2 Project stage: Request L-2012-059, Response to NRC Mechanical and Civil Engineering Branch (Emcb) Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-02-29029 February 2012 Response to NRC Mechanical and Civil Engineering Branch (Emcb) Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-075, Response to NRC Mechanical and Civil Engineering Branch (Emcb) Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-03-0606 March 2012 Response to NRC Mechanical and Civil Engineering Branch (Emcb) Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-100, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-03-0606 March 2012 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-094, Response to NRC Steam Generator Tube Integrity and Chemistry Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-03-0808 March 2012 Response to NRC Steam Generator Tube Integrity and Chemistry Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-106, Response to Nuclear Performance and Code Review Branch Request for Additional Information Identified During an Audit of Analyses Supporting the Extended Power Uprate License Amendment Request2012-03-15015 March 2012 Response to Nuclear Performance and Code Review Branch Request for Additional Information Identified During an Audit of Analyses Supporting the Extended Power Uprate License Amendment Request Project stage: Request L-2012-114, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-03-16016 March 2012 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-113, Response to Request for Additional Information Identified During Audit of the Loss of Coolant Accident Safety Analyses Calculations for the Extended Power Uprate License Amendment Request2012-03-17017 March 2012 Response to Request for Additional Information Identified During Audit of the Loss of Coolant Accident Safety Analyses Calculations for the Extended Power Uprate License Amendment Request Project stage: Response to RAI L-2012-116, Response to Request for Additional Information Identified During Audit of the Reactor Systems Branch (Srxb) Fluid System Analyses for the Extended Power Uprate License Amendment2012-03-25025 March 2012 Response to Request for Additional Information Identified During Audit of the Reactor Systems Branch (Srxb) Fluid System Analyses for the Extended Power Uprate License Amendment Project stage: Response to RAI L-2012-141, Response to NRC Steam Generator Tube Integrity and Chemical Engineering Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-03-31031 March 2012 Response to NRC Steam Generator Tube Integrity and Chemical Engineering Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-131, Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-04-0505 April 2012 Response to NRC Reactor Systems Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-122, Response to NRC Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request2012-04-0505 April 2012 Response to NRC Nuclear Performance Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request Project stage: Request L-2012-150, Response to Request for Additional Information Identified During Audit of the Non-Loss of Coolant Accident Safety Analyses Calculations for the Extended Power Uprate License Amendment Request2012-04-0606 April 2012 Response to Request for Additional Information Identified During Audit of the Non-Loss of Coolant Accident Safety Analyses Calculations for the Extended Power Uprate License Amendment Request Project stage: Response to RAI L-2012-157, Response to Request for Additional Information Identified During Audit of the Reactor Systems Branch (Srxb) Fluid System Analyses for the Extended Power Uprate License Amendment Request2012-04-10010 April 2012 Response to Request for Additional Information Identified During Audit of the Reactor Systems Branch (Srxb) Fluid System Analyses for the Extended Power Uprate License Amendment Request Project stage: Response to RAI 2011-08-26
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Category:Letter type:L
MONTHYEARL-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) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump 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-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 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, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 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 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 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) 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) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 ML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022 Subsequent License Renewal Application Revision 1, Supplement 4 L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022 Subsequent License Renewal Application Revision 1 - Supplement 1 ML22010A0962022-01-0505 January 2022 Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar ML21285A1072021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1 ML21285A1082021-10-12012 October 2021 Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1 ML21285A1112021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021 Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML21215A3152021-08-0303 August 2021 Application for Subsequent Renewed Facility Operating Licenses ML21215A3162021-08-0303 August 2021 Enclosure 1: Subsequent License Renewal Application Enclosures Summary ML21215A3192021-08-0303 August 2021 Appendix E - Applicant'S Environmental Report for St. Lucie L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021 Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020 License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020 License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019 License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019 Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018 License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018 License Amendment Request Iodine Removal System Elimination L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018 Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018 Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018 License Amendment Request to Reduce the Number of Control Element Assemblies L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications2018-06-25025 June 2018 License Amendment Request to Remove the Site Area Map from the Technical Specifications L-2018-111, Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-06-0707 June 2018 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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-2018-031, License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme2018-01-31031 January 2018 License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2017-12-19019 December 2017 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors L-2017-139, License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2017-09-14014 September 2017 License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply 2023-06-14
