ML18036A212
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| ML18036A212 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/28/2017 |
| Revision: | 0 |
| From: | Cibik S J Environmental Consulting & Technology |
| To: | Florida Power & Light Co, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18036A180 | List: |
| References | |
| ECT 150595-ASOO, L-2018-015 | |
| Download: ML18036A212 (48) | |
Similar Documents at Saint Lucie | |
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Category:Report
MONTHYEARL-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023
[Table view]Subsequent License Renewal Application - Second Annual Update 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-2023-028, 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-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report ML22227A0532022-08-15015 August 2022 Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant ML22124A0112022-04-30030 April 2022 Scoping Summary Report - Final L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022 Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI2022-01-14014 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld2022-01-12012 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld ML22010A0942022-01-0404 January 2022 Trp 29 St. Lucie SLRA - Tank Breakout L-2021-178, Report of 10 CFR 50.59 Plant Changes2021-11-0808 November 2021 Report of 10 CFR 50.59 Plant Changes L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 ML19252A4002019-09-0909 September 2019 FPL to NRC, Notification of Smalltooth Sawfish Capture at St. Lucie L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds ML18096B3952018-04-0606 April 2018 Exhibit III Estimate of Construction Costs and Exhibit IV Technical Qualifications of Contractors ML18088B1952018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 9, Auxiliary Systems and Chapter 10, Steam and Power Conversion System ML18088B1942018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 11, Radioactive Waste Management System, Chapter 12, Radiation Protection, and Chapter 13, Conduct of Operations ML18088A0942018-03-29029 March 2018 Unit II Plants ECCS Performance Results L-2017-173, Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event2017-09-28028 September 2017 Environmental Protection Plan Report, Unusual or Important Environmental Event - Turtle Mortality - 09/11/2017 Event L-2018-081, Kld Engineering, Pc - 2017 Population Update Analysis2017-09-20020 September 2017 Kld Engineering, Pc - 2017 Population Update Analysis L-2017-117, Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-12017-06-20020 June 2017 Submittal of SL2-23 Outage, Owner'S Activity Report, Form OAR-1 L-2018-015, Plan of Study 316(b) Implementation2017-04-28028 April 2017 Plan of Study 316(b) Implementation L-2017-015, PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee.2016-04-30030 April 2016 PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee. ML16084A6162016-03-24024 March 2016 Submittal of Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant, Units 1 and 2 in St. Lucie County, Florida ML16063A0072016-02-26026 February 2016 Participation in Additional Work Under the Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0 PA-MSC-0983 R2 Cafeteria Task 8 and Acceptance Criteria for Measurement Of.. ML15352A0532016-01-0707 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights L-2015-297, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan2015-12-10010 December 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, and Submittal of Site FLEX Final Integrated Plan L-2015-300, ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report.2015-11-30030 November 2015 ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report. ML15314A1602015-10-29029 October 2015 St. Lucie, Units 1 and 2 - License Renewal Commitment, Submittal of Pressurizer Surge Line Welds Inspection Program L-2015-221, Report of 10 CFR 50.59 Plant Changes2015-10-16016 October 2015 Report of 10 CFR 50.59 Plant Changes ML15240A1542015-09-0808 September 2015 Staff Observations of Sump Strainer Head Loss Testing at Alden Laboratory for Generic Safety Issue 191 L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-2062015-07-31031 July 2015 ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206 L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 12015-06-30030 June 2015 Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1 L-2015-143, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2015-05-14014 May 2015 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 20152015-05-0808 May 2015 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 L-2016-052, TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182.2015-03-31031 March 2015 TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182. L-2015-091, ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR2015-03-31031 March 2015 ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report ML15083A2642015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report2015-03-10010 March 2015 St. Lucie, Units 1 and 2 - Submittal of Revision 0 to FPL-072-PR-002, Flooding Hazards Reevaluation Report L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 1092015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 109 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-92015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End2015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End ML15083A2652015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 ML15083A2662015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report ML14338A5552014-12-0404 December 2014 NRC-2013-TN3079-NRC 2014 St. Lucie License Renewal ML14338A5542014-12-0404 December 2014 NRC-2013- TN2986-NRC 2014 St. Lucie L-2014-125, Report of 10 CFR 50.59 Plant Changes2014-05-0606 May 2014 Report of 10 CFR 50.59 Plant Changes ML13360A2022013-12-12012 December 2013 EPA Echo Report Martin County, Fl 2023-09-28 Category:Technical MONTHYEARL-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022
