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.:.-.N USCALE-'•li"POWER" L0-02 16-21534

Enclosure 1:

"NuScale Nuclear Analysis Codes and Methods Topical Report," PM-0216-21 523-NP,

Revision 0, nonproprietary version

NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928

www.nuscalepower.com

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NuScale Nuclear Analysis Codes andMethods Qualification Topical Report

Chris Kirby, Guy Rhoden, Allyson KittoCore Design Engineers

~February 18, 2016

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Revison: 0Copyright 2016 by NuScale Power, LLC.

Acknowledgement and DisclaimerThis material is based upon work supported by the Department of Energyunder Award Number DE-NE0000633.

This presentation was prepared as an account of work sponsored by an agencyof the United States Government. Neither the United States Government norany agency thereof, nor any of their employees, makes any warranty, expressor implied, or assumes any legal liability or responsibility for the accuracy,completeness, or usefulness of any information, apparatus, product, or processdisclosed, or represents that its use would not infringe privately owned rights.Reference herein to any specific commercial product, process, or service bytrade name, trademark, manufacturer, or otherwise does not necessarilyconstitute or imply its endorsement, recommendation, or favoring by the UnitedStates Government or any agency thereof. The views and opinions of authorsexpressed herein do not necessarily state or reflect those of the United StatesGovernment or any agency thereof.

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Agenda* Purpose

* Background

* Nuclear analysis codes description

* Underlying methodology

• How code qualification is performed

* How code bias and bias uncertainty are determined

* Code qualification and benchmarking results

• Code bias and bias uncertainty determination

* Code application for NuScale

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PurposeThe purpose of this presentation is to provide anintroduction to the NuScale Nuclear Analysis Codes andMethods Topical Report, which will be submitted in May2016.

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Background* The Studsvik Scandpower's Core Management Software

(CMS) includes CASMO5, SIMULATE5 and S3K

* The CMS safety evaluation report requires eachorganization using these codes to submit separatedocumentation of

- how the codes will be used

- justification of modeling assumptions

- design specific data

* NuScale seeks the U.S. NRC's approval to use CMScodes for the design and analysis of the NuScale reactor

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Background* Extensive Licensing history

- CASMO/SIMULATE

NRC letter to Nuclear Management Company LLC, September 13, 2000, SUBJECT: PRAIRIE ISLAND NUCLEARGENERATING PLANT, UNTS 1 AND 2- -SAFETY EVALUATION ON TAPICAL REPORT, NSPNAD-8101, REVISION 2,"QUALIFIACTION OF REACTOR PHYSICS METHODS FOR APPLICATION PRAIRIE ISLAND UNITS 1 AND 2" (TAC NOS.MA7997 AND MA7998)

* NRC letter to Omaha Public Power District, March 11, 2005, SUBJECT: FORT CALHOUN STATION, UNIT 1 - ISSUANCE OFAMENDMENT (TAC NO. MC4304)

*NRC letter to Virginia Electric and Power Company, March 12, 2003, SUBJECT VIRGINIA ELECTRIC AND POWER COMPANY- ACCEPTANCE OF TOPICAL REPORT DOM-NAF-1, 'QUALIFICATION OF THE STUDSVIK COREANAGEMENT SYSTEMREACTOR PHYSICS METHODS FOR APPLICATION TO NORTH ANNA AND SURRY POWER STATIONS" (TAC NOW.MB5434, MB 5436, AND MB5437)

* NRC letter to Duke Energy Corporation, August 20, 2004, SUBJECT: FINAL SAFETY EVALUATION FOR DUKE TOPICALREPORT DPC-NE-1005P, "NUCLEAR DESIGN METHODOLOGY USING CASMO-4/SIMULATE-3 MOX"

* NRC letter to Southern California Edison Company, December 15, 2009, SUBJECT: SAN ONOFRE NUCLEAR GENERATINGSTATION, UNITS 2 AND 3 -ISSUANCE OF AMENDMENTS REVISING TECHNICAL SPECIFICATION 5.7.1.5, "COREOPERATING LIMITS REPORT (COLR)" (TAC NOS. ME0604 AND ME0605)