[Table view] Category:Technical Specifications
MONTHYEARML23275A1112023-10-0202 October 2023 Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 ML23275A1192023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 ML23275A1182023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8 ML23275A1212023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11 ML23275A1202023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10 ML23275A1172023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7 ML23275A1162023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 ML23275A1222023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12 ML23275A1132023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request NRC Request for Additional Information and FPL Responses Database - Volume 3 ML23275A1152023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5 ML23275A1142023-10-0202 October 2023 Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4 ML23275A1122023-10-0202 October 2023 Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2 ML23275A1242023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14 ML23275A1232023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13 ML23275A1252023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15 ML23275A1262023-10-0202 October 2023 Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16 L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023 Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal L-2022-014, Supplement to License Amendment to Allow Risk Informed Completion Times for the 120-Volt AC Instrument Bus Requirements2022-01-13013 January 2022 Supplement to License Amendment to Allow Risk Informed Completion Times for the 120-Volt AC Instrument Bus Requirements ML22013A6602021-11-11011 November 2021 Amendment 31 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications L-2021-159, Enclosures 1,3,4,5, and 6 - Contents of the St. Lucie Plant, Units 1 and 2, Improved Technical Specifications (ITS) Submittal2021-09-15015 September 2021 Enclosures 1,3,4,5, and 6 - Contents of the St. Lucie Plant, Units 1 and 2, Improved Technical Specifications (ITS) Submittal ML21265A2882021-09-15015 September 2021 Enclosure 2 - Volume 3 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Chapter 1.0 Use and Application, Revision 0 ML21265A2862021-09-15015 September 2021 Enclosure 2 - Volume 1 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion Application of Selection Criteria to the St. Lucie Plant Units 1 and 2 Technical Specifications, Revision 0 ML21265A2892021-09-15015 September 2021 Enclosure 2 - Volume 4 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Chapter 2.0 Safety Limits, Revision 0 ML21265A3012021-09-15015 September 2021 Enclosure 2 - Volume 16 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Chapter 5.0 Administrative Controls, Revision 0 ML21265A2922021-09-15015 September 2021 Enclosure 2 - Volume 7 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.2 Power Distribution Limits, Revision 0 ML21265A2992021-09-15015 September 2021 Enclosure 2 - Volume 14 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.9 Refueling Operations, Revision 0 ML21265A3002021-09-15015 September 2021 Enclosure 2 - Volume 15 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Chapter 4.0 Design Features, Revision 0 ML21265A2982021-09-15015 September 2021 Enclosure 2 - Volume 13 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.8 Electrical Systems, Revision 0 ML21265A2952021-09-15015 September 2021 Enclosure 2 - Volume 10 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.5 Emergency Core Cooling Systems (Eccs), Revision 0 ML21265A2972021-09-15015 September 2021 Enclosure 2 - Volume 12 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.7 Plant Systems, Revision 0 ML21265A2942021-09-15015 September 2021 Enclosure 2 - Volume 9 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.4 Reactor Coolant System (Rcs), Revision 0 ML21265A2932021-09-15015 September 2021 Enclosure 2 - Volume 8 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.3 Instrumentation, Revision 0 ML21265A2912021-09-15015 September 2021 Enclosure 2 - Volume 6 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.1 Reactivity Control Systems, Revision 0 ML21265A2902021-09-15015 September 2021 Enclosure 2 - Volume 5 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.0 LCO and SR Applicability, Revision 0 ML21265A2962021-09-15015 September 2021 Enclosure 2 - Volume 11 - St. Lucie Plant, Units 1 and 2, Improved Technical Specifications Conversion ITS Section 3.6 Containment Systems, Revision 0 ML20141L6642020-05-0404 May 2020 Amendment 30 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map 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-2018-006, Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b2018-02-0101 February 2018 Third Response to Request for Additional Information Regarding License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Risk Informed Extended Completion Times - RITSTF Initiative 4b ML16341C1752016-12-19019 December 2016 Correction to Amendment No. 237 Regarding the Update to Appendix B to the Renewed Facility Operating Licenses to Incorporate the 2016 Biological Opinion ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle ML16124A3832016-05-25025 May 2016 St. Lucie Plant, Unit No. 1 - Issuance of Amendment Regarding Changes to the Snubber Surveillance Requirements (CAC No. MF6490) ML16063A1212016-04-19019 April 2016 Redacted - Issuance of Amendment Regarding License Amendment Request for the Transitioning to Areva Fuel ML15344A3462016-03-31031 March 2016 Issuance of Amendments Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with Title 10 of the Code of Federal Regulations Section 50.48(c) (CAC Nos. MF1373 & MF1374) ML16034A0802016-03-0707 March 2016 Issuance of Amendments Regarding Technical Specification Change to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents L-2015-303, Technical Specification Correction for License Amendment Request to Standardize the Required Actions for Inoperability of Auxiliary Feedwater Pumps2015-12-15015 December 2015 Technical Specification Correction for License Amendment Request to Standardize the Required Actions for Inoperability of Auxiliary Feedwater Pumps 2023-10-02
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F PL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachment 3.
November 4, 2011 L-2011-466 10 CFR 50.90 10 CFR 2.390 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Plant Unit 2 Docket No. 50-389 Renewed Facility Operating License No. NPF-16 Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification 5.6, Design Features - Fuel Storage - Criticality
References:
(1) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-021), "License Amendment Request for Extended Power Uprate," February 25, 2011, Accession No. ML110730116.
(2) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-409), "Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts," October 14, 2011.
