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{{Adams
#REDIRECT [[L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report]]
| number = ML15092A097
| issue date = 03/24/2015
| title = St. Lucie, Units 1 and 2, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report
| author name = Katzman E S
| author affiliation = Florida Power & Light Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000335, 05000389
| license number =
| contact person =
| case reference number = L-2015-093
| document type = Graphics incl Charts and Tables, Letter, Report, Technical
| page count = 5
}}
 
=Text=
{{#Wiki_filter:0FPL.March 24, 2015L-2015-09310 CFR 50.46U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555Re: St. Lucie Units 1 and 2Docket Nos. 50-335 and 50-389Acceptance Criteria for Emergency Core CoolingSystems for Light Water Nuclear Power Reactors10 CFR 50.46 Annual ReportPursuant to 10 CFR 50.46(a)(3)(ii), the nature of any change to or error discovered in the evaluationmodels for emergency core cooling systems (ECCS), or in the application of such models, thataffect the fuel cladding temperature calculations for St. Lucie Units 1 and 2 is reported in theattachment to this letter. The estimated effect from any such change or error on the limiting ECCSanalysis for each unit is also addressed. The data interval for the report is from January 1, 2014through December 31, 2014.Please contact Ken Frehafer at 772-467-7748 should you have any questions regarding thissubmittal.Sincerely,Eric S. KatzmanLicensing ManagerSt. Lucie PlantES K/K WFAttachmentFlorida Power & Light Company6501 S. Ocean Drive, Jensen Beach, FL 34957 L-2015-093AttachmentPage 1 of 4St. Lucie Units I and 210 CFR 50.46 Annual ReportEmergency core cooling system (ECCS) analyses for St. Lucie Unit 1 and St. Lucie Unit 2 are performed byAREVA and Westinghouse Electric Company (W), respectively. The following information pertaining to theevaluation 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 CFR50.46(a)(3)(ii). A summary of calculated peak cladding temperature (PCT) changes is provided in Tables I and 2(for St. Lucie Units I and 2, respectively). The data interval for this report is from January 1, 2014 throughDecember 31, 2014. A discussion of the changes follows.1.0 ST LUCIE UNIT 11.1 Changes to SBLOCAOne error was found in the SBLOCA ECCS performance analysis since the previous annual report ofReference 3.1.The vapor absorptivity correlation was incorrectly applied outside of the bounds of the correlation. When theequations using the correlation were truncated at the appropriate conditions, the estimated impact was 90 'F.This error was previously reported in a 30-day report in Reference 3.2.The limiting SBLOCA PCT with the above estimated impact is 1870 'F and is documented in Table 1.1.2 Changes to LBLOCAThere were two errors found in the LBLOCA ECCS performance analysis since the previous annual report ofReference 3.1.The vapor absorptivity correlation was incorrectly applied outside of the bounds of the correlation. When theequations using the correlation were truncated at the appropriate conditions, the estimated impact was 0 'F.The modal decomposition (re-mapping of neutronics nodes to S-RELAP5 node structure) resulted in non-physical axial shapes being generated in some cases. For PSL I the shapes generated still remained applicable,therefore the estimated impact was 0 'F.The limiting LBLOCA PCT with the above estimated impact is 1672 'F and is documented in Table 1.2.0 ST. LUCIE UNIT 22.1 Changes to SBLOCANo errors were found in the SBLOCA ECCS performance analysis since the previous annual report ofReference 3.1. The limiting SBLOCA PCT remains at 1903 'F and is documented in Table 1.2.2 Changes to LBLOCANo errors were found in the LBLOCA ECCS performance analysis since the previous annual report ofReference 3.1. The limiting LBLOCA PCT remains at 2087 'F and is documented in Table 1.
L-2015-093AttachmentPage 2 of
 
