
- •Introduction for English Version
- •Toshiaki Enomoto
- •Foreword
- •Table of Contents
- •Xj nsra, Japan
- •X;;; nsra, Japan
- •Chapter 5
- •Chapter 6
- •Chapter 1 General
- •History of Nuclear Power Plant Development
- •Experiences in Nuclear Power Generation and Safety Research
- •Comparison of Schemes of Nuclear and Thermal Power Generation
- •Effective Reactor Fuel Loading
- •Reactor Self-Regulation Characteristics
- •Reactor Decay Heat
- •Confinement of fPs
- •Reactor Steam Conditions
- •Safety Design Principles for npPs
- •Prevention of Occurrence of Abnormal Conditions (Level 1)
- •Figure 1.4.1 Defense-in-Depth philosophy
- •Prevention of Expansion of an Abnormal Event (Level 2)
- •Prevention of Abnormal Release of Radioactive Materials and Mitigation of Consequence (Level 3)
- •Emergency core cooling system
- •Confinement of radioactive materials by five barriers
- •Outline of Laws, Regulations and the Regulatory Framework
- •Domestic Framework
- •Permit to establish a power generating reactor
- •Sanction of the construction plan
- •Approval of technical specifications
- •Regulations after start of commercial operation
- •Iaea Safety Standards
- •Figure 1.5.4 Structure of iaea safety standards
- •Chapter 2 Systems of bwr Nuclear Power Plants
- •General Design Philosophy
- •Fuel Rods
- •Reactor Core
- •Reactor Coolant Pressure Boundary
- •Engineered Safety Features
- •Instrumentation and Control System
- •Other Systems
- •Plant Layout
- •Plot Plan
- •Grade level planning
- •Configuration of the buildings
- •Road planning
- •Pipe conduits and electric cable conduits planning
- •Construction area planning
- •Harbor and water intake/discharge planning
- •Other considerations
- •Main Buildings and Auxiliary Buildings
- •Figure 2.2.2 Overall plant layout of a bwr npp
- •Reactor building
- •Turbine building
- •Figure.2.2.7 Main building arrangements (two-unit site)
- •Main control room (Control building)
- •Radioactive waste treatment facility building
- •Service building
- •Exhaust stack
- •Advanced boiling water reactor (abwr) plant arrangement
- •Nuclear Reactor and Core
- •Fuel Rod and Fuel Assembly
- •Structure of fuel rod and fuel assembly
- •Figure 2.3.1 9x9 Fuel assembly (a type) and fuel rod structure (example)
- •Fuel rod and assembly designs
- •Reactor and Reactor Core
- •Structure of reactor and reactor core
- •Figure 2.3.4 Internal structure of a reactor pressure vessel (cut out view)
- •Vessel (rpv)
- •Incore monitor housing
- •Hpcf sparger top Fuel guide—
- •Reactivity control system
- •Core Design
- •Figure 2.3.20 Control rod with the maximum reactivity worth
- •Core stability
- •Operation and management of the core
- •Primary Coolant System
- •System Summary
- •Primary loop recirculation (plr) system
- •Main steam (ms) system
- •Feed water (fdw) system
- •Key Components
- •Reactor pressure vessel (rpv)
- •Figure 2.4.3 Control rod drive mechanism and in- core monitor housing
- •Recirculation pumps
- •Safety relief valve (srv)
- •Turbine System
- •System Summary
- •Main Turbine System and Auxiliary Equipment
- •Iypes of nuclear plant steam turbines
- •Steam turbine
- •Moisture separator and heater
- •Electro-hydraulic turbine control (ehc) unit
- •Main Steam System and Condensate Feed Water System
- •Main steam line and turbine bypass system
- •Steam extraction system and feed water heater drain system
- •Condenser and circulating water system
- •Condensate and feed water system and condensate cleanup system
- •Instrumentation and Control System
- •Reactor Instrumentation and Control System
- •Plant control system
- •Reactor neutron monitoring system (nms)
- •0 Source range monitor (srm) 4 detectors q Power range monitor (prm) 43x4detectors
- •Main Control Room
- •Structure and functions of control panels
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- •Remote shutdown system (rss)
- •Emergency operational facilities
- •Process Instrumentation System
- •Reactor process instrumentation system
- •Figure 2.6.14 Reactor water level and pressure instrumentation
- •Radiation monitoring system
- •2.7 Engineered Safety Features
- •Design Policy of Engineered Safety Features
- •Basic safely philosophy
- •Philosophy to prevent occurrence of serious incidents
- •Philosophy to mitigate serious incidents
