X;;; nsra, Japan

List of Tables

Table3.4.6 Primary coolantpipingspecifications (example)

344

Table 1.1.1 Status of development of nuclear power

Table3.4.7 Reactor coolant pump (Type 96 A-l)main data

345

generation in the world

1-3

Table 3.5.1 Function of main components of turbine system

349

Table 1.2.1 Individual risks of acute fatality due to

Table 3.5.2 Turbine tyix‘ and applicable output

350

several causes

1-6

Table 3.5.3 Comparison of feed water pump (1200MWe class)

358

Table 1.5.1 Reactor facility technical specifications

1-13

Table 3.6.1 list of reactor trip signals

Table 3.6.2 List of permissive signals for reactor trip signals

364

365

Chapter 2

Table 2.4.1 Key specifications of a reactor primary

Table 3.6.3 Function of reactor trip signals

Table 3.6.4 list of engineering safety feature (ESF)

367

coolant system (l,100MWe class)

2-38

actuation signals

368

Table 2.5.1 List of steam turbine shutdown system trip signals 2-52

Table 3.6.5 List of permissive sign als of engineering safety

Table 2.5.2 Specifications of 1,100 MWe class turbine system

2-53

feature (ESF) actuation signals

369

Table 2.6.1 Reactor shutdown system trip signals

2-62

Table 3.6.6 Functions of reactor control subsystems

371

Table 2,6.2 ESF initiation signals

2-64

Table 3.6.7 Main equipment in emergency shutdown panel

Table 2.6.3 Comparison of automation extent in tliree

outside main control

3-79

MCR generations

2-73

Table 3.6.8 Process monitor channel (example)

381

Table 2.6.4 Process radiation monitors (example)

2-78

Table 3.6.9 Location of area monitor (example)

381

Table 2.6.5 Area radiation monitors (example)

2-79

Table 3.6.10 Radioactivity measurement during accident

381

Table 2.7.1 ECCS functions (BWR-5)

Table 2.7.2 ECCS redundancy for active component

2-85

Table 3.10.1 Main Generator Specification (examole)

Table 3.11.1 Demineralized water quality specification

3115

single failure assumption

2-86

(Typical at outlet of demineralizer)

3120

Table2.8.1 Basic specifications of the main components of

Table 3.12.1 Basic specifications of APWR

3128

the RHR system

2-94

Table 3.12.2 Main specifications of steam generator

3131

Table 2.8.2 Basic specifications of the main components of

Table 3.12.3 Main specifications of reactor coolant pumps

3132

the RCIC system

2-95

Table 3.12.4 Emergency core cooling system configurations

3133

Table 2,8.3 Basic specifications of main components of the CUW system

Table 2,8.4 Key specifications of main components of

2-98

Table 3.12.5 Main specifications of reactor containment facility 3135

Chapter 4

theFPC

2-99

Table 4.1.1 Major legislation and regulations for operation

Table 2.10.1 Main generator specifications (example)

2-107

and maintenance of nuclear power plants

4-1

Table 2.11.1 Examples of plant water uses or users

2-112

Table 4.1.2 Surveillance test items during plant

Table 2.11.2 Examples of auxiliary steam uses or users

2-114

operation (example)

4-9

Table 2.11.3 Examples of compressed air uses or users

2-116

Table 4.2.1 Periodic inspection items (example)

4-16

Table 2.12.1 Technical features of an ABWR and

Table 4.2.2 Check items for major components

4-17

overall characteristics of the plant

2-119

Table 4.3.1 Components subject to individual inspections

Table 2.12.2 Comparison of safety features

Chapter 3

2-126

and inspection methods

Chapter 5

4-28

Table 3.3.1 Basic fuel design parameters

Table5.1.1 Example of periodic test

310

(high burnup Step-2 fuel)

3-16

Table 5.2.1 Periodical Inspection Items

316

Table 3.3.2 Fuel rod design criteria and basic considerations

Table 3.3.3 Specifications of Japanese reactors and their cores

3-20

322

Table 5.2.2 Overhaul inspection required by regulations

324

Table3.4.1 Reactor vessel specifications (3-loop)

