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Category:Annual Operating Report
MONTHYEARL-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-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2022-062, Annual Radiological Environmental Operating Report for Calendar Year 20212022-04-13013 April 2022 Annual Radiological Environmental Operating Report for Calendar Year 2021 L-2021-082, Submittal of 2020 Annual Environmental Operating Report2021-04-15015 April 2021 Submittal of 2020 Annual Environmental Operating Report L-2021-066, CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2021-04-14014 April 2021 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2020-044, Report of 10 CFR 50.59 Plant Changes2020-04-20020 April 2020 Report of 10 CFR 50.59 Plant Changes L-2020-068, 2019 Annual Environmental Operating Report2020-04-15015 April 2020 2019 Annual Environmental Operating Report L-2020-041, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2020-04-14014 April 2020 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2020-027, 2019 Annual Operating Report2020-01-12012 January 2020 2019 Annual Operating Report L-2019-044, Report of 10 CFR 50.59 Plant Changes2019-03-27027 March 2019 Report of 10 CFR 50.59 Plant Changes L-2019-057, Cf~ 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2019-03-19019 March 2019 Cf~ 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2019-039, 2018 Annual Operating Report2019-02-27027 February 2019 2018 Annual Operating Report L-2018-087, Transmittal of 2017 Annual Environmental Operating Report2018-04-10010 April 2018 Transmittal of 2017 Annual Environmental Operating Report L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications2018-03-26026 March 2018 CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications L-2018-051, 2017 Annual Operating Report2018-02-22022 February 2018 2017 Annual Operating Report L-2017-071, Submittal of Report of 10 CFR 50.59 Plant Changes, Tests and Experiments2017-05-0404 May 2017 Submittal of Report of 10 CFR 50.59 Plant Changes, Tests and Experiments L-2017-056, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 Annual Report2017-03-27027 March 2017 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 Annual Report L-2017-016, Transmittal of 2016 Annual Operating Report2017-02-0707 February 2017 Transmittal of 2016 Annual Operating Report L-2016-049, Annual Operating Report for St. Lucie 1 and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors2016-03-0202 March 2016 Annual Operating Report for St. Lucie 1 and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors L-2014-095, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2014-03-31031 March 2014 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2004-050, Cy 2003 Corrections to Annual Radioactive Effluent Release Report (L-2004-050 Dated February 27, 2004) Section 10. Process Control Program (PCP) Revisions, Page 6 and AP 0520025 Revision 13A with mark-up2014-02-27027 February 2014 Cy 2003 Corrections to Annual Radioactive Effluent Release Report (L-2004-050 Dated February 27, 2004) Section 10. Process Control Program (PCP) Revisions, Page 6 and AP 0520025 Revision 13A with mark-up L-2014-048, Annual Operating Report2014-02-12012 February 2014 Annual Operating Report L-2013-012, Annual Operating Report2013-01-0909 January 2013 Annual Operating Report L-2012-361, Report of 10 CFR 50.59 Plant Changes2012-10-0101 October 2012 Report of 10 CFR 50.59 Plant Changes L-2012-170, Annual Environmental Operating Report2012-04-24024 April 2012 Annual Environmental Operating Report L-2012-080, Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011, C-200, Offsite Dose Calculation Manual Revision 35.2012-03-0101 March 2012 Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011, C-200, Offsite Dose Calculation Manual Revision 35. ML12068A2072012-03-0101 March 2012 Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011 L-2012-073, 2011 Annual Operating Report2012-02-21021 February 2012 2011 Annual Operating Report L-2011-147, 2010 Annual Environmental Operating Report2011-04-20020 April 2011 2010 Annual Environmental Operating Report L-2011-116, Annual Radiological Environmental Operating Report for Calendar Year 20102011-04-19019 April 2011 Annual Radiological Environmental Operating Report for Calendar Year 2010 ML1109701462011-03-30030 March 2011 Units I and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2010-058, Annual Radiological Environmental Operating Report for Calendar Year 20092010-03-22022 