Letter Sequence Supplement |
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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
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Text
Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 FPL.
April 19, 2012 L-2012-177 10 CFR 50.90 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 Supplemental Response to NRC Mechanical and Civil Engineering Branch (EMCB) Regarding Extended Power Uprate License Amendment Request
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) Email from T. Orf (NRC) to C. Wasik (FPL), "St. Lucie 2 EPU draft RAIs -
Mechanical & Civil Engineering Branch (EMCB)," January 13, 2012.
(3) R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2012-059),
"Response to NRC Mechanical and Civil Engineering Branch (EMCB) Request for Additional Information Regarding Extended Power Uprate License Amendment Request," February 29, 2012, Accession No. ML12065A148.
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).
By email from the NRC Project Manager dated January 13, 2012 [Reference 2],
additional information was requested by the NRC staff in the Mechanical and Civil Engineering Branch (EMCB) to support their review of the EPU License Amendment Request (LAR). The request for additional information (RAI) identified 47 questions. By letter L-2012-059 dated February 29, 2012 [Reference 3], FPL provided the requested information. In that letter, FPL also committed to provide a supplemental response to RAI EMCB-1 in a separate submittal. The attachment to this letter provides FPL's first supplemental response to RAI EMCB-1.
Aoo0La 4 .
an FPL Group company
L-2012-177 Page 2 of 2 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.
I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge.
Executed on 1"7- 4pr; i-AC,/.2 Very truly yours, hard L.nde Site Vice President St. Lucie Plant Attachment (1) cc: Mr. William Passetti, Florida Department of Health
L-2012-177 Attachment Page 1 of 5 Supplemental Response to NRC Mechanical and Civil Engineering Branch (EMCB) Request for Additional Information The following information is provided by Florida Power & Light (FPL) in response to the U. S.
Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI). This information was requested to support Extended Power Uprate (EPU) License Amendment Request (LAR) for St. Lucie Nuclear Plant Unit 2 that was submitted to the NRC by FPL via letter (L-2011-021) dated February 25, 2011, Accession Number ML110730116.
In an email dated January 13, 2012 from NRC (Tracy Oft) to FPL (Chris Wasik),
Subject:
St.
Lucie 2 EPU draft RAIs - Mechanical & Civil Engineering Branch (EMCB), the NRC requested additional information regarding FPL's request to implement the EPU. The RAI consisted of forty-seven (47) questions from the NRC's Mechanical and Civil Engineering Branch (EMCB).
By letter L-2012-059 dated February 29, 2012, Accession No. ML12065A148, FPL provided the requested information. In that letter, FPL also committed to provide a supplemental response to RAI EMCB-1 in a separate submittal. This attachment provides FPL's first supplemental response to RAI EMCB-1.
EMCB-1 The staff requests that the licensee provide assurance that all structural modifications and/or additions have been identified and designed and that all structural evaluations and required design calculations to demonstrate that all systems, structures and components (SSCs) credited to and/or affected by the proposed extended power uprate (EPU) have been completed and controlled documentation exists which finds said SSCs structurally adequate to perform their intended design functions under EPU conditions.
Supplemental Response:
As described in letter L-2012-059, FPL advised the NRC that with the exception of the EPU modifications listed below, applicable safety related and/or seismic piping and associated structural evaluations and design calculations for affected systems, structures and components (SSCs) credited to and/or affected by the proposed EPU have been completed. The following EPU modifications were identified as not being complete at that time:
" Main Steam, Feedwater, and Condensate Pipe Support Modification,
" Chemical and Volume Control System (CVCS) Vent Modification,
- Control Room Air Conditioning Margin Improvement.
This supplemental response provides the completed design details for the first two EPU modifications.
Piping stress summary data for the safety-related and/or seismic main steam and feedwater piping systems impacted by EPU is provided in Table 1. A list of the safety-related and/or seismic main steam and feedwater pipe support modifications that are required for the EPU is provided in Table 2. Note that the attachment steel calculations for the main steam and feedwater piping support modifications located in the Turbine Building are not complete at this time. A supplemental response will be submitted to NRC providing confirmation that these structural steel calculations are complete.
L-2012-177 Attachment Page 2 of 5 There are no safety-related and/or seismic piping or pipe support modifications for the St. Lucie Unit 2 condensate piping system.
Piping stress summary data for the chemical and volume control system (CVCS) vent modification is provided in Table 3 and a list of the associated pipe support modifications is provided in Table 4.
Design information regarding the control room air conditioning margin improvement modification is not complete. Design details regarding this EPU modification will be provided to NRC in a supplemental response.