- •Emergency Core Cooling System (eccs)
- •Roles of the eccs
- •Criteria for design and evaluation of eccs
- •Design policies for the eccs
- •Eccs configuration
- •Eccs configuration of an abwr
- •Reactor Containment Facility
- •Roles of reactor containment facility
- •Primary containment vessel (pcv)
- •Containment spray system (css)
- •Flammable gas control system (fcs)
- •Standby gas treatment system (sgts)
- •Reactor containment facility of an abwr
- •Reactor Auxiliary Systems
- •Residual Heat Removal (rhr) System
- •Operating modes
- •System functions and configuration
- •Reactor Core Isolation Cooling (rcic) System
- •System functions and configuration
- •Reactor Water Cleanup (cuw) System
- •System functions and configuration
- •Key components and features
- •Fuel Pool Cooling and Cleanup (fpc) System
- •System functions and configuration
- •Figure 2.8.8 cuw pump (canned motor type)
- •Reactor Building Cooling Water (rcw) System and Reactor Building Cooling Seawater (rcws) System
- •System functions and configurations
- •Key components and features
- •Figure 2.8.10 Basic concept of rcw and rcws systems (example)
- •Fuel Handling and Storage System
- •Spent fuel storage pool
- •Cask pit
- •Refueling machine
- •Radioactive Waste Treatment Systems
- •Gaseous Waste Treatment System
- •Figure 2.9.1 a typical flow sheet of gaseous wastes treatment system (Example of a 1,100 mWe bwr plant)
- •Liquid Waste Treatment System
- •Solid Waste Treatment System
- •Generator excitation system
- •Major Transformers and Switchyard System
- •Major transformers
- •Switchyard system
- •Plant Auxiliary Power System
- •Plant auxiliary power supply system
- •Emergency diesel generator system
- •Direct current (dc) power supply system
- •Instrumentation and control power supply system
- •Plant Auxiliary Systems
- •Plant Water System
- •Plant water treatment system
- •Make-up water system
- •Auxiliary Steam System (House Boiler System)
- •Design philosophy
- •Key equipment
- •Compressed Air Supply System
- •Design philosophy
- •Key equipment
- •Heating, Ventilating and Air Conditioning (hvac) System
- •Design philosophy
- •Key equipment
- •Figure 2.11.6 Outline of hvac system of the turbine building
- •Figure 2.11.7 Outline of hvac system of the main control room
- •Fire Protection System
- •Key equipment
- •Advanced bwr (abwr)
- •Design Principles
- •Enhanced safety and reliability
- •Figure 2.12.2 Reactor buildings (a 1,100 mWe bwr and an abwr)
- •System design
- •Advanced core
- •Reactor system
- •Reinforced concrete containment vessel (rccv)
- •Turbine system
- •Enhanced Safety
- •Improved reactor shutdown capabilities
- •I turbine driven reactor feedwater pump||
- •Figure 2.12.8 abwr safety features
- •Enhanced reactor cooling capability
- •Enhanced capability for containing radioactive materials
- •Overall safety
- •Figure 2.12.10 abwr eccs (three divisions)
- •Enhanced Operability and Maneuverability
- •Improved monitoring and maneuverability
- •Enhanced operability
- •Chapter 3 Systems of pwr Nuclear Power Plants
- •General Design Philosophy
- •Fuel Rods
- •Reactor Core
- •Engineered Safeguard Systems
- •Instrumentation and Control System
- •Other Systems
- •Plant Layout
- •Plot Plan
- •Intake and discharge structures
- •Switchyard
- •Reactor building and reactor auxiliary building
- •Turbine building
- •Water supply and treatment system
- •Radioactive waste storage building
- •Cask storage building
- •Harbor facilities
- •Access control system
- •Equipment Arrangement
- •Reactor building
- •Reactor auxiliary building
- •Turbine building
- •Fuel handling and storage building and facilities
- •Plant Layout Considerations
- •Building composition
- •General requirements of plant layout design
- •Decontamination Pi t
- •Isolation Valve
- •2 Loop Plant
- •3 Loop Plant
- •Figure 3.2.7 Buildings configurationn of nuclear power plants in japan
- •Figure 3.3.1 Schematic of fuel assembly and fuel rod
- •Structure of the fuel rods and fuel assemblies
- •Design of fuel rods and fuel assemblies
- •Figure 3.3.2(2) Support grid structure (2)
- •Reactor and Reactor Core
- •Structure of reactor and reactor core
- •Dynamic characteristics of the nuclear reactor
- •Core stability
- •Reactivity control
