Attachment 3

CRDM Meeting Slides Non-Proprietary Version

babcock & wilcox nuclear energy, inc.

9

nuclear energy

B& W mPower TM Reactor

Control Rod Drive Mechanism Design and TestingMarch 23, 2011 - USNRC, Rockville, MD

I THE BABCOCK & WILCOX COMPANY. ALL RIGHTS RESERVED

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AGENDA

" OBJECTIVES

" INTRODUCTIONS

" REACTOR DESIGN OVERVIEW

• CRDM DESIGN OVERVIEW

" CRDM TESTING PROGRAM

* CONCLUSIONS

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Reactor Design Overview

ýe 2011 B a bcoc'ý& \V I [GO ML]cleai Energ,,, Inc All rights reserved.

Overview of the B&W mPower Reactor Design

High-Level Requirements* 125 MWe plant net output per module & 60-year plant life* NSSS forging diameter allows domestic forgings, unrestricted

rail shipment* Passive safety requirements - emergency (diesel) power is

not required*Minimize primary coolant penetrations, maximize elevation ofpenetrations

* Large reactor coolant inventory

* Low core power density

* Standard fuel (less than 5% enriched U-235)

* Long fuel cycle, 4+ year core life

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High-Level Requirements-Cont.

" Spent fuel storage on site for life of plant

" No soluble boron in primary system for normal reactivitycontrol

" Conventional / off-the-shelf balance of plant systems andcomponents

" Accommodate air-cooled condensers (Baseline) as well aswater-cooled condensers

" Flexible grid interface (50 Hz or 60Hz)

" Digital instrumentation and controls compliant with NRCregulations

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Containment Requirements

Underground containment and fuelstorage buildings

" Favorable seismic response

" Missile protection

" Environment suitable for humanoccupancy during normal operation

" Simultaneous refueling and NSSSequipment inspections

" Volume sufficient to limit internalpressure for all design basis accidents

Site Development

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Technology Overview

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Integral Nuclear Steam Supply System

• Integrates core, steam generator, and pressurizer into asingle vessel

0 Control rod drive mechanisms (CRDMs) and primarycoolant pumps inside vessel

* Reactor coolant pressure boundary penetration size andlocation minimize coolant loss during LOCA - core remainscovered throughout the design basis LOCA

0 Housed within a steel lined, reinforced concrete, drycontainment

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Overall Reactor Arrangement

Pressurizer

Steam Generator Tubes

Steam Outlet

Feedwater Inlet

ReactorCoolant Pumps

Upper Internals withControl Rod DriveMechanisms

Lower Vessel

Core --

Inherent Safety Features

*Large reactor coolant volume* Large RCSvolume

" More coolant to protect the core

* Small penetrations at high elevation" High penetration locations

* Small penetrations

Balance of Plant Design

* Plant designed to produce anominal 125 MWe

• Air-cooled condenser (Baseline)* Water-cooled condenser

* Conventional steam cycleequipment (small, easy tomaintain and replace)

* BOP operation not credited fordesign basis accidentsAll fuel can be cooled for a minimum of 72hours without any BOP system

Air CooledCondense

Generato•

LP turbine

HP turbine-, - CondensatePump

HaFWHeatersFW Pump

ConentonaAi- U-ldCodneB&WmPower Reactor125 MWe Module

Instrumentation and Controls

State of the art digital system

Provides monitoring,control, andprotection functions

Separate safety andnon-safety systems

Implement lessonslearned from currentlicensing activities

Northrop Grumman under contractto develop I&C architecture

Summary" NSSS utilizes an integral PWR design

" Uses a single integral economizer once through steam generator to producesuperheated steam

" Internal reactor coolant pumps and control rod drive mechanisms" Internal pressurizer

* Passive safety systems, inherent NSSS safety features" Long operating cycle

* Underground containment

* Spent fuel storage on site for life of plant

* Reactor plants for multiple module designs

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