ML14135A511

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Enclosure 4 to BSEP 14-0048 - Areva Mellla+ Methods Applicability Presentation (Non-Proprietary Version)
ML14135A511
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/17/2014
From:
AREVA
To:
Office of Nuclear Reactor Regulation
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ML14136A059 List:
References
BSEP 14-0048
Download: ML14135A511 (34)
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{{#Wiki_filter:Enclosure 4BSEP 14-0048AREVA MELLLA+ Methods Applicability Presentation (Non-Proprietary Version) AREVAforward-looking energy AREVA MELLLA+Methods Applicability AAREVAforward-looking energy AGENDAO Overview of the AREVA MELLLA+ Methods Applicability DocumentHistory of AREVA experience in licensing and testing0o Enhanced Option IIIO AREVA application of fuel specific limitations and conditions from generic MELLLA+ topical NEDO-33006A AAREVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014 --p.3 Applicability of AREVAMethods in MELLLA+io The applicability of AREVA methods to MELLLA+ conditions is described in the Methods Applicability Report (ANP-3108) Address AREVA topical reports" Review all SE restrictions for applicability to MELLLA+" Review that the codes have been appropriately benchmarked to cover expectedMELLLA+ operation Describes the AREVA modeling of bypass voidingDescribes AREVA implementation of any methodology deviations

  • i.e. AREVA's approach to thermal conductivity degradation Content of this report covers methodologies needed to support thenecessary fuel specific analyses that AREVA is performing for Brunswick MELLLA+This report will be submitted with the Brunswick MELLLA+ LARAAREVAARE VA MELLLA+ Methods Applicability

