pm-0614-7392-np - nuscale comprehensive flow-induced

NuScale ComprehensiveFlow-Induced Vibration

Program

Dr. Tamas Liszkai, P.E.

Reactor Module Design Supervisor

July 23, 2014

NuScale Nonproprietary

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Agenda" Overview

* Abbreviations

* Scope

* CVAP plan

* Key elements of CVAP

* Flow velocity

* Test plan

* Summary

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Purpose" Address and outline steps for NuScale SSC and its FOAK

design in the area of

- Regulatory Guide 1.20 Rev. 3, Comprehensive VibrationAssessment Program

- scope of program

- FIV analysis and testing of SSC

" Provide a description of additional activities planned forthese programs to support DCA application and the COLapplication

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Abbreviations

ASME American Society of Mechanical Engineers

BPVC boiler and pressure vessel code

CFD computational fluid dynamics

CIV containment isolation valve

CNSG consolidated nuclear steam generator

CNV containment vessel

COL combined operating license

CRA control rod assembly

CRDS control rod drive system

CVAP comprehensive vibration assessment program

FEI fluid elastic instability

FIV flow-induced vibration

FOAK first-of-a-kind

HCSG helical coil steam generator

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AbbreviationsI Reco ese nenl

ICI in-core instrument

ISI inservice inspection

IST inservice testing

MARAD U.S. Dept of Transportation-Maritime Administration

MS main steam

NDE nondestructive examination

PSD power spectral density

PWR pressurized-water reactor

RCPB reactor coolant pressure boundary

RCS reactor coolant system

RMS root mean square

RQTP Reactor Qualification Test Plan

RVI reactor vessel internals

SG steam generator

SSC structure, system, and component

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Scope" NuScale design is a FOAK plant and meets the definition

of prototype design criteria as delineated in RG 1.20

" Due to the NuScale integral design, SSCs included in theCVAP are

- RVI perASME BPVC, Section III, Subsection NG

- HCSG RCPB tubes

- NuScale Power Module main steam and main feedwater piping upto, and including, main steam isolation valves

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Pre-DCA Submittal CVAP Plan

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Post-DCA CVAP Plan

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NuScale Power Module Components

ClVs

CNV •

RXM piping

RW -

RPV

integrated PZRbaffle plate andsteam plenum

SG annularspace

RVI lower riserassembly

RVI core supportassembly

CIV = containment isolation valve

CNV = containment vessel

PZR = pressurizer

RPV = reactor pressure vessel

RRV = reactor recirculation valve

RVI = reactor vessel internals

RVV = reactor vent valve

RXM = reactor module

SG = steam generator

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Flow-Induced Vibration Mechanisms

Phnmeo Scenn Criteria

Fluid elasticinstability

Vortex shedding

Turbulent buffeting

Acoustic resonance

1. Array of cylinders (minimum one row) (i.e., geometry)

2. Array pitch/diameter < 2.0; array must sufficiently confine fluid to allow

feedback between adjacent cylinders

1. Bluff body (or edge of a cavity in-line with flow) (i.e., geometry)

2. Subject to cross-flow

3. Absence of downstream structures to disrupt vortices

1. Subject to turbulent flow (axial, cross-flow or combination)

1. Suitable geometry to generate an acoustic resonance, typically a hollow or

cavity2. Single phase gas/vapor environment within hollow/cavity

Leakage flowinstability

1.2.3.

1.2.

Narrow annular flow path exists (i.e., geometry)

Flexible structure in annulus, bounded by fixed surface

Annular flow path is diverging (restriction at inlet to annulus) or parallel

Noncircular cross section (i.e., geometry)

Aspect ratio (length/width) in prevailing direction of flow is 4.0 or greater (for

rectangular structure)Galloping/flutter

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Component List for FIV

113(a)

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Component FIV Applicability Screening

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SG FIV Screening

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RVI Riser Assembly FIV Screening

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RVI Core Support FIV Screening

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Vibration and Stress Analysis" Determination of critical characteristics for FIV

* Common input to FIV analysis

" Basis for testing development

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Key Elements for Structural Analysis

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Key Elements for Thermal Hydraulics

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Key Elements for Damping

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Key Elements for Turbulence

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Average and Maximum Flow Velocities'

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Flow Velocity ComparisonAvrg Veoct at10%Pwe ftUta Downcomer*Ioe Upe Snternals

NuScale it}}3(a)

