nuscale reactor module asme piping - nrc.gov · overview 9 address and outline design strategy for...

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NuScale Reactor ModuleASME Piping

Dr. Tamas Liszkai, P.E.

Reactor Module Design Supervisor

July 23, 2014

NuScale Nonproprietary

NUSCALEPOWER-PM-0614-7303-NP © 2014 NuScale Power, LLC

Purpose* Provide an introduction to NuScale reactor module(RXM) piping design

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Overview9 Address and outline design strategy for NuScale

structure, system, and components and its first-of-a-kind(FOAK) design in the area of

- NuScale reactor module piping systems arrangement

- ASME Class 1 and 2 piping inside containment

e Discuss application of 10 CFR 50 Appendix A and GDC 4,protection against dynamic effects

- high energy line break (HELB) considerations (SRP 3.6.2,BTP 3-4)

- feasibility evaluation of leak before break (LBB) (SRP 3.6.3)

* Provide a description of additional activities planned forthese programs to support DCA application

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Agenda* Piping systems considered

* General design information

* Considerations for piping

* Overview of design layout

* Piping sizing calculations

* Preliminary ASME code stress analysis

* Piping support design

* Postulated piping break locations and leak before break

* Summary

* Future work

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Abbreviations

BTP branch technical position

CES containment evacuation system

CFR Code of Federal Regulations

CNV containment vessel

COL combined license

CVCS chemical and volume control system

DCA design certification application

DHRS decay heat removal system

FOAK first-of-a-kind

GDC general design criterion

HELB high energy line break

HPD high point degasification

ISI inservice inspection

ITAAC inspections, tests, analyses, and acceptance criteria

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AbbreviationsAbbevato Definitio

LBB

LOCA

NRC

OBE

RCCWS

RXM

SAM

SBAC

SQUIRT

SRP

SSE

TAM

leak before break

loss-of-coolant accident

U.S. Nuclear Regulatory Commission

operating basis earthquake

reactor component coolant water system

reactor module

seismic anchor movement

smooth bounding analysis curve

seepage quantification of upsets in reactor tubes

Standard Review Plan

safe shutdown earthquake

thermal anchor movement

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Introduction" Development of NuScale Power Module (NPM) piping

layout and supports, piping drawing and preliminaryASME Code stress analyses

* Design and analysis conducted with approved industrystandard requirements and appropriate computationalmethods (AutoPIPE and ANSYS)

* Piping systems designed with high flexibility due tothermal and seismic demands

" Consideration for manufacturing limitations, maintenance,in-service inspection, water hammer/steam hammerpreclusion, thermal fatigue mitigation, and acousticresonance

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Piping Systems Considered

• Main steam (MS), {{" Feedwater (FW), {{

}}3(a)

}}3(a)

* Chemical and volume control system (CVCS),}}3(a)

- reactor coolant system (RCS) discharge line

- RCS injection line

- pressurizer (PZR) spray supply line

- reactor pressure vessel (RPV) high point degasification (HPD) line

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Piping Systems Considered

* Decay heat removal system (DHRS),}}3(a)

* Containment evacuation system (CES),}}3(a)

• Reactor component coolant water system (RCCWS),S11}}3(a)

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General Design Information9 NuScale design uses the 2007 edition of ASME Code,

Section III, Rules for Construction of Nuclear FacilityComponents- Subsection NB (Class 1)

- Subsection NC (Class 2)

- Subsection NF and Appendix F (Supports)

}}3(a)

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General Design Information

}}3(a)

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General Design InformationTemperature and pressure for thermal anchor movement(TAM)

}}3(a)

Note 1 - 625 0F is the normal operating temperature of the RPV in the PZR section. The temperature of the RPV belowthe PZR section will range from 590°F (above the steam generator) to 500OF (below the steam generator).Note 2 - 350°F is the normal operating temperature of the CNV head. The temperature of the CNV below the CNV headwill range from 100OF to 3500 F.

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General Design Information

}}3(a)

Sy (ksi) Su (ksi) Sm (ksi) S (ksi)

304

304L

Dual-Cert

30

25

30

70

70

70

16.2 16.2

Lower allowable

Dual-certification of stainless steel implies maintaining the chemistrywith a low-carbon content L-grade and strength properties of thestraight grade.

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General Design Information" Corrosion

- corrosion degradation of 0.15 mils per year (0.00015 in.) for 60years

" Tolerance and bends- minimum wall thickness employs 12.5% reduction on nominal

wall, for standard pipe schedule tolerance

- thickness allowance included for thinning in producing 5D bends

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Considerations for Pipingi Piping layout

}}3(a)

* In-service inspection

- minimized number of welds and supports to reduce extent ofinservice inspection (ISI) (e.g., custom made tee)

- welds and supports are accessible for ISI

}}3(a)

9 Maintenance

- piping layout to maximize amount of open space within CNV tofacilitate maintenance

- piping layout to facilitate access to critical components inside CNV

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Considerations for Piping

}}3(a)

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Considerations for Piping" Manufacturing

