Improved transient performance

Appendixes

300MWe class

600MWe class

800MWe class

HOOMWe class

1500MWe class

Westinghouse Electric Corporation design

Japan improved type

Westinghouse Electric Corporation design

Japan improved type

APWR

Number of loops

2

3

4

Fuel type (Initial load)

14x14

15x15

17x17

Average core power density (kW/t)

71

83-95

92

100

105

103

Heat transfer area (ft²) of steam generator

36,390

44,430-

51,500

51,500

About

70,000

Coolant pump

63 type

93A type

93A, 93A-1 type

93Atype

93A-1 type

100A type

PCV type

Steel semi-double

Steel semi-double, Steel double

Steel double

Ice condenser

PCCV

PCCV

Turbine type

TC2F44

TC4F40,

TC4F44

TC6F40

TC6F44

TC6F54

NSRA, Japan _app_t - /2

Improved Items in the 2^nd I/S Project

Improved Items in the 3^rd I/S Project

Items

Improvement

Items

Improvement

Items

Improvement

Reliability

• Desalination of RCW cooling System

• Measures against Stcrss Corrosion Cracking(SCC)

• Instrumentation

-Additional intermediate loop of RCW cooling system

Individual or combination of the following measures, -Evaluation of material (change to carbon steel or super-low carbon stainless steel)

-Post welding solid solution heat treatmcnt(SHT) -Heat sink welding(HSW)

-Corrosion resistant cladding(CRC)

-Induction heating stress improvcment(IHSI) -De-aeration in reactor startup operation

-Multiplexing of moisture separator high drain-level -Multiplexing of reactor high water-level

Reliability and Availability

•Fuel

■Reactor core design

■Measures against Sterss Corrosion

Cracking(SCC)

■ Control Rod Dnve(CRD) ■Measures against thermal stress reduction at feed­water nozzle

-Use of pressurized fuel -Improvement of control rod head -Use of new type 8^X8 fuel assembly -Use of super-low carbon stainless steel(316 stainless steel for nuclear reactor)

- Use of high speed scram CRD

-Injection of high temperature return water from reactor water cleanup system to feed-water system

-Addition of small valves using for flow control on feed­water line

Inspection Efficiency

• Shortning of process time for turbine system periodical inspection

• Improvement of dose reduction relating equipment

-Shortening of process time for periodical inspection of turbine (double overhead cranes, use of small exclusive cranes)

-Automation (robotization) of turbine relating work

■Automation ofcleaning and decontaminaiting of rotor

■ Automation of cleaning and decontaminaiting of diaphragm

•Automation of turbine axial dimension measuring -Automatic CRD overhaul machine -Automatic fuel inspection machine -Automatic ultrasonic test equipment of bend pipe weld

Radiation Dose Reduction

• Improvement of Pump gland seal & Sampling devices

• Prevention and Removal of Cladding

• Measures for ALAP

■Improvement of

Sampling devices •Automation and work­ability enhancement for In-service Inspection (ISI)

-Addition of mechanical seal purge system

-Dissolved oxygen control

-Adoption of oxygen injection equipment -Condensate filter demineralizer -Feed water retreatment circulation piping -Use of low carbon material

-Radioactive noble gas holdup equipment -Use of clean steam for turbine gland seal system -Use of small bellow seal valves for high radioactive and high temperature system and stem leak-off Imes for large valves

-Improvement of sampling line and sampling racks

-Remote automation of RPV ISI

-Retaining work space for ISI and improvement of accessibility

Radiation Dose Reduction

■Use of cobalt-free material

• Animation of nuclid . analysis

■ Improvement of valve gland seal

•Automation and workability enhancement for In-service Inspection

-Abrasion resistance material (e.g.: pin roller of control rod)

-Improvement of gas component in stack

-Improvement of packing

-Enlargement of automation

-Development of high speed system for processing and analyzing inspection data

Radioactive Waste Process ing

-Change of number of radioactive noble gas holdup containers

-Change of number of collecting tanks for high conductivity liquid waste

-Commoditizing of spare demineralizers between low and high conductivity liquid waste system

-Commoditizing between storm drain and shower drain system

-Streamlining of high conductivity liquid waste storage tanks

-Use of hollow fiber filters for low conductivity liquid waste filtration facility

Inspection Efficiency

■PCV configuration

■Maintenance of Control Rod Drive (CRD)