By letter L-2011-021 dated February 25, 2011 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. NPF-16 and revise the St.
Lucie Unit 2 Technical Specifications (TS). The proposed amendment will increase the unit's licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt and revise the Renewed Facility Operating License and TS to support operation at this increased core thermal power level. This represents an approximate increase of 11.85% and is therefore considered an Extended Power Uprate (EPU).
FPL is proposing to revise the information presented in Attachment 1 of the St. Lucie Unit 2 EPU License Amendment Request (LAR) [Reference 1], specifically Section 3.1, Renewed Facility Operating License and Technical Specification Changes, Item 26, TS 5.6, DESIGN FEATURES - FUEL STORAGE - CRITICALITY. The proposed TS changes include the following:
an FPL Group company
L-2011-466 Page 2 of 3
- 1. revising TS Table 5.6-1 with respect to providing information that updates the fuel loading curve minimum burnup coefficients,
- 2. adding TS 5.6.1.a.6 to include Areal Density Criteria for Metamic Inserts, and
- 3. removing the TS option to develop new fuel storage configurations to meet criticality requirements from TS 5.6.1.a.4.
The information in Attachment 1 to this letter presents the revision to the proposed TS change submitted by FPL via Reference 1. contains the marked-up and clean pages to support the proposed TS revision.
The proposed changes to TS Table 5.6-1 are based upon updated information provided in , which is Holtec Report No. HI-2104753, Rev. 2, "St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU Fuel." Revision 1 of the this Holtec report was previously submitted to the NRC via Reference 1, as Appendix G to Attachment 5 of the EPU LAR. The proposed change related to Areal Density Criteria for Metamic Inserts is being adopted by St.
Lucie Unit 2 in consideration of a similar TS change proposed for St. Lucie Unit 1 [Reference 2].
TS 5.6.1 .a.4 is updated to ensure storage of enriched fuel assemblies complies only with the storage configurations allowed by TS 5.6.1 .c. contains Holtec Proprietary Information and is considered proprietary in its entirety. Attachment 4 contains the Holtec Proprietary Information Affidavit. The Affidavit, signed by Holtec as the owner of the information, sets forth the basis for which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of § 2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that the information which is proprietary to Holtec be withheld from public disclosure in accordance with 10 CFR 2.390.
This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2011-021 [Reference 1].
This submittal contains no new commitments and no revisions to existing commitments.
In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to the designated State of Florida official.
Should you have any questions regarding this submittal, please contact Mr. Christopher Wasik, St. Lucie Extended Power Uprate LAR Project Manager, at 772-467-7138.
L-2011-466 Page 3 of 3 I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.
Executed on o - - IvI Very truly yours, Rnard L. Anderson Site Vice President St. Lucie Plant Attachments (4) cc: Mr. William Passetti, Florida Department of Health
L-2011-466 Attachment 1 Page 1 of 3 Attachment I St. Lucie Unit 2 Technical Specification Section 5.6 Design Features - Fuel Storage - Criticality Revision To Proposed Change Submitted By FPL Letter L-2011-021 Regarding Extended Power Uprate License Amendment Request By letter L-2011-021 dated February 25, 2011, Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating License No. NPF-16 and revise the St. Lucie Unit 2 Technical Specifications (TS). The proposed amendment will increase the unit's licensed core thermal power level from 2700 megawatts thermal (MWt) to 3020 MWt and revise the Renewed Facility Operating License and TS to support operation at this increased core thermal power level. This represents an approximate increase of 11.85% and is therefore considered an Extended Power Uprate (EPU). Included in the EPU License Amendment Request (LAR) were changes to TS 5.6 DESIGN FEATURES - FUEL STORAGE - CRITICALITY. FPL is modifying the proposed TS changes as described below:
Description of the Change Subsequent to the submittal of the St. Lucie Unit 2 EPU LAR, FPL updated the fuel loading curves in order to preclude the need to extrapolate the values associated with the determination of the minimum required fuel assembly burnup. As a result, the changes proposed by FPL in EPU LAR Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specification Changes, Item 26, TS 5.6, DESIGN FEATURES - FUEL STORAGE -
CRITICALITY require that the entries under the "Coefficients" column in Table 5.6-1 be revised to reflect the new fuel loading curves.
TS Table 5.6-1 Minimum Burnup Coefficients - NEW TABLE 5.6-1 is replaced by the revised NEW TABLE 5.6-1 information provided in Attachment 2.
In addition to the above, FPL proposes to supplement EPU LAR Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specification Changes, TS 5.6, DESIGN FEATURES - FUEL STORAGE - CRITICALITY in consideration of a recent TS change proposed for St. Lucie Unit 1 relative to the inclusion of a 10B areal density criteria for Metamic inserts [Reference 1].
TS 5.6 DESIGN FEATURES - FUEL STORAGE - CRITICALITY is being revised to add TS 5.6.1.a.6 to read:
- 6. The Metamic neutron absorber inserts shall have a 10B areal density greater than or equal to 0.015 grams 10B/cm 2 .
