Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement
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MONTHYEARL-2010-302, License Amendment Request for Extended Power Uprate2010-12-15015 December 2010 License Amendment Request for Extended Power Uprate 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 ML1105906632011-03-0909 March 2011 Acceptance for Review of License Amendment Request for Extended Power Uprate Project stage: Acceptance Review ML1110100982011-04-19019 April 2011 Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Project stage: RAI NRC-2011-0128, St. Lucie, Unit 1 - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Documents Access to Sensitive Unclassified Nonsafeguards Information2011-06-0202 June 2011 St. Lucie, Unit 1 - Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Documents Access to Sensitive Unclassified Nonsafeguards Information Project stage: Approval ML11119A0852011-06-0202 June 2011 Notice of Consideration of Issuance of Amendment to Facility Operating License, and Opportunity for a Hearing and Order Imposing Procedures for Documents Access to Sensitive Unclassified Nonsafeguards Information Project stage: Other ML11119A0842011-06-0808 June 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 Sensitive Unclassified Non Safeguards Information Project stage: Other ML12037A1472011-07-21021 July 2011 NRR E-mail Capture - Efh Species for St. Lucie Project stage: Request 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-2011-397, Unusual or Important Environmental Event - Reportable Fish Kill2011-09-20020 September 2011 Unusual or Important Environmental Event - Reportable Fish Kill Project stage: Request L-2011-410, Environmental Protection Plan Report 316(b) Related Documentation2011-09-30030 September 2011 Environmental Protection Plan Report 316(b) Related Documentation Project stage: Request L-2011-450, Submittal of Final Revised Industrial Wastewater Facility Permit No. FL0002208, and Environmental Protection Plan Report2011-10-20020 October 2011 Submittal of Final Revised Industrial Wastewater Facility Permit No. FL0002208, and Environmental Protection Plan Report 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 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 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 ML12053A3452012-03-20020 March 2012 Request to Initiate Abbreviated Efh Consultation for Proposed Extended Power Uprate at St. Lucie Plant, Units 1 and 2 Project stage: Other L-2012-079, Supplemental Information for Extended Power Uprate License Amendment Request (LAR) Sections 2.1.7 (Protective Coating Systems) and 2.8.7.2 (Natural Circulation Cooldown)2012-03-22022 March 2012 Supplemental Information for Extended Power Uprate License Amendment Request (LAR) Sections 2.1.7 (Protective Coating Systems) and 2.8.7.2 (Natural Circulation Cooldown) Project stage: Supplement L-2012-199, Response to Request for Additional Information on Draft Environment Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate2012-05-0202 May 2012 Response to Request for Additional Information on Draft Environment Assessment and Draft Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Draft Response to RAI ML12132A0672012-05-0202 May 2012 NRR E-mail Capture - FW: St. Lucie Unit 1 and 2 EPU - Draft EA RAI Responses Project stage: Draft RAI ML12144A0082012-05-21021 May 2012 NRR E-mail Capture - FW: NRC St Lucie Plant; NMFS Comments Project stage: Request ML12144A3162012-05-23023 May 2012 NRR E-mail Capture - Federal Consistency Review Regarding the Czma Project stage: Request ML12165A5122012-06-25025 June 2012 Federal Register - Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Request ML12165A5112012-06-25025 June 2012 Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Acceptance Review ML12191A2362012-07-0909 July 2012 Technical Specification Pages Project stage: Acceptance Review ML12156A2082012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate Project stage: Approval ML12181A0192012-07-0909 July 2012 Issuance of Amendment Regarding Extended Power Uprate (Redacted) Project stage: Approval ML12194A2872012-07-12012 July 2012 Correction to Amendment No. 213 Regarding Extended Power Uprate Project stage: Other ML12195A1682012-07-13013 July 2012 Letters to H. Mueller, A. Hubbard, and S. Norton Re Environmental Assessment and Finding of No Significant Impact Related to Proposed Extended Power Uprate Project stage: Acceptance Review L-2012-309, FPL Review Comments on Extended Power Uprate Safety Evaluation2012-08-0707 August 2012 FPL Review Comments on Extended Power Uprate Safety Evaluation Project stage: Other L-2012-382, Extended Power Uprate Cycle 24 Startup Report2012-10-19019 October 2012 Extended Power Uprate Cycle 24 Startup Report Project stage: Other 2012-01-30