• Sealing Water Plug of Main Steam Noslcs

•Automation of Refueling Machine

• Exchanging of Neutron Monitor

-Retaining work space

-Accessibility improvement by addition of stairs -Reduction of working hours by addition of safety relief valve carry in/out hatch

-Streamlining of work by exclusive monorail -Remote and automatic CRD exchanger

-More reliable water seal plug for RPV main steam line nozzle

-Remote and automatic fuel exchanger

■In-core guide for installation of core internals -Improvement of cable connector

Inspection Efficiency

• Speedup of fuel exchange

• Speedup of exchange of control rod drive (CRD)

• Speedup of exchange of neutron monitoring dcvice(LPRM and dry tube)

• Improvement of single stud tensioner

-Speedup of refueling machine by extensive computer application

-Use of CRD automatic exchanging machine available for automatic positioning and automatic replacing of CRD mounting bolt

-Improvement of flushing device for valve seat -Long-life detector for LPRM

-Automation of replacing ofRPV flange nuts and cleaning of scud screw

Construction Method

-Reduction of field work (laborsaving) -Increasing of parallel work -Streamlining of field work construction method

Instrument and Operation

-Practical application of instruction system

-Practical application of automatic inspection system in PCV

-Improvement of operating management system -Improvement of automatic operating system -Improvement of signal transmitting system -Improvement of cabling system

■Improvement of instrumentation system focused on turbine system

■7

Improved Items in the 2^nd I/S Project

Improved Items in the 3^rd I/S Project

Items

Improvement

Items

Improvement

Items

Improvement

Enhancement of Reliability

• Minimization of fuel bowing (bending)

• Prevention of SG tube wall from thinning and corrosion

■Improvement in the speed and accuracy of ECT for SG tubes

-Adaption of improved grid spring design -Increased number of grids (9 gnds) -Enhancement of Zircaloy-2 water chemistry specifications -Adaption of improved design SGs

-Simultaneous flaw testing with multiple frequencies

Enhancement of Reliability

•Comprehensive approaches to resolve the fuel bowing issue

■ Survey/development of SG tube material

• Countermeasures for SG tube denting

-Verification via irradiation experiments in actual reactors of measures for reducing fuel bowing, such as fuel grid soft springs

-Adaption of thermally treated Inconel 600 tubes

-Improved shape of tube support plate holes

-Improved material for tube support plates (SUS4O5 instead of carbon steel)

Improvement for ISI

■ Increased efficiency in ISI

-Studies to shorten ISI durations for turbine systems -Comprehensive study on ISI procedures (including design improvement to reduce radiation dose to plant workers)

-SG water chamber automatic cleaning equipment

-Automation of primary water chemistry control/analysis equipment

-Verification tests of primary side crud removal system

Increased Efficiency in Maintenancc/Inspections and Reduced Radiation Dose to Plant Workers

■ Improvement in reactor vessel head stud-tensioner design

•Quick installation/ removal of reactor vessel head

•Improvement in fuel handling system design

■Automation of instrumcntation/control system equipment

- Enhancement related to valves

-Increased number of stud-tensioners

-Larger diameter of hydraulic pressure line hose -Addition of a stop valve in each hydraulic pressure line to stud-tensioners

-Adaption of improved tightening devices for thermo-couple cono-seals

-Improved design of CRDM cooling duct connections

-Addition of sipping cans

-Improved design of reactor cavity cleaning unit -Improved shape of cavity wall comers

-Improved cavity sealing ring gasket -Increased number of tool racks

-Adaption of automatic sampling unit for iodine and tritium measurement

-Installation of automatic pH meters on SG blow-down lines and in WDS

-Adaption of non-leakagc valves and graphite packing valves

-Expansion of ranges of automatic/remotely operated valve application

Increased Efficiency in Mainlenance/Inspections and Reduced Radiation Dose to Plant Workers

■One-piece design of reactor vessel head structures

•Development of manipulator used in SG water chambers and mounting equipment for it

■Refinement in SG water chamber nozzle plug design

■Improved fuel inspection system

■ Automation of ISI equipment

•Non-leakage type valves for low pressure applications

-One-piece design of reactor vessel head and structures installed on it

-Adaption of high speed multi-purpose manipulator and its mounting equipment

-Adaption of refined design plugs for easy mating and un-matmg

-Adaption of inspection-pit type fuel inspection system

-Improved reactor vessel UT machine and automatic piping UT machine

-Adaption of improved rubber diaphragm valves

Improvement/Standardization ofWDS

-Change of shared ranges ofWDS equipment -Rationalization of laundry/hot shower drain treating system

