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| {{#Wiki_filter:* F=PL. .. 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 MAR 2 7 20t7 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 Annual Report L-2017-056 10 CPR 50.46 Pursuant to 10 CPR 50.46(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. | | {{#Wiki_filter:*F=PL.. |
| The data interval for this report is from January 1, 2016 through December 31, 2016. Please contact Ken Prehafer at 772-467-77 48 should you have any questions regarding this submittal. | | MAR 2 7 20t7 L-2017-056 10 CPR 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 CPR 50.46 Annual Report Pursuant to 10 CPR 50.46(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 this report is from January 1, 2016 through December 31, 2016. |
| Sincerely, Licensing Manager St. Lucie Plant MJS/K\W Attachment cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Nuclear Plant Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2017-056 Attachment Page 1 of 3 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 (W), 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, 2016 through December 31, 2016. A discussion of the changes follows. | | Please contact Ken Prehafer at 772-467-77 48 should you have any questions regarding this submittal. |
| 1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA No errors were found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1.
| | Sincerely, |
| Table 1 provides a summary of PCT changes for St. Lucie Unit 1.
| | ~if;£/ |
| 1.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1.
| | Licensing Manager St. Lucie Plant MJS/K\W Attachment cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Nuclear Plant Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957 |
| Table 1 provides a summary of PCT changes for St. Lucie Unit 1.
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| 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.
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| Table 2 provides a summary of PCT changes for St. Lucie Unit 2.
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| 2.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1.
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| Table 2 provides a summary of PCT changes for St. Lucie Unit 2.
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| ==3.0 REFERENCES==
| | L-2017-056 Attachment Page 1 of 3 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 (W), 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, 2016 through December 31, 2016. A discussion of the changes follows. |
| | 1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA No errors were found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 1 provides a summary of PCT changes for St. Lucie Unit 1. |
| | 1.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 1 provides a summary of PCT changes for St. Lucie Unit 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. Table 2 provides a summary of PCT changes for St. Lucie Unit 2. |
| | 2.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 2 provides a summary of PCT changes for St. Lucie Unit 2. |
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| 3.1 Letter L-2016-049, Eric Katzman to U.S. Nuclear Regulatory Commission Attn: Document Control Desk, "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," March 2, 2016 (ML16077A230). | | ==3.0 REFERENCES== |
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| L-2017-056 Attachment Page 2 of 3 Table 1: 2016 St. Lucie Unit 1 SBLOCA and LBLOCA PCT Summary Unit 1 SBLOCA Summary | | 3.1 Letter L-2016-049, Eric Katzman to U.S. Nuclear Regulatory Commission Attn: Document Control Desk, 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, March 2, 2016 (ML16077A230). |
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| Evaluation Model: EMF-2328(P)(A) Rev. 0 as supplemented by ANP-3000(P), Revision 0. | | L-2017-056 Attachment Page 2 of 3 Table 1: 2016 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 Absolute PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections - |
| | A +22 °F 82 °F up to Year 2015 Prior 10 CFR 50.46 Changes or Error Corrections - |
| | B None None Year 2016 C 10 CFR 50.46 Changes in Year 2016 Since Item B None None D Sum of 10 CFR 50.46 Changes +22 °F 82 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1850 F < 2200 F impact for changes and errors identified since this analysis Unit 1 LBLOCA Summary Evaluation Model: EMF-2103(P)(A) Rev. 0 as supplemented by ANP-2903(P), |
| | Revision 1. |
| | Evaluation Model PCT: 1788°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections A +6 °F 6°F |
| | - up to Year 2015 Prior 10 CFR 50.46 Changes or Error Corrections B None None |
| | - Year 2016 C 10 CFR 50.46 Changes in Year 2016 Since Item B Incorrect cutback ratio applied to gadolina bearing |
| | +0 °F 0 °F rods D Sum of 10 CFR 50.46 Changes +6 °F 6°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1794 F < 2200 F impact for changes and errors identified since this analysis |
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| Evaluation Model PCT: 1828°F
| | L-2017-056 Attachment Page 3 of 3 Table 2: 2016 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°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections - |
| Net PCT Effect Absolute PCT Effect A Prior 10 CFR 50.46 Changes or Error Corrections - up to Year 2015 +22 °F 82 °F B Prior 10 CFR 50.46 Changes or Error Corrections -
| | A 0 °F 0 °F up to Year 2015 Prior 10 CFR 50.46 Changes or Errors Corrections - |
| Year 2016 None None C 10 CFR 50.46 Changes in Year 2016 Since Item B None None D Sum of 10 CFR 50.46 Changes +22 °F 82 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis 1850 F < 2200 F Unit 1 LBLOCA Summary
| | B None None Year 2016 C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1903 °F < 2200 °F impact for 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 Effect Prior 10 CFR 50.46 Changes or Error Corrections - |
| Evaluation Model: EMF-2103(P)(A) Rev. 0 as supplemented by ANP-2903(P), Revision 1.