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Category:Letter
MONTHYEARIR 05000335/20230102024-01-26026 January 2024 NRC Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000335/2023010 and 05000389/2023010 L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) IR 05000335/20230042024-01-24024 January 2024 Integrated Inspection Report 05000335/2023004 and 05000389/2023004 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, ML23332A1772023-11-28028 November 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals IR 05000335/20230032023-11-0606 November 2023 Integrated Inspection Report 05000335/2023003 and 05000389/2023003 ML23270B8882023-10-23023 October 2023 Regulatory Audit Summary Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structure, Systems, and Components for Nuclear Power Reactors EPID L-2022-LLA-0182 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A1102023-10-0202 October 2023 License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 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 IR 05000335/20233012023-09-20020 September 2023 NRC Operator License Examination Report 05000335/2023301 and 05000389/2023301 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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes 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-2023-112, 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 ML23219A0042023-09-0101 September 2023 Transmittal Letter - Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1and 2, Revision 1 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update 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 IR 05000335/20230022023-08-0707 August 2023 Integrated Inspection Report 05000335/2023002 and 05000389/2023002 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment ML23212B2652023-07-27027 July 2023 Operator Licensing Written Examination Approval 05000335/2023301 and 05000389/2023301 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 ML23200A1232023-07-21021 July 2023 Transmittal Letter for the St. Lucie SLRA Review 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) ML23184A0352023-06-30030 June 2023 Notification of St. Lucie Units 1 & 2 Focused Engineering Inspection (FEI) 05000335/2023010 and 05000389/2023010 and Initial Information Request 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) IR 05000335/20234032023-06-29029 June 2023 Security Inspection Report 05000335/2023403 and 05000389/2023403 IR 05000335/20234022023-06-20020 June 2023 Security Baseline Inspection Report 05000335/2023402 and 05000389/2023402 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 IR 05000335/20234012023-05-16016 May 2023 Cyber Security Inspection Report 05000335/2023401 and 05000389/2023401 (Cover Letter) IR 05000335/20230012023-05-0909 May 2023 Integrated Inspection Report 05000335/2023001 and 05000389/2023001 ML23109A1132023-04-30030 April 2023 SLRA Change Schedule Letter 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 ML23097A1642023-04-17017 April 2023 Summary of March 23, 2023, Meeting with Florida Power and Light on St. Lucie and Turkey Point Improved Technical Specifications Conversion License Amendment Requests L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report 2024-01-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23226A0762023-08-14014 August 2023 NRR E-mail Capture - Request for Additional Information - St. Lucie Plant, Units 1 and 2 - Adopt 10 CFR 50.69 (L-2022-LLA-0182) ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23254A4022023-01-24024 January 2023 RP Inspection_2023-001_Document Request ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22325A0692022-11-18018 November 2022 RAI Set 4 ML22270A1482022-09-26026 September 2022 SLRA Second Round RAI Letter 2 - Class 1 Fatigue (Final) ML22217A0022022-08-0404 August 2022 Email from Brian Harris (NRC) to Robert Coffey (FPL) - St. Lucie SLRA Second Round RAI Letter 1) ML22217A0032022-08-0404 August 2022 SLRA Second Round RAI Letter 1) ML22193A0872022-07-11011 July 2022 Letter RAI Set 3 (Final) ML22133A0032022-05-12012 May 2022 SLRA Rai'S Set 1 ML22101A2322022-05-0202 May 2022 Summary of the Environmental Remote Audit Related to the Review of the Subsequent License Renewal Application Enclosure RCIs and RAIs ML22094A1672022-04-0101 April 2022 2022 St. Lucie POV Inspection Information Request ML22075A1212022-03-16016 March 2022 Stl Problem Identification and Resolution (Pi&R) Information Request Final Report ML21350A4262021-12-21021 December 2021 Supplemental Information Needed for Acceptance of Licensing Amendment Request Concerning Technical Specification Conversion to NUREG-1432, Revision 