3-38

Chapter 6

Table 3.4.2 Laws, regulations and standards relating to

Table 6.3.1 Radioactive nuclides in LWR primary coolant

35

primary coolant system components

3-38

Table 6.3.2 Contribution of nuclides to the dose equivalent

Table 3.4.3 History of steam generator improvement

341

rate of piping of the reactor coolant system

36

Table 3.4.4 Steam generator specifications (example)

341

Table 6.3.3 Materials constituting the primary

Table 3.4.5 Pressurizer specifications (3-Loop)

343

system components

36

Table 6.3.4

Example measures for dose reduction

6-8

Table 10.9.3

Table 6.4.1

Design base doses

fr9

Table 6.4.2

Examples of shielding design classification

Table 10.9.4

and shielding design base dose rates

6-10

Table 10.9.5

Table 6.5.1

Criteria for controlled area classification

(examples)

6-11

Table 10.9.6

Table 6.5.2

Example radioactive material measurement items

and their frequencies of measurement

6-13

Table 10.9.7

Table 6.6.1

Measures for exposure reduction and assurance of a safe work environment

6-15

Table 6.6.2

ALARA check sheet (example)

6-16

Table 6.7.1

Classification of persons and items and frequencies for dose evaluation

6-20

Table 6.8.1

Disposal methods of the radioactive solid wastes of NPPs

6-29

Table6.8.2

Treatment methods of radioactive gaseous wastes according to their natures

6-31

Chapter 7

Table 7.1.1

Safety evaluation in Japan

7-4 ■

Table 7.3.1

Evaluation of individual dose during accidents

7-12

Table 7.4.1

Dose evaluation results for major accidents and hypothetical accidents

7-18

Chapter 8

Table 8.3.1

Evaluation of dose in accidents

(Examples for a 3-loop plant)

8-12

Table 8.4.1

Result of safety evaluation for major/

hypothetical accident(examples for 3-loop plants) 8-17

Table 8.5.1

Accident management measures (4-loop plant)

8-22

Chapter 9

Table 9.3.1

Radioactive materials released to the PCV

during a major accident and a hypothetical accident

(source term)

9-6

Table 9.5.1

Classification of importance in seismic design

9-9

Table 9.5.2

Seismic classification and design seismic forces

9-10

Table 9.5.3

Tested facilities and size

9-17

Chapter 10

Table 10.3.1

Seven inputs on management review

10-13

Table 10.3.2

Three outputs on management review

10-13

Table 10.6.1

Examples of design and development inputs

10-18

Table 10.6.2

Examples of verification items in the design review

10-19

Table 10.7.1

Examples of purchase requirements

10-22

Table 10.8.1

Controlled conditions and their examples

10-24

Table 10.8.2

Examples of identification

10-25

Table 10.9.1

Examples of inspections, tests and the stages when they are conducted

10-27

Table 10.9.2

Examples of degrees of independence

10-27

List of Figures

Figure 2.3.22

Trends in annual power generations

1-1

figure 2.3.23

Defense-in-Depth philosophy

1-10

Figure 2.4.1

Safety examination system for permit to

figure 2.4.3

establish a power generating reactor

1-12

Safety regulatory guides

1-13

Figure 2.4.2

Outline of the procedures from site

Figure 2.4.4

selection to operation

1-14

Structure oflAEA standards

1-15

figure 2.4.6

figure 2.4.5

Chapter 2

Figure 2.4.7

Site plot plan conceptual model (cross section)

27

figure 2.4.8

Overall plant layout of a BWR NPP

27

figure 2.4.9

Typical equipment layout of a 1,100 MWe class plant

figure 2.4.10

28

Figure 2.5.1

Conceptual design of a 1,100 MWe class

figure 2.5.2

primary con tainment vessel

210

Comparison of original plant and improved

Figure 2.5.3

and standardized plant

211

Main building arrangements

212

Figure 2,5.4

Main building arrangements (two-unit site)

213

Advanced boiling water reactor(ABWR)

Figure 2.5.5

plant arrangement

216

Figure 2.5.6

9x9 Fuel assembly (A type) and fuel rod

figure 2.5.7

structure (example)

2-18

Figure 2.5.8

Fuel assembly structure (9x9 fuel A type)

