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Category:Letter type:L
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-004, Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years2024-01-18018 January 2024 Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years L-2024-002, Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2024-01-0808 January 2024 Withdrawal of Proposed Alternative to American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-179, Unusual or Important Environmental Event - Turtle Mortality2023-12-14014 December 2023 Unusual or Important Environmental Event - Turtle Mortality L-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023 License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5 L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update L-2023-136, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-26026 September 2023 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-122, Corrections to the 2022 Annual Radiological Environmental Operating Report2023-09-20020 September 2023 Corrections to the 2022 Annual Radiological Environmental Operating Report L-2023-127, Correction to the 2022 Annual Radioactive Effluent Release Report2023-09-18018 September 2023 Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-113, Correction to the 2020 Annual Radiological Environmental Operating Report2023-09-14014 September 2023 Correction to the 2020 Annual Radiological Environmental Operating Report L-2023-118, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-11011 September 2023 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2023-108, Report of 10 CFR 50.59 Plant Changes2023-09-11011 September 2023 Report of 10 CFR 50.59 Plant Changes L-2023-112, Corrections to the 2021 Annual Radioactive Effluent Release Report2023-09-0606 September 2023 Corrections to the 2021 Annual Radioactive Effluent Release Report L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023 Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4 L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-105, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump2023-07-26026 July 2023 Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches2023-07-26026 July 2023 Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches L-2023-097, Subsequent License Renewal Application Revision 1 - Supplement 62023-07-13013 July 2023 Subsequent License Renewal Application Revision 1 - Supplement 6 L-2023-076, In-Service Inspection Program Owner'S Activity Report (OAR-1)2023-07-11011 July 2023 In-Service Inspection Program Owner'S Activity Report (OAR-1) L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023 Subsequent License Renewal Application Revision 1, Supplement 5 L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-059, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response2023-04-21021 April 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 4 Supplemental Response L-2023-055, 2022 Annual Environmental Operating Report2023-04-12012 April 2023 2022 Annual Environmental Operating Report L-2023-041, Annual Radiological Environmental Operating Report for Calendar Year 20222023-04-0404 April 2023 Annual Radiological Environmental Operating Report for Calendar Year 2022 L-2023-051, Report of 10 CFR 50.59 Plant Changes2023-04-0404 April 2023 Report of 10 CFR 50.59 Plant Changes L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023 Periodic Update of Population Data within 10 and 50 Miles of the Plant L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023 Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4 L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023 Cycle 27 Core Operating Limits Report L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023 2022 Annual Radioactive Effluent Release Report L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023 2022 Annual Operating Report L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023 Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023 Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022 L-2023-009, Owner'S Activity Report2023-01-31031 January 2023 Owner'S Activity Report L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022 Unusual or Important Environmental Event - Turtle Mortality L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022 Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022 Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022 Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022 Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 2024-01-08
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARL-2019-051, Unusual or Important Environmental Event - Turtle Mortalities - February 4, 2019 and February 11, 20192019-02-27027 February 2019 Unusual or Important Environmental Event - Turtle Mortalities - February 4, 2019 and February 11, 2019 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-2018-005, Submittal of Emergency Core Cooling 30-Day Report2018-01-12012 January 2018 Submittal of Emergency Core Cooling 30-Day Report L-2014-248, Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours2014-07-28028 July 2014 Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours L-2014-134, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report2014-05-12012 May 2014 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Change Report L-2014-013, Submittal of Technical Specification Special Report2014-01-13013 January 2014 Submittal of Technical Specification Special Report L-2011-345, Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours2013-12-23023 December 2013 Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours L-2013-291, Submittal of Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours2013-10-0101 October 2013 Submittal of Technical Specification Special Report Radiation Monitor Inoperable Greater than 72 Hours L-2013-217, Revised Technical Specification Special Report, Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms) on June 4, 20132013-07-0303 July 2013 Revised Technical Specification Special Report, Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms) on