March 2010 Annual Radiological Environmental Operating Report for Calendar Year 2009 ML1006106442010-02-25025 February 2010 St. Lucie, Units 1 and 2, Combined Annual Radioactive Effluent Release Report for the Period January 1, 2009 Through December 31, 2009 L-2010-033, St. Lucie, Units 1 and 2, Combined Annual Radioactive Effluent Release Report for the Period January 1, 2009 Through December 31, 20092010-02-25025 February 2010 St. Lucie, Units 1 and 2, Combined Annual Radioactive Effluent Release Report for the Period January 1, 2009 Through December 31, 2009 L-2009-090, Annual Radiological Environmental Operating Report for Calendar Year 20082009-04-13013 April 2009 Annual Radiological Environmental Operating Report for Calendar Year 2008 L-2009-061, Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors2009-03-11011 March 2009 Submittal of Annual Report Acceptance Criteria for Emergency Core Cooling System Analyses for Light Water Nuclear Power Reactors L-2008-169, Amended Annual Radiological Environmental Operating Report for Calendar Year 20072008-07-28028 July 2008 Amended Annual Radiological Environmental Operating Report for Calendar Year 2007 L-2008-046, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report2008-03-18018 March 2008 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report L-2007-074, 2006 Annual Environmental Operating Report2007-04-25025 April 2007 2006 Annual Environmental Operating Report L-2007-021, Annual Operating Report2007-02-21021 February 2007 Annual Operating Report L-2006-263, Report of 10 CFR 50.59 Plant Changes During Period of February 15, 2005 Through June 12, 20062006-12-0505 December 2006 Report of 10 CFR 50.59 Plant Changes During Period of February 15, 2005 Through June 12, 2006 ML0612501642006-04-27027 April 2006 St. Lucie, Units 1 & 2 - 2005 Annual Environmental Operating Report L-2006-098, Annual Radiological Environmental Operating Report for Calendar Year 20052006-04-18018 April 2006 Annual Radiological Environmental Operating Report for Calendar Year 2005 L-2005-095, Annual Environmental Operating Report2005-04-26026 April 2005 Annual Environmental Operating Report L-2005-069, Annual Radiological Environmental Operating Report for Calendar Year 20042005-03-31031 March 2005 Annual Radiological Environmental Operating Report for Calendar Year 2004 L-2005-038, 2004 Annual Radioactive Effluent Release Report2005-02-28028 February 2005 2004 Annual Radioactive Effluent Release Report L-2005-037, Letter Transmitting, St. Lucie Units 1 and 2, 2004 Annual Overating Report2005-02-28028 February 2005 Letter Transmitting, St. Lucie Units 1 and 2, 2004 Annual Overating Report L-2004-081, Annual Radiological Environmental Operating Report2004-04-13013 April 2004 Annual Radiological Environmental Operating Report L-2004-070, Annual Environmental Operating Report2004-04-13013 April 2004 Annual Environmental Operating Report L-2004-012, Transmittal of the 2003 Annual Operating Report2004-02-12012 February 2004 Transmittal of the 2003 Annual Operating Report 2023-09-20
[Table view] 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] |
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0 F=PLo March 2, 2016*L-2016-049 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report Pursuant to 10 CFR SO0.46(a)(3)(ii), the nature of any change to or error discovered in the evaluation models for emergency core cooling systems (ECCS), or in the application of such models, that affect the fuel cladding temperature calculations for St. Lucie Units 1 and 2 is reported in the attachment to this letter. The estimated effect from any such change or error on the limiting ECCS analysis for each unit is also addressed.
The data interval for the report is from January 1, 2015 through December 31, 2015.Please contact Ken Frehafer at 772-467-7748 should you have any questions regarding this submittal.
Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant~'e ~kESK/KWF Attachment Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2016-049 Attachment Page 1 of 5 St. Lucie Units 1 and 2 10 CFR 50.46 Annual Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 and St. Lucie Unit 2 are performed by AREVA and Westinghouse Electric Company respectively.
The following information pertaining to the evaluation models for small break loss of coolant accidents (SBLOCA) and large break loss of coolant accidents (LBLOCA), and the application of such models to each St. Lucie Unit, is provided pursuant to 10 CFR 50.46(a)(3)(ii).
