Read New Reactor Presentation text version

Shaw Group Nuclear

Mike O'Connell ­ Project Manager AP1000 Projects

UML 2007

1

2011- 2051 Global Coming Attractions Energy

Fuel Source Coal Oil

+

Lots of it in ground, cheap Easy to transport

SO2 + NOx + landfills + CO2 Decreasing amounts, prices going higher + CO2 Decreasing amounts, prices going higher + CO2 Long term waste handling + high initial cost

Natural gas Nuclear Hydro, Solar & Wind

Easy to transport and least polluting of the combustion technologies

No CO2, low fuel cost,

"free" inputs, No CO2 Low energy density, NIMBY

2

U.S. Energy Demand

America Is Projected to Need 50% More Electricity by 2025

3,839B kWh

5,787B kWh

1970

1980

1990

2003

2015

2025

Source: U.S. Department of Energy

3

World View

· · · · 440 nuclear power plants ~367 GWe 16% of world's electricity Displaces 2.5 billion metric tons of CO2/year 38 GW online since 2000 plus under construction

Ukraine Taiwan China South Korea Romania Russia Japan Pakistan Iran

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Brazil

Czech Republic Finland India

Current Unit Expansion in Asia/Europe

Country India South Korea Russia Japan China Ukraine Pakistan Iran Romania Finland Operating Units 14 20 30 52 9 8 2 0 1 4 Currently Planned & Under Construction 8 6 4 3 20 2 -- 1 1 2 Long-Term Plan (GWe) 29.5 26.6 40 15 40 22 8.5 -- -- -- By (year) 2022 2015 2020 2025 2020 2030 2030 -- -- --

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U.S. Nuclear Energy

· 104 nuclear plants (1 returned in 2007)

­ 20% of the nation's electricity ­ Power Uprates have added the equivalent of 5 nuclear units over past 20 years ­ Watts Bar 2 setting up for finish of construction

· Displaces 680 million metric tons of CO2/yr

­ Equivalent to 131 million passenger cars/yr

· Despite low profile, nuclear is strong and about to grow substantially

6

United States New Generation

Southern Constellation Dominion SCE&G Entergy Duke Progress Energy TVA FPL NRG AREVA Westinghouse General Electric Toshiba MHI

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Uti lit

ies

olo hn Tec s g ie

EPR

ESBWR

AP 1000 ABWR

U.S. Nuclear Industry--First Movers

Constellation Nine Mile 1 EPR

Color Code

Planned New Nuclear Planned New Westinghouse Shaw Group Construction Permit Requested TXU Comanche Peak 2 APWR Entergy Grand Gulf 1 ESBWR TVA Bellefonte 2 AP1000 Ameren Callaway 1 EPR Constellation Calvert Cliffs 1 EPR Dominion North Anna 1 ESBWR TVA Watts Bar 2 1 W PWR Duke WL Lee 2 AP1000 SCE&G V.C. Summer 2 AP1000 Southern Vogtle 2 AP1000

Nuclear Plants in Northeast

NRG Energy South Texas 2 ABWR

Entergy River Bend 1 ESWBR

Progress Energy Florida Plant 2 AP1000

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The AP1000 Design

Reactor Inside Containment Turbine Generator

Support Systems & Buildings

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AP1000 Specification

· · · · · · Approximately 1150 MWe 2 Steam Generator Design 60 year design life No AC driven components needed for immediate accident response Passive Safety System/containment design features Small safety related foot print

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The AP1000 is Smaller and Dramatically Simpler than Evolutionary Plants

Sizewell B

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AP1000

What is different this time around?

· Use passive safety systems to respond to most transients and events

2 ­ Passive technologies give factor of 102 improvement in safety ­ Fewer moving parts = less to go wrong + less to buy + less to maintain for 60 years!

· State of the Art methods & components

­ Modular design ­ Fiber optic & digital controls

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AP1000 Compact Control Room

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Passive Systems Use Squib Valves

M

#1

M

ADS STAGES 1-3 (1 OF 2)

M

#2

M

M

#3

M

CONTAINMENT

REFUEL CAVITY

M

CORE MAKEUP TANK (1 OF 2)

PRESSURIZER

PRHR HX

SPARGERS (1 OF 2)

14"

M

IRWST

IRWST SCREEN (1 OF 2)

LOOP COMPART.

FAI

M M M

FO

ADS STAGE 4 (1 OF 2)

RECIRC SCREEN (1 OF 2)

8" 8"

HL

RNS PUMPS CL

RNS PUMPS

ACCUM. (1 OF 2)

N2

DVI CONN. (1 OF 2)

CORE REACTOR VESSEL

M

14

Squib Valve, Closed / Open

Closed Open

O UT LE T

Flow Once Squib is Fired

OUTLET

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Automatic Depressurization System Use of Squib Valves

· Squib Valves Were Selected for ADS Stage 4

­ ­ ­ ­ ­ ­ ­ ­ ­ ­ Very reliable to open on demand, better than AOVs, MOVs Ability to have independent actuation circuits, has 2 PMS & 1 DAS have independent actuation Diverse from ADS stage 1/2/3 MOVs, improves PRA Diverse from ADS stage Very low chance of inadvertent opening Zero leakage during normal operation Zero leakage during Simplified IST, ISI, maintenance Simplified IST, ISI, maintenance Reduced capital cost Reduced capital cost Reduced development costs // uncertainties vs alternative valve Reduced development costs uncertainties Compact size, weight Compact size, weight Suggested / supported by U.S. utilities during AP600 design

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AP1000 Improvements in Safety

U. S. NRC Requirements Current Plants US Utility Requirements

AP1000 Results

1 x 10-4 (a)

5 x 10-5

1 x 10-5 (a)

5.1 x 10-7 (a)

Core Damage Frequency per Year

Note (a) CDF includes random and internal hazard events from at-power and shutdown conditions.