-17 April 2014- p.4 forward.loking energy Applicability of AREVAMethods in MELLLA+.Po Topical Report ReviewNo SER restrictions on power level or flow in AREVA topical reports.No SER restrictions on the parameters most impacted by the increased power level: steam flow, feedwater flow, jet pump M-ratio, and coreaverage void fractionOo AREVA methodologies are characterized by technically rigorous treatment of phenomena and are very wellbenchmarked Il Recent experience is tabulated on the following slidesFor comparison Power/Flow ratio is used as the figure of meritAAREVAAREVA MELLLA+ Methods Applicability -17 April 2014- p.5 forward-ook(ng eiergy AREVA Experience BasePlantClass Rated PowerMWtMin Core Flowat Rated Power(Mlb/hr) (estimated) Power/Flow MW/MIb/hr Brunswick EPUBrunswick EPU and EFWChinshanSusquehanna Grand GulfRiver BendKuoshengBWR4BWR4BWR4BWR4BWR6BWR6BWR62923.002923.001840.003952.003833.003091.002894.0076.2365.4542.0299.0084.3870.1463.3838.3444.6643.7939.9245.4344.0745.66AAR EVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014 -p.6 AREVA Experience Baselo Applicability of AREVA MethodsAs can be seen from this information, the power I flow ratio in thisexperience base exceeds that associated with MELLLA+ for Brunswick The validity of AREVA methods to the Brunswick core design are furtherillustrated by combining both test data and assembly conditions used inthe qualification of MICROBURN-B2 and compared on the next slideThe data is presented in terms of the key physical phenomena (e.g. fluidexit quality and assembly flow) as they relate closely to the exit voidfractions AAREVA MELLLA+ Methods Applicability -17 April 2014 -p.7 AR EVAforward-looking energy AREVA Experience BaseAAREVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014 -p.8 Applicability of AREVAMethods in MELLLA+Oo. AREVA licensing methodology is required to push the limits to theSafety Limit conditions This approaches boiling transition for the worst assembly regardless of thecore conditions lo Pressure drop testing is performed of boiling transition Oo Void measurements are performed point of boiling transition as close as possible to the pointas close as possible to theOo AREVA models are qualified to the point of boiling transition AAREVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014 -p.9 Applicability of AREVAMethods in MELLLA+lo AREVA uses conservative methods to address the potential for boiling in the bypass I Water Channel regionsWater Channels /Rods are modeled explicitly and separately from thebypass region in the areas of potential bypass voiding[For the LPRM detector response analyses are performed with CASMO-4to determine the sensitivity to water density in the bypass region andappropriate penalties are applied to the OPRM setpoints. AAREVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014 -p.10 Applicability of AREVAMethods in MELLLA+Pp AREVA uses Zubar-Findlay drift flux model for predicting voidfractionS[ ] void correlation is used in nuclear design, frequency domain stability, and nuclear AOO transient and accident analysesOhkawa-Lahey void correlation is used in thermal-hydraulic design,system transient AOO and accident, and loss of coolant accidentBoth correlations have been validated against the FRIGG experiments, aswell as void fraction measurements for ATRIUM-10 and ATRIUM IOXM atthe KATHY test facilityATRIUM 1OXM tests measured void fractions up to [ ]AAREVA MELLLA+ Methods Applicability -17 April 2014 -p.11 AR EVAforward-looking energy Applicability of AREVAMethods in MELLLA+AAREVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014 -p. 12 Applicability of AREVAMethods in MELLLA+AAR EVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014- p.13 Applicability of AREVAMethods in MELLLA+lo Void quality correlations have been benchmarked usingATRIUM-10 and ATRIUM 1OXM dataI ] matches data with very little biasOhkawa-Lahey exhibits some bias in the 0.5-0.8 void fraction rangee Still within 5% of measured voidSensitivity studies performed with a modified void-quality correlation toremove the bias* Also performed analyses with a void-quality correlation that was biased by +/-_.5%" Analyses with the best-estimate void quality correlation showed an insignificant change in results" Impact of the +/-5% bias to correlation was shown to be bound by the conservatism built into the methodAAREVAAREVA MELLLA+ Methods Applicability -17 April 2014 -p.14 forward-looking energy Thermal Conductivity Degradation Oo Fuel thermal conductivity degradation with exposure has beenevaluated Halden ultra-high-burnup experiment indicated steady degradation in thethermal conductivity of uranium fuel pellets with increasing exposureNRC expressed concern that some vendors might still be using codes forsafety analyses that do not account for this phenomenon and therefore may produce non-conservative resultsAREVA uses RODEX4 for thermal-mechanical analyses (which containsmodels for TCD)Methodologies based on RODEX212a are affected" AOO transient methodology (COTRANSA2/XCOBRA/XCOBRA-T) " LOCA (RELAX/RODEX2/HUXY) " Overpressurization (COTRANSA2/RODEX2) " Fire Event (RELAX/RODEX2/HUXY) AAREVA MELLLA+ Methods Applicability -17 April 2014 -p. 15 AR EVA Thermal Conductivity Degradation lo AOO Transient Methodology (COTRANSA21XCOBRA/XCOBRA-T) Benchmarking to Peach Bottom Turbine Trip did not include conductivity degradation AURORA-B was used to determine the sensitivity to conductivity degradation " AURORA-B is RODEX4 based* AURORA-B sensitivity studies show that the impact of fuel thermal conductivity degradation with exposure results in a decrease in the ACPR of [] increase in the transient LHGR excursion " For Brunswick MELLLA+ LHGR evaluation will be done with RODEX4 so thermalconductivity degradation is already accounted for" Effect is small and within the conservatism of the methodology

  • MCPR and LHGR limits are not impactedAAR EVAAREVA M ELLLA+ Methods Applicability

-17 April2014-p.16 forward-looking energy Thermal Conductivity Degradation No LOCA (RELAX/RODEX2/HUXY) Degraded thermal conductivity in the fuel will increase centerline temperature increasing the fuel stored energy" Following the loss of coolant, the heat transfer is driven by the degraded heat transferto the coolant" Temperature profile in the pellet is very flat so RELAX and HUXY models are notsensitive to conductivity RODEX4 was used to determine the change in stored energyUsed to increase the RODEX2 calculated stored energy to account forconductivity degradation e Very conservative since RODEX2 was designed to produce conservatively high storedenergy for AREVA Appendix K LOCA calculations Brunswick MELLLA+ LOCA analyses were evaluated for the effect ofthermal conductivity degradation

  • BOL remains limiting when no conductivity degradation has yet occurredAAR EVAAREVA M ELLLA+ Methods Applicability

-17 April 2014- p.17 forward-looking energy Thermal Conductivity Degradation lo Overpressurization (COTRANSA2/RODEX2) ASME Overpressurization

  • 30% reduction in fuel thermal conductivity showed a slight reduction in peak pressure* No credit taken for this reduction ATWS Overpressurization 9 30% reduction in fuel thermal conductivity increased the pressure increase by [The effects of thermal conductivity on overpressurization analyses willbe tracked and applied each reloadPo Fire event (RELAX/RODEX21HUXY)