2-19

Fuel rod arrangement (example)

219

Figure 2.6.1

Internal structure of a reactor pressure vessel

figure 2.6.2

(cut out view)

222

Figure 2.6.3

Core shroud and coolant flow in RPV

2-23

figure 2.6.4

Core and lower core structures

223

figure 2.6.5

Fuel support piece structure

224

Figure 2.6.6

Moisture separator unit

225

Steam dryer

225

Figure 2.6.7

Jet pumps

Cut-away view of an ABWR reactor

226

Figure 2.6.8

pressure vessel

226

Figure 2.6.9

ECCS network (ABWR)

PCVTypeMark-I

PCVTypeMark-II

PCVTypeMark-I (improved)

Outline of the RHR system for ABWR

2-93

figure 3.2.1

Plot plan of nuclear power plant

35

Figure 2.8.3

RHR pump for 1,100 MWe BWR

2-94

Figure 3.2.2

Main buildings arrangement

figure 2.8.4

Basic system configuration of RCIC for 1,100

(single type & twin type)

38

MWe WR

395

Figure 3.2.3

Buildings arrangement plan (3F)

39

Figure 2.8.5

An example of the basic configuration of the

Figure 3.2.4

Buildings arrangement section (A-A)

39

Figure 3.2.5(1)Fuel handling through reactor bldg. & fuel handling bldg.

397

(new fuel loading procedure)

Figure 2.8.8 CUW pump (canned motor type)

2-98

Figure 3.2.5(2)Fuel handling through reactor bldg. &

Figure 2.8.9 Outline of FPC system

2-99

fuel handling bldg.

Figure 2.8.10 Basic concept of RCW and RCWS systems

(spent fuel unloading procedure)

(example)

2-100

Figure 3.2.6 Fuel handling facilities

figure 2.8.11 Outline of spent fuel storage pool

3101

Figure 3.2.7 Buildings configurationn of nuclear power

Figure 2.8.12 Outline of refueling machine

2-102

plants in japan

Figure 2.9.1 A typical flow sheet of gaseous wastes

figure 3.2.8 Variation in buildings arrangement with basic

treatment system

module of reactor building

(example of a 1,100 MWe BWR plant)

2-103

Figure 3.2.9 Variation of earthquake-resistant configuration

figure 2.9.2 A typical flow sheet of liquid waste treatment system

figure 3.2.10 Turbine building arrangement

2-104

Figure 3.2.11 Divided block arrangement

Figure 2.9.3 A typical flow shee t of the latest radioactive

figure 3.3.1 Schematic of fuel assembly and fuel rod

waste treatment systems

3106

Figure 3.3,2 (l)Support grid structure (1)

Figure 2.10.1 Main generator cross sectional view

2-107

Figure 3.3.2(2)Support grid structure (2)

Figure 2.10.2 Excitation system

2-108

Figure 3.3.3 Arrangement of fuel rods containing

Figure 2.10.3 A single line diagram of a 1,100 MWe BWR plant 2-110

Gd (example)

Figure 2.11.1 Outline of the plant water treatment system

figure 3.3.4 Reactor andinternal structures

and themake-up water system

3111

Figure 3.3,5 Upper core support structure

Figure 2.11.2 Outline of the auxiliary steam system

2-113

Figure 3.3.6 Lower core support structure

figure 2.11.3 Outline of house boiler system

Figure 3.3.7 Flow char t of core size dete rmination

(example of heavy oil boiler)

2-115

Figure 3.3.8 Boiling characteristics

Figure 2.11.4 Outline of the compressed air supply system

3115

figure 3.3.9 Temperature inside fuel rod (example)

Figure 2.11.5 Outline of HVAC system of the reactor building

3116

Figure 3.3.10 Structure of burnable poison assembly

Figure 2.11.6 Outline of HVAC system of the turbine building

3117

Figure 3.3.11 Structure of control rod clusters

Figure 2.11.7 Outline of HVAC system of the main control room

Figure 3.3.12 Control rod drive mechanism

2-117

Figure 3.3.13 Critical boron concentration vs. burnup

figure 2.11.8 Outline of the fire protection system

3118

(hot full power (HFP), all rods out)

figure 2.12.1 ABWR plot plan (a twin-unit plant)