5 ML21119A3142021-04-28028 April 2021 Requests for Additional Information Regarding License Amendment Requests to Apply Risk Informed Completion Times (RICT) for the 120-Volt AC (EPID L-2020-LLA-0283) (Email) ML21063A3192021-03-0404 March 2021 Request for Additional Information Regarding Relief Request RR 15 - Extension of RPV Welds from 10 to 20 Years ML20092G3442020-04-0101 April 2020 RAIs for LAR to Revise Technical Specifications 6.8.4.o, Reactor Coolant Pump Flywheel Inspection Program ML20094G2022020-03-30030 March 2020 Request for Additional Information Regarding License Amendment Request to Adopt EAL Schemes Pursuant to NEI 99-01 (L-2019-LLA-0210) ML19225D3152019-08-13013 August 2019 NRR E-mail Capture - St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Relocate the MOV Thermal Overload Bypass Devices (L-2019-LLA-0106) ML19218A2742019-08-0606 August 2019 Notification of Inspection and Request for Information ML19193A1982019-07-12012 July 2019 Emailed St. Lucie Heat Sink RFI ML19192A1372019-07-11011 July 2019 NRR E-mail Capture - Request for Additional Information - St. Lucie Plant, Unit No. 2, Fall 2018 Refueling Outage Steam Generator Tube Inspection Report ML19192A1352019-06-25025 June 2019 NRR E-mail Capture - Draft Request for Additional Information - St. Lucie Plant, Unit No. 2, Fall 2018 Refueling Outage Steam Generator Tube Inspection Report ML19151A8312019-05-31031 May 2019 NRR E-mail Capture - St. Lucie Plant, Unit Nos. 1 and 2, Request for Additional Information Regarding Emergency Diesel Generator Surveillance Requirement Amendment Request ML19151A5092019-05-21021 May 2019 NRR E-mail Capture - Draft Request for Additional Information - St. Lucie Plant, Unit Nos. 1 and 2 Emergency Diesel Generator Surveillance Requirement Amendment Request ML19109A1392019-04-18018 April 2019 NRR E-mail Capture - St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding the License Amendment Request Pertaining to the Iodine Removal System ML19053A2242019-02-0101 February 2019 NRR E-mail Capture - St. Lucie Plant Unit No. 1 - Draft Request for Additional Information Related to Relief Request 6 Regarding the Refueling Water Tank Bottom Liner L-2018-018, St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L-2018-0181)2018-10-22022 October 2018 St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L-2018-0181) ML18296A2052018-10-22022 October 2018 NRR E-mail Capture - St. Lucie Plant, Unit No. 2, Request for Additional Information Regarding License Amendment Request to Reduce the Number of Control Element Assemblies (EPID L-2018-0181) ML18197A4112018-08-0101 August 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request to Reduce the Number of Control Element Assemblies ML18019A0712018-01-18018 January 2018 NRR E-mail Capture - Request for Additional Information - St. Lucie Inop AFW Steam Supply LAR (L-2017-LLA-0296) ML17331B1532017-11-27027 November 2017 NRR E-mail Capture - Request for Additional Information - St. Lucie IST Relief Request #5 - PR-01 (L-2017-LLR-0113) ML17277A3692017-10-0404 October 2017 NRR E-mail Capture - Request for Additional Information - St. Lucie Rict LAR - MF5372/MF5373 ML17152A1842017-06-0101 June 2017 Request for Additional Information - RPS Rate of Change and LCO Change LAR (CACs MF9119 9120) ML16356A1432016-12-20020 December 2016 Notification of Inspection and Request for Information ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16308A3232016-11-0303 November 2016 NRR E-mail Capture - Request for Additional Information - St. Lucie EDG Day Tank LAR - MF8006 ML16292A8212016-10-14014 October 2016 Emergency Preparedness Inspection and Request for Information ML17003A0452016-10-11011 October 2016 NRR E-mail Capture - (External_Sender) FW: St. Lucie Response to RAI on SL2-22 SG Tube Inspection Report (MF7604) ML16244A2602016-08-26026 August 2016 Notification of Inspection and Request for Information ML16155A3502016-06-0303 June 2016 Notification of Inspection and Request for Information ML16089A0052016-03-28028 March 2016 NRR E-mail Capture - Request for Additional Information - St. Lucie Srxb Mtc Surv - MF7269 & MF7270 ML16077A1062016-03-17017 March 2016 NRR E-mail Capture - Request for Additional Information - St Lucie Vacuum Gothic LAR - MF6980/MF6981 ML16068A2612016-03-0808 March 2016 NRR E-mail Capture - Request for Additional Information - St Lucie TSTF-422 - MF6683/MF6684 ML16068A0412016-03-0808 March 2016 NRR E-mail Capture - Request for Additional Information - St Lucie Unit 1 Relief Request No. 10 - MF6685 ML16013A2152016-01-13013 January 2016 NRR E-mail Capture - St. Lucie RAIs (Rvi Aging Management Plan) MF6777 and MF6778 ML15336A8882015-12-16016 December 2015 Request for Additional Information Regarding License Amendment Request for Changes to the Snubber Surveillance Requirements ML15308A6152015-11-23023 November 2015 Request for Additional Information on License Amendment Request for Changes to the Required Actions for Inoperability of Auxiliary Feedwater Pumps ML15233A0362015-09-0404 September 2015 Redacted Request for Additional Information Regarding Proposed License Amendment Request and Exemption Request to Allow the Transition to Areva Fuel 2023-08-31
