Letter Sequence Request |
---|
|
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
|
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
[Table View] |
|
---|
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] |
Text
0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 FFIL December 27, 2011 L-2011-524 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 Response to NRC Steam Generator Tube Integrity and Chemistry Branch Request for Additional Information 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 1 EPU - draft RAIs SG Tube Integrity and Chem. Engineering Branch (CSGB)," October 28, 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).
By email from the NRC Project Manager dated October 28, 2011 [Reference 2],
additional information related to MetamicTm inserts was requested by the NRC staff in the Steam Generator Tube Integrity and Chemical Engineering Branch (CSGB) to support their review of the St. Lucie Unit 1 EPU License Amendment Request (LAR).
Subsequent conversations with the NRC Project Manager requested that the St. Lucie Unit 1 RAIs also be applied to the St. Lucie Unit 2 EPU LAR. The request for additional information (RAI) identified six questions. The response to these RAIs is provided in the attachment to this letter.
an FPL Group company
L-2011-524 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. However, the attachment to this letter contains a revision to the EPU LAR commitment pertaining to the spent fuel pool MetamicTM insert surveillance program. In accordance with the manufacturer's recommendations, FPL is revising the EPU LAR Attachment 5, Section 2.8.6.2.2.6 commitment related to physical measurement inspections. FPL will perform physical measurement inspections on coupons, not on the MetamicTM inserts as previously committed.
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 Al - l4.oe.le.r -,to I I Very truly yours, Richard L. Ande o Site Vice President St. Lucie Plant Attachment cc: Mr. William Passetti, Florida Department of Health
L-2011-524 Attachment Page 1 of 6 Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information The following information is provided by Florida Power & Light Company (FPL) in response to the U. S. Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI). This information was requested to support the review of the Extended Power Uprate (EPU) License Amendment Request (LAR) for St. Lucie 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 October 28, 2011 from T. Orf (NRC) to C. Wasik (FPL),
Subject:
St. Lucie 1 EPU - draft RAIs SG Tube Integrity and Chem. Engineering Branch (CSGB), the NRC staff requested additional information regarding FPL's request to implement the St. Lucie Unit 1 EPU.
Subsequent conversations with the NRC Project Manager requested that the St. Lucie Unit 1 RAIs also be applied to the St. Lucie Unit 2 EPU LAR. The RAI consisted of six questions from the NRC's Steam Generator Tube Integrity & Chemical Engineering Branch (CSGB). These six RAI questions and the FPL responses are documented below.
CSGB-4 The letter submitted on November 22, 2010 cites Holtec Report HI-2043215, Source for Metamic Performance Assessment, Revision 1. Please provide this report.
Response
Holtec International (Holtec) has submitted Holtec Report HI-2043215 Revision 3, "Sourcebook for Metamic Performance Assessment" (Proprietary), directly to the NRC Document Control Desk via Holtec letter dated December 2, 2011. This is the latest revision and was used to support the EPU LAR as stated in FPL letter L-2011-466, "Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification 5..6, Design Features - Fuel Storage -
Criticality," November 4, 2011 (ML11314A111), Attachment 3, Holtec Report No. HI-2104753, Rev. 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," Section 10, Reference 18.
CSGB-5 Provide a description of how the Metamic TM inserts will be manufactured:
- a. Specifically, will the inserts be a formed insert design, welded design, a combination design incorporating both techniques, or a separate technique from the ones listed.
- b. Additionally, how will the surveillance program capture all of the areas of interest in the different design types of inserts used (i.e., base material, welds, heat affected zones, bend areas, galvanic coupling).
Response
- a. The inserts are a combination design. For each insert, a single MetamicTM panel is formed into a chevron cross-section with an inward-projecting top flange. No welding of or to MetamicTM is performed. A head piece (landing element) made from several aluminum parts is attached to the top flange of the formed MetamicTM using a pinned connection.
L-2011-524 Attachment Page 2 of 6
- b. As discussed in the EPU LAR Attachment 5, Section 2.8.6.2.2.6, the surveillance program consists of three major parts; visual inspection, physical measurements and neutron attenuation testing. The surveillance program is discussed in more detail in the response to RAI CSGB-7. The items listed in RAI question 5.b. are covered by the visual inspection program. Five inserts are selected for the visual inspection. The visual in-service inspection method will be a camera-aided visual examination of the insert base material, its edges, regions of the insert where base material has been formed (i.e., bent to shape),
as well as any connection to the base metal. Non-welded connections will also be examined. Interior and exterior bend radii and front and back faces of the insert will be inspected. Visual examination is sufficient to detect evidence of galvanic coupling, cracking, corrosion pitting or other gross damage. As there are no welds to the Metamic material, there are no welds or heat affected zones requiring inspection.
