1. Nuclear Power Update for The Society of American Military Engineers
September 15, 2010

2. Nuclear Power Facilities- Safety is Key
Multiple Layers of Safety
45 inch steel-reinforced concrete
1/4 inch steel liner
36 inch concrete shielding
8 inch steel reactor vessel
The large reactor vessel has steel walls 8 inches thick. The vessel is surrounded by 3 feet of concrete shielding. At most plants, a leak-tight steel liner covers the inside wall of the containment building. The containment building is a massive, reinforced concrete structure with walls 4 feet thick.
nuclear fuel assemblies

3. Industry Activities
Licensing risk is a key issue for the industry to move forward with actual plant orders
Previously separate construction and operating licenses were required
No certainty provided by this process
Many physical changes were required prior to receipt of operating licenses
Costs increased due to schedule delays and rework required
Industry has adopted new process which results in combined construction and operating license

4. New Licensing Process provides regulatory certainty
New page 23
New Licensing Process provides regulatory certainty
Licensing decisions finalized before major construction begins
Inspections to verify construction
Limited work may be authorized before license is issued
Pre-Construction
Construction Verification
Early Site Permit
Standard Design
Certification
Combined License
Review, Hearing,
and Decision
Verification of
Regulations
with ITAAC
Reactor
Operation
Decision
Optional
Pre-Application
Review

5. Industry Activities Industry has adopted several standard designs
Westinghouse AP 1000 (design certified 1/2006)
General Electric ESBWR
General Electric ABWR (design certified 5/1997)
Areva US EPR
Mitsubishi US APWR

6. New Technology - Advanced Reactor Characteristics
Safety
Use of passive safety systems
Gravity flow and natural circulation designs for cooling
Design
Reduced number of components and bulk commodities
Eliminate pumps and valves previously needed
Use digital controls and fiber optic cables
Procurement
Standardization of components based on NRC approved design

7. Fewer Components Reduce Plant Costs
45% Less Seismic Building Volume
70% Less Cable
50% Fewer Valves
35% Fewer Pumps
80% Less Pipe
Confidential and Proprietary

8. New Technology - Advanced Reactor Characteristics
Construction
Extensive use of modular construction improves quality and reduces on-site construction requirements
Digital controls reduce size and complexity of systems
Shorter construction schedule
Operation and Maintenance
Use of proven systems and components
Man-machine interface advancements
Fewer systems to maintain and test reduces staff

9. Smaller and Simpler than Current Plants
Many Evolutionary plants improve PRA and safety by adding equipment thereby adding redundancy (4 train) and diversity.
Passive safety presents an alternative approach to improved safety which simplifies the plant.
Sizewell B is a 1250MW 4-loop PWR in England. AP1000 net electrical output is 1117MW.
The comparison is to scale. The AP1000 is much smaller and simpler than Sizewell B.
The four colors represent the Safety related Electrical Divisions for AP1000 and Sizewell.
Sizewell B
AP1000
74147A

10. Economics What makes Nuclear attractive?
Fuel volatility, both gas and coal, is a major concern
Fuel transport and supplies are showing signs of capacity constraints
Environmental compliance measures are increasing cost of coal base load resources
Regulation of carbon dioxide (CO2) emissions is gaining traction
New licensing process expected to allow cost control
New design units are smaller and less costly to construct

11. Costs of Competing Fuels

12. Plant Vogtle Reactor Containment Bldg. Cooling Towers
Turbine Bldg Electrical Switchyard

13. Plant Vogtle Expansion

14. PSC Certification Process (complete)
Schedule Overview
2005
2006
2007
2008
2009
2010
2011
2012
2013
2014
2015
2016
2017
ESP Preparation
ESP and LWA Review
ESP and LWA Received
PSC Certification Process (complete)
EPC Contract Signed
4-8-08
PSC Certification received
COLA Preparation
NRC COL Review
COLA Submitted
COL Received
Fall 2011
Pre-Construction
LWA Activities
Construction
S/U
COD U3
Commercial operation date is April 2016 & 2017 for Units 3&4
S/U
As of 6/30/2010

15. Permit and License Activities
Early Site Permit
Submitted to NRC in 2006
Issued by NRC August 2009
First to include Limited Work Authority
Combined License Application
COL Application Filed in March 2008
Application Under Review at NRC
Anticipate License in Fall 2011
Vogtle Named Reference Plant

16. Vogtle 3 & 4 Construction Phases
Pre Certification
Pre Construction
LWA
COL
Surveying
Subsurface Exploration
Environmental Protection
Site-clearing
Demolition & Relocation of existing facilities
Construction of training & storage buildings
Excavation of the nuclear island
Back Fill
Waterproof Membrane
Rebar
Basemat Concrete
Safety Related Construction
Onsite Workers
2009
2010
2011
2012
PSC Certification
LWA
COL

17. Construction Activities – Module Assembly Building

18. Construction Activities
Steam Generator Head
Circulating Water Pipe
Reactor Vessel Head

19. Construction Activities – Foundation Excavation and Backfill

20. Chinese Construction AP1000
Sanmen U1 Nuclear Island

21. Questions