- •Figure 3.3.13 Critical boron concentration vs. Burnup (hot full power (hfp), all rods out)
- •Power distribution control
- •Figure 3.3.15 Reactivity worth of control group bank d (beginning of cycle, hot zero power, no xenon; example 4-loop core)
- •Figure 3.3.16 Structure of primary neutron source assembly
- •Figure 3.3.17 Structure of secondary neutron source assembly
- •Core management
- •Reactor Coolant System
- •Outline
- •System summary
- •System functions
- •Main Components
- •Reactor vessel
- •Steam generators
- •Pressurizer
- •Vertical u-lube type heat exchanger 7.D8 mPa [gage]
- •17.16 MPa (gage]
- •Reactor coolant piping
- •Reactor coolant pumps
- •IVol. Seal
- •Turbine System
- •Outline
- •Main Turbine and Its Appurtenances
- •Characteristics of Nuclear Power Plant Turbines
- •Turbine types, blade designs and steam cycles
- •Structures of turbines
- •Table 3.5.2 Turbine type and applicable output
- •Turbine governor system
- •Turbine steam inlet valves
- •Turbine protection system
- •Main Steam System
- •Main steam safety and relief valves
- •Main steam isolation and check valves
- •Turbine bypass valves
- •Condensate, Feedwater System and Other Related Systems
- •Condensate, feedwater system
- •Auxiliary feedwater system
- •Circulating water system
- •Instrumentation and Control System
- •Reactor Instrumentation and Control System
- •10 5 Neutron Source Range Trip Point
- •Figure 3.6.1 Out-of-core nuclear instrumentation range of measurement
- •High Neutron Flux {Power Range High Selling)
- •Sleam Generator Feedaler Flow Level tl *
- •Interlock
- •Reactor
- •Turbine Load Neutron Flux Level
- •Injection Pump Actuation
- •2/4 Logic
- •Figure 3.6.6 Pressurizer pressure protection and control system
- •Reactor control system
- •Figure 3.6.11 Feedwater control system
- •Main Control Room
- •Composition of main control board
- •Methods for monitoring and operation
- •Alarm system
- •(1) Vdu monitor operation example of the screen (system screen)
- •(2) Vdu monitor operation example of the screen (control screen)
- •(3) Vdu monitor operation example of the screen (screen monitors only)
- •Operator assisting system
- •Plant operation management
- •Reactor shutdown panel outside the main control room
- •Emergency support plan
- •Process Instrumentation System
- •Primary system
- •Secondary system
- •Radiation Monitoring System
- •Process radiation monitors
- •Area monitors
- •Radiation measurement during accidents
- •Engineered Safety Feature
- •Systems and Their Functions
- •Emergency core cooling system (eccs)
- •Reactor containment facility
- •Containment spray system
- •Annulus air clean-up system
- •Safety component room air clean-up system
- •General points
- •Emergency Core Cooling System (eccs)
- •Functions
- •System configuration
- •Reactor Containment Facility
- •Functions and configuration
- •Functions and structure of the different containment vessels
- •External shield building
- •Annulus
- •Containment Spray System
- •Function
- •System configuration
- •Iodine removal chemicals tank
- •Functions
- •Components
- •Safety Component Area Air Clean-up System
- •Functions
- •Components
- •Reactor Auxiliary Systems
- •Chemical and Volume Control System (cvcs)
- •System composition and functions
- •Inside coo tai oment
- •Injection pump —:—
- •Components
- •Residual Heat Removal System (rhrs)
- •System composition and functions
- •Component cooling water |m1
- •Components
- •Component Cooling Water System (ccws)
- •System composition and functions
- •Components
- •Instrument air compressor a
- •Instrument air cos pressor b
- •I .Aurillary components,
- •I [important for safetyj
- •Sea Water System (sws)
- •Spent Fuel Pit Cooling and Clean-up
- •Fuel Handling System
- •Radioactive Waste Disposal System
- •Gaseous Waste Disposal System
- •Liquid Waste Disposal System
- •Figure 3.9.4 Boron recycle system evaporator (immersion heater type)
- •Solid Waste Disposal System
- •Electrical Systems
- •Main Generators and Appurtenances
- •Appurtenances of the main generators
- •Generator excitation system
- •Voltage regulator
- •Major Transformers and Transmission System
- •Generator load break switch (glbs)
- •Switchyard
- •Plant Auxiliary Power Supply
- •Figure 3.10.4 Switchyard bus composition
- •311 Power transformer
