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B •w babcock & wilcox nuclear power generationB 800 main street 0 iynchburg, va 24504 b phone 434.522.6800
0 fax 434.522.6837 P www.babcockcorn
July 16, 2009
U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockville PikeRockville, MD 20852-2738
SUBJECT: Non-Proprietary Slides for B&W mPowerTM Modular Reactor Approach to Reactivity.
REFERENCE: B&W Transmittal letter dated July 6, 2009.
The B&W Nuclear Power Generation Group met with the NRC staff on July 7 th 2009 in a closed meeting todiscuss the reactivity control approach for the B&W mPowerTM Reactor. During that meeting, and in thereferenced letter, B&W committed to providing a redacted, non-proprietary version of the presentation.
The attached sets of slides are provided as non-proprietary and releasable to the public without restriction.
Questions concerning this submittal may be directed to Jeff Halfinger at (434) 522-5941.(Email: iahalfinqerbabcock.com).
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cc: Thomas J. Kenyon, NRC, TWFN-6 C34William D. Reckley, NRC, TWFN-6 C34
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nuclear power generation
Modular Reactor Approach toReactivity Control
July 7, 2009 NRC Pre=Application Review
Redacted material marked with square brackets and noted by[CCI per Affidavit 4(a)-(d)]
a Babcock & Wilcox company
mpower babcock & wilcox nuclear power cgeneration
Presentation Outline* Introduction
* B&W mPower safety design features
[CCI per Affidavit 4(a)-(d)]
m Reactivity control approach
* Regulatory requirements for reactivity control, General Design Criteria 26, 27, and 29, Anticipated Transients Without Scram (ATWS) /7
m Summary
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Key B&W mPower Safety Design FeaturesContainment - Traditional PWR fuel assemblies
Integral operated at lower power densityNSSS
* Integral nuclear steam supplysystem (NSSS)
* Natural circulation decay heatremoval system (DHRS)
* Containment with passive heatabsorption
[CC I per Affidavit 4(a)-(d)]
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Traditional PWR Fuel Assembly
17 x 17 fuel rod array
Control rod guide thimble
Bottom spacer grid
Bottom nozzle -
Top nozzle
Top spacer grid
Intermediate spacer grid
Fuel rod
* Lower power density
" Corrosion resistantZircaloy
* Large plenum volume
--- Top end plug
Upper plenum
• Clip
Top spacer
Fuel pellet column
Bottom spacer
Standoff
Bottom end plug
Shrene an Sipife Covntoa Fuel Assml Design
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Integral Nuclear Steam Supply System
PressurizationVolume
Steamgeneratorcoils
Control RodDriveMechanisms
Reactorcoolantpumps
DHRS heat
exchangers
Core
" Pressurizer and pressure relief at thehigh point of the vessel
" CRDMs inside vessel
* DHRS heat exchangers insidepressure vessel
* Large reactor coolant inventory
" RC penetrations at the top of thevessel and are small( ] [CCI per Affidavitvess l an aresmal [ I 4(a)-(d)]
" Core remains covered throughoutdesign basis LOCA without coolantaddition
No Lag BI~~:reak LOC
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Natural Circulation DHRSDHRS pool
m Decay heat removal system(DHRS) serves as emergencycore cooling system
* Multiple independent heatexchanger loops fed from storedwater source(s)
m System is operable at all reactorpressures and temperatures
m Passive heat removal for morethan 72 hours
DHRS heatexchangers
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Containment
NSSS and all high energy pipecontaining reactor coolant is locatedwithin containment
" Spent fuel stored inside containment
" Containment provides sufficient thermalstorage to drop peak pressure afterLOCA by >50% within 24 hours
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Reactivity Control Regulatory Requirements
*General Design Criteria0 GDC 26 - Two independent reactivity control systems
o GDC 27 - Capable of reliably controlling reactivity changes
, GDC 29 - Highly reliable capability of performing safety function
*10 CFR 50.62 reduction in risk from anticipated transientswithout scram (ATWS)
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General Design Criterion 26
Two independent reactivity control systems of different design principlesshall be provided. One of the systems shall use control rods, preferablyincluding a positive means for inserting the rods, and shall be capable ofreliably controlling reactivity changes to assure that under conditions ofnormal operation, including anticipated operational occurrences, and withappropriate margin for malfunctions such as stuck rods, specifiedacceptable fuel design limits are not exceeded. The second reactivitycontrol system shall be capable of reliably controlling the rate of reactivitychanges resulting from planned, normal power changes (including xenonburnout) to assure acceptable fuel design limits are not exceeded. One ofthe systems. shall be capable of holding the reactor core subcritical undercold conditions.
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General Design Criterion 27
The reactivity control systems shall be designed to have acombined capability, in conjunction with poison addition by theemergency core cooling system, of reliably controllingreactivity changes to assure that under postulated accidentconditions and with appropriate margin for stuck rods thecapability to cool the core is maintained.
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General Design Criterion 29
The protection and reactivity control systems shall be designedto assure an extremely high probability of accomplishing theirsafety functions in the event of anticipated operationaloccurrences.
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K [CCI per Affidavit 4(a)-(d)] 7Q 2009 The Babcock & Wilcox Company. All rights reserved.
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10 CFR 50.62 -ATWS* (c)(1) PWRs must have independent, diverse, reliable equipment for
auxiliary feedwater initiation and turbine trip upon indication of an ATWS
[Privileged information per Affidavit 6(b)]
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10 CFR 50.62 -ATWS(c)(2) pressurized water reactors manufactured by... Babcock andWilcox must have a diverse, independent, reliable scram system.
[CCI per Affidavit 4(a)-(d)]
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Summary
[CCI per Affidavit 4(a)-(d)]
" Reactivity control system has diverse, independent,reliable scram systems and meets the requirementsfor ATWS
" B&W mPower design fully complies with GeneralDesign Criteria 26, 27, and 29
" Design assures the capability to cool the core underpostulated accident conditions
" Design provides a highly reliable and passiveapproach to safety
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