-Change of spent resin transfer system

Enhancement Related to Plant Operation

■ Design improvement for plant operability

-Adaption of monitoring/indication system based on CRT displays

Improved Construction Method

-Construction method to reduce the amount of field works

-Construction method utilising expanded ranges of parallel works

-Rationalization of field works

■ Improved design of pumps

-Adaption of spool-piece design to reactor coolant pumps

-Adaption of hard packing to reciprocating charging pumps

-Installation of leak-detection devices on reciprocating charging pumps

Other Technical

Developments

■Feasibility study ofPCCV

-Adaption of PCCV design for 4-loop plants

Enhancement Related to Instrumentation and Plant Operation

-Practical utilization of instruction system -Development of automatic inspection equipment

design to be used in containment

-Development of improved control/monitoring system design

-Development of improved reactor controVprotection

* Sampling system

-Adaption of sinks for local liquid sampling

system design

■ Automation of ISI Equipment

-Adaption of automatic reactor vessel UT units

-Improvement of cabling systems

* Measures for radiation

-Installation of charcoal filter unit in the condenser air

exposure ALAP

ejector discharge line

-Connection of the deaerator vent to the condenser

-Enhanced inspection system for SG tubes

-Automation of ECT systems

• Improved workability of

-ECT of SG tubes

activities in containment

-Access routes for SG inspections/maintenancc -Access routes for RCP maintenance

-Improved designs to ease ISI tasks

-Organized piping/supports design in the pressurizer compartment

-Reservation of lay-down spaces

Appendix 7 Key Specifications of BWR, PWR, ABWR and APWR Plants (1/4)

BWR(l,100MWe class) (Kashiwazaki Kariwa 3/4 unit at commercial operation start)

ABWR(l,300MWe class) (Kashiwazaki Kariwa 6/7 unit at commercial operation start)

PWR(l,100MWe class) (Ohi 3/4 unit at planning)

APWR(l,500MWe class) (Tsuruga 3/4 unit at planning)

1.Power

Thermal power

MWt

3,293

3,926

3,423

4,466

Electricity

MWe

1,100

1,356

1,180

1,538

2.Thennal Efficiency

%

33.4

34.5

34.5

34.4

3.CooIant

Inlet temperature

°C

279

278

289

289

Outlet temperature

°C

286 (steam)

287

325

325

Operating pressure (gauge) Total amount

kg/cm²

70.7 (steam)

272t (in reactor vessel and recirculation loop)

7.07MPa

306t (in reactor vessel)

157

35 Im³ (at rated output)

157

452m³ (at rated output)

4 .Reactor Core

Height

m

3.71

3.71

3.66 (active)

3.66 (active)

Diameter

m

4.75

5.16

3.37 (equivalent)

3.89 (equivalent)

Core flow rate

tih

48.3X10³

52xl0³

60.1X10³

60.1X10³

Power density

kW/I

50.0

50.6

105

103

5,Fuel

Specific power

MWt/tU

24.9

26.2

39.7

37.3

Loading weight

MTU

132

150

86

121

Enrichment (initial/equilibrium)

wt%

2.5Z3.4

2.6/3.5

1^st region; 2.3 2^nd region; 2.9 3^rd region; 3.5

1^st region; 1.9

2^nd region; 3.1

3^rd region; 4,3

Bumup (initial/equilibrium)

MWd/t

27,000/39,500

27,000/39,500

24,000/34,000

35,000/49,000

Number of fuel assemblies

—

764

872

193

257

Arrangement of fuel elements

—

8x8

8x8

17x17

17x17

Fuel elements per fuel assembly

—

60

60

264

264

Cladding material

—

Zircaloy-2

Zircaloy-2

Zircaloy-4

Zircaloy-4

Cladding thickness

mm

0.86

0.86

0.64

0.57

Total length of fuel element

m

4.2 (incl. end piece)

4.2 (incl. end piece)

3.9 (incl. end piece)

4.0 (incl. end piece)