- •Dc power supply systems
- •Instrument power systems
- •Figure 3.10.6 Direct current power supply system (one of safety system)
- •Board feu | 4 c Icard for j I c
- •(Note)Wllh mechanical Interlock
- •Compressed Air Systems
- •Drain line
- •Sieaj control valve for turbine
- •Inside containment
- •Heating, Ventilating and Air Conditioning Systems
- •Figure 3.11.5 Auxiliary building heating, ventilating and air-conditioning system diagram (general & safety component rooms)
- •Figure 3.11.6 Auxiliary building heating, ventilating and air-conditioning system diagram (main control room)
- •Fire Protection System
- •Figure 3.12.1 Schematic view of apwr steam generators
- •Enhancement of reliability
- •Improvement of operability
- •Reduction of radiation exposure
- •Plant Design
- •Core internals
- •Steam generator
- •Instrument and control system
- •Turbine generator
- •Conclusion
- •Chapter 4 Operation and Maintenance of bwr Plants
- •Plant Operation
- •Plant Startup
- •Figure 4.1.1 Schematic diagram of bwr plant system
- •Figure 4.1.2 Startup curve after periodic inspection
- •Figure 4.1.3 Operating range of core thermal power and core flow
- •Normal Plant Operation
- •Implementing surveillance tests
- •Core management during operation
- •Chemistry control during plant operation
- •Other operational activities
- •Plant Shutdown
- •Chemistry control during plant shutdown
- •Plant Maintenance
- •Figure 4.2.1 Administrative classification of maintenance
- •Periodic Inspections and Licensee’s Periodic Inspections
- •Periodic inspections
- •Licensee’s periodic inspections
- •Time to carry out licensee’s periodic inspections (including the periodic inspections) and periodic checks
- •Items for the periodic inspections and licensee’s periodic inspections
- •Procedure and Work Schedule of Periodic Inspections
- •VII) Preparations for startup
- •IV) Fuel exchange & shuffling
- •VI) pcv upper head Qf ’
- •Other major work activities
- •Figure 4.2.4 Reactor recirculation pump
- •Contents of isIs
- •Remote automatic ultrasonic testing device for isIs
- •Checks and Maintenance during Plant Operation
- •Switching components during operation
- •Maintenance during operation
- •Efficiency Improvement of Periodic Inspection Work
- •Improvement of plant layout
- •Reduction of the time needed for the periodic inspection
- •Maintenance Against Plant Aging
- •Technical Study on Aging
- •Upgrading of evaluation technology
- •Maintenance Technology against Aging
- •Figure 4.3.3 Concept of seal weld
- •Figure 4.3.5 Core shroud tie rod
- •Figure 4.3.8 Principle of crc
- •Figure 4.3.11 Conceptual diagram of wol pipe cross section
- •Upgrading by Facility Replacement
- •Chapter 5 Operation and Maintenance of pwr Plants
- •Plant Operation
- •Reactor Control Systems
- •Control rod control system
- •Turbine bypass control system
- •Pressurizer pressure control system
- •Pressurizer water level control system
- •Steam generator water level control system
- •Plant Startup
- •Plant Normal Operation
- •Operator Activities during Plant Normal Operation
- •Plant Shutdown
- •Chemistry Control
- •Outline of chemistry control of primary system
- •Outline of chemistry control of secondary system
- •Management of waler trealment chemicals
- •Sg blow down water recovery system
- •Plant Maintenance
- •Maintenance Management Policy
- •Periodical Inspections and Periodical Utility Inspections
- •Figure 5.2.2 Framework of plant in-service inspection system
- •Major activities in the periodical inspection period
- •0Utline of other major activities
- •Table 5.2.2 Overhaul inspection required by regulations
- •Maintenance during plant normal operation
- •Checks during plant normal operation
- •Maintenance dining plant normal operation
- •Rationalization of Plant Features Related to Periodical Inspections
- •Optimization of plant equipment arrangement
- •Reduction of durations for periodical inspections
- •Reduction of radiation dose
- •Maintenance to Cope with Plant Aging
- •Technical Evaluation of Aging Effects
- •Maintenance Techniques to Cope with Plant Aging
- •Maintenance of Alloy 600
- •Upgrading of Plants by the Renewal of Systems
- •Chapter 6 Radiation Control
- •Purposes of Radiation Protection
- •Regulation for Radiation Protection