Effect of thermal conductivity similar to LOCAHowever, PCT is much lower than LOCASimilar to LOCA, PCT is limiting at BOLAAREVAAREVA MELLLA+ Methods Applicability -17 April 2014 -p. 18 forward-looking energy LOCA Analysis ApproachAAR EVAforward-looking energyAREVA MELLLA+ Methods Applicability -17 April 2014 -p.19 Enhanced Option IIIPl AREVA has performed the fuel specific analyses required tosupport Enhanced Option III (EO-Ill)Enhanced Option III is an extension of the original Option III Long TermStability Solution to the MELLLA+ domain" Original Option III methodology maintained

  • An additional automatic scram region to protect against single channel oscillations was introduced to maintain applicability of Option III in MELLLA+EO-Ill approved for MELLLA+ application in ANP-10262PA Rev 0Approval of EMF-3028PA Volume 2 Rev 4 formally approved use ofRAMONA5-FA in MELLLA+ and removed the interim 10% penalty onRAMONA5-FA MELLLA+ results AREVA will provide channel exclusion region boundaries and OPRM setpointcalculations
  • Provided in the MELLLA+ Reload Safety Analysis Report (ANP-3280(P))

AAR EVAAREVA MELLLA+ Methods Applicability -17 April 2014- p.20 forward Iooking energy Review of Generic MELLLA+Limitations and Conditions lo The restrictions for fuel dependent analyses presented inNEDO-33006A were reviewed for applicability to AREVAmethodsMost restrictions have been appliedSome restrictions are specific to the methodology being usedMethodology specific restrictions were adapted to provide a comparable AREVA resultMethodology independent restrictions are appliedSummary of fuel specific implementation of MELLLA+ limitations andconditions from Section 12 of the SE to NEDO-33006A followsAAREVAAREVA MELLLA+ Methods Applicability -17 April 2014- p.21 forward-looking energy Review of Generic MELLLA+Limitations and Conditions Oo Section 12.1: GEXL-PLUS Requirement: Plant-specific application will confirm that for operation within the boundary defined by the MELLLA+ upper boundary andmaximum CF range, the GEXL-PLUS experimental data base covers thethermal-hydraulic condition the fuel bundles will experience " AREVA licensing methods are programmed to determine whether assemblyconditions fall outside of the approved range for the CHF correlation " If conditions are outside of approved range the codes impose the approved corrective actions* The implementation of AREVA correlations is discussed in Methods Applicability Report ANP-3108P Requirement: In addition, the plant-specific application will confirm that theexperimental pressure drop database for the pressure drop correlation coversthe pressure drops anticipated in the MELLLA+ range.* The range of the experimental database was shown in a previous slide and isdocumented in Methods Applicability Report ANP-3108P AAREVAAREVA MELLLA+ Methods Applicability -17 April 2014-- p.22 forward-looking energy Review of Generic MELLLA+Limitations and Conditions Po Section 12.3: Concurrent changesRequirement: If a new GE fuel product line or another vendor's fuel is loadedat the plant, the applicability of any generic sensitivity analyses supporting theMELLLA+ application shall be justified in the plant-specific application. If thegeneric sensitivity analyses cannot be demonstrated to be applicable, theanalyses will be performed including the new fuel.* New analyses are being provided for any analysis that is potentially impacted by fuelOo Section 12.4: Reload Analysis Submittal Requirement: The plant-specific MELLLA+ application shall provide the plant-specific thermal limits assessment and transient analysis results.9 Provided in the MELLLA+ Reload Safety Analysis Report (ANP-3280(P)) Requirement: Additionally, the SRLR for the initial MELLLA+ implementation cycle shall be submitted for NRC staff confirmation o The Reload Safety Analysis Report for the initial MELLLA+ implementation cycle willbe submitted when available AAREVA MELLLA+ Methods Applicability -17 April 2014 --p.23 AR EVAforward-looking enrergy Review of Generic MELLLA+Limitations and Conditions I' Section 12.6: SLMCPR Statepoints and CF Uncertainty Requirement: Until such time when the SLMCPR methodology (References 40 and 41) for off-rated SLMCPR calculation is approved by the staff forMELLLA+ operation, the SLMCPR will be calculated at the rated statepoint (120 percent P/100 percent CF), the plant-specific minimum CF statepoint (e.g., 120 percent P/80 percent CF), and at the 100 percent OLTP at 55percent CF statepoint

  • AREVA performs SLMCPR analyses to bound the full power/flow domain" Performed analyses at 1 00%P/1 04.5%F, 1 00%P/85%F, and 55% core flow andhighest licensed power level" Results for all three statepoints are provided in the MELLLA+ Reload Safety AnalysisReport (ANP-3280(P))

Requirement: The currently approved off-rated CF uncertainty will be 'usedfor the minimum CF and 55 percent CF statepoints. The uncertainty must beconsistent with the CF uncertainty currently applied to the SLO operation or asNRC-approved for MELLLA+ operation.