FPL also proposes to revise EPU LAR Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specification Changes, TS 5.6, DESIGN FEATURES - FUEL STORAGE
- CRITICALITY, TS 5.6.1 .a.4 to ensure storage of enriched fuel assemblies complies only with the storage configurations allowed by TS 5.6.1.c.
Note that the marked-up TS pages in Attachment 2 are markups of the pages submitted in the EPU LAR. The remaining changes proposed for TS 5.6, as presented in EPU LAR Attachment 1, remain valid.
L-2011-466 Attachment 1 Page 2 of 3 Basis for the Change - Fuel Loading Curve The basis for the change is founded upon FPL updating the fuel loa'ding curves to preclude the need to extrapolate the values associated with determining the minimum required fuel assembly burnup. Attachment 3 provides Revision 2 to Holtec Report No. HI-2104753 "St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU Fuel" and is the technical basis for updated fuel loading curves. This analysis was previously submitted to the NRC under cover of Reference 2, as Appendix G to Attachment 5 of the EPU LAR. The results of this revised analysis are consistent with the results presented in the EPU LAR.
No Si-gnificant Hazards Consideration - Fuel Loading Curve This change precludes the need to extrapolate data from the fuel loading curves in order to determine the minimum required fuel assembly burnup. The changes to TS Table 5.6-1 are administrative and provide revised inputs which are used to perform minimum required burnup calculations for fuel assemblies. As such, the conclusions of EPU LAR Attachment 1, Section 5.2, No Significant Hazards Consideration, Item N., Design Features - Fuel Storage, remain valid. Accordingly, the proposed change 1) does not involve a significant increase in the probability or consequences of an accident previously evaluated, 2) does not create the possibility of a new or different kind of accident from any previously evaluated, and 3) does not result in a significant reduction in a margin of safety.
Environmental Evaluation - Fuel Loading Curve This change is administrative in that it provides data which is included in TS Table 5.6-1 which in turn is used to perform minimum required burnup calculations for fuel assemblies. The environmental considerations evaluation contained in the EPU LAR remain valid. Accordingly, the proposed license amendment is eligible for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 50.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed license amendment.
Basis for the Change - Areal Density of Metamic Inserts This change is based upon industry trends to include information in the TS pertaining to Areal Density Criteria for Metamic Inserts. This change is consistent with the spent fuel pool criticality analysis provided in Attachment 3, Holtec Report No. HI-2104753, "St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU Fuel," Revision 2.
No Significant Hazards Consideration - Areal Density of Metamic Inserts This change supplements the proposed EPU LAR Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specification Changes, TS 5.6, DESIGN FEATURES - FUEL STORAGE - CRITICALITY, with information relative to Areal Density Criteria for Metamic Inserts. The change to TS 5.6 is administrative and provides a statement that the Metamic neutron absorber inserts shall have a 10B areal density greater than or equal to 0.015 grams 10B/cm 2 . As such, the conclusions of EPU LAR Attachment 1, Section 5.2, No Significant Hazards Consideration, Item N., Design Features - Fuel Storage, remain valid. Accordingly, the proposed change 1) does not involve a significant increase in the probability or consequences of an accident previously evaluated, 2) does not create the possibility of a new or different kind of accident from any previously evaluated, and 3) does not result in a significant reduction in a margin of safety.
L-2011-466 Attachment 1 Page 3 of 3 Environmental Evaluation-Fuel Loading Curve - Areal Density of Metamic Inserts This change is administrative in that it provides supplemental information which is included in TS 5.6 that establishes a 10B areal density greater than or equal to 0.015 grams 10B/cm 2. The environmental considerations evaluation contained in the EPU LAR remain valid. Accordingly, the proposed license amendment is eligible for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 50.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed license amendment.
Basis for the Change - Removal of the TS Option to Develop New Configurations to Meet Criticality Requirements This TS change deletes portions of TS 5.6.1.a.4 of the proposed St. Lucie Unit 2, EPU LAR , Section 3.1, Renewed Facility Operating License and Technical Specification Changes, TS 5.6, DESIGN FEATURES - FUEL STORAGE - CRITICALITY to ensure storage of enriched fuel assemblies complies only with the storage configurations allowed by TS 5.6.1 .c.
No Significant Hazards Consideration - Removal of the TS Option to Develop New Configurations to Meet Criticality Reguirements This change revises TS 5.6.1.a.4 of the proposed EPU LAR Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specification Changes, TS 5.6, DESIGN FEATURES - FUEL STORAGE - CRITICALITY. The change to TS 5.6 is administrative. The proposed TS revision clarifies allowable fuel storage configurations. As such, the conclusions of EPU LAR Attachment 1, Section 5.2, No Significant Hazards Consideration, Item N., Design Features - Fuel Storage, remain valid. Accordingly, the proposed change 1) does not involve a significant increase in the probability or consequences of an accident previously evaluated,
- 2) does not create the possibility of a new or different kind of accident from any previously evaluated, and 3) does not result in a significant reduction in a margin of safety.