- maximum length in which dual certified Type 304/304L can besupplied is limited

- custom bends with 5D radius to avoid issues with ovality, wallthinning and excessive pipe wall thickness

- custom forged reducing tee to minimize number of welds

" Acoustic resonance

avoid shear wave instability that leads to acoustic resonancepalfeC. AcouMt'c

dvaloity Pressure(Qtnt Wave. p

SideBranch SardousiSndnWane

Leadingng

PEdge

V D

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E

Main Steam Piping Layout

}}3(a)

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Feedwater Piping Layout

})3(a)

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CVCS Piping Layout

}}3(a)

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RCCW and CES Piping Layout

}}3(a)

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DHRS and Overall Piping Layout

)}3(a)

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Piping Sizing CalculationsTypical sizing calculations for piping internal pressure useapplicable Class 1 (NB-3640) or

NB-3640 LZZ>

PDoti = 2(Sin + Py) + A

Pd +2A(Sm,+Py)til= 2(Sill + Py - P)

Class 2 (NC-3640) rulestm = minimum required wall thickness

P = internal design pressure

Do= outside pipe diameter

Sm = maximum allowable membranestress intensity

A = mill tolerance & corrosion allowance

y = factor for pressure in radial direction

d = inside pipe diameter

NC-3640i= PDO

2 (S + Py) +A

Pd + 2SA +2yPAtill 2(S + Py - P)

S = maximum allowable stress

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Overview of Piping Size

)}3(a)

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Preliminary Code Stress Analysis

" Piping stress analysis performed with AutoPIPE

- advanced design/analysis program for calculating piping loads,deflections, and stresses under static and dynamic conditions

- NQA-1 and ISO-9001 compliant

- models the piping geometry in 3D

- piping stress solution based on beam connectivity

" Preliminary ASME Code stress analysis

- pressure sizing

- thermal expansion including thermal anchor motion (TAM)

- dead weight

- seismic (static equivalent) with seismic anchor movement (SAM)}}3(a)

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Feedwater Piping Stress Analyses

}}3(a)

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Preliminary Stress Analysis Results

113(a)

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Postulated Pipe Break Locations* Piping evaluated against criteria for piping break

exclusion (BTP 3-4)

- sum of occasional stress and sustained stress shall not exceed0.8 times the sum of the stress limits given by Eq. 9 and Eq. 10 ofNC-3653 for intermediate piping breaks to be excluded

}}3(a)

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Regulatory Requirements* 10 CFR 50 Appendix A, GDC 4

- GDC 4 requires that structures, systems, and components important to safety ...shall be appropriately protected against dynamic effects, including the effects ofmissiles, pipe whipping, and discharging fluids, ...

- However, dynamic effects associated with postulated pipe ruptures in nuclearpower units may be excluded from the design basis when analyses reviewed andapproved by the Commission demonstrate that the probability of fluid system pipingrupture is extremely low under conditions consistent with the design basis for thepiping

* Requirements in SRP 3.6.3

- compliance with GDC 4

- high energy ASME Code Class 1 or 2 piping

- individual piping system for LBB approval

- ITAAC in DC application

- ITAAC in COL application

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Leak Before Break Guidelines" Potential failure mechanism evaluation

" Design bases loads and as-built piping configuration

" Leakage detection systems and margin on leakage rate

* Material properties: tensile data, fracture toughness,thermal aging

* Analysis steps- identify the computational methods and demonstrate the accuracy

- specify the loads at the least favorable locations

- postulate a through-wall crack

- for a specified leak rate, the leakage crack size is calculated to generate 10 timesthe leak rate. A crack with double the leakage crack size needs to be stable

- for a critical crack, half the crack size should result in a leakage rate that is 10times the detectable leak rate

- crack instability analysis (J/T criteria, limit load analysis)

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Leak Detection Time Frame" RG 1.45 specifies a time frame of 1 hour for leakage

detection to ensure that plant operators have timelyinformation about unidentified leakage

" However, leakage detection for LBB purposes does notrequire the same time frame

- A time frame of 3.5 days is acceptable, as stated in AP1 000 FSER(NUREG-1793), because of the safety margins applied andrelatively slow crack growth

1}3(a)

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Preliminary LBB Evaluation for MS Piping

113(a)

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Summary* Piping layout calculations were conducted with

- appropriate industry standard (ASME Code, 2007) for pressure sizing,thermal, and seismic loads

- technically acceptable computational methods

- adequate conservatism

- consideration for thermal fatigue, water/steam hammer events,maintenance, and ISI

- active interaction with manufacturers to determine feasibility of pipinglayout

" Piping systems show structural integrity under assessed loads

" Once final seismic loads and service level loading are established,additional design calculations will be performed

" Preliminary LBB evaluations for MS/FW/CVC PZR spray/RPVdegasification piping systems show applicability

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11333 Woodglen Ave., Suite 205Rockville, MD 20852301.770.0472

httpI//www. nuscalepower. com

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nuscale reactor module asme piping - nrc.gov · overview 9 address and outline design strategy for...

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