L-2012-177 Attachment Page 3 of 5 Table 1 Main Steam and Feedwater Piping Stress Summary at EPU Conditions Piping Analysis Loading Existing EPU Design Psiptiong ANai 3 Condition Stress Stress Allowable s Margin Description (Note 3) (Note 2) (psi) (psi) Stress (psi) (Note 1)
Main Steam Piping from Equation 8 6,624 9,062 15,000 0.60 SG-2A to Containment Equation 9U 4,169 10,975 18,000 0.61 Penetration P-1 Equation 9F 4,582 10,600 36,000 0.29 Equation 10 8,208 7,986 22,500 0.35 Equation 8 6,613 8,711 15,000 0.58 Main Steam Piping from Equation 9U 4,755 11,025 18,000 0.61 SG-2B to Containment Penetration P-2 Equation 9F 5,033 11,037 36,000 0.31 Equation 10 8,427 7,943 22,500 0.35 Equation 8 7,828 7,926 15,000 0.53 Main Steam Piping from Equation 9U 9,567 13,170 18,000 0.73 Containment Penetrations P-1 and P-2 to HP Turbine Equation 9F 5,693 13,186 36,000 0.37 Equation 10 19,149 20,535 22,500 0.91 Equation 8 5,222 6,061 15,000 0.40 Feedwater Piping from Containment Penetration Equation 9U 8,840 10,013 18,000 0.56 P-3 to SG-2A Equation 9F 8,276 9,477 36,000 0.26 Equation 10 14,089 12,096 22,500 0.54 Feedwater Piping from Equation 8 5,664 6,325 15,000 0.42 Containment Penetration Equation 9U 7,567 9,010 18,000 0.50 P-4 to SG-2nn Equation 9F 9,144 9,339 36,000 0.26 Equation 10 9,330 11,304 22,500 0.50 Feedwater Piping from Equation 8 8,321 8,730 15,000 0.58 Feedwater Pumps to Equation 9U 7,371 13,911 18,000 0.77 Containment Penetrations Equation 9F 7,371 13,924 36,000 0.39 P-3 and P-4 Equation 10 16,119 17,950 22,500 0.80 Notes:
- 1. Stress Interaction Ratio (also called "Design Margin") is based on the ratio of EPU stress divided by the Allowable stress.
- 2. The pipe stress analysis equation numbers listed in this table correspond to ASME Section III, NB-3650, NC-3650, and ND-3650 equation numbers.
- 3. Description is based on pipe stress analysis segment of a given system included in the analysis.
L-2012-177 Attachment Page 4 of 5 Table 2 Main Steam and Feedwater Pipe Support Modifications for EPU Conditions Support Mark Pipe Size Building Modification Description Item Number (in.) Location 1 MS-4100-6080 MS 34 Reactor Containment New support 2 MS-4100-6080 MVS 34 Reactor New support 2 MS-4101-315A MVS 34 Containment New support 3 MS-4102-274 MS 38 Turbine Bldg Add weld 4 MS-4102-32B MS 38 Turbine Bldg Add cover plate 5 MS-4102-48 MS 38 Turbine Bldg Add tube steel brace 6 MS-4102-3910 MS 38 Turbine Bldg Add weld 7 BF-4004-258 FW 20 Turbine Bldg Add weld 8 BF-4004-38 FW 20 Turbine Bldg Replace snubbers Notes:
FW = Feedwater MS = Main Steam Table 3 Maximum Piping Stress for Chemical and Volume Control (CVCS) Vent Modification Code Existing EPU Allowable Equation Maximum Maximum Stress1 (psi) Stress Ratio Stress (psi) Stress (psi)
Equation 8 4835 4979 17200 .0.289 Equation 9B 6386 12037 20640 0.583 Equation 9D. 6974 17186 41280 0.416 Equation 10 13222 9950 27800 0.358 Note:
- 1. The allowable stress values are based on a design temperature of 250 0F.
L-2012-177 Attachment Page 5 of 5 Table 4 Pipe Supports Affected by Chemical and Volume Control (CVCS) Vent Modification Pipe Support Mark Piping System Number Support Attribute Of Concern Resolution CH-136-Ri Added pipe line CH-1 011 New Support CH-136-R2 Added pipe line CH-1 011 New Support CH-1 36-R3 Added pipe line CH-1 011 New Support CH-136-R4 Added pipe line CH-1012 New Support CH-136-R5 Added pipe line CH-1 004 New Support CH-136-R6 Added pipe line CH-1 004 New Support CH-136-R7 Added pipe line CH-1 019 New Support CH-136-R8 Added pipe line CH-1 017 New Support CH-136-R9 Added pipe line CH-1019 New Support CH-136-RlO Added pipe line CH-1007 New Support CH-136-R11 Added pipe line CH-1013 New Support CH-136-R12 Added pipe line CH-1 013 New Support CH-136-R13 Added pipe line CH-1 013 New Support CH-136-R14 Added pipe line CH-1 013 New Support CH-136-R15 Added pipe line CH-1014 New Support CH-136-R16 Added pipe line CH-1005 New Support Chemical and Volume Control CH-136-R17 Added pipe line CH-1020 New Support System (CVCS) CH-136-R18 Added pipe line CH-1 015 New Support Vent Modification CH-136-R19 Added pipe line CH-1015 New Support CH-136-R20 Added pipe line CH-1 015 New Support CH-136-R21 Added pipe line CH-1 015 New Support CH-136-R22 Added pipe line CH-1 016 New Support CH-136-R23 Added pipe line CH-1 006 New Support CH-136-R24 Added pipe line CH-1 006 New Support CH-136-R25 Added pipe line CH-1 006 New Support CH-136-R26 Added pipe line CH-1 021 New Support CH-136-R27 Added pipe line CH-1 018 New Support CH-136-R28 Added pipe line CH-1 008 New Support CH-136-R29 Added pipe line CH-1 008 New Support CH-2082-39 Existing Support Acceptable CH-2082-1 01 Existing Support Acceptable CH-2082-106 Existing Support Acceptable CH-2082-115 Existing Support Acceptable CH-2082-126 Existing Support Acceptable