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Modular Construction

· Approximately 300 modules · Some are major structural elements inside the containment · Some are skid mounted system · Some are prefabricated elements · Pipe Racks, etc that have been done before by Shaw for combined cycle plant construction projects

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Major Sub-Assembly 1 ­ Key Plan (these modules will hold the Reactor Vessel, Steam Generators and Pressurizer inside containment)

86'-5" 33'-9" 41'-8" 11'-0"

N

Major Sub-Assembly 4

1101S0129 1100S0130

1102S0131

1102S0132

31'-6"

Major Sub-Assembly 3

1101S0128 1102S0146 1102S0133 1102S0139 1101S0127 1102S0134 1100S0117 1142S0138 1102S0136 1101S0119 1102S0116 1101S0125

1101S0122

1101S0121

1101S0120

1101S0118

1150S0135

95'-0"

32'-0"

1101S0123

1102S0115

C Reactor L

1101S0124 1104S0126 1103S0114 1134S0137 (BELOW)

1104S0102

1104S0103

1104S0111

1100S0112

1103S0113 1104S0101 1104S0104

1104S0106

Reactor

31'-6"

Major Sub-Assembly 1

1104S0105

1103S110

Major Sub-Assembly 2

1103S0109

1104S0107

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C L

1100S0108

86'-5"

Sections Delivered by Truck or Rail

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Larger Assemblies Built Up in On Site Fabrication Yard

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Major Assembly Ready for Lift

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AP1000 Simplifications Benefit Reliability, Availability, Maintainability

Safety Valves

Pumps Safety Pipe

Seismic Building Volume

Cable

Reduced Number of Components:

Safety Valves Pumps Safety Piping Cable Seismic Building Volume 1000 MW Reference 2844 280 4 11.0 x 10 feet 9.1 mil. feet 3 12.7 mil. ft AP1000 1400 184 4 1.9 x 10 feet 1.2 mil. feet 3 5.6 mil. ft Reduction 51% 34% 83% 87% 56%

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Reliability in the AP1000

· AP1000 Is Designed for < 1 Reactor Trip / yr

­ Current PWR have been achieving ~ 0.5 RT / yr for many years Current PWR have been achieving ~ 0.5 ­ AP1000 will do better with simplifications, improvements AP1000 will do better with simplifications, · Man-machine interface, engineered / tested to reduce errors · I&C improvements incorporated I&C improvements incorporated ­ 2 / 4 logic, on-line diagnostics, periodic testing in bypass periodic testing in bypass mode without use of jumpers, "hot swapping" of modules mode without use of jumpers, "hot swapping" of modules · Canned motor Reactor Coolant Pumps are very reliable · Canned motor Reactor Coolant Pumps are very reliable · MFW control improved · control improved ­ Redundant instrument inputs, auto control over 0 ­ 100% ­ Redundant instrument inputs, auto control over 0 ­ 100% power power · Margins increased · increased · Reactor trip parameters selected reduce potential for · Reactor trip parameters selected unnecessary RT unnecessary RT

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Availability in the AP1000

· AP1000 Is Designed for > 93% Availability

­ Current PWRs are operating close to this goal ­ AP1000 will do better with simplifications, improvements

· Passive safety systems safety systems

­ Greatly reduced safety components with Tech Spec ­ Greatly reduced safety components with Tech Spec

· · · · ·

Canned motor RCPs are very reliable Canned motor RCPs Replacement SGs are very reliable Replacement SGs are very reliable Chance of reactor trip greatly reduced Chance of reactor trip greatly reduced Improved materials Improved materials Short refueling outage

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Maintainability in the AP1000

· Improved Maintenance / Inspection

­ Greatly reduced amount of maintenance / inspection required reduced amount of maintenance

· Passive system simplifications · Passive system simplifications · No planned maintenance for canned motor RCPs · No planned maintenance for canned motor RCPs

­ Increased laydown area inside containment ­ Access platforms for equipment maintenance/inspection built into plant

· Permanent service connections (air, power, computers) provided close by · Permanent service connections (air, power, computers) provided close by

­ Improved Access to Containment Improved Access

· 2 Equipment hatches and personnel airlocks, grade and operating deck · 2 Equipment hatches and personnel airlocks, grade and operating deck levels levels

­ One equipment hatch has truck access into containment ­ One equipment hatch has truck access into containment

· Large staging areas in aux bldg just outside equipment hatches · Large staging areas in aux bldg just outside equipment hatches

­ Improved containment laydown areas Improved containment ­ Non-safety active systems can be maintained at power

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Short Refueling Outage Schedule

· Refueling Outage Schedule is 15 Days

­ Breaker to breaker ­ Simplified passive systems eliminate most ISI, IST, maintenance · Especially for complex rotating pumps, DG, chillers, ... ­ Nonsafety active systems can be maintained at-power Nonsafety active systems can be maintained at-power ­ Lessons learned (vacuum refill, effective degas/cleanup, ...)

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Nuclear Wrap Up

· Outlook ­ several southern US utilities in discussions on AP1000 orders · NRC has three Combined Operating License (COL) applications on the docket

­ Bellefonte 3 & 4 (based on AP1000) ­ Calvert Cliffs 3 (based on EPR) ­ STP 3 & 4 (based on ABWR)

· "the reactor is critical, commencing to raise power to the point of adding heat"

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New Reactor Presentation

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