* NRC letter to Arizona Public, March 20, 2001, SUBJECT: PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND3- -ISSUANCE OF AMENDMENTS ON CASMO-4/SIMULATE-3" (TAC NOS. MA9279, MA9280, AND MA9281)

- S3K

* NRC letter to Duke Energy Corporation, September 22, 1999, SUBJECT: MCGUIRE NUCLEAR STATION, UNITS I AND 2 RE:ISSUANCE OF AMENDMENTS" (TAC NOS. MA241 1 AND MA2412)

* NRC letter to Duke Energy Corporation, September 22, 1999, SUBJECT: CATAWBA NUCLEAR STATION, UNITS 1 AND 2 RE:ISSUANCE OF AMENDMENTS" (TAC NOS. MA2359 AND MA2361)

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Previous Interactions* Codes and Methods meetings

- submitted initial codes and methods report RP-07-00020 inNovember 2008

- utilized CMS codes since 2008 for NuScale design

* CASMO-4/SIMULATE-3

- Codes and Methods plan updates and status reports

* June 2010, October 2011, February 2014

* CMS5 (CASMO5/SlMULATE5)

-November 2015

* presented CMS5 code methodology and applications

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CMS Methodology

Chris Kirby

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CMS Code Methodology* Purpose: provide general description and functionality of

the NuScale nuclear design and analysis codes* Studsvik Scandpower CMS Code Suite

- CASMO5 (lattice physics)

- SIMULATE5 (core simulator)

- SIMULATE-3K (3-D transient)

* NuScale will use the codes for- nuclear design and analysis

- physics input to safety analysis

- operations I reactor engineering support

- core follow

- startup physics testing

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CMS Program Flow Chart

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CASMO5 Introduction• Multigroup, 2-D transport theory code

- generates lattice physics parameters for light water reactors (LWRs)

•cross-sections, nuclide concentrations, pin power distributions, discontinuity factors - for use inSIMULATE5

• CASMO5 enhancements

- enhanced scattering kernel for improved Doppler coefficient predictions

- improved Gd depletion model

- improved energy release model

* Neutron data library comparison

- enhanced resonance treatment, improved accuracy

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CASMO5 Calculation Flow

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CASMO5 Case Matrix

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SIMULATE5 Introduction* SIMULATE5 is a 3-D steady-state, multi-group, nodal diffusion theory,

reactor simulator code

- attempt to model 'real' physics (no ad hoc models)Enhancements compared to SIMULATE-3

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SIMULATE5 Calculation Flow

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SIMULATE-3K Introduction* S3K is a 3-D transient version of

SIMULATE-3

- used to analyze core transients

NuScale control rod ejectionaccident

-coupled two-group nodal modelto detailed fuel pin and channelhydraulic model

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CMS Qualification Approach

Allyson Kitto

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CMS Qualification Approach

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CMS Qualification: EmpiricalData Benchmarking

Allyson Kitto

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Empirical Data Benchmarking•CMS empirical data benchmarking

-is intended to demonstrate the ability of the CMS software toaccurately predict core physics parameters for the NuScale design

-is achieved by CMS comparisons to empirical data for systemsthat have characteristics relevant to the NuScale designapplication

-is not used to determine bias and bias uncertainty values forNuScale core physics calculations

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Empirical Data Benchmarking•CMS empirical data benchmark selection goals

-physical characteristics bound/represent important NuScalereactor design characteristics (e.g., fuel type, enrichment,geometry, moderation, reflection, etc.)

-include measured data for the important core physics parametersof specific interest to NuScale

-parameters of interest are derived from a consideration offunctional requirements by evaluating software end-use

* nuclear reactor core design

* in-core fuel management

* nuclear analysis and input to transient and sub-channel analysis

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NuScale Core Design

* Thermal power rating* Nominal operating.......pressure ... .... .