- •Legislative System for Radiation Protection
- •Specific Applications of Legislation
- •Industrial Safety and Health Law
- •Radiation Sources at npPs
- •Actual Conditions concerning Radiation Sources
- •Figure 6.3.1 (1) Trends in dose equivalent rates of the bwr plr system piping
- •Area Control
- •Standards of Area Control in Accordance with Legislation
- •Confirmation of Radiation Environment
- •Access to and Exit from Controlled Areas
- •Work Management
- •Study of Work Methods
- •Approval of Radiation Work
- •Confirmation of Work Environment
- •Completion of Work
- •Fundamentals of Radiation Protection for Work Management
- •6.7 Controls of the Individual
- •Qualification of Radiation Workers
- •Evaluation of Individual Dose
- •Target of Individual Dose Control
- •Records of Individual Dose
- •Track Record of Individual Dose
- •Figure 6.7.1 History of the number of npPs, number of radiation workers, and total dose in Japan (excluding gcr)
- •Fiscal year Figure 6.7.5 Trends in annual average total doses per npp in major counties
- •Radioactive Waste Management
- •Radioactive Solid Wastes
- •Radioactive liquid Wastes
- •Figure 6.8.3 Trends in total amount of solid wastes stored as of the end of each fiscal year (for each type of light water reactor) and the number of drums sent to the Rokkasho Center
- •Tire level to classify the "materials not required to heat as radioactive materials" as the radioactivity is low enough
- •Figure 6.8.5 Outline of the clearance system
- •Fiscal year
- •Figure 6.8.6 Trends in discharged radioactivity of radioactive liquid wastes (excluding tritium) (total discharge for each reactor type)
- •Fiscal year
- •Environmental Radiation Monitoring
- •Chapter 7 Safety Evaluation of
- •Bwr Plants
- •Basic Policy for Safety Evaluation
- •Objectives of Safety Evaluation
- •Anticipated Operational Occurrences
- •Assumption of Event
- •Abnormal Withdrawal of Control Rods during Reactor Startup
- •Loss of Feed Water Heater
- •Loss of Load
- •Features of abwr Transient Analysis
- •Accidents
- •Assumption of Events
- •Loss of Reactor Coolant (in case of a Large Break)
- •Time after the accident (s)
- •Characteristics of abwr Accident Analysis
- •Major Accidents and Hypothetical Accidents
- •Assumption of Events
- •Loss of Reactor Coolant
- •Main Steam Line Break
- •(Note) These numbers are to be used for the whole body dose evaluation together with those of noble gases.
- •Figure 7.4.2(1) Process of iodine release during the main steam line break (major accident)
- •Dose Evaluation
- •(Note) These numbers are to be used for the whole body dose evaluation together with those of noble gases.
- •Probabilistic Safety Assessment (psa) for bwRs
- •Psa during Operation
- •Figure 7.5.1 Contribution of each sequence to the core damage frequency
- •Psa during Shutdown
- •Severe Accident
- •Chapter 8 Safety Evaluation of
- •Pwr Plants
- •Basic Principles for Safety Evaluation
- •Purposes of Safety Evaluation
- •Methodology for Safety Evaluation
- •Abnormal Transients during Operation
- •Postulation of Events
- •Partial Loss of Reactor Coolant Flow
- •Figure 8.2.1 Partial loss of reactor coolant flow (• indicates the initial value)
- •Uncontrolled Control Rod Withdrawal at Reactor Startup
- •Loss of Normal Feedwater Flow
- •Figure 8.2.2 Uncontrolled control rod withdrawal at reactor startup (•Indicates the initial value)
- •Accidents
- •Postulation of Events
- •Loss of Reactor Coolant
- •Steam Generator Tube Rupture
- •Major Accidents and Hypothetical Accidents
- •Postulation of Events
- •Loss of Reactor Coolant
- •Steam Generator Tube Rupture
- •Release from fuel rods to the reactor system
- •Release from the primary system to the secondary system
- •Release into the atmosphere
- •Probabilistic Safety Assessment (psa) for pwr Plants
- •Outline of Probabilistic Safety Assessment
- •Use of psa for safety management in the shutdown state
- •Chapter 9 Siting
- •Site Assessment
- •Site Conditions
- •Procedures for Site Assessment
- •Environmental impact assessment
- •Preliminary public hearing
- •Designation of important electric power development area
- •Basic Philosophy of Site Safety
- •Site Review Procedures and Contents
- •Hie Concept of Site Safety in the iaea Site Safety Standard
- •Reactor Site Criteria in the u.S.