==43.0 REFERENCES==
3.1 Letter L-2014-095, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St.Lucie Units I and 2 Docket Nos. 50-335 and 50-389 Acceptance Criteria for Emergency Core CoolingSystems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report," March 31, 2014.3.2 Letter L-2014-134, Eric Katzman to U.S. Nuclear Regulatory Commission Document Control Desk, "St.Lucie Unit I Docket No. 50-335 Acceptance Criteria for Emergency Core Cooling Systems for LightWater Nuclear Power Reactors 10 CFR 50.46 Change Report," May 12, 2014.
L-2015-093AttachmentPage 3 of 4Table 1: 2014 St. Lucie Unit 1 SBLOCA and LBLOCA PCT SummaryUnit 1 SBLOCA SummaryEvaluation Model: EMF-2328(P)(A) Rev. 0 as supplementedEvaluation Model PCT: 18071Fby ANP-3000(P), Revision 0Net PCT EffectAbsolute PCTEffectPCTPrior 10 CFR 50.46 Changes or ErrorA Corrections -Previous Years -27 OF 27 OF 1780 OF(Reference 3. 1)B Prior 10 CFR 50.46 Changes or Errors See below See belowCorrections -Current Year (Reference 3.2)Vapor absorptivity correlation applied +90 OF 90 OF 1870 0Foutside the bounds of the correlationC 10 CFR 50.46 Changes in Current Year 0 OF 0 OF 1870 OFSince Item BD Absolute Sum of 10 CFR 50.46 Changes APCT 117 OFThe sum of the PCTfrom the most recent analysis using anacceptable evaluation model and the estimates of PCT impact for 1870 OF < 2200 OFchanges and errors identified since this analysisUnit 1 LBLOCA SummaryEvaluation Model: EMF-2103(P)(A) Rev. 0 as supplemented by ANP-2903(P), Revision 1Evaluation Model PCT: 16670FAbsolute PCTNet PCT Effect Effe PCTEffectPrior 10 CFR 50.46 Changes or ErrorA Corrections -Previous Years +5 OF 23 OF 1672 OFS(Reference 3.1)B Prior 10 CFR 50.46 Changes or Errors +0 OF 0 OF 1672 OFCorrections -Current YearC 10 CFR 50.46 Changes in Current Year See below See belowSince Item BVapor absorptivity correlation applied +0 OF 0 OF 1672 OFoutside the bounds of the correlationModal decomposition generation of non- +0 OF 0 OF 1672 OFphysical shapesD Absolute Sum of 10 CFR 50.46 Changes APCT 230FThe sum of the PCTfrom the most recent analysis using anacceptable evaluation model and the estimates of PCT impact for 1672 OF < 2200 OFchanges and errors identified since this analysis L-2015-093AttachmentPage 4 of 4Table 2: 2014 St. Lucie Unit 2 SBLOCA and LBLOCA PCT SummaryUnit 2 SBLOCA SummaryEvaluation Model: CENPD-137, Supplement 2-P-A (S2M)Evaluation Model PCT: 19031FNet PCT EffectAbsolute PCTEffectPCTPrior 10 CFR 50.46 Changes or ErrorA Corrections -Previous Years 0 OF 0 OF 1903 OF(Reference 3.1)B Prior 10 CFR 50.46 Changes or Errors 0 OF 0 OF 1903 OFCorrections -Current YearC 10 CFR 50.46 Changes in Current Year 0 OF 0 OF 1903 OFSince Item BD Absolute Sum of 10 CFR 50.46 Changes APCT 0 &deg;FThe sum of the PCTfrom the most recent analysis using anacceptable evaluation model and the estimates of PCT impact for 1903 OF < 2200 OFchanges and errors identified since this analvsisUnit 2 LBLOCA SummaryEvaluation Model: CENPD-132, Supplement 4-P-A (1999 EM)Evaluation Model PCT: 20871FAbsolute PCTNet PCT Effect EfetPCTEffectPrior 10 CFR 50.46 Changes or ErrorA Corrections -Previous Years 0 OF 0 OF 2087 OF(Reference 3.1)B Prior 10 CFR 50.46 Changes or Errors 0 OF 0 OF 2087 OFCorrections -Current YearC 10 CFR 50.46 Changes in Current Year 0 OF 0 OF 2087 OFSince Item BD Absolute Sum of 10 CFR 50.46 Changes APCT 0 OFThe sum of the PCTfrom the most recent analysis using anacceptable evaluation model and the estimates of PCT impact for 2087 OF < 2200 OFchanges and errors identified since this analysis}}

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