Environmental Evaluation-Fuel Loading Curve - Removal of the TS Option to Develop New Configurations to Meet Criticality Requirements This change is administrative in that it revises TS 5.6.1.a.4 of the proposed St. Lucie Unit 2, EPU LAR, Attachment 1, Section 3.1, Renewed Facility Operating License and Technical Specification Changes, TS 5.6, DESIGN FEATURES - FUEL STORAGE - CRITICALITY to clarify allowable fuel storage configurations. The environmental considerations evaluation contained in the EPU LAR remain valid. Accordingly, the proposed license amendment is eligible for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 50.22(b),
no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed license amendment.
References
- 1. R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-409), "Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts," October 14, 2011.
- 2. R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-021), "License Amendment Request for Extended Power Uprate," February 25, 2011, Accession No. ML110730116.
L-2011-466 Attachment 2 ATTACHMENT 2 St. Lucie Unit 2 Technical Specification Section 5.6 Design Features-Fuel Storage-Criticality Revision To Proposed Change Submitted By FPL Letter L-2011-021 Regarding Extended Power Uprate License Amendment Request Marked-up and Clean Technical Specification Pages This coversheet plus 7 pages
DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a. The spent fuel storage racks are designed and shall be maintained with:
- 1. A keff equivalent to less than 1.0 when flooded with unborated water, including a conservative allowance for biases and uncertainties as 500 described in Section 9.1 of the Updated Final Safety Analysis Report.
- 2. A e valent to less than or equal to 0.95 when flooded with water containi &2-9 ppm boron, including a conservative allowance for biases Analysis Report. as described in Section 9.1 of the Updated Final Safety and uncertainties
- 3. A no 96 inch center-to-center distance between fuel assemblies placed in the spent fuel pool storage racks and a nominal 8.80 inch center-to-center distance between fuel assemblies placed in the cask pit storage rack.
The eask put steFage Faek shall eentain nebltFen abseFbing FnateFial (BeFal)
EED_ý 4- Dotwoon ztaroa ruol a cm~iioo wnon inctaiioa in tno ~oont mci ~aai.
r i
- ii b- Fuel plaeed in Rogien I of the speont fuel ctcragc racko Shall be ctcrod in a configuration that Will assuro complianco with 5.6.1 a.1 and 6.6.1 a.2, abovo, withi the following considcrationo:
4-~ Frccsh fuel shall have a nominal avcragc U 235 onrichmecnt of Icco than or equal te 4.5 weight porcont.
2- The roactivity offoct of CE!!As placcd in fuel assemblics may be eonoidercd.
a-Thae -easioye 1 HiVaUioIinl Io rIIco of burnfablo abcorbcrc May be eens~deFed.
i dI 4-: no roocti~it. ..Tk.0t~,T TuOl acco mDiv I I I
-- A Durnuo
. ana aocav
..... ........... may j timo j 6-A
-- v eonsidc"*r a...... in Fgurcs 6.6 1 trogh
'c.pc ".6 1o.
e_ Fuel placcd in Region 11of the spent fuel storago racks shall be plaeed in a configuration that will 88Suro complianco with 6.6.1 a.1 and 5.6.1 a.2, abevc,-with the following conzidcratione:
4- Fuel placod in the Region 11spent fuel peol storage racks shall mooet the bu.RnIp and decay tome .. qUi..m.nts sp.. ifiod inFiguc 5.6 Ila or 6.6 lb.
Fuel placod in the Rg1i;e II cck Pit Getfrg ra1k shall moot the bunup rcquircmcntG Gpccifiod in Figurc 5.6 ifr The roactivity offoct ef GCEAs placcd in fuel assemblies may be considcrcd.
I The roactivity ee~e~eie cquivalencing cifocts of buffnablc absorboro may be ST. LUCIE - UNIT 2 5-4 Amendment No. 7, 96, 4-4-, 43, 4-
- 4. For storage of enriched fuel assemblies, requirements of Specification 5.6.1 .a.1 and 5.6.1 .a.2 shall be met by positioning fuel in the spent fuel pool storage racks consistent with the, requirements of Specification 5.6.1 .c configurotionc that have.~ been shawn to eemply with Spccificatiens 6.6.1 .a-.4 and 5.6.1 .a.2 using the mcthedeleg'; as dcccribed in Soction 0.1 of the Updated Finol Safety Anolysis Repcrt.
- 5. Fissile material, not contained in a fuel assembly lattice, shall be stored in accordance with the requirements of Specifications 5.6.1 .a. 1 and 5.6.1 .a.2.
- b. The cask pit storage rack shall contain neutron absorbing material (Boral) between stored fuel assemblies when installed in the spent fuel pool.
