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Overview of ABWR Safety

Features

INPRO Dialogue Forum November 19-23, 2013

J. Alan Beard Principal Engineer

Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

GE Hitachi nuclear alliance and businesses

  • Tokyo, Japan
  • Wilmington, NC

USA
Peterborough, ON Canada
Wilmington, NC USA

Wilmington, NC

Yokosuka, Japan

•Nuclear Power Plants: ABWR,

ESBWR and PRISM

•Nuclear Services
•Uranium Enrichment

… Third

•Nuclear Fuel Fabrication

….BWR and CANDU

•CANDU Services

•Advanced Programs …

Recycling

Generation

Technology
•Fuel Engineering and Support

Services

•GENUSA European Fuel Joint Venture

2
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

BWR legacy around the world

Dodewaard - Netherlands

  • K6/K7 - Japan
  • KKM - Switzerland

Dresden 1 – USA

KRB - Germany
Lungmen - Taiwan
Santa María de Garoña - Spain

Vallecitos – USA
Garigliano - Italy
Laguna Verde - Mexico

Tarapur 1&2 – India

3
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Recent project experience

Kashiwazaki-Kariwa 6/7 ABWR

COD 1996/1997

Hamaoka-5 ABWR

COD 2005

Shika-2 ABWR

Continuously building for 58 years

COD 2006

Images copyright TEPCO, Hokuriku Electric Power, Chugoku Electric Power, and J-Power; Provided by Hitachi GE Nuclear Energy

4
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Current project status

Ohma ABWR

Ohma 1

• 38% complete

Shimane 3

• 94% complete

Under Construction

Shimane-3 ABWR

• Approaching fuel load

Lungmen 1&2

• 94% complete • Startup and Pre-Op testing

Under Construction

Lungmen-1/2 ABWR

Continuously building for 58 years

Under Construction

Images copyright TEPCO, Hokuriku Electric Power, Chugoku Electric Power, and J-Power; Provided by Hitachi GE Nuclear Energy

5
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

GE Hitachi’s new reactor portfolio

PRISM

ABWR

ESBWR

Revolutionary technology with a rich, 40-year heritage
Evolutionary Gen III+ technology
Operational Gen III technology

• Lowest core damage frequency of any Generation III+ reactor
• Passive cooling for >7 days w/o

AC power or operator action
• Lowest projected operations,

maintenance and staffing costs1
• 25% fewer pumps, valves and

motors than active safety plants
• Lowest core damage frequency of any Generation III reactor
• Extensive operational

• Passive air-cooling; no operator

or mechanical actions needed
• The answer to the used fuel

dilemma - can reduce nuclear waste to ~300-year radiotoxicity2 while generating electricity experience since 1996
• Licensed in US, Taiwan & Japan

  • 1
  • Claims based on the U.S. DOE commissioned ‘Study of Construction Technologies

and Schedules, O&M Staffing and Cost, and Decommissioning Costs and Funding

Requirements for Advanced Reactor Designs’ and an ESBWR staffing study

performed by a leading independent firm

  • 2
  • To reach the same level of radiotoxicity as natural uranium

6
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

ABWR Basic Parameters

3,926 Megawatt core thermal power ~1,360 MWe gross

• Nominal summer rating

Reactor Recirculation with Internal Pumps

• External recirculation piping eliminated

Active safety systems

• 72 hours automated capability

Operating cycle length of 12 to 24 months

7
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

BWR Evolution

Dresden 1

KRB

Dresden 2
Oyster Creek

ABWR
ESBWR

8
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Containment Evolution

9
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

ABWR Overall Flowchart

10
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

ECCS Systems Evolution

Typical
Typical

BWR/4

ABWR

RCIC
LPCF/RHR

BWR/5 BWR/6

HPCS
HPCI

ADS

LPCS LPCI LPCI
LPCS LPCI LPCI
HPCF
LPCF/RHR
HPCF
LPCI/RHR

LPCS
LPCI/RHR LPCI
RHR
RHR

LPCF/RHR

ADS
ADS

5000
1900

29000
12
High pressure capacity Low Pressure capacity

No. of large pipes below core

Peak clad temperature (App K), °F
2800
42000

12

19000
0

1600

1100

No uncovery
Required

  • Operator action
  • Required

Automated >72

hours

11
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Emergency Core Cooling System

12
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Emergency Core Cooling

HPCF
LPCF/RHR

ADS

RCIC
HPCF

LPCF/RHR

LPCF/RHR

Core is always under water

13
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

ABWR Reactor Core Isolation Cooling (RCIC)

14
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

ABWR High Pressure Core Flooder (HPCF)

15
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

ABWR Residual Heat Removal (RHR)

16
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Automatic Depressurization System (ADS)

17
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

ABWR Key Design Features – Onsite AC Power

18
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

Severe Accident Features

ABWR passive features which mitigate severe accidents:

• Inerted Containment

• Lower Drywell flood capability

• Lower Drywell special concrete & sump protection

• Suppression pool - fission

products scrubbing & retention

• Containment overpressure protection

19
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

AC Independent Water Addition (ACIWA)

Hard piped fire water connections Seismic Category 1

On-site fire protection system connection

Truck connection

• Ties to RHR C

20
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

References

ABWR

Design Certification Document, Rev. 4:

http://www.nrc.gov/reactors/new-reactors/design-cert/abwr.html#dcd

Safety Evaluation Report, NUREG-1503 and NUREG-1503 Supplement 1:

http://pbadupws.nrc.gov/docs/ML0806/ML080670592.html

Design Certification Rule, 10CFR52 Appendix A:

http://www.nrc.gov/reading-rm/doc-collections/cfr/part052/part052- appa.html

Revision 5 of the ABWR DCD can be found here:

http://pbadupws.nrc.gov/docs/ML1100/ML110040323.html

Reference BWR (Grand Gulf NPP) NUREG-1150

http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1150/

21
Copyright 2013 GE Hitachi Nuclear Energy International, LLC - All rights reserved

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