CSGB-6 Specify the following:
- a. Material composition of the MetamicTM inserts (i.e. weight percent of boron carbide, type of aluminum alloy used in the Metamic TM , and the areal density of the B-10),
- b. Physical dimensions of the inserts,
- c. Material of the landing element,
- d. The weld material to be used to attach the MetamicTM panel to the landing element,
- e. The type of weld used to attach the panel to the landing element.
Response
- a. The MetamicTM used for the inserts shall have a boron carbide weight percentage of 24.5% minimum. Alloy 6061 aluminum powder is used in the manufacture of MetamicTM.
The areal density of B-10 in the inserts shall be 0.0160 gm/cm2 nominal and 0.0150 gm/cm2 minimum.
- b. The overall length of the inserts is approximately 156.5 inches. The cross-section width of the inserts is approximately 8.3 inches square. The MetamicTM panel thickness is nominally 0.070 inches thick.
- c. The landing element material is constructed from 6061-series aluminum.
- d. The formed MetamicTM panel is attached to the head piece (landing element) using a pinned connection. The top flange of the formed MetamicTM panel is sandwiched between upper and lower aluminum pieces. There are four aluminum pins, passing through holes in the top flange of the MetamicTM panel, which are welded to the upper and lower aluminum pieces. There is no welding of or to MetamicTM.
- e. The formed Metamic TM panel is attached to the head piece (landing element) using a pinned connection. There is no welding of or to MetamicTM.
L-2011-524 Attachment Page 3 of 6 CSGB-7 For each element of the surveillance program (visual inspection, physical measurement, and neutron attenuation testing), provide details on how the results from the performance of that element will measure the expected material performance.
The details should include, at a minimum, the following:
- a. The number of inserts to be examined during each surveillance and the criterion for expansion of the number of inserts to be examined during that surveillance and future surveillances,
- b. The selection criteria for the inserts inspected/measured and rationale for their selection,
- c. Detailed description of how. of each element will be performed,
- d. Acceptance criteria and the bases for these criteria.
Response
- a. As described in EPU LAR Attachment 5, Section 2.8.6.2.2.6, the visual inspections will be at 4, 8, 12, 20, and 30 years after initial installation and the physical measurement inspections and neutron attenuation testing will be at 4, 12, 20 and 30 year intervals. FPL intends to schedule MetamicTM insert surveillance campaigns to avoid refueling intervals and periods when fresh fuel is stored in fuel pool racks in preparation for refueling.
In-service inspections will be performed on installed MetamicTM inserts and coupons; with five inserts selected for visual inspection.
In accordance with the manufacturer's recommendations, FPL is revising the EPU LAR Attachment 5, Section 2.8.6.2.2.6 commitment related to physical measurement inspections. FPL will perform physical measurement inspections on coupons, not on the MetamicTM inserts as previously committed. Two coupons will be used for both physical measurement inspections and neutron attenuation testing.
Should insert anomalies be noted on the visual inspections, then an additional set of five inserts will be inspected. Issues identified during the visual inspections will be included in the FPL corrective action program for investigation and resolution.
Should physical measurement inspections of the coupons result in a failure to meet acceptance criteria for thickness, then an additional two coupons will be inspected. Issues identified during physical measurements inspection will be included in the FPL corrective action program for investigation and resolution.
Should a coupon failure to meet acceptance criteria during neutron attenuation testing, then an additional two coupons will be tested. Issues identified during neutron attenuation testing will be included in the FPL corrective action program for investigation and resolution.
Should MetamicTM inserts no longer be required for control of neutron multiplication within the spent fuel pool (e.g., as a result of vacating the fuel pool to dry storage), insert surveillance and inspections may be terminated.
L-201 1-524 Attachment Page 4 of 6
- b. MetamicTM inserts inspected as part of the initial surveillance campaign will be selected by considering the following criteria and generally selecting the most challenging conditions:
- Results of pre-installation inspections (e.g., select inserts that have pre-existing conditions),
Experience gained during installation (e.g., select inserts that required higher insertion or removal forces),
Spatial variations in cooling water flow within the pool, specifically considering effects of the fuel pool cooling system suction and discharge piping,
- Storage arrangements and the characteristics of fuel assemblies adjacent to each insert, especially heat generation rates,
- Noteworthy or unique aspects of St Lucie fuel pool-related operating experience during the in-service interval, such as atypical water chemistry or impact by a foreign object, and
- Relevant operating experience from other plants.