- c. Loading of spent fuel pool storage racks shall be controlled as described below.
- 1. The maximum initial planar average U-235 enrichment of any fuel assembly inserted in a spent fuel pool storage rack shall be less than or equal to 4.6 weight percent.
- 2. Fuel placed in Region 1 of the spent fuel pool storage racks shall comply with the storage pattern definitions of Figure 5.6-1 and the minimum burnup requirements as defined in Table 5.6-1. (See Specification 5.6.1 .c.7 for exceptions)
- 3. Fuel placed in Region 2 of the spent fuel pool storage racks shall comply with the storage pattern definitions or allowed special arrangement definitions of Figure 5.6-2 and the minimum burnup requirements as defined in Table 5.6-1.
(See Specification 5.6.1 .c.7 for exceptions)
- 4. The 2x2 array of fuel assemblies that span the interface between Region 1 and Region 2 of the spent fuel pool storage racks shall comply with the storage pattern definitions of Figure 5.6-3 and the minimum burnup requirements as defined in Table 5.6-1. The allowed special arrangements in Region 2 as shown in Figure 5.6-2 shall not be placed adjacent to Region 1.
(See Specification 5.6.1 .c.7 for exceptions)
- 5. Fuel placed in the cask pit storage rack shall comply with the storage pattern definitions of Figure 5.6-4 and the minimum burnup requirements as defined in Table 5.6-1. (See Specification 5.6.1 .c.7 for exceptions)
- 6. The same directional orientation for Metamic inserts is required for contiguous groups of 2x2 arrays where Metamic inserts are required.
- 7. Fresh or spent fuel in any allowed configuration may be replaced with non-fuel hardware, and fresh fuel in any allowed configuration may be replaced with a fuel rod storage basket containing fuel rod(s). Also, storage of Metamic inserts or control rods, without any fissile material, is acceptable in locations designated as completely water-filled cells.
DESIGN FEATURES (continued)
CRITICALITY (continued maximum planar averaqe 5.6.1 d. The new fuel storage racks are designed for dry storage of u ,radiated fuel assemblies having aa -235 enrichment less than or equal to -weight percent, while maintaining a keff of less than or equal to 0.98 under the most reactive condition.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.
CAPACITY 1491 5.6.3 The spent fuel pool storage racks are design and shall be maintained with a storage capacity limited to no more than -- 1-43-fuel assemblies, and the cask pit storagejrack is designed and shall be maintained with a storage capacity limited to no more than 225 fuel assemblies. The total Unit 2 spent fuel pool and cask pit storage capacity is limited to no more than fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 1716 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
- 6. The Metamic neutron absorber inserts shall have a 10B areal density greater than or equal to 0.015 grams 1°B/cm 2 .
ST. LUCIE - UNIT 2 5-4A Amendment No. -7,494,4,36
NEW TBLE .6-1 TABLE 5.6-1 Minimum Burnup Coefficients Fuel Type Cooling Time Coefficients (Years) A BC "1 0 -33.4237 25.6742 -1.6:8f 2 0 -25.3198 14.3200 -M042 3 0 -23.4150 16.2050 /-0.5500 4 0 -33.6414 25.0670 -1.5551 2.5 -32.3764 23.9988 -1.5075 5 -30.9234 22.9382,/ -1.4372
",0 -28.4951 21.1,54"1 -1.3029 1\ -27.2024 2 .802 -1.2479 20 -25.2009 ,18.6218 -1.0364 5 0 -24.8402 23.5991 -1.2082 2.5 -23.0170 21.6493 -1.0298 5 "_.1.929, 20.6257 -0.9730 10 -2 0 3 19.0808 -0.9022 15 -1 . 3 18.5429 -0.9129 20 X-1 8.748-3 0 17.7308 -0.8390 6 0 -32.4900 25.3077 -1.5518 2.5 -31.1598 23.9185 -1.4435 5 -29.2169 "\2.5424 -1.3274 1, -26.8886 2N.662 -1.1425
,f5 -25.5703 19.7 9 -1.1129
_ 20 -24.5754 18.905(ý, -1.0147 7 0 -24.6989 24.1660 -1.2578 2.5 -23.0399 22.3047 -1.0965 5 -21.3290 20.7413 "-0.9613 10 -20.0836 19.4780 - .949 15 -19.2480 18.5880 -0.8 5 20 -18.6424 18.1241 -0.8950(\
8 0 -47.5000 12.5000 0.0000 NOTES:
- 1. To qualify in a fuel type, the calculated burnup of a fuel assembly must exceed the "minimum burnup" determined for the "cooling time" and "maximum initial planar enrichment" of the fuel assembly. The "minimum burnup" for any fuel type is determined from the following polynomial function:
BU = A + B*E + C*E 2 , where:
BU = Minimum Burnup (GWD/MTU)
E = Maximum Initial Planar Average Enrichment (weight percent U-235)
A, B, C = Coefficients for each fuel type
- 2. Interpolation between values of cooling time is not permitted.