[Table view]Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal L-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI2022-01-14014 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld2022-01-12012 January 2022 Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021 Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021 L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds ML18096B3952018-04-0606 April 2018 Exhibit III Estimate of Construction Costs and Exhibit IV Technical Qualifications of Contractors ML18088B1942018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 11, Radioactive Waste Management System, Chapter 12, Radiation Protection, and Chapter 13, Conduct of Operations ML18088B1952018-03-29029 March 2018 Hutchinson Island Plant Units 1 and 2 - Chapter 9, Auxiliary Systems and Chapter 10, Steam and Power Conversion System ML18088A0942018-03-29029 March 2018 Unit II Plants ECCS Performance Results L-2018-081, Kld Engineering, Pc - 2017 Population Update Analysis2017-09-20020 September 2017 Kld Engineering, Pc - 2017 Population Update Analysis L-2018-015, Plan of Study 316(b) Implementation2017-04-28028 April 2017 Plan of Study 316(b) Implementation L-2017-015, PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee.2016-04-30030 April 2016 PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee. ML16084A6162016-03-24024 March 2016 Submittal of Biological Opinion for the Continued Operation of St. Lucie Nuclear Power Plant, Units 1 and 2 in St. Lucie County, Florida ML16063A0072016-02-26026 February 2016 Participation in Additional Work Under the Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0 PA-MSC-0983 R2 Cafeteria Task 8 and Acceptance Criteria for Measurement Of.. L-2015-300, ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report.2015-11-30030 November 2015 ANP-3352NP, Revision 1, Transition License Amendment Request, Technical Report. L-2015-206, ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-2062015-07-31031 July 2015 ANP-3428NP, Revision 0, St. Lucie Unit 2 Fuel Transition: Response to SNPB-RAI-1, Attachment 4 to L-2015-206 L-2015-177, Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 12015-06-30030 June 2015 Fuel Transition Small Break LOCA Summary Report, ANP-3345NP, Revision 1 L-2015-272, 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 20152015-05-0808 May 2015 1301103.401, Revision 0, Flaw Tolerance Evaluation of St. Lucie Surge Line Welds Using ASME Code Section XI, Appendix L, May 2015 L-2016-052, TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182.2015-03-31031 March 2015 TN-5696-00-02, Revision 0, Technical Note Assessment of Laboratory PWSCC Crack Growth Rate Data Compiled for Alloys 690, 52, and 152 with Regard to Factors of Improvement (Foi) Versus Alloys 600 and 182. L-2015-091, ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR2015-03-31031 March 2015 ANP-3396NP, Revision 0, Fuel Transition Supplemental Information to Support the LAR L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2015-03-24024 March 2015 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 1092015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Cover Page to Page 109 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-92015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End2015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End ML15083A2652015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9 ML15083A2662015-02-0606 February 2015 to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Figure 4-10 Through the End L-2014-366, ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report2014-12-31031 December 2014 ANP-3352NP, Revision 0, St. Luice, Unit 2, Fuel Transition License Amendment Request, Technical Report ML14149A1952013-02-0404 February 2013 Pacific Northwest National Laboratory Technical Letter Report for Evaluation of Alternative to 10 CFR 50.55a(G)(6)ll)(F)(4) for Limitations to Volumetric Examination of Dissimilar Metal Welds ML12340A3522012-11-30030 November 2012 St. Lucie, Unit 1, 12Q4116-RPT-001, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic L-2012-427, Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic2012-11-30030 November 2012 Q4116-R-002, Rev. 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Force Recommendation 2.3: Seismic ML12097A2682012-04-17017 April 2012 Biological Assessment for Formal Section 7 Consultation at the St. Lucie Plant, Units 1 and 2 L-2012-072, ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 32012-02-29029 February 2012 ANP-2903Q2(NP), Rev 0, St. Lucie, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with Zr-4 Fuel Cladding, Attachment 3 ML12061A2492012-02-29029 February 2012 ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill L-2012-072, ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill2012-02-29029 February 2012 ANP-3067, Rev. 1, St. Lucie, Unit 1 EPU - Information to Support NRC Review of RCS Depressurization with Pressurizer Overfill L-2011-471, ANP-3057(NP), Revision 0, St. Lucie Unit 1 EPU - Responses to NRC Questions SRXB-58, SRXB-59, and SRXB-60.2011-10-31031 October 2011 ANP-3057(NP), Revision 0, St. Lucie Unit 1 EPU - Responses to NRC Questions SRXB-58, SRXB-59, and SRXB-60. 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 L-2011-311, ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 22011-08-31031 August 2011 ANP-3019NP, Revision 0, St. Lucie Unit 1 EPU - Information to Support NRC Review of Steam Generator Tube Rupture, Attachment 2 L-2011-342, ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb)2011-08-31031 August 2011 ANP-3028(NP), Revision 0, St. Lucie Plant, Unit 1 EPU RAIs - Nuclear Performance & Code (Snpb) L-2011-228, 103-87735, Heated Water Plan of Study2011-06-30030 June 2011 103-87735, Heated Water Plan of Study L-2011-206, ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 72011-05-31031 May 2011 ANP-2903(NP), Revision 1, St. Lucie Nuclear Plant, Unit 1 - EPU Cycle Realistic Large Break LOCA Summary Report with ZR-4 Fuel Cladding, Attachment 7 ML11153A0492011-05-31031 May 2011 ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6 L-2011-206, ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 62011-05-31031 May 2011 ANP-3000(NP), Rev. 0, St. Lucie Nuclear, Unit 1 - EPU-Information to Support License Amendment Request, Attachment 6 L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix D, List of Key Acronyms2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix D, List of Key Acronyms L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B Additional Codes and Methods2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B Additional Codes and Methods ML1107302992011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Licensing Report L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix a Safety Evaluation Report Compliance2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix a Safety Evaluation Report Compliance L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix F, Camereron Ultrasonics Engineering Reports, Cover2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix F, Camereron Ultrasonics Engineering Reports, Cover L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix E, Supplement to Licensing Report Section 2.4.1 Reactor Protection, Engineered Safety Feature Actuation, and Control Systems2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix E, Supplement to Licensing Report Section 2.4.1 Reactor Protection, Engineered Safety Feature Actuation, and Control Systems L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix G, Holtec Report No. HI-2104753, St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix G, Holtec Report No. HI-2104753, St. Lucie Unit 2 Criticality Analysis for EPU and Non-EPU L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5, Appendix C, Grid Stability Analysis and System Impact Study for St. Lucie Plant with Proposed EPU2011-02-25025 February 2011 St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 5, Appendix C, Grid Stability Analysis and System Impact Study for St. Lucie Plant with Proposed EPU 2022-04-13 |
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