  • SLO core flow uncertainty applied to the 85% and 55% core flow analysesAAR EVAAREVA MELLLA+ Methods Applicability

-17 April 2014 -p.24 ar E erforward-looking energy Review of Generic MELLLA+Limitations and Conditions I' Section 12.6: SLMCPR Statepoints and CF Uncertainty Requirement: The calculated values will be documented in the SRLR* Provided results for all calculated power/flow points in the MELLLA+ Reload SafetyAnalysis Report (ANP-3280(P)) Analyses showed that the limiting statepoint is the 55% core flow pointA 0.01 increase in SLMCPR is required for MELLLA+9 MELLLA+ SLMCPR for TLO is 1.09AAREVA MELLLA+ Methods Applicability -17 April 2014 -p.25 AR EVA Review of Generic MELLLA+Limitations and Conditions lo Section 12.10: ECCS-LOCA Off-Rated Multiplier Requirement: The plant-specific application will provide the 10 CFR Part 50,Appendix K, and the nominal PCTs calculated at the rated EPU power/rated CF, rated EPU power/minimum CF, at the low-flow MELLLA+ boundary(Transition Statepoint). For the limiting statepoint, both the upper bound andthe licensing PCT will be reported" Analyses performed at Rated power/[] consistent with definition of the transition statepoint from SEsection 4.3.1.3" Appendix K PCTs reported in the Break Spectrum Report (ANP-3105P) Requirement: The M+SAR will justify why the transition statepoint ECCS-LOCA response bounds the 55 percent CF statepoint " The transition statepoint is defined per Section 4.3.1.3 of the SE to NEDO-33006A " Discussion of the transition statepoint given in the Break Spectrum Report (ANP-3105P)AAR EVAAREVA MELLLA+ Methods Applicability -17 April 2014 -p.26 forward-ooking energy Review of Generic MELLLA+Limitations and Conditions Oo Section 12.10: ECCS-LOCA Off-Rated Multiplier

4. Requirement:

The COLR and the SRLR will contain confirmation that the off-rated limits assumed in the ECCS-LOCA analyses bound the cycle-specific off-rated limits calculated for the MELLLA+ operation e Confirmation that the limits assumed in the LOCA analysis is bounded by cycle-specific limits is provided in the MELLLA+ Reload Safety Analysis Report (ANP-3280(P))Requirement: Off-rated limits will not be applied to the minimum CFstatepoint S[ ] as discussed in the BreakSpectrum Report (ANP-3105P) AAREVA MELLLA+ Methods Applicability -17 April 2014 -p.27 AR EVAforw~ard-looking energy Review of Generic MELLLA+Limitations and Conditions Oo Section 12.11: ECCS-LOCA Axial Power Distribution Evaluation Requirement: For MELLLA+ applications, the small and large break ECCS-LOCA analyses will include toppeaked and mid-peaked power shape inestablishing the MAPLHGR and determining the PCT* Both top and mid-peaked results are provided in the Break Spectrum Report (ANP-3105P)Requirement: The plant-specific applications will report the limiting small andlarge break licensing basis and upper bound PCTs* Results for a broad range of break sizes (encompassing both small and large break) isprovided in the Break Spectrum Report (ANP-3105P) AAREVA MELLLA+ Methods Applicability -17 April 2014 -p.28 AR EVA Review of Generic MELLLA+Limitations and Conditions Oo Section 12.12: ECCS-LOCA Reporting Requirement: Both the nominal and Appendix K PCTs should be reported forall of the calculated statepoints " AREVA LOCA methodology is Appendix K based and no nominal PCTs are available " Appendix K PCTs for all calculated statepoints are provided in the Break SpectrumReport (ANP-3105P) Requirement: The plant-variable and uncertainties currently applied will beused, unless the NRC staff specifically approves a different plant variableuncertainty method for application to the non-rated statepoints