ST. LUCIE - UNIT 2 5-4o Amendment No. xxx
The data presented below replaces the data in NEW TABLE 5.6-1, there are no changes to the balance of the table.
FuelType Cooling Time Coefficients (Years) A B C 1 0 -33.4237 25.6742 -1.6478 2 0 -25.3198 14.3200 -0.4042 3 0 -23.4150 16.2050 -0.5500 0 -33.2205 24.8136 -1.5199 2.5 -31.4959 23.4776 -1.4358 5 -30.4454 22.7456 -1.4147 10 -28.4361 21.2259 -1.2946 15 -27.2971 20.3746 -1.2333 20 -26.1673 19.4753 -1.1403 0 -24.8402 23.5991 -1.2082 2.5 -22.9981 21.6295 -1.0249 5 -21.8161 20.5067 -0.9440 10 -20.0864 19.0127 -0.8545 15 -19.4795 18.3741 -0.8318 20 -18.8225 17.7194 -0.7985 0 -33.1568 26.0086 -1.7227 2.5 -30.6688 23.6229 -1.4025 5 -29.2169 22.5424 -1.3274 10 -27.2539 21.0241 -1.2054 15 -25.7327 19.8655 -1.1091 20 -25.2717 19.5222 -1.1163 0 -24.6989 24.1660 -1.2578 2.5 -23.0399 22.3047 -1.0965 5 -21.2473 20.6553 -0.9403 10 -20.1775 19.5506 -0.9015 15 -19.4037 18.6626 -0.8490 20 -18.3326 17.7040 -0.7526 8 0 -43.4750 11.6250 0.0000
DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a. The spent fuel storage racks are designed and shall be maintained with:
- 1. A keff equivalent to less than 1.0 when flooded with unborated water, including a conservative allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report.
- 2. A keff equivalent to less than or equal to 0.95 when flooded with water containing 500 ppm boron, including a conservative allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report.
- 3. A nominal 8.965 inch center-to-center distance between fuel assemblies placed in the spent fuel pool storage racks and a nominal 8.80 inch center-to-center distance between fuel assemblies placed in the cask pit storage rack.
- 4. For storage of enriched fuel assemblies, requirements of Specification 5.6.1 .a.1 and 5.6.1 .a.2 shall be met by positioning fuel in the spent fuel pool storage racks consistent with the requirements of Specification 5.6.1 .c.
- 5. Fissile material, not combined in a fuel assembly lattice, shall be stored in accordance with the requirements of Specifications 5.6.1 .a.1 and 5.6.1 .a.2.
10
- 6. The Metamic neutron absorber inserts shall have a B areal density greater than or equal to 0.015 grams 10B/cm 2 .
- b. The cask pit storage rack shall contain neutron absorbing material (Boral) between stored fuel assemblies when installed in the spent fuel pool.
- c. Loading of spent fuel pool storage racks shall be controlled as described below.
- 1. The maximum initial planar average U-235 enrichment of any fuel assembly inserted in a spent fuel pool storage rack shall be less than or equal to 4.6 weight percent.
- 2. Fuel placed in Region I of the spent fuel pool storage racks shall comply with the storage pattern definitions of Figure 5.6-1 and the minimum burnup requirements as defined in Table 5.6-1. (See Specification 5.6.1.c.7 for exceptions)
- 3. Fuel placed in Region 2 of-the spent fuel pool storage racks shall comply with the storage pattern definitions or allowed special arrangements definitions of Figure 5.6-2 and the minimum burnup requirements as defined in Table 5.6-1. (See Specification 5.6.1.c.7 for exceptions)
ST. LUCIE - UNIT 2 5-4 Amendment No. 7, 96, 404, 435, 4W8
TABLE 5.6-1 Minimum Burnup Coefficients Fuel Type Cooling Time Coefficients (Years) A B C 1 0 -33.4237 25.6742 -1.6478 2 0 -25.3198 14.3200 -0.4042 3 0 -23.4150 16.2050 -0.5500 0 -33.2205 24.8136 -1.5199 2.5 -31.4959 23.4776 -1.4358 5 -30.4454 22.7456 -1.4147 10 -28.4361 21.2259 -1.2946 15 -27.2971 20.3746 -1.2333 20 -26.1673 19.4753 -1.1403 0 -24.8402 23.5991 -1.2082 2.5 -22.9981 21.6295 -1.0249 5 5 -21.8161 20.5067 -0.9440 10 -20.0864 19.0127 -0.8545 15 -19.4795 18.3741 -0.8318 20 -18.8225 17.7194 -0.7985 0 -33.1568 26.0086 -1.7227 2.5 -30.6688 23.6229 -1.4025 5 -29.2169 22.5424 -1.3274 10 -27.2539 21.0241 -1.2054 15 -25.7327 19.8655 -1.1091 20 -25.2717 19.5222 -1.1163 0 -24.6989 24.1660 -1.2578 2.5 -23.0399 22.3047 -1.0965 5 -21.2473 20.6553 -0.9403 10 -20.1775 19.5506 -0.9015 15 -19.4037 18.6626 -0.8490 20 -18.3326 17.7040 -0.7526 8 0 -43.4750 11.6250 0.0000 NOTES:
- 1. To qualify in a fuel type, the calculated burnup of a fuel assembly must exceed the "minimum burnup" determined for the "cooling time" and "maximum initial planar enrichment" of the fuel assembly. The "minimum burnup" for any fuel type is determined from the following polynomial function:
BU = A + B*E + C*E2 , where:
BU = Minimum Burnup (GWD/MTU)
E = Maximum Initial Planar Average Enrichment (weight percent U-235)
A, B, C = Coefficients for each fuel type
- 2. Interpolation between values of cooling time is not permitted.