EPR1 N/A 24 16 30 5

API1000 2 N/A 19 16 40 5

US-APWR 3 N/A 23 14 30 5

SONGS 4 18 N/A N/A N/A

1. UK EPR DCD Chapters 3, 4, and 52. AP1000 DCD Chapters 4 and 53. US-APWR DCD Chapter 4 and 54. U.S. Nuclear Regulatory Commission, "San Onofre Nuclear Generating Station-NRC Augmented Inspection Team Report

05000361/2012007 and 05000362/20112007," July 20125. Cross flow velocity estimated as half hot leg velocity

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NuScale Reactor Qualification Test Plan

e The Reactor Qualification Test Plan (RQTP) includestesting required to support the DCA

e Includes SG FIV testing needed to support CVAP

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CRA/ICI guide tubes

- most complex geometry outside SG in RCS flow path

- need for flow testing is under evaluation to establish boundingforcing functions

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Pressures Due to Secondary Side Boiling

9 SIET TF-1 test

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TF-1 Test Conditions-Pressure Measurements

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Fluid Elastic Instability (FEI)* Review of previous (public domain) testing, indicates no FEI tests of

full helical tube arrays, only helical segments

- Chen: testing at Argonne National Lab (ANL)l

- B&W: testing of CNSG design for MARAD 2

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" FEI design data (ASME Appendix N-1 300) is based on straight tubearrays

* Limited Chen and B&W testing of helical segments indicated straighttube array data should bound helical array FEI

* To provide additional confidence in FEI design margins for NuScaleHCSG, full helical bundle FEI test will be performed

il Chen, S.S., et al., "Tube Vibration in a Half-Scale Sector Model of a Helical Tube Steam Generator," Journal of Sound and Vibration, Vol.

91, pages 539-569 (1983).21 Glasser, R.P., "Experimental Evaluation of Helical Consolidated Nuclear Steam Generator (CNSG) Tubes and Supports, MA-RD-920-

76019, November 1975.

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NuScale FEI Test* Will utilize existing test section for fluid heated test (TF-2)

at SIET

- test section employs a NuScale tube support concept

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9 Testing will include secondary flow (including two-phase)

- investigate the potential for unknown effects due to two-phasesecondary flow forcing coupled with primary flow

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Turbulent Forcing Functions" NuScale has evaluated all geometries in the reactor

vessel internals (including SG and SG tube supports) toidentify turbulent forcing functions

" Turbulent forcing functions consist of three components

- correlation length (A)

- convective velocity (v)

- power spectral density (PSD)

" Based on geometry and/or correlations, specificcorrelation lengths and convective velocities for all RVIand SG components have been identified

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SG Power Spectral Densities* Limited open source PSDs exist for

- HCSG tube external flow 1'2

- annular turbulent flow 2

- parallel flow over 2D surfaces

- cross flow around 1 D structures

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ii American Society of Mechanical Engineers, Boilerand Pressure Vessel Code, Section III, "Rules for Construction of Nuclear FacilityComponents," Appendix-N, 2007 Edition with no Addenda.21 Au-Yang, M.K., "Flow-Induced Vibration of Power and Process Plant Components," ASME Press, New York, 20113i Snyder, M., et al., Progress in the Generation of Flow Turbulence Excitation Forces from CFD Analyses and Experimental Data, Paper ID000127, 6th International Conference on Nuclear Thermal Hydraulic, Operations and Safety (NUTHOS-6), Nara, Japan, October 4-8, 2004.

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Turbulent Annular Flow PSD1

E+O

E-I

E-2

(-,

0

0 1.0 2.0 3.0 4.0

F=JRJ/V

5.0

11 Au-Yang, M.K., "Flow-Induced Vibration of Power and Process Plant Components," ASME Press, New York, 2011

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Summary" NuScale CVAP to satisfy RG 1.20 requirements

" Screening for all potential FIV mechanisms inside RPV

" Analyses or evaluations are performed for all susceptiblecomponents

" Generally very low susceptibility due to low flow rates

" Pre-DCA testing needs have been identified

" The key is to provide sufficient details in the DCA, suchthat the NuScale analysis, testing, and inspectionmethodology including uncertainties for FIV can beevaluated by the NRC

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6650 SW Redwood Lane, Suite 210Portland, OR 97224503. 715.2222

1100 NE Circle Blvd., Suite 200Corvallis, OR 97330541.360.0500

11333 Woodglen Ave., Suite 205Rockville, MD 20852301.770.0472

http ://www. nuscalepower com

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