* Nominal inlet temperaturE

* Number of assemblies

* Assembly pitch{

* Refueling interval

* Lattice geometry

* Enrichment

* Fuel Rods per Assembly

* Guide/Instr. Tubes per.... Assembly.. . .

* Control Rod Material

* Active core height

160 MWTH (gross) -3400 MWTH (gross)

12.7 MPa (1850 psia) 2250 psia

e 493 F37

{{ }}2(a).(c).Ec,

24 months

17x17UO2 (< 4.95% 235uenrichment)

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Hybrid Ag-In-Cd and B4C

2.0 m

~545 F~200

21.504 cm

18-24 months

1 7x1 7u02 (< 4.95% 235uenrichment)

264

24/1

Ag-In-Cd or B4C

-3.7 m

* Burnable poison* Clad material

* Fuel Pellet OD

* Clad ID

* Clad OD

M5®

}2acE~I Gd20 3,or IFBA

Zirconium based

-0.819

~0.836

Edl -0.950

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Figure: Plan view of the control rod assembly (CRA)and in-core instrumentation (ICl) locations in thecore.

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Empirical Data Benchmarking•Parameters tested by empirical data benchmarks include

- Eigenvalue

- relative power distribution

- reactivity coefficients

- critical boron concentration

- boron worth

- control rod worth

• CMS empirical data benchmarking comparisonsencompass- critical experiment data

- experimental reactor data

- commercial reactor critical data

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Empirical Data Benchmarking•Critical experiments

- used mostly to show CMS ability to accurately predict keff

•limited other parameter comparisons are also available, such as for rodworth, soluble boron concentrations, or kinetics parameters

-taken from the International Handbook of Evaluated CriticalitySafety I Reactor Physics Benchmark Experiments(IHECSBEIIHERPBE)

-configurations are typically of small, cold, zero powerconfigurations

-all evaluated experiments have physical characteristicscommensurate with the range of those expected in NuScaledesign* low enriched uranium with enrichments in anticipated design range* square lattices with comparable moderation (pin pitch)* similar fuel and cladding dimensions

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Empirical Data Benchmarking•Experimental reactors

-demonstrate same general capabilities as critical experiments, andadditionally can be used to show ability of CMS to calculate fissiondensities/rates, rod worth, boron worth, at higher temperaturesand power levels than critical experiments

-experiments are taken from IHECSBE/IHERPBE and industrystandard experimental facilities

-configurations are typically of small, cold, zero power or low powercores

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Empirical Data Benchmarking•Commercial reactors

-used to show CMS ability to accurately predict PWR neutron ics inmore detail than available from critical experiments andexperimental reactors

-data is taken from EPRI documentation

-configurations are for typical PWRs (large cores) with high ratedthermal powers, often over various cycles

-although larger than the NuScale core, commercial reactorsdemonstrate the ability to correctly predict important physicsparameters with consideration for depletion, such as* critical boron concentration and boron letdown* control rod worth* reactivity coefficients and boron worth* power distributions

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Empirical Data Benchmarking* Summary of empirical data evaluated for CMS

benchmarking

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Empirical Data Benchmarking

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Empirical Data Benchmarking* Empirical data benchmarking range

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Empirical Data Benchmarking•Summary

-empirical data benchmarking

* includes CMS comparisons to empirical data for systems that havecharacteristics relevant to the NuScale design

*demonstrates the general adequacy of the CMS software in corephysics applications relevant to the NuScale design

*provides confidence that the CMS code system can accurately performcore physics calculations for the NuScale design

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CMS Qualification: Higher-OrderCode Benchmarking

Guy Rhoden

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Higher-Order Code Benchmarking* Higher-order code comparisons

- existing experimental data encompasses systems with individualphysical parameters within the range of the NuScale design

- no operating data exists for the NuScale design

* CMS code-to-code comparisons are performed withMCNP

- MCNP is considered a higher order code

- MCNP model is both detailed and specific to NuScale design

* All values presented are preliminary

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Higher-Order Code Benchmarking°Code-to-code comparisons used for bias and biasuncertainty determinations specific to NuScale design