Diameter of fuel element

mm

12.3

12.3

9.5

9.5

Maximum linear power density

kW/m

44

44

41.5

59.1

6.Reactor Pressure Vessel

Operating pressure

87.9kg/ cm²

8.62MPa

175kg/cm²

17.16MPa

Operating temperature

°C

302

302

343

343

Inner diameter x Height(inside measure)

m

6.4x22

7.1x21

4.39x12.9

5.2x13

Weight

t

740

910

400

560

NSRA, Japan _app. -

BWR(l,100MWe class) (Kashiwazaki Kariwa 3/4 unit at commercial operation start)

ABWR(l,300MWe class) (Kashiwazaki Kariwa 6/7 unit at commercial operation start)

PWR(l,100MWe class) (Ohi 3/4 unit at planning)

APWR(l,500MWe class) (Tsuruga 3/4 unit at planning)

7.Control Rod

Number of rods

Driving method Material

Shape

—

185

hydraulic pressure drive boron carbide (partially hafnium) crisscross

205

motor drive / hydxauEc pressure drive

boron carbide (partially hafnium) crisscross

1,272 (53 clusters) magnetic jack-type silver-indium-cadmium ahoy cluster

1,656 (69 clusters) magnetic jack-type silver-indium-cadmium alloy cluster

8.Reactivity Control

Long-term reactivity control

Short-term reactivity control Emergency reactivity control

Backup reactivity control for shutdown

—

control rod and burnable neutron absorber (Gd₂O₃) recirculation flow rate control rod boric acid water injection system or standby Equid control system

control rod and burnable neutron absorber (Gd₂O₃) recirculation flow rate control rod boric acid water injection system or standby liquid control system

concentration of the boron, burnable poison (boron selicate glass) control rod cluster control rod cluster

concentration of the boron, burnable poison

■ (boron sehcate glass) control rod cluster control rod cluster

9.Steam Generator

Type

Number of generators

Number of heat transfer tubes (per unit) Material of heat transfer tube

Total height

m

—

—

vertical U-type heat exchanger 4

3,382 nickel-chromium-iron alloy 21

vertical U-type heat exchanger

4

5,830 nickel-chromium-iron alloy 21

10.Primary Coolant Pump

Type

Number of pumps

Flow rate per pump

Head

Type of motor

Rating per motor

m³/h m

kW

(recirculation pump) longitudinal centrifugal type 2

9,700

243 three-phase induction motor 5,800

(recirculation pump) single-stage diagonal type 10

7,700

40

three-phase induction motor

830

vertical shaft slant flow type 4 20,100

84 three-phase induction motor 4,500

vertical shaft slant flow type 4

25,800

89 three-phase induction motor 6,000

11.Pressurizer

Type

Number of pressurizers

Outside diameter

Total height

Electric heater

ID m

vertical cylindrical vessel with hemispherical top and bottom head

1

2.4

15.9

penetrate (l,800kW)

vertical cylindrical vessel with hemispherical top and bottom head

1

2.7

16

penetrate (l,800kW)

Appendix 7 Key Specifications of BWR, PWR, ABWR and APWR Plants (3/4)

BWR(l,100MWe class) (Kashiwazaki Kariwa 3/4 unit at commercial operation start)

ABWR(l,300MWe class) (Kashiwazaki Kariwa 6/7 unit at commercial operation start)

PWR(l,100MWe class) (Ohi 3/4 unit at planning)

APWR(l,500MWe class) (Tsuruga 3/4 unit at planning)

12.Primary Containment Vessel

Type

Inner diameter

Height

Charged gas

Charged gas pressure

Design pressure

Design temperature

Number of spray systems

m m

kg/cm²-a

°C

pressure suppression type

29

48 nitrogen

1.0

3.16kg/cm²

171

2

pressure suppression type

29

36 nitrogen

1-1

310kPa

171

2

cylinder with hemispherical top type (PCCV) 43

65.6

4kg/cm²

144

2

cylinder with hemispherical top type (PCCV) 45.5

69

392kPa

144

4

13.Emergency Core Cooling System

High Pressure Core Spray System

Number of systems: 1

System flow rate: 360-l,570m³/h

High Pressure Core Injection System

number of systems: 2 system flow rate per system: 180-730m³/h

Low head injection

Number of systems: 2

System flow rate: 1,020 m³/h

Number of pumps: 2

—

Automatic Depressurization System

Number of valves: 7

Valve flow rate: 377tih (at 79.4kg/cm²-g)

Automatic Depressurization System

Number of valves: 8

Valve flow rate: 380tih (at 7.92MPa(gauge])