  • Uncertainties were applied per the AREVA approved methodology as described in theBreak Spectrum Report (ANP-3105P)

AAREVAAREVA MELLLA+ Methods Applicability -17 April 2014 -p.29 forward-looking energy Review of Generic MELLLA+Limitations and Conditions Pp Section 12.13: Small Break LOCARequirement: Small break LOCA analysis will be performed at the MELLLA+minimum CF and the transition statepoints for those plants that: (1) are smallbreak LOCA limited based on small break LOCA analysis performed at therated EPU conditions; or (2) have margins of less than or equal to [[ ]relative to the Appendix K or the licensing basis PCTe Results for all statepoints for a broad range of break sizes (encompassing both smalland large break) is provided in the Break Spectrum Report (ANP-3105P)

0. Section 12.14: Break SpectrumRequirement:

The scope of small break LOCA analysis for MELLLA+operation relies upon the EPU small break LOCA analysis results. Therefore, the NRC staff concludes that for plants that will implement MELLLA+, sufficient small break sizes should be analyzed at the rated EPU power level to ensurethat the peak PCT break size is identified

  • The full break spectrum analysis performed for EPU/MELLLA+

is documented in theBreak Spectrum Report (ANP-3105P) AAR EVAAREVA MELLLA+ Methods Applicability -17 Apr11 2014- p.30 energy Review of Generic MELLLA+Limitations and Conditions lo Section 12.15: Bypass Voiding Above the D-LevelRequirement: Plant-specific MELLLA+ applications shall identify where in theMELLLA+ upper boundary the bypass voiding greater than 5 percent will occurabove the D-level* The maximum bypass voiding at LPRM Level D is given in the MELLLA+ ReloadSafety Analysis Report (ANP-3280(P)) Pl Section 12.16: RWERequirement: Plants operating at the MELLLA+ operating domain shallperform RWE analyses to confirm the adequacy of the generic RBM setpoints " AREVA performs RWE on a cycle-specific basis" Results of the RWE analysis is given in the MELLLA+ Reload Safety Analysis Report(ANP-3280(P)) AAR EVAAREVA MELLLA+ Methods Applicability -17 April 2014- p.31 energy Review of Generic MELLLA+Limitations and Conditions Io Section 12.24: Limitations from Fuel Dependent Analyses RAIEvaluations Requirement: For EPU/MELLLA+ plant-specific applications that use TRACGor any code that has the capability to model in-channel water rod flow, thesupporting analysis will use the actual flow configuration " AREVA will utilize explicit water rod models in methodologies that support thecapability " Discussed in the Methods Applicability Report ANP-3108P Requirement: The EPU/MELLLA+ application would provide the exit voidfraction of the high-powered bundles in the comparison between theEPU/MELLLA+ and the pre-MELLLA+ conditions " Maximum exit void for Brunswick Unit 1 Cycle 19 MELLLA+ operation given in theMELLLA+ Fuel Cycle Design Report (ANP-3013P) " Maximum exit void for Brunswick Unit 1 Cycle 19 MELLLA operation given in theMELLLA Fuel Cycle Design Report (ANP-3005P) AAREVA MELLLA+ Methods Applicability -17 April 2014 -p.32 AR EVAforward-looking energy Applicability of AREVAMethods in MELLLA+!o SummaryThe steady state and transient neutronics and thermal-hydraulic analytical methods and code systems supporting MELLLA+ are within NRC approvedapplicability ranges* the conditions for MELLLA+ application are equivalent to existing core and assemblyconditions in other plants for which the AREVA methodology was benchmarked V The calculational and measurement uncertainties applied in MELLLA+applications are valid* the conditions for MELLLA+ application are equivalent to existing core and assemblyconditions for which the AREVA methodology was benchmarked The assessment database and uncertainty of models used to simulate theplant response at MELLLA+ conditions are equivalent to core and assemblyconditions for which the AREVA methodology was benchmarked A Applicability of approved AREVA methods to Brunswick MELLLA+ established AREVA analyses will comply with the fuel-specific limitations and conditions from the generic MELLLA+ SE to NEDO-33006A a Analysis reports will be submitted as part of the LAR AAR EVAAREVA MELLLA+ Methods Applicability -17 April 2014 -p.33 forward-ookng e nergy}}

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