-keff, peaking factors, power distribution, critical boronconcentration, reactivity coefficients

-data from code-to-code comparisons will consist of tens tohundreds of data points for each parameter being examined

-each data set is examined using standard statistical techniques todetermine the bias and uncertainty for each parameter

-data points represent either an absolute or relative differencebetween CMS and MCNP

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Higher-Order Code Benchmarking

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Higher-Order Code Benchmarking•Code bias and bias uncertainty evaluated by higher-ordercode benchmarking include

- Eigenvalue

- relative power distribution


- critical boron concentration

- boron worth

- CRA worth

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Higher-Order Code Benchmarking* Bias and bias uncertainty summary

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Higher-Order Code Benchmarking• Bias and bias uncertainty conclusions

* Code-to-code comparisons

- good agreement demonstrated for all parameters of interest

- uncertainty factors for parameters are generally typical of theindustry

• Nuclear reliability factors- expected to be generally comparable to values seen for full sized

PWRs

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CMS Qualification: S3K CodeBenchmarking

Chris Kirby

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S3K to SIM5 Code-to-Code Comparison Reactivity

100% Power BOO

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100% Power EOC

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50% Power BOC

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50% Power EOC

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S3K to SIM5 Code-to-Code Comparison Power Peaking

BOO 100% Power

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EOC 100% Power

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S3K to SIM5 Code-to-Code Comparison Power Peaking

BOO 50% Power

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EOC 50% Power

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S3K to SIM5 Code-to-Code Comparison Radial Power Distributions

ECI

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S3K to SIM5 Code-to-Code Comparison Radial Power Distributions

ECI

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S3K to SIM5 Code-to-Code Comparison Axial Power Distributions

BOC 100% Power

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EOC 100% Power

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S3K to SIM5 Code-to-Code Comparison Axial Power Distributions

BOC 50% Power

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EOC 50% Power

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S3K Rod Ejection Benchmarking

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CMS Application

Chris Kirby

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CMS Application to NuScale Core* CMS code suite will be used for

- core design

- safety analysis input

- startup predictions

- operations I reactor engineering support

- core follow

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Core Design Constraints

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Core Design Results* Sample NuScale results from SIMULATE5

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In put to Safety AnalysisParameters used for safety analysis

- care reactivity

- power distributions* assembly and fuel rod power peaking (radial, 3-D)

* axial offset


- kinetics parameters

- control rod worth

- critical boron concentration and boron worth

*Biases and uncertainties are applied to calculated parameters to ensureconservative application in safety analyses

- best estimate predicted value = SIMULATE5 calculated value + bias

- uncertainty interval (absolute) = best estimate ± NRF

- uncertainty interval (relative) = best estimate ± (best estimate x NRF)

* uncertainty is applied in a conservative direction and dependent on the parameter, andtransient scenario

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Sample Calculation Parameters

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Control Rod Ejection• SIMULATE-3K 3-D transient nuclear analysis

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Startup Physics Testing and Core Follow

Startup Physics Testing* Physics parameters are

generated for the followingstartup testing sequences

- control rod testing

- low power physics testing

- at-power physics testing

* Key physics parameters- isothermal temperature

coefficients

- control rod worth

- assembly and rod powerdistributions

- assembly and rod power peaking

- axial offset

Core Follow*Physics parameters are generated

for core follow to ensureacceptable core performance anddetect anomalies during the entirecycle of operation

* Key physics parameters

- assembly and rod power distributions

- assembly and rod power peaking

- axial offset

- core tilt

- assembly burnup

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Summary* NuScale plans on using the CMS code suite for nuclear

design and analysis

* CMS qualification is supported by benchmarkingcomprising suitable critical experiments, experimentalreactors, commercial reactors, and code-to-codecomparisons

* CMS qualification has resulted in the determination ofbiases and uncertainties that are comparable to thosetypically found for commercial PWRs using similarcomputational methods

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Submittal Schedule* Nuclear Analysis Codes and Methods Qualification

Topical Report: May 201.6

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• y- NUSCAL E• = -.;POWE RT

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