A summary of calculated peak cladding temperature (PCT)changes is provided in Tables 1 and 2 (for St. Lucie Units 1 and 2, respectively).
The data interval for this report is from January 1, 2015 through December 31, 2015. A discussion of the changes follows.St. Lucie Unit 1 transitioned to M5 fuel rod cladding during the year 2015 and the new evaluation model PCT with M5 cladding was reported to the NRC in Reference 3.2.1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCTto support the change to M5 cladding.
No errors were found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.2. The limiting SBLOCA PCT remains at 1850 0 F and is documented in Table 1.1.2 Changes to LBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCT to support the change to M5 cladding.
There was one error found in the LBLOCA ECCS performance analysis since the previous report of Reference 3.2.The error is in the cutback ratio (relative power) for once-burned gadolina bearing fuel rod compared to rods containing only U235. This resulted in gadolina bearing rods being modeled at an artificially reduced power, and when corrected results in an estimated impact to the PCT of 0 0 F The limiting LBLOCA PCT with the above estimated impact remains at 1794 °F and is documented in Table 1.2.0 ST. LUCIE UNIT 2 2.1 Changes to SBLOCA No errors were found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. The limiting SBLOCA PCT remains at 1903 0 F and is documented in Table 2.
L-2016-049 Attachment Page 2 of 5 2.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. The limiting LBLOCA PCT remains at 2087 0 F and is documented in Table 2.
3.0 REFERENCES
3.1 Letter L-2015-093, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Units 1 and 2 Docket Nos. 50-33 5 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report," March 24, 2015 (ML 15092A097).
3.2 Letter L-2015-1 55, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Unit 1 Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report," May 14, 2015 (ML 15149A150).
L-20 16-049 Attachment Page 3 of 5 Table 1: 2015 St. Lucie Unit 1 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary Evaluation Model: EMF-2328(P)(A)
Rev. 0 as supplemented by ANP-3000(P), Revision 0.Evaluation Model PCT: 1828°F Net PCT Effect Absolute PCT Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections
-Previous Years ANA N/A N/A (New evaluation model during Year 2015, ReferenceN/
3.2) ________Prior 10 CFR 50.46 Changes or Errors Corrections
-B Current Year (Reference 3.2)Vapor absorptivity correlation applied outside the +2 0 2 0 80 0 bounds of the correlation Design Change for Initial Pressurization of Fuel Rod -30 0 F 30 0 F 1850 0 F C 10 CFR 50.46 Changes in Current Year Since Item B 0 0 F 0 0 F 1850 0 F D Sum of 10 CFR 50.46 Changes +22 0 F 82 0 F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1850 °F < 2200 °F changes and errors identified since this analysis L-20 16-049 Attachment Page 4 of 5 Unit 1 LBLOCA Summary Evaluation Model: EMF-2103(P)(A)
Rev. 0 as supplemented by ANP-2903(P), Revision 1.Evaluation Model PCT: 1788 0 F Net PCT Effect Absolute PCT Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections
-A Previous YearsN/NA (New evaluation model during Year 2015, ReferenceN/
3.2)Prior 10 CFR 50.46 Changes or Errors Corrections
-B Current Year (Reference 3.2)S-RELAP5 RODEX3a Trapped Stack Coding Error +6 °F 6 °F 1794 0 F S-RELAP5 Vapor Absorptivity Correlation Error 0 °F 0 °F 1794 °F Modal Decomposition Generation of Non-Physical 0 ° 0 °F 1794 0 F Shapes Design Change for Initial Pressurization of Fuel Rod 0 0 F 0 °F 1794 0 F C 10 CFR 50.46 Changes in Current Year Since Item B Incorrect cutback ratio applied to gadolina bearing rods +0 0 F 0 °F 1794 0 F D Sum of 10 CFR 50.46 Changes +6 °F 6 0 F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1794 0 F < 2200 0 F changes and errors identified since this analysis L-201 6-049 Attachment Page 5 of 5 Table 2: 2015 St. Lucie Unit 2 SBLOCA and LBLOCA PCT Summary Unit 2 SBLOCA Summary Evaluation Model: CENPD-137, Supplement 2-P-A (S2M)Evaluation Model PCT: 1903 0 F Net PCT Effect Absolute PCT Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections
-A Previous Years 0 °F 0 °F 1903 °F (Reference 3.1)B Prior 10 CFR 50.46 Changes or Errors Corrections
-0 ° 0 0 F 1903 0 F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0 F 0 0 F 1903 0 F D Sum of 10 CFR 50.46 Changes 0 0 F 0 0 F The sum of the PCTfitom the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1903 0 F < 2200 °F changes and errors identified since this analysis Unit 2 LBLOCA Summary Evaluation Model: CENPD-132, Supplement 4-P-A (1999 EM)Evaluation Model PCT: 2087°F Absolute PCT Net PCT Effect EfetPCT Prior 10 CFR 50.46 Changes or Error Corrections
-A Previous Years 0 °F 0 °F 2087 °F (Reference 3.1)__________
B Prior 10 CFR 50.46 Changes or Errors Corrections
-0 0 F ,0 0 F 2087 0 F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0 F 0 0 F 2087 0 F D Sum of 10 CFR 50.46 Changes 0 0 F 0 0 F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 2087 °F < 2200 °F changes and errors identified since this analysis 0 F=PLo March 2, 2016*L-2016-049 10 CFR 50.46 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report Pursuant to 10 CFR SO0.46(a)(3)(ii), the nature of any change to or error discovered in the evaluation models for emergency core cooling systems (ECCS), or in the application of such models, that affect the fuel cladding temperature calculations for St. Lucie Units 1 and 2 is reported in the attachment to this letter. The estimated effect from any such change or error on the limiting ECCS analysis for each unit is also addressed.
The data interval for the report is from January 1, 2015 through December 31, 2015.Please contact Ken Frehafer at 772-467-7748 should you have any questions regarding this submittal.
Sincerely, Eric S. Katzman Licensing Manager St. Lucie Plant~'e ~kESK/KWF Attachment Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2016-049 Attachment Page 1 of 5 St. Lucie Units 1 and 2 10 CFR 50.46 Annual Report Emergency core cooling system (ECCS) analyses for St. Lucie Unit 1 and St. Lucie Unit 2 are performed by AREVA and Westinghouse Electric Company respectively.
The following information pertaining to the evaluation models for small break loss of coolant accidents (SBLOCA) and large break loss of coolant accidents (LBLOCA), and the application of such models to each St. Lucie Unit, is provided pursuant to 10 CFR 50.46(a)(3)(ii).
A summary of calculated peak cladding temperature (PCT)changes is provided in Tables 1 and 2 (for St. Lucie Units 1 and 2, respectively).
The data interval for this report is from January 1, 2015 through December 31, 2015. A discussion of the changes follows.St. Lucie Unit 1 transitioned to M5 fuel rod cladding during the year 2015 and the new evaluation model PCT with M5 cladding was reported to the NRC in Reference 3.2.1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCTto support the change to M5 cladding.
No errors were found in the SBLOCA ECCS performance analysis since the previous report of Reference 3.2. The limiting SBLOCA PCT remains at 1850 0 F and is documented in Table 1.1.2 Changes to LBLOCA Reference 3.2 notified the NRC of a change in evaluation model PCT to support the change to M5 cladding.
There was one error found in the LBLOCA ECCS performance analysis since the previous report of Reference 3.2.The error is in the cutback ratio (relative power) for once-burned gadolina bearing fuel rod compared to rods containing only U235. This resulted in gadolina bearing rods being modeled at an artificially reduced power, and when corrected results in an estimated impact to the PCT of 0 0 F The limiting LBLOCA PCT with the above estimated impact remains at 1794 °F and is documented in Table 1.2.0 ST. LUCIE UNIT 2 2.1 Changes to SBLOCA No errors were found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. The limiting SBLOCA PCT remains at 1903 0 F and is documented in Table 2.
L-2016-049 Attachment Page 2 of 5 2.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. The limiting LBLOCA PCT remains at 2087 0 F and is documented in Table 2.