June 4, 2013 L-2013-215, Technical Specification Special Report - Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms)2013-06-0404 June 2013 Technical Specification Special Report - Failure of Channel a Reactor Vessel Level Monitoring System (Rvlms) L-2010-139, LER, St. Lucie, Unit 1, Submittal of Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B2010-06-28028 June 2010 LER, St. Lucie, Unit 1, Submittal of Technical Specification Special Report, Inoperable Containment Sump Wide Range Level Channel B L-2009-289, Submittal of Technical Specification Special Report Reactor Vessel Level Monitoring System a Channel Level Probe (Hjtc) Out of Service2009-12-14014 December 2009 Submittal of Technical Specification Special Report Reactor Vessel Level Monitoring System a Channel Level Probe (Hjtc) Out of Service L-2009-250, Date of Event: October 6, 2009, Technical Specification Special Report, Sodium Hypochlorite Spill Greater than 100 Pounds2009-11-0505 November 2009 Date of Event: October 6, 2009, Technical Specification Special Report, Sodium Hypochlorite Spill Greater than 100 Pounds L-2009-097, LER for St. Lucie, Unit 2 Regarding Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours2009-04-20020 April 2009 LER for St. Lucie, Unit 2 Regarding Technical Specification Special Report, Radiation Monitor Inoperable Greater than 72 Hours L-2007-166, Technical Specification Special Report, Radiation Monitoring Inoperable Greater than 72 Hours2007-10-18018 October 2007 Technical Specification Special Report, Radiation Monitoring Inoperable Greater than 72 Hours L-2007-100, Technical Specification Special Report, Pressurizer Power Operate Relief Valve (PORV)2007-06-13013 June 2007 Technical Specification Special Report, Pressurizer Power Operate Relief Valve (PORV) L-2004-291, Technical Specification Special Report on Inoperable Containment Sump Wide Range Level Channel B2004-12-22022 December 2004 Technical Specification Special Report on Inoperable Containment Sump Wide Range Level Channel B L-2004-052, Technical Specification Special Report Regarding Radwaste Building Exhaust System Plant Ventilation Exhaust Monitor - Out-of-Service2004-02-23023 February 2004 Technical Specification Special Report Regarding Radwaste Building Exhaust System Plant Ventilation Exhaust Monitor - Out-of-Service L-2003-196, Special Report Re Inoperable Loose Parts Monitoring Channel, Per Requirements of Updated Final Safety Analyses Report Section 13.7.4.1 Action a2003-07-23023 July 2003 Special Report Re Inoperable Loose Parts Monitoring Channel, Per Requirements of Updated Final Safety Analyses Report Section 13.7.4.1 Action a ML18113A2701977-02-25025 February 1977 Forwards Non-Routine Radioactive Effluent Report ML18113A2861977-01-20020 January 1977 Forwards Non-Routine Environmental Operating Report Titled Impingement of Aquatic Organisms ML18088A9381976-07-29029 July 1976 Letter Attaching Reportable Occurrence 335-B-76-03 St. Lucie Unit 1 Date of Occurrence: July 1, 1976 Volume Control Tank. L-76-247, Letter Attaching Reportable Occurrence No. 335-B-76-02 Failure to Determine Condenser Delta T.1976-07-0707 July 1976 Letter Attaching Reportable Occurrence No. 335-B-76-02 Failure to Determine Condenser Delta T. 2019-02-27
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FPL JAN 1 2 2018 L-2018-005 10 CFR 50.46(a)(3)(ii)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Florida Power & Light Company St. Lucie Units 1 and 2
. Docket Nos. 50-335, 50-389 10 CFR 50.46 -Emergency Core Cooling 30-Day Report In accordance with 10 CFR 50.46(a)(3)(ii), Florida Power & Light Company (FPL) is submitting this 30-day report of an error affecting the St. Lucie Nuclear Plant (PSL), Units 1 and 2 for the emergency core cooling system (ECCS) analysis performed by AREVA Incorporated.
FPL was informed by AREVA of an error affecting the oxidation calculation in the small break loss of coolant accident (SBLOCA) analyses ofrecord. Enclosure 1 to this letter contains a description and impact of the error for Unit 1, and Enclosure 2 is provided for Unit 2.
Please contact Larry Nicholson at (561) 304-6224 should you have any questions regarding this submittal.
.:ini~
Larry ~holson Director, Nuclear Licensing and Regulatory Compliance Enclosures (2)
Florida Power & Light Company 700 Universe Boulevard, Juno Beach, FL 33408
St. Lucie Units 1 and 2 L-2018-005 Docket No. 50-335, 50-389 Enclosure 10 CFR 50.46 30-Day Report Page 1 of 4 Enclosure 1 St. Lucie Unit 1 10 CPR 50.46 30-Day Report Emergency core cooling system (ECCS) small break loss of coolant accident (SBLOCA) analysis for St.
Lucie Unit 1 is performed by AREVA Inc. The following 30-Day report, pertaining to the application of the AREVA SBLOCA evaluation model, is provided pursuant to 10 CPR 50.46(a)(3)(ii). A summary of the model changes/errors and the estimated impact on the peak cladding temperature tPCT) for SBLOCA is provided in Table 1.
1.0 SBLOCA Model Changes o S-RELAP5 Calculations of Oxidation Due to High Temperature Metal-Water Reaction AREVA determined that there is an error in the oxidation model related to high temperature metal-water reaction. In a LOCA event, the cladding can swell (and potentially rupture) due to high difference in pressure between the fuel and the system which causes the clad to thin. The clad radius increases, while the thickness decreases. It was discovered that the S-RELAP5 oxidation calculations used cold cladding dimensions and therefore did not fully account for the swelling phenomena. The error can lead to an under-prediction of the oxidation and heat from the metal-water reaction.
- The PCT impact of the oxidation error is estimated to be +2 °P for St. Lucie Unit 1.
Previous SBLOCA PCT changes are documented in Reference 2.1. Table 1 summarizes the estimated impact of the changes/errors on the St. Lucie Unit 1 SBLOCA PCT, along with the cumulative effect of absolute PCT changes.
The cumulative impact for the SBLOCA evaluation model PCT is 84 °P. The final PCT including all changes/errors, is 1852 °P, which maintains significant margin to the limit of2200 °F.