| | A up to Year 2015 0 °F 0 °F (Reference 3.1) |
| | | Prior 10 CFR 50.46 Changes or Errors Corrections - |
| Evaluation Model PCT: 1788°F
| | B None None Year 2016 C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 2087 °F < 2200 °F impact for changes and errors identified since this analysis}} |
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| Net PCT Effect Absolute PCT Effect A Prior 10 CFR 50.46 Changes or Error Corrections - up to Year 2015 +6 °F 6°F B Prior 10 CFR 50.46 Changes or Error Corrections - Year 2016 None None C 10 CFR 50.46 Changes in Year 2016 Since Item B Incorrect cutback ratio applied to gadolina bearing rods +0 °F 0 °F D Sum of 10 CFR 50.46 Changes +6 °F 6°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis 1794 F < 2200 F L-2017-056 Attachment Page 3 of 3 Table 2: 2016 St. Lucie Unit 2 SBLOCA and LBLOCA PCT Summary Unit 2 SBLOCA Summary
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| Evaluation Model: CENP D-137, Supplement 2-P-A (S2M) | |
| Evaluation Model PCT: 1903°F Net PCT Effect Absolute PCT Effect A Prior 10 CFR 50.46 Changes or Error Corrections - up to Year 2015 0 °F 0 °F B Prior 10 CFR 50.46 Changes or Errors Corrections - | |
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| Year 2016 None None C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis 1903 °F < 2200 °F Unit 2 LBLOCA Summary | |
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| Evaluation Model: CENP D-132, Supplement 4-P-A (1999 EM) | |
| Evaluation Model PCT: 2087°F Net PCT Effect Absolute PCT Effect A Prior 10 CFR 50.46 Changes or Error Corrections - up to Year 2015 (Reference 3.1) 0 °F 0 °F B Prior 10 CFR 50.46 Changes or Errors Corrections - | |
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| Year 2016 None None C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis 2087 °F < 2200 °F}} | |
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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 type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
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MAR 2 7 20t7 L-2017-056 10 CPR 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 CPR 50.46 Annual Report Pursuant to 10 CPR 50.46(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 this report is from January 1, 2016 through December 31, 2016.
Please contact Ken Prehafer at 772-467-77 48 should you have any questions regarding this submittal.
Sincerely,
~if;£/
Licensing Manager St. Lucie Plant MJS/K\W Attachment cc: USNRC Regional Administrator, Region II USNRC Senior Resident Inspector, St. Lucie Nuclear Plant Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
L-2017-056 Attachment Page 1 of 3 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 (W), 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, 2016 through December 31, 2016. A discussion of the changes follows.
1.0 ST LUCIE UNIT 1 1.1 Changes to SBLOCA No errors were found in the SBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 1 provides a summary of PCT changes for St. Lucie Unit 1.
1.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 1 provides a summary of PCT changes for St. Lucie Unit 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. Table 2 provides a summary of PCT changes for St. Lucie Unit 2.
2.2 Changes to LBLOCA No errors were found in the LBLOCA ECCS performance analysis since the previous annual report of Reference 3.1. Table 2 provides a summary of PCT changes for St. Lucie Unit 2.
3.0 REFERENCES
3.1 Letter L-2016-049, Eric Katzman to U.S. Nuclear Regulatory Commission Attn: Document Control Desk, 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, March 2, 2016 (ML16077A230).
L-2017-056 Attachment Page 2 of 3 Table 1: 2016 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 Absolute PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections -
A +22 °F 82 °F up to Year 2015 Prior 10 CFR 50.46 Changes or Error Corrections -
B None None Year 2016 C 10 CFR 50.46 Changes in Year 2016 Since Item B None None D Sum of 10 CFR 50.46 Changes +22 °F 82 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1850 F < 2200 F impact for changes and errors identified since this analysis Unit 1 LBLOCA Summary Evaluation Model: EMF-2103(P)(A) Rev. 0 as supplemented by ANP-2903(P),
Revision 1.
Evaluation Model PCT: 1788°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections A +6 °F 6°F
- up to Year 2015 Prior 10 CFR 50.46 Changes or Error Corrections B None None
- Year 2016 C 10 CFR 50.46 Changes in Year 2016 Since Item B Incorrect cutback ratio applied to gadolina bearing
+0 °F 0 °F rods D Sum of 10 CFR 50.46 Changes +6 °F 6°F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1794 F < 2200 F impact for changes and errors identified since this analysis
L-2017-056 Attachment Page 3 of 3 Table 2: 2016 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°F Absolute PCT Net PCT Effect Effect Prior 10 CFR 50.46 Changes or Error Corrections -
A 0 °F 0 °F up to Year 2015 Prior 10 CFR 50.46 Changes or Errors Corrections -
B None None Year 2016 C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 1903 °F < 2200 °F impact for 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 Effect Prior 10 CFR 50.46 Changes or Error Corrections -
A up to Year 2015 0 °F 0 °F (Reference 3.1)
Prior 10 CFR 50.46 Changes or Errors Corrections -
B None None Year 2016 C 10 CFR 50.46 Changes in Current Year Since Item B None None D Sum of 10 CFR 50.46 Changes 0 °F 0 °F The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT 2087 °F < 2200 °F impact for changes and errors identified since this analysis