US-APWR4th Pre-Application Review Meeting

Nuclear Design Overview

January 31, 2007

Mitsubishi Heavy Industries, Ltd.

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Meeting Attendant

Manabu Hamasaki

P.E.Jp (Nuclear & Radiation)

Manager,Core Engineering SectionReactor Core Engineering DepartmentNuclear Energy Systems Engineering CenterMitsubishi Heavy Industries, LTD.

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Objectives

> Show that all design features, procedures andmethodologies implemented in the US-APWR nucleardesign have been approved by US NRC and haveextensive experience in the United States

> Describe the NRC-approved nuclear design codes tobe applied to the US-APWR

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Contents

1. Nuclear Design Process

2. Approach by Core Design Variation Analysis

3. Nuclear Design Code System

3.1 Methodology Summary of PARAGON andANC codes

3.2 Topical Reports Approved by NRC

3.3 Applicability to US-APWR

4. Conclusions

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Nuclear Design Process

4r Design Input

Core Design Analyses -Plant Concept & RCS Spec-Regulatory Req. (SRP,RG)

using PARAGONIANC -Customers Req.

Design Output Possible Feedback

> Nuclear Fuel Specs & LP*- U235 Enrichment Interfaces with- Absorber Loading etc -Fuel Systems Design

> Core Characteristics -Fuel Rod Design- Reactivity Coefficients, - T&H Design- Power Peaking & Distr.

-Critical Boron etc - Fluid Systems Design- Pattern - Safety Analysis

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Approach by Core Design Variation Analysi4•

> Basic Design Includes Analyses of DifferentReload Cores as well as Initial Core to ProvideRobustness for Core Variation

/ 24 month Initial Core,

V 12 to 24 month Equilibrium Cycle Cores• Investigate Variation of Core Characteristics to be

Considered• Establish Bounding Inputs for Safety Parameters• Provide Reload Design Flexibility

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Nuclear Design Code System i,

>Code System: PARAGONIANC

V'Nuclear Design Code System for PWRs

/Jointly Developed by MHI & Westinghouse* Over 10 year old history* Works published as numerous open papers

v/Approved by NRC

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Methodology of PARAGONIANC

> PARAGONV/2D Multi-Group Transport Code Based on Current

Coupling Collision Probability (CCCP)V Generate Nuclear Data for ANC Core Simulator

- Two-Group Cross Sections, Discontinuity Factors, PinPower Factors, Reflector Constants, etc.

> ANC (Advanced Nodal Code)V 3D 2-Group Diffusion Code Based on

Nodal Expansion Method (NEM)V Predict Various Core Characteristics

* Reactivity (Critical Boron, Control Rod Worth, etc.)• Reactivity Coefficients (DTC, MTC, etc.)* Rod-wise Power Distribution

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Topical Reports of PARAGONIANC<

> Topical Reports Issued by Westinghouse,& Approved by NRCV "ANC: A Westinghouse Advanced Nodal

Computer Code", WCAP-1 0965-P-A, and WCAP-10966-A, September, 1986

V "Qualification of the PHOENIX-P/ANC NuclearDesign System for Pressurized Water ReactorCores", WCAP-1 1596-P-A, and WCAP-1 1597-A,June, 1988

V"Qualification of the Two-Dimensional TransportCode PARAGON," WCAP-1 6045-P-A, March,2003

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Topical Reports of PARAGON/ANC (cont.)

> Topical Reports Show the Applicability toWide Variety of Core Configurations,/Wide Variety of Design Configuration

" Std. Westinghouse and CE Type Plants- 2-, 3- and 4-loop

" Various Fuel Lattices, Burnable Absorbers and AxialBlanket Designs

- 14x14, 15x15, 16x16, and 17x17- IFBA, WABA, PYREX, Gadolinia, Erbia and B4C- Enriched annular, natural solid

V Cycle length : 310 to 654 EFPDVUO 2 enrichment :1.30 to 4.95wt%'"Fuel rod size: 0.360 to 0.440 inches

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Applicability to US-APWR

> MHI Has Ample Experience of PARAGON /ANC Analyses

" Critical Experiments and PIE Analysis by PARAGON• Including 10wt% Gadolinia PIE* Including MOX Critical Experiments* Critical Experiments with Steel Neutron Reflector

/ Operating Plant Core Analyses by PARAGON/ANC" Std. Westinghouse type 2-, 3- and 4-loop Plants in

Japan• Including 1Owt% Gadolinia Core" European MOX Cores

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Applicability to US-APWR (cont.) q

> US-APWR Characteristics fall within theRange of Proven Applicability

/17x17 4-LOOP/ < 5.Owt% U-235 enrichment/ Gadolinia and PYREX burnable absorberV/257 fuel assembliesV 14-foot fuel/ Up to 24 month operation

, Steel Neutron Reflector• Applicability confirmed based on Critical Experiments and

MCNP reference calculations

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Conclusions> The US-APWR nuclear design uses proven design features

that have been used extensively in the United States

> The NRC approved nuclear design code systemPARAGON/ANC is applicable to all aspects of US-APWR,and no special, unique, or unapproved procedure ormethodologies are required for analysis

> MHI will reference applicable and previously approvedtopical reports to describe the nuclear design proceduresand methodologies. No additional topical reports areanticipated for US NRC review.

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