2.0 References 2.1 L-2017-157, "St. Lucie Unit 1 Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CPR 50.46 30-Day Report," September 13, 2017.
(MLl 7258A037)
St. Lucie Units 1 and 2 L-2018-005 Docket No. 50-335, 50-389 Enclosure 10 CFR 50.46 30-Day Report Page 2 of 4 Enclosure 1 Table 1 St. Lucie Unit 1 SBLOCA Margin Summary Sheet - 30 Day Report Plant Name: St. Lucie Unit 1 Utility Name: NextEra Energy Evaluation Model: EMF-2328(P)(A) Rev. 0 as supplemented by ANP-3000(P), Revision 0.
Evaluation Model PCT: 1828°P Net PCT Absolute PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections -
A +22 °P 82 °P up to Year 2016 Prior 10 CPR 50.46 Changes or Error Corrections - 0 op 0 op B
Reported in Year 2017 C 10 CPR 50.46 Changes in Year 2017 Since Item B Error in oxidation calculations due to high +2 op 2 op temperature metal-water reaction D Sum of 10 CPR 50.46 Changes +24 °P 84 °P The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates of PCT 1852 °F < 2200 °F impact for changes and errors identified since this analysis
St. Lucie Units 1 and 2 L-2018-005 Docket No. 50-335, 50-389 Enclosure 10 CFR 50.46 30-Day Report Page 3 of4 Enclosure 2 St. Lucie Unit 2 10 CFR 50.46 30-Day Report Emergency core cooling system (ECCS) small break loss of coolant accident (SBLOCA) analysis for St.
Lucie Unit 2 is performed by AREVA Inc. The following 30-Day report, pertaining to the application of the AREVA SBLOCA evaluation model, is provided pursuant to 10 CFR 50.46(a)(3)(ii). A summary of the model changes/errors and the estimated impact on the peak cladding temperature (PCT) for SBLOCA is provided in Table 1.
1.0 SBLOCA Model Changes o M5 LOCA Swelling and Rupture Model (SRM) Update AREVA determined that certain aspects of the SRM model would be impacted when considering additional M5 cladding rupture test data since the model's approval by the NRC as part of M5 licensing. Following the same approach as the original model, an updated M5 SRM was developed to take into account the updated test database.
- The PCT impact of the updated model is estimated to be O °F for St. Lucie Unit 2.
o S-RELAP5 Calculations of Oxidation Due to High Temperature Metal-Water Reaction AREVA determined that there is an error in the oxidation model related to high temperature metal-water reaction. In a LOCA event, the cladding can swell (and potentially rupture) due to high difference in, pressure between the fuel and the system which causes the clad to thin. The clad radius increases, while the thickness decreases. It was discovered that the S-RELAP5 oxidation calculations used cold cladding dimensions and therefore did not fully account for the swelling phenomena. The error can lead to an under-prediction of the oxidation and heat from the metal-water reaction.
- The PCT impact of the oxidation error is estimated to be +57 °F for St. Lucie Unit 2.
o Change in Analysis HPSI Flow Assumption In order to offset some of the impact of the aforementioned error, a change is made to the HPSI flow to credit some of the available conservatism in the HPSI flow, while still maintaining adequate margin to the pump test criteria.
- The PCT impact of the HPSI flow change is estimated to be -336 °F for St. Lucie Unit 2.
Previous SBLOCA PCT changes are documented in Reference 2.1. Table 1 summarizes the estimated impact of the changes/errors on the St. Lucie Unit 2 SBLOCA PCT, along with the cumulative effect of absolute PCT changes.
The cumulative impact for the SBLOCA evaluation model PCT is 393 °F. The final PCT including all changes/errors, is 1778 °F, which maintains significant margin to the limit of 2200 °F.
2.0 References 2.1 . L-2017-056, "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 27, 2017. (MLl 7086A321).
St. Lucie Units 1 and 2 L-2018-005 Docket No. 50-335, 50-389 Enclosure 10 CFR 50.46 30-Day Report Page 4 of 4 Enclosure 2 Table 1 St. Lucie Unit 2 SBLOCA Margin Summary Sheet- 30 Day Report Plant Name: St. Lucie Unit 2 Utility Name: NextEra Energy Evaluation Model: EMP-2328(P)(A) Rev. 0 Evaluation Model PCT: 2057°P Net PCT Absolute PCT Effect Effect Prior 10 CPR 50.46 Changes or Error Corrections - 0 op 0 op A
up to Year 2016 Prior 10 CPR 50.46 Changes or Error Corrections-B None None Reported in Year 2017 C 10 CPR 50.46 Changes in Year 2017 Since Item B SRM Model Update due to new rupture test data 0 op 0 op Error in oxidation calculations due to high
+57 °P 57 °P temperature metal-water reaction Change in analysis HPSI flow assumption -336 °P 336 °P D Sum of 10 CPR 50.46 Changes -279°P 393 °P The sum of the PCTfrom the most recent analysis using an acceptable evaluation model and the estimates ofPCT 1778 °F < 2200 °F impact for changes and errors identified since this analysis