The coupon selection criteria is discussed in the response to CSGB-8.
Development of follow-on inspection campaigns will be determined by results from this initial in-service inspection. Some of the same sample of inserts/coupons may be included in future in-service inspections.
- c. The visual in-service inspection method will be a camera-aided visual examination of the insert base material, its edges, regions of the insert where base material has been formed (i.e., bent to shape), as well as any connection to the base metal. Non-welded connections will also be examined. Interior and exterior bend radii and front and back faces of the insert will be inspected. Visual examination is sufficient to detect evidence of cracking, corrosion pitting or other gross damage. Inspections may be performed on inserts underwater, after they have been removed from their storage rack cell location, or inserts may be temporarily removed from the fuel pool water, if radiation and surface contamination levels permit.
Physical measurement inspections (length, width, thickness, and weight) and neutron attenuation testing will be performed on the MetamicTM coupons. In accordance with manufacturer's recommendations, two coupons will be inspected at each surveillance interval.
d.. The acceptance criteria and the bases for these criteria include the following:
- As discussed in the EPU LAR Attachment 5, Section 2.8.6.2.2.6, visual inspection of MetamicTM inserts is performed to assess the physical condition of the material. Key goals of these inspections are to identify any surfaced-based abnormalities, such as, through-wall corrosion/damage, bubbling, blistering, corrosion pitting, cracking, or flaking.
- Of the physical measurement inspections (length, width, thickness, and weight), the most important is the thickness measurement as a monitor of potential swelling. The acceptance criterion is based on manufacturer's recommendations and is that an increase in thickness at any point should not exceed 25% of the initial thickness at that point. The remaining measurement parameters (length, width, and weight) serve a supporting role and should be examined for early indications of the potential onset of
L-2011-524 Attachment Page 5 of 6 neutron absorber degradation, if any, that would suggest the need for further attention and possibly a change in the measurement schedule. This is consistent with manufacturer's recommendations.
The acceptance criteria for neutron attenuation testing specified in the proposed Technical'Specifications (TS). Proposed TS 5.6.1.a.6 contains the acceptance criteria for neutron attenuation testing and states that B-10 areal density is to be greater than or equal to 0.015 grams B-10 per square centimeter as stated in FPL letter L-2011-466, "Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification 5.6, Design Features - Fuel Storage - Criticality,"
November 4, 2011 (ML11314A111).
Failure to meet the acceptance criteria for either of these two physical measurement parameters (coupon thickness or B-10 areal density) requires investigation and engineering evaluation and early retrieval and measurement of two additional coupons to provide corroborative evidence that the indicated change(s) is real. If the deviation is determined to be real, an engineering evaluation shall be performed to identify further testing or any corrective action that may be necessary.
CSGB-8 Provide the location(s) in the spent fuel pool where the Metamic M T
coupons will be placed and a rationale for that location.
Response
The coupon surveillance program will monitor how the MetamicTM absorber material properties change over time under the radiation, chemical and thermal environment found in the spent fuel pool (SFP) to ensure that the physical and chemical properties of MetamicTM behave in a similar manner as that found in the MetamicTM qualification data.
A coupon tree will be installed that holds 10 coupons in the SFP. The coupons are identical in composition and manufacturing process as the MetamicTM inserts. The coupon tree will be placed in a SFP cell in a location that will ensure a representative dose to the coupons. In M
T addition, this location will simulate the flow characteristics, and pool chemistry that the Metamic inserts placed in the SFP will experience. The cell location will be in Region 2 of the SFP which typically has highly burned permanently discharged fuel.
CSGB-9 Provide details about baseline examinations that will be performed on the MetamicTM inserts prior to being placed in the spent fuel pool (i.e. areal density, dimensional measurements, weight, visual inspections, and photographs). In addition, discuss whether the baseline inspections will be performed at the fabrication facility, at the site, or at both locations.
Response
Baseline examinations will be performed at the fabrication facility and include determination of B4 C weight percentage, dimensional measurements, weight measurement, visual examination for any MetamicTM panel defects (inclusions, cracks, etc.), and operability checks (interface with handling tool). The following physical measurements are made:
L-2011-524 Attachment Page 6 of 6 Dimensional Measurement Information Recorded Insert length As-Found Values Metamic TM panel width As-Found Values MetamicTM thickness As-Found Values MetamicTM panel longitudinal bend radius Pass/Fail MetamicTM panel bend angle Pass/Fail A panel map is made to document any observed panel defects. Results of all baseline examinations are recorded in the inserts documentation package for future availability.