High head injection

Number of systems: 2

System flow rate: 320 m³/h

High head injection

Number of systems: 4

System flow rate: 300 m³/h

Low Pressure Core Spray System

Number of systems: 1 System flow rate: l,440m³/h

Reactor Core Isolation Cooling System

Number of systems: 1

System flow rate: 190m³/h

Accumulator injection

Number of systems: 4 System flow rate: 38m³

Number of tanks: 4

Accumulator injection

Number of systems: 4 System flow rate: 90m³ Number of tanks: 4

Residual Heat Removal System (low pressure injection mode) Number of systems: 3 System flow rate per system: I,690m³/h Number of pumps: 3

Residual Heat Removal System (low pressure injection mode) Number of systems: 3 System flow rate per system: 950m³/h

Number of pumps: 3

14.ResiduaI Heat Removal System Number of systems

Flow rate per system

Heat removal capacity per system

m³/h kcal/h

Residual Heat Removal System (shutdown cooling mode) 2 l,690m³/h

1.0xl0⁷kcal/h

Residual Heat Removal System (shutdown cooling mode) 3 950m³/h

8.2xl0³kW

Residual Heat Removal System

2

681 m³/h

^SxlO^kcal/h

Residual Heat Removal System

4

442 m³/h 2.4x10^^/ (atprimary containment vessel spray)

NSRA, Japan - 18

BWR(l,100MWe class) (Kasiwazaki Kariwa 3/4 unit at commercial operation start)

ABWR(l,300MWe class) (Kasiwazaki Kariwa 6/7 unit at commercial operation start)

PWR(l,100MWe class) (Ohi 3/4 unit at planning)

APWR(l,500MWe class) (Tsuruga 3/4 unit at planning)

15.Steam Conditions

Steam temperature

Steam pressure

°C

282 (at main steam stop valve inlet)

66.8kg/cm²

(at main steam stop valve inlet)

284 (at main steam stop valve inlet)

6.69MPa

(at main steam stop valve inlet)

273.9 (at main steam stop valve inlet) 59.7kg/cm²(at Main Steam Stop Valve inlet)

274 (at main dteam dtop valve inlet) 5.7MPa (at dain dteam dtop valve inlet)

16.Steam Turbine

Type

Ouiput

Speed

Inlet steam pressure Outlet steam temperature Steam flow rate

MWe rpm

°C t/h

tandem compound, six-flow, exhaust condensing turbine

1,100

1,500

66.8kg/cm² (at turbine rating)

282

6,400

tandem compound, six-flow, exhaust reheat, regenerative condensing turbine

1,356

1,500

6.69MPa (at turbine rating)

284

7,300

tandem compound, 4 cylinders, 6 flows, reheat regenerative type

1,180

1,800 59.7kg/cm² (at turbine rating)

273.9

6,700

tandem compound, 6 flows, reheat regenerative condensate type 1,538 1,800

5.7Mpa (at turbine rating) 274

8,600

17.Generator Type

Capacity

Type of cooling

Speed

kVA ipm

horizontal, cylindrical and revolving-field type, three-phase synchronous

1,300,000 hydrogen cooling (rotor) / hydrogen cooling (stator coil)

1,500

horizontal, cylindrical and revolving-field type, three-phase synchronous

1,540,000 hydrogen cooling (rotor) / water and hydrogen cooling (stator coil)

1,500

horizontal, cylindrical and revolving-field type, totally-enclosed self-ventilating, three-phase synchronous 1,310,000 internal hydrogen cooling (rotor)/ water cooling (stator coil)

1,800

horizontal, cylindrical and revolving-field type, totally-enclosed self-ventilating, three-phase synchronous 1,715,000 internal hydrogen cooling (rotor)/ water and hydrogen cooling (stator coil) 1,800

18.Feedwater Feedwater temperature Feedwater pump Type Number of pumps Flow rate per pump

°C

m³/h

216

centrifugal

turbine drive: 2 motor drive: 2 turbine drive: 3,900m³/h

motor drive: l,950m³/h

216

centrifugal

turbine drive: 2 motor drive: 2 turbine drive: 4,700m³/h motor drive: 2,300m³/h

223

centrifugal

turbine drive: 2 motor drive: 1 turbine drive: 4,300m³/h motor drive: 3,300m³/h

227

centrifugal

turbine drive; 2 motor drive; 1 turbine drive; 5,600m³/h motor drive: 3,100m³/h