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 19, 2011 Mr. Mano Nazar Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 ST. LUCIE PLANT, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE (TAC NO. ME5091)
Dear Mr. Nazar:
By letter dated November 22, 2010, Florida Power & Light Company submitted a license amendment request for St. Lucie Plant, Unit NO.1. The proposed amendment would increase the licensed core power level from 2700 megawatt thermal (MWt) to 3020 MWt. The Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). It is requested that your RAI response be provided within 30 days of the date of this letter. Sincerely, Tracy J. Ort, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
Request for Additional cc w/enclosure:
Distribution via REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE ST. LUCIE PLANT, UNIT NO.1 DOCKET NO. 50-335 CVIB-1 : The limiting material with regard to adjusted reference temperature (ART) and the pressurized thermal shock reference temperature (RT PTS) for the St. Lucie, Unit 1 reactor vessel (RV) is Lower Shell Axial Weld 3-203 AlC, Heat Number 305424. This material heat is not contained in the St. Lucie, Unit 1 surveillance program but is contained in the Beaver Valley, Unit 1 surveillance program. Reference 1, Table 2.1.2-4 provides a copper content of 0.27 weight percent, a nickel content of 0.63 weight percent, and a chemistry factor (CF) of 188.8 degrees Farenheit (F) determined using Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials," Revision 2, Position 1.1. The reference given for the CF is a letter dated August 28, 1997 (Reference 2), forwarding updated information in response to Generic Letter 92-01 Revision 1, "Reactor Vessel Structural Integrity." Reference 2 references Combustion Engineering (CE) report CE NPSD-1039, Revision 2, "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds" (Reference 3). However, Beaver Valley, Unit 1 reported three additional chemistry measurements for Heat Number 305424 in Reference 4 that are not included in Reference
- 3. The staff, therefore, requests the following information: Provide a discussion of how the additional chemistry measurements reported in Reference 4 were accounted for in the determination of the best estimate CF for weld 3-203 AlC (Heat Number 305424), reported in the St. Lucie, Unit 1 extended power uprate (EPU) Licensing Report, or provide a justification for not using the additional chemistry data. Revise the CF for weld 3-203 AlC (heat number 305424) if necessary.
CVIB-2: Reference 5 provides the basis for the revised pressure-temperature (P-T) limits for St. Lucie, Unit 1, incorporating revised neutron fluence values that account for the EPU. Figures 3.4-2a and 3.4-2b of the technical specifications have been revised to incorporate the new P-T limits. ENCLOSURE
-The P-T limits must meet the minimum temperature requirements of Title 10, Code of Federal Regulations (10 CFR) Part 50, Appendix G, "Fracture Toughness Requirements." For normal operation, including heatups and cooldowns, and anticipated operational occurrences, 10 CFR Part 50, Appendix G, requires that the RV pressure may not exceed 20 percent of the preservice hydrostatic test (PSHT) pressure until the RV temperature exceeds by 120 degrees F the highest reference temperature of the material in the closure flange region of the RV that is highly stressed by bolt preload. For St. lucie, Unit 1, 20 percent of the PSHT pressure is 636.25 pounds per square inch gauge (psig). With the indicated pressure correction factor applied, this becomes 557.3 psig. Section 2.7 of Reference 5 states the maximum RT NDT of the closure flange region is 50 degrees F, which means that 557.3 pounds per square inch differential should not be exceeded until a temperature of 170 degrees F is reached. However, revised Technical Specification Figures 3.4-2a and Figure 3.4-2b as well as Figures 2-3 and 2-4 of Reference 5 show the heatup curves exceeding the 20 percent PSHT pressure at 165 degrees F, which Reference 5 indicates is the lowest service temperature as defined by the American Society of Mechanical Engineers Code,Section III, Paragraph NB-3211 (158 degrees F), plus 7 degrees F to account for instrument uncertainty.