3120

Figure 3.3.14 Arrangement of control rods

Figure 2.12.2 Reactor buildings (a 1,100 MWe BWR and an ABWR)

(example 4-Loop core)

3120

Figure 3.3.15 Reactivity worth of control group bank D

figure 2.12.3 Cross-sectional and horizontal views of ABWR

(beginning of cycle, hot zero power, no xenon;

reactor and turbine buildings

2-120

example 4-loop core)

Figure 3.3.16

Structure of primary neutron source assembly

3-29

Figure 3.6.13

Main control board

3-76

Figure 3.3.17

Structure of secondary neutron source assembly 3-29

Figure 3.6.14

EachVDU screen

3-77

Figure 3.3.18

Effects of control rods position, power level,

Figure 3.7.1

Emergency core cooling system flow diagram

burnup distribution and Xe on power distribution 3-30

(4-Loop)

3-84

Figure 3.3.19

Essentials of constant axial offset control

Figure 3.7.2

Emergency core cooling system flow diagram

(CAOC) operation method

3-31

(3-Loop)

885

Figure 3.3.20

Fuel loading patterns (examples)

3-32

Figure 3.7.3

Reactor containment (PCCV)

888

Figure 3.3.21

Arrangement of in-core neutron detectors

Figure 3.7.4

Reactor containment (SCV)

888

(example 3-loop core)

3-33

Figure 3.7.5

Internal structure of PCCV

3-89

Figure 3.3.22

Schematic of reloading/unloading fuel

Figure 3.7.6

Reactor containment spray system

3-91

assemblies

3-33

Figure 3.7.7

Annulus air clean-up system

8-92

Figure 3.4.1

Primary coolant system

3-35

Figure 3.7.8

Safety component area air clean-up system

3-94

Figure 3.4.2

Reactor vessel structure

336

Figure 3.8.1

Chemical and volume control system flow

Figure 3.4.3

O-ring seal for reactor vessel

336

diagram

896

Figure 3.4.4

Monitoring and prevention of embrittlement by

Figure 3.8.2

Residual heat removal system flow diagram

899

irradiation

337

Figure 3.8.3

Component cooling water system flow diagram

8101

Figure 3.4.5

Steam generator

339

Figure 3.8.4

Sea water system flow diagram

8103

Figure 3.4.6

Pressurizer

342

Figure 3.8.5

Spent fuel pit cooling and clean-up system flow

Figure 3.4.7

Pressurizer heater

342

diagram

8104

Figure 3.4.8 (1) Primary coolant piping I

343

Figure 3.9.1

Gaseous waste disposal system

8106

Figure 3.4.8(2) Primary coolant piping H

343

Figure 3.9.2

Charcoal bed noble gas holdup system

8106

Figure 3.4.9

Reactor coolant pump (l'ype93A-l)

345

Figure 3.9.3

Liquid waste disposal system

8107

Figure 3.4.10

Shaft seal structure

345

Figure 3.9.4

Boron recycle system evaporator

Figure 3.4.11

Shaft seal system

346

(immersion heater type)

3-109

Figure 3.4.12

Reactor coolant pump motor

346

Figure 3.9.5

Waste evaporator (circulation heating type)

8109

Figure 3.4.13

Pressurizer safety valve (example)

347

Figure 3.9.6

Laundry/Hot shower waste processing unit

Figure 3.4.14

Pressurizer relief valve specifications (example)

348

(activated sludge membrane separation type)

8110

Figure 3.5.1

Nuclear turbine steam expansion diagram

350

Figure 3.9.7

Solid waste disposal system

8111

Figure 3.5.2

Cut-away view of nuclear turbine (example)

351

Figure 3.9.8

Spent resin processing unit

Figure 3.5.3

Nuclear turbine governor system (example)

352

(sulfuric acid dissociation type)

8111

Figure 3.5.4

Turbine system (example)

353

Figure 3.9.9

Technical requirements for low-level radioactive

Figure 3.5.5

Condenser (example)

355

waste drums

113

Figure 3.5.6

Cut-away view of deaerator (example)