3.0 REFERENCES
3.1 Letter L-2015-093, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Units 1 and 2 Docket Nos. 50-33 5 and 50-389 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report," March 24, 2015 (ML 15092A097).
3.2 Letter L-2015-1 55, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St. Lucie Unit 1 Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report," May 14, 2015 (ML 15149A150).
L-20 16-049 Attachment Page 3 of 5 Table 1: 2015 St. Lucie Unit 1 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary Evaluation Model: EMF-2328(P)(A)
Rev. 0 as supplemented by ANP-3000(P), Revision 0.Evaluation Model PCT: 1828°F Net PCT Effect Absolute PCT Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections
-Previous Years ANA N/A N/A (New evaluation model during Year 2015, ReferenceN/
3.2) ________Prior 10 CFR 50.46 Changes or Errors Corrections
-B Current Year (Reference 3.2)Vapor absorptivity correlation applied outside the +2 0 2 0 80 0 bounds of the correlation Design Change for Initial Pressurization of Fuel Rod -30 0 F 30 0 F 1850 0 F C 10 CFR 50.46 Changes in Current Year Since Item B 0 0 F 0 0 F 1850 0 F D Sum of 10 CFR 50.46 Changes +22 0 F 82 0 F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1850 °F < 2200 °F changes and errors identified since this analysis L-20 16-049 Attachment Page 4 of 5 Unit 1 LBLOCA Summary Evaluation Model: EMF-2103(P)(A)
Rev. 0 as supplemented by ANP-2903(P), Revision 1.Evaluation Model PCT: 1788 0 F Net PCT Effect Absolute PCT Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections
-A Previous YearsN/NA (New evaluation model during Year 2015, ReferenceN/
3.2)Prior 10 CFR 50.46 Changes or Errors Corrections
-B Current Year (Reference 3.2)S-RELAP5 RODEX3a Trapped Stack Coding Error +6 °F 6 °F 1794 0 F S-RELAP5 Vapor Absorptivity Correlation Error 0 °F 0 °F 1794 °F Modal Decomposition Generation of Non-Physical 0 ° 0 °F 1794 0 F Shapes Design Change for Initial Pressurization of Fuel Rod 0 0 F 0 °F 1794 0 F C 10 CFR 50.46 Changes in Current Year Since Item B Incorrect cutback ratio applied to gadolina bearing rods +0 0 F 0 °F 1794 0 F D Sum of 10 CFR 50.46 Changes +6 °F 6 0 F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1794 0 F < 2200 0 F changes and errors identified since this analysis L-201 6-049 Attachment Page 5 of 5 Table 2: 2015 St. Lucie Unit 2 SBLOCA and LBLOCA PCT Summary Unit 2 SBLOCA Summary Evaluation Model: CENPD-137, Supplement 2-P-A (S2M)Evaluation Model PCT: 1903 0 F Net PCT Effect Absolute PCT Effect PCT Prior 10 CFR 50.46 Changes or Error Corrections
-A Previous Years 0 °F 0 °F 1903 °F (Reference 3.1)B Prior 10 CFR 50.46 Changes or Errors Corrections
-0 ° 0 0 F 1903 0 F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0 F 0 0 F 1903 0 F D Sum of 10 CFR 50.46 Changes 0 0 F 0 0 F The sum of the PCTfitom the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 1903 0 F < 2200 °F changes and errors identified since this analysis Unit 2 LBLOCA Summary Evaluation Model: CENPD-132, Supplement 4-P-A (1999 EM)Evaluation Model PCT: 2087°F Absolute PCT Net PCT Effect EfetPCT Prior 10 CFR 50.46 Changes or Error Corrections
-A Previous Years 0 °F 0 °F 2087 °F (Reference 3.1)__________
B Prior 10 CFR 50.46 Changes or Errors Corrections
-0 0 F ,0 0 F 2087 0 F Current Year C 10 CFR 50.46 Changes in Current Year Since Item B 0 0 F 0 0 F 2087 0 F D Sum of 10 CFR 50.46 Changes 0 0 F 0 0 F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for 2087 °F < 2200 °F changes and errors identified since this analysis