Given the information above, the staff, therefore, requests the licensee to explain how the P-T limits for St. lucie, Unit 1 meet the requirements of 10 CFR Part 50, Appendix G. CVIB-3: Clarify whether the minimum temperature for core critical operation and the hydrostatic test temperature is 268.2 degrees F, as shown on Figures 2-1 and 2-2 of Reference 5, or 270.7 degrees F, as stated at the top of page 2-17 of Reference
- 5. CVIB-4: Section 61 of 10 CFR Part 50, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," defines RT pTs as the reference temperature, RT NDT , evaluated for the end of life (EOl) fluence, where EOl fluence means the best-estimate neutron fluence projected for a specific RV beltline material at the clad-base metal interface on the inside surface of the RV at the location where the material receives the highest neutron fluence on the expiration date of the operating license. In Reference 1, Section 2.1.3, the RT PTS evaluation was based on the neutron f1uence for 52 effective full power years (EFPY). Additionally, Reference 1, Table 2.1.1-2, "Comparison of Peak 0° and 15° Azimuth VessellD Fluence Values at 52 EFPY," implies that 52 EFPY is the expected maximum EFPY value for St. lucie, Unit 1 corresponding to 60 calendar years, when the renewed operating license expires. However, for the ART evaluation supporting the revised P-T limits, ART values were projected for both the 52 EFPY and 54 EFPY neutron fluences.
Reference 1, Section 2.1.2.2 states that new 60-year P-T limits have been generated based on the neutron f1uence projected to 54 EFPY to provide margin for fuel management.
-Based on the above information, given that the 54 EFPY neutron fluence was used as a basis for the ART used to develop the P-T curves to provide margin for fuel management, the staff requests the licensee discuss whether the 54 EFPY neutron fluence should also be applied to the pressurized thermal shock evaluation.
eVIB-5: In Reference 1, the effects of EPU are evaluated for the following aging mechanisms of the reactor vessel internals (RVI): fuel cladding corrosion, irradiation assisted stress corrosion cracking (IASee), stress corrosion cracking (SeC), irradiation embrittlement, thermal embrittlement, void swelling, and irradiation-enhanced stress relaxation.
The susceptibility of the St. Lucie, Unit 1 RVI components to these mechanisms (with the exception of fuel cladding corrosion) was assessed for license renewal as documented in the St. Lucie, Units 1 and 2 License Renewal Application (LRA, Reference
- 6) and the associated Safety Evaluation Report (Reference 7). The LRA identified the following aging effects and the mechanisms that cause the aging effect: 1) cracking due to sec and IASee, 2) reduction in fracture toughness due to irradiation embrittlement and thermal embrittlement, 3) loss of material due to wear, 4) loss of mechanical closure integrity due to cracking (SeC and IASeC) and stress relaxation, 5) loss of preload due to stress relaxation, and 6) dimensional change due to void swelling.
Neutron fluence and temperature are important parameters with respect to assessing the susceptibility of RVI components to many of these aging mechanisms.
In particular, threshold neutron fluence levels are identified for certain aging mechanisms in industry guidance documents and topical reports such as WeAP-14577, Revision 1, "License Renewal Evaluation:
Aging Management for Reactor Internals (Reference 8), and similar threshold neutron fluence values are also identified in Reference 1 for several of the aging mechanisms evaluated, including IASee, irradiation embrittlement, void swelling, and stress relaxation.
It is not clear to the staff whether any additional components were identified as susceptible to these mechanisms as a result of EPU, compared to those identified in the LRA. For example, Reference 1, Section 2.1.4.2.3.
D lists components that are susceptible to irradiation embrittlement.
This list does not exactly match the components listed as susceptible to irradiation embrittlement in Section 3.1.4.2.2 of the LRA. It is not clear how the screening for susceptibility to these mechanisms was accomplished.
Based on the above, the staff requests the following information: Describe the method of determining if additional RVI components become susceptible to the aging effects of 1) cracking due to sec or IASee, 2) reduction of fracture toughness due to irradiation embrittlement;
- 3) loss of material due to wear; 4) loss of mechanical closure integrity due to IASee, irradiation embrittlement, irradiation creep, or stress relaxation;
- 5) loss of preload due to stress relaxation; and 6) dimensional change due to void swelling.
The discussion should address whether a detailed neutron 1'Iuence and temperature map was used, and whether stresses in individual components were reevaluated.
-Confirm whether the design projections of gamma heating bound the projected amount of gamma heating of the RVI components under EPU conditions.
Discuss the acceptability of the effects of gamma heating on the RVI components under EPU conditions. Clarify whether any additional RVI components were determined to be susceptible to the aging effects listed in part "a" of this question as a result of EPU, compared to those listed as susceptible to these mechanisms in the LRA (Reference 6). CVIB-6: In Section 3.1.4.2.1 of Reference 7, the staff concurred with the licensee's conclusion from the LRA (Reference
- 6) that loss of material due to wear was an aging effect requiring management for certain St. Lucie, Units 1 and 2 RVI components.