356

Figure 3.9.10

Waste drum shipment inspection unit

8113

Figure 3.5.7

Cut-away view of moisture separator reheater

Figure 3.10.1

Main generator cross sectional view (example)

8114

(example)

357

Figure 3.10.2

Brushless excitation concept

8115

Figure 3.6.1

Out-of-core nuclear instrumentation range of

Figure 3.10.3

Startup transformer method vs GLBS method

measurement

360

8117

Figure 3.6.2

In & Out-of core nuclear instrumentation

361

Figure 3.10.4

Switchyard bus composition

8117

Figure 3.6.3

Reactor protection and engineered safety

Figure 3.10.5

In-station one line diagram

8118

features actuation system

363

Figure 3.10.6

Direct current power supply system

Figure 3.6.4

Reactor protection system block diagram

366

(one of safety system)

8119

Figure 3.6.5

Block diagram Illustrating engineered safety

Figure 3.10.7

I & C power supply system

feature actuation

366

(two of safety systems)

8119

Figure 3.6.6

Pressurizer pressure protection and

Figure 3.11.1

Water supply and treatment system diagram

8121

control system

370

Figure 3.11.2

Auxiliary steam system diagram

8122

Figure 3.6.7

Reactor control system

372

Figure 3.11.3

Instrument air system diagram

8123

Figure 3.6.8

Control rod control system

373

Figure 3.11.4

Containment heating, ventilating and

Figure 3.6.9

Pressurizer pressure control system

373

air-conditioning system diagram

8124

Figure 3.6.10

Pressurizer water level control

373

Figure 3.11.5

Auxiliary building heating, ventilating

Figure 3.6.11

Feedwater control system

374

andair-conditioning system diagram

Figure 3.6.12

Turbine bypass control system

374

(general & safety component rooms)

8125

Figure 3.11.6 Auxiliary building heating, ventilating andair-conditioning system diagram

(main control room)

3-126

Figure 3.11.7

Water fire protection system diagram

3-127

figure 3.12.1

Schematic view of apwr steam generators

3-129

figure 3.12.2

Control rod drive mechanism pressure housing

with the canopy-less structure

3-130

Figure 3.12.3

Comparison of neutron reflector and

baffle structure

3-130

Figure 3.12.4

Improvements of APWR steam generator

3-131

figure 3.12.5 APWR reactor coolant pump

3-132

Figure 3.12.6

ECCS configurations

3-134

Figure 3.12.7

Function of the high performance

accumulator tank

3-134

Figure 3.12.8

Principle of flow switching in the high

performance accumulator tank

3-135

Figure 3.12.9

Advanced main control board

(model for validation)

3-136

Chapter 4

Figure 4.1.1 Schematic diagram of BWR plant system 4-3

Figure 4.1.2 Startup curve after periodic inspection 4-5

Figure 4.1.3 Operating range of core thermal power and core

flow 4-7

Figure 4.1.4 Unit shutdown curve 4-11

Figure 4.2.1 Administrative classification of maintenance 4-12

4-19

Figure 4.2.3(5)-(8) Schematic diagram of major works

related to reactor

4-20

figure 4.2.4

Reactor recirculation pump

4-23

Figure 4.2.5

Example of remote au tomatic ul trasonic testing

device

4-24

figure 4.2.6

Example of a monitoring robot for the

inside of a reactor containment vessel

4-24

figure 4.3.2

Principle of water jet peening

4-29

Figure 4.3.1

Principle of laser peening

4-29

Figure 4.3.5

Core shroud tie rod

4-30

Figure 4.3.4

Schematic of laser seal welding

4-30

Figure 4.3.3

Concept of seal weld

4-30

Figure 4.3.6

Flow of shroud replacement work

4-31

Figure 4.3.7

Principle ofTHSI

4-32

figure 4.3.8

Principle of CRC

432

figure 4.3.9

Principle of HSW

432

figure 4.3.11

Conceptual diagram of WOLpipe cross section

433

Figure 4.3.10

Conceptual diagram ofWOL

433

Figure 4,3.13

Schematic diagram of LDI

(example, wall thinning downstream from

an orifice due to liquid droplet impingement)

434

Figure 4.3.14 Wall thinning management rank for FAC

434