- •Siting Philosophy
- •Site Assessment
- •Procedure for Radiation Effect Evaluation
- •Nuclear Emergency Preparedness
- •Seismic Safety
- •Basic Policy on Seismic Design
- •Figure 9.5.1 Formulation flow chart of design basis earthquake ground motion Ss ote£g)
- •Elastically design earthquake ground motion Sd (edegmSd)
- •Seismic Assessment
- •In the equipments
- •Seismic assessment of equipment and piping system
- •Maritime Environment Protection
- •The Effects of Thermal Effluent
- •Hie Effects of Coastal Structures
- •Advanced Siting Concept
- •General
- •Need for qa Activities in Nuclear Power Plants (npPs)
- •Addressing qa
- •International Trends in qa Activities for npPs
- •Development of Commercial qa Standards in Japan
- •1996 (Country taking part in un)
- •Establishment of jeac4111-2003
- •Quality Management System (qms)
- •Figure 10.2.2 Process diagram on npp (example)
- •Stipulation of qms
- •Provision of quality policy and quality objectives
- •Presentation of evidence of effective operation of qms
- •Document Control
- •Record Control
- •Management Responsibility (Top Management)
- •Quality Policy and Quality Objectives
- •Management Representative
- •Review by Management (Management Review)
- •Table 10.3.2 Three outputs on management review
- •Education and Training (Human Resources)
- •Product Realization Planning (Work Planning)
- •Product Realization Planning (Work Planning)
- •Noncon forming action/corrective action
- •Preventive action
- •Relationship with Customer
- •Determination and Review of Requirements related to the Product (Work)
- •Customer Communication and Customer Satisfaction
- •10.6 Design and Development
- •Planning of Design and Development
- •Verification
- •Validation
- •Figure*! 0.6.1 Process flow of design and development
- •Inputs to Design and Development
- •Outputs from Design and Development
- •Review of Design and Development
- •Table 10.6.2 Examples of verification items in the design review
- •Verification of Design and Development
- •Validation of Design and Development
- •Configuration Management of Design and Development
- •Purchasing
- •Purchasing Process
- •Communication with Suppliers
- •Purchasing Requirements
- •Verification of Purchased Products
- •Table10.7.1 Examples of purchase requirements
- •10.8 Production and Service Provision (Implementation of Work)
- •Control of Production and Service Provision (Control of Work)
- •Validation of Processes
- •Analysis of data and improvement (Sec.10.10)
- •Analysis of data
- •Nonconforming action / corrective action
- •Preventive action
- •Table 10.8.1 Controlled conditions and their examples
- •Identification and Traceability
- •Control of Monitoring and Measuring Devices
- •Monitoring & Measurement and Internal Audit
- •Product realization(Sec.L0.5) Production and service provision (implementation of work) (Sec. 10.8)
- •Monitoring and Measurement of Processes
- •Table 10.9.5 Examples of the monitored and measured items for npPs
- •Internal Audit
- •Analysis of Data and Improvement
- •Analysis of Data
- •Nonconforming Control & Corrective Action
- •Product realization(Sec.L0.5) Production and service provision (implementation of work) (Sec. 10.8)
- •Figure 10.10.1 pdca cycle for product realization in the quality management system
- •Preventive Action
- •Appendixes
- •Appendix 1 Chronology of Nuclear Power Plants
- •Improved transient performance
- •Improvement of plant availability
- •Improved main control board (1990s)
- •Appendix 8 The Outline of International Nuclear Event Scale (ines)
next periodical inspections. During the shutdown period of the
plant, any necessary actions are taken to enhance the reliabilities
of plant equipment and systems.
In the planning and implementation of preventive maintenance
activities, three considerations are taken in account and described
below.
)Routine checks during the plant operation
For the purpose of detecting any failure of components or systems at
an early stage, or any sign of their failures during the plant
operation, system and component parameters including pressures,
temperatures, flow rates, and vibrations are monitored and recorded,
and components and systems accessible during the plant normal
operation are checked in the course of operator patrols.
Confirmations are made that the systems and components are normally
operating without any leakage or unusual sound. Components and
equipment including engineered safeguard systems which are at
standby conditions during the plant normal operation, are
temporarily isolated from the system during the plant operation, and
they are tested and verified as able to fulfill their required
functions.
inspections during the
plant shutdown for periodical inspections
Overhaul and maintenance
The soundness of mechanical components is effectively verified by
periodically overhauling them and visually checking their individual
parts. Sliding surfaces of parts are checked and repaired if
necessary, and consumable parts such as packing and gaskets are
replaced. In establishing a plant maintenance plan, overhaul
frequencies of components and equipment are determined on the basis
of their performance in the past and the requirement that the whole
plant should be systematically and efficiently verified as to its
soundness.
In-service inspections
A plant in-service inspection plan is established to systematically
confirm the soundness of components and piping of the plant, i.e.
mainly the integrity of welds. Nondestructive inspections are
performed using various methods based on the plan.
Calibration and characteristic tests
Calibrations and characteristic tests of electrical and
instrumentation equipment such as process monitoring instruments
are conducted to confirm their soundness. Corrections are made for
drifts in instrumentation caused by changes over time, as necessary.
iii)Evaluations and reflection on operating experiences in other
plants
Issues which should be solved to ensure the safety and the
reliability of the plant are clarified, based on comprehensive
surveys and evaluations of operational information not only on the
plant of concern, but also on other plants, domestic and overseas.
Necessary actions are taken and measures are implemented to resolve
the issues during the plant shutdown for periodical inspections.
The present inspection system was established in October 2003, as
part of the system modifications initiated by the Japanese
government
Voluntary inspections which had been practiced by electric utilities
on their own initiatives were changed to periodical utility
inspections required by law. Electric utilities operating NPPs are
obliged to verify that the plant designs are in conformity with the
technical standards defined by the METI. In addition, systems of
utilities to execute the inspection are periodically examined by the
JNES, and subsequently by government examiners who evaluate the
results comprehensively.
Furthermore, maintenance activities by electric utilities are
considered as part of the
activities to assure the quality (or nuclear safety) of plants, and
the government or the JNES evaluate the performance and the system
of maintenance activities as part of quality assurance activities.
Quality assurance requirements are also specified in the plant
safety preservation rules set up by the utilities and approved by
the government. Subsequently, the government verifies the adherence
of utilities to the requirements as part of its inspections.
Periodical inspections are executed on the safetyimportant
systems and functions. 'Hie
government or JNES verifies the results of periodical inspections of
utilities by witnessing the actual inspections or
NSRA,
Japan
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14
Periodical Inspections and Periodical Utility Inspections
Chapter
5 Operation and Maintenance of PWR
Plants
Inspections and Assessments
by
the Government
Periodical Inspections
(by
NISA/JNES)
Periodical Assessments
of
Safety ManagementQNES)
Safety
Preservation
Inspections (NISA)
Safety
Preservation Activities by Utility Based
on Safety Preservation
Rules
Application of Quality
Assurance Rules
OEAC4111-2003)
Safety Preservation
Inspections: Inspections by the Government to verify adherence to
safety preservation rules
of utilities
Periodical Inspections:
Inspections by the Government to verify the compatibility of
safety-important systems to applicable technical standards
Periodical Assessment of Safety Management; Assessment by the
Government to verify
systems of utility to execute periodical utility inspections
(Periodical Utility Inspections): (Inspections by the utility to
verify the compatibility of plant systems to applicable technical
standards)
[Source] Material distributed
at the "20th study
committee on proper inspection systems” (Sept.7, 2006)
by checking the inspection records. The time between periodical
inspections of plant systems and periodical utility inspections is
limited in the Electricity Utilities Industry Law and Ordinances and
Rules of the Law, so as not to
exceed 13 months.
(1)Planning
and timing of the periodical inspections and the periodical utility
inspections
Timing of the periodical inspections and the periodical utility
inspections of a plant is decided by the utility when laying down a
service plan and is based on consideration of the following factors:
)to execute the inspections within the period defined in the
Electric Utilities Industry Law;
)to ensure electricity production based on the service plan;
to keep plant power generation rates and grid demands in balance;
and
to manage burnup of fuel.
Duration of the inspections is decided considering time needed for
the following activities, in addition to a certain time period for
the standard activities in the plant shutdown, refueling and startup
operations:
execution of the periodical inspections and the
periodical utility inspections;
special checks or large-scale
modifications of the plant, if any, based on a long-term
maintenance scheme; and
feedback on problems or operational experiences in domestic and
overseas plants.
(2) Items and schedules of
the periodical inspection and periodical utility inspection
Items of the periodical inspections are defined in Section 90, Item
2 of the Electric Utilities Industry Law. The government,
represented by inspectors from the NISA (Nuclear and Industrial
Safety Agency) or the JNES, witness inspection activities and check
inspection records made by the utility.
The important electric
structures, defined as items to be inspected in the periodical
inspections, are the reactor vessel, reactor coolant system
equipment, fuel assemblies, radiation control system, waste disposal
system equipment, containment vessel, emergency standby generating
unit, and the steam turbine and its appurtenances. The main items of
periodical inspections by the government are shown in Table 5.2.1.
Equipment which should be verified as to its compatibility to the
technical standards in the
5-
15
NSRA,
Japan
Figure 5.2.2 Framework of plant in-service inspection system
Table
5.2.1 Periodical Inspection Items |
RPV, and leakage tests of the RPV and RPV associated structures
4.1nspections to verify the shutdown margin of the reactor |
(2) RCS (Reactor Coolant System) Equipment |
equipment, common in this section), and support structures for them defined in the Ministerial Order Defining Technical Standards for Power Generating Reactor Plants, Section 2, and leakage tests of Class 1 and Class 2 components
relief valves 3.Operational tests of pressurizer relief valve stop valves 4.Leakage tests and operational tests of main steam safety and relief valves 5.Operational tests of main steam stop valves 6.Non-destructive inspections of ECCS pumps and main valves, and operational tests of ECCS 7.Operational tests of CCWS 8.Noirdestructive inspections of AFW pumps and operational tests of AFW system |
(3) Instrumentation and Control System Equipment |
l.Non-destructive inspections of Class 1 and Class 2 components (limited to instrumentation and control system equipment, common in this section), and support structures for them defined in the Ministerial Order Defining Technical Standards for Power Generating Reactor Plants, Section 2, and leakage tests of Class 1 and Class 2 components 2.Operational tests of the Instrument Air System
6.Operational tests of monitoring instruments used at the time of accidents and the Postaccident Sampling System equipment |
(4) Fuel Equipment |
Fuel assembly holding function tests of the fuel handling equipment after power is lost |
(5) Radiation Management Equipment |
1. Performance tests of the Reactor Containment Air Circulation System filters 2.Operafional tests of the Annulus Air Circulation and Exhaust System, and performance tests of filters in the system 3.0perational tests of the Main Control Room Air Emergency Circulation System and performance tests of filters in the system |
(6) Disposal Equipment |
Operational tests of the Gaseous Waste Disposal System |
(7) Reactor Containment Facility |
facility, common in this section), and support structures for them defined in the Ministerial Order DefiningTechnical Standards for Power Generating Reactor Plants, Section 2, and leakage tests of Class 2 components
tests of reactor containment isolation valves 4.Operational tests of the reactor containment vacuum relief valves 5. Non-destr uctive inspections of containment spray system pumps and main valves, and operational tests of the Containment Spray System 6.1nspections of the cooling performance of ice-condenser units 7.Operational tests of the reactor containment hydrogen re-combiner units |
(8) Emergency Standby Power Generation Devices |
verification tests of diesel-generators
|
[Source]
Ordinances and Rules of the Electricity Utilities Industry Law
NSRA,
Japan
5
—
16
Chapter
5 Operation and Maintenance of PWR Plants
periodical utility inspections of a plant is defined as follows in
the Ordinances and Rules of the Electricity Utilities Industry Law,
Section 94: reactor vessel; reactor coolant system equipment;
instrumentation and control system equipment, fuel; radiation
control system; reactor containment system; exhaust stack; auxiliary
boilers; emergency standby generating unit; steam turbine; and
appurtenances of steam turbine
Details of inspected items are shown in JEAC4209-2003 “Maintenance
Management Rules of Nuclear Power Plants” published by the Japan
Electric Association, and summarized in Figure 5.2.3.
During a periodical inspection period the inspections defined in the
Electricity Utilities Industry Law are carried out, as well as
refueling operations, government checks based on the Industrial
Safety and Health Law, and modifications of plant systems to improve
the overall reliability and maintainability. A typical schedule of
periodical inspections of a PWR NPP is shown in Figure5.2.4.
Although the periodical inspections and the periodical utilities
inspections are important to ensure the plant safety, long times
needed for the
inspections cause degradations in plant availabilities and affect
stabilization of electricity service. The utilities have struggled
to shorten the durations of the inspections, based on analyses and
evaluation of performance of equipment in the past, improvement of
techniques and personnel skills, improvement and development of
tools for checks and
inspections, and improvement of plant systems. Standard durations of
the inspections range between 40 to 60 days at present. When special
check activities or large scale modifications of plant systems are
executed, more time is needed for the activities. Other efforts have
been made to reduce durations of periodical inspections, such as the
pre-purchasing of materials, the seeming
of personnel, and managing of detailed schedules of sub-activities
to keep the planned inspection schedules. Moreover, since many of
the activities for the periodical inspections and the periodical
utility inspections have to be done in areas with radioactivity,
utilities have also struggled to improve the conditions for
inspections by reducing radioactivity levels, to conduct check and
inspection work automatically, to use remotely operated equipment,
and so on.
All Facilities of the Power
Generating Plant |
Service Buildings, etc.
Maintenance Management Rules!
■ [