Reference 7 states that loss of material from wear occurs due to relative motion between the interfaces and mating surfaces of components caused by flow-induced vibration during plant operation, differential thermal expansion and contraction movements during plant heat up and cool down, and changes in power operating cycles. Additionally in Section 3.1.4.2.1 of Reference 7, the staff concurred with the licensee's conclusion from the LRA that for the St. Lucie, Unit 1 RVI, loss of mechanical closure integrity of fuel alignment plate guide lug bolts, fuel alignment plate guide lug insert bolts, and control element assembly shroud bolts can occur due to cracking and stress relaxation, and that loss of mechanical closure integrity associated with the core shroud tie rods and snubber bolts can occur due to cracking, reduction in fracture toughness due to irradiation embrittlement, and stress relaxation.
However, loss of material due to wear and loss of mechanical closure integrity are not included among the relevant degradation (aging) mechanisms evaluated in Section 2.1.4 of Reference
- 1. The staff therefore requests the licensee provide an evaluation of the following aging mechanisms considering EPU: loss of mechanical closure integrity loss of material The evaluation should address whether additional RVI components (compared to those listed as susceptible to these aging effects in the LRA) become susceptible to these aging effects as a result of EPU. References Licensing Report, Attachment 5 to Letter from Richard L. Anderson to NRC dated November 22, 2010, Re: St. Lucie Plant Unit 1, Docket No. 50-335, Renewed License No. DPR-67, License Amendment Request for an Extended Power Uprate, Florida Power & Light (FPL) Letter No. L-2010-259 (ADAMS Accession No. ML103560429).
-FPL Letter, L-97-223, St. Lucie Units 1 and 2, Docket Nos. 50-335 and 50-389, NRC Reactor Vessel Integrity Generic Letter 92-01, Revision 1 Updated Information, August 28,1997 (ADAMS Legacy Accession No. 9709040378). CE NPSD-1039, Revision 2, "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds," prepared for the CE Owners Group, June 1997. WCAP-15770, Revision 2, "Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation, April 2001, Westinghouse Electric Co. (ADAMS Accession No. ML011870482). WCAP-17197-NP Revision 0, "St. Lucie Unit 1 RCS [Reactor Coolant Systems] Pressure and Temperature Limits and Low-Temperature Overpressure Protection Report For 54 Effective Full Power Years," Appendix G to the EPU licensing Report for Saint Lucie, Unit 1 (ADAMS Accession No. ML103560511). Application for Renewed Operating Licenses, St. Lucie Units 1 & 2 (ADAMS Accession No. ML013400292). NUREG-1779, "Safety Evaluation Report Related to the License Renewal of St. Lucie Nuclear Plant, Units 1 and 2, Docket Nos. 50-335 and 50-389, Florida Power &Light Company," September, 2003, (ADAMS Accession No. ML032940205). WCAP-14577, Rev. 1-A, "License Renewal Evaluation:
Aging Management for Reactor Internals," March 2001 (ADAMS Accession No. ML011080790). "Application for Exemption from Section IV.A.2 of Appendix G to 10 CFR 50 Requirements when Computing Pressure-Temperature Limits for St. Lucie 1," Attachment 1 to Letter from Richard L. Anderson to NRC dated March 3, 2011, Re: St. Lucie Plant Unit 1, Docket No. 50-335, Renewed Facility Operating License No. DPR-67, Response to NRC Request for Additional Information (RAI) Regarding Extended Power Uprate License Amendment Request (ADAMS Accession No. ML110660300).
- 10. Westinghouse Report, CE-NPSD-683-A Task-1174, Revision 06, "Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and LTOP [Low-Temperature Overpressure Protection]
Requirements from the Technical Specifications," April 2001 (ADAMS Accession No. ML011350387).
April 19, 2011 Mr. Mano Nazar Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 ST. LUCIE PLANT, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE (TAC NO. ME5091)
Dear Mr. Nazar:
By letter dated November 22, 2010, Florida Power &Light Company submitted a license amendment request for St. Lucie Plant, Unit No.1. The proposed amendment would increase the licensed core power level from 2700 megawatt thermal (MWt) to 3020 MWt. The Nuclear Regulatory Commission staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). It is requested that your RAI response be provided within 30 days of the date of this letter. Sincerely, IRA! Tracy J. Ort, Project Manager Plant licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
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