ST. LUCIE - UNIT 2 5-4o Amendment No.
L-2011-466 Attachment 4 ATTACHMENT 4 St. Lucie Unit 2 Technical Specification Section 5.6 Design Features - Fuel Storage - Criticality Revision To Proposed Change Submitted By FPL Letter L-2011-021 Regarding Extended Power Uprate License Amendment Request Holtec Affidavit Pursuant To 10 CFR 2.390 This coversheet plus 5 pages
m m M Mm Holtec Center, 555 Lincoln Drive West, Marlton, NJ 08053 H O LTEC INTERNATIONAL Telephone (856) 797-0900 Fax (856) 797-0909 Holtec International Document ID 1867-AFFI-04 AFFIDAVIT PURSUANT TO 10 CFR 2.390 I, Thomas V. Fitzpatrick, being duly sworn, depose and state as follows:
(1) I have reviewed the information described in paragraph (2) which is sought to be withheld, and am authorized to apply for its withholding.
(2) The information sought to be withheld is information provided with Holtec letter 1867008, specifically Holtec Report HI-2104753 which contains Holtec Proprietary information and is appropriately marked as such.
(3) In making this application for withholding of proprietary information of which it is the owner, Holtec International relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4) and the Trade Secrets Act., 18 USC Sec. 1905, and NRC regulations 10CFR Part 9.17(a)(4), 2.390(a)(4), and 2.390(b)(1) for "trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here sought is all "confidential commercial information", and some portions also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d1280 (DC Cir. 1983).
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Holtec International Document ID 1867-AFFI-04 AFFIDAVIT PURSUANT TO 10 CFR 2.390 (4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by Holtec's competitors without license from Holtec International constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.
- c. Information which reveals cost or price information, production, capacities, budget levels, or commercial strategies of Holtec International, its customers, or its suppliers;
- d. Information which reveals aspects of past, present, or future Holtec International customer-funded development plans and programs of potential commercial value to Holtec International;
- e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraph 4.b, above.
(5) The information sought to be withheld is being submitted to the NRC in confidence. The information (including that compiled from many sources) is of a sort customarily held in confidence by Holtec International, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by Holtec International. No public disclosure has been made, and it is not available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or 2 of 5
Holtec International Document ID 1867-AFFI-04 AFFIDAVIT PURSUANT TO 10 CFR 2.390 proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge.
Access to such documents within Holtec International is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his designee), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation.
Disclosures outside Holtec International are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information classified as proprietary was developed and compiled by Holtec International at a significant cost to Holtec International. This information is classified as proprietary because it contains detailed descriptions of analytical approaches and methodologies not available elsewhere. This information would provide other parties, including competitors, with information from Holtec International's technical database and the results of evaluations performed by Holtec International. A substantial effort has been expended by Holtec International to develop this information. Release of this information would improve a competitor's position because it would enable Holtec's competitor to copy our technology and offer it for sale in competition with our company, causing us financial injury.
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Holtec International Document ID 1867-AFFI-04 AFFIDAVIT PURSUANT TO 10 CFR 2.390 (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to Holtec International's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of Holtec International's comprehensive spent fuel storage technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology, and includes development of the expertise to determine and apply the appropriate evaluation process.
The research, development, engineering, and analytical costs comprise a substantial investment of time and money by Holtec International.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
Holtec International's competitive advantage will be lost if its competitors are able to use the results of the Holtec International experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to Holtec International would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive Holtec International of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.
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Holtec International Document ID 1867-AFFI-04 AFFIDAVIT PURSUANT TO 10 CFR 2.390 STATE OF NEW JERSEY )
) ss:
COUNTY OF BURLINGTON )
Mr. Thomas V. Fitzpatrick, being duly sworn, deposes and says:
That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of her knowledge, information, and belief.
Executed at Marlton, New Jersey, this 2 nd day of November, 2011.
Thomas V. Fitzpatrick Holtec International Subscribed and sworn before me this day of 2011.
of MAIL of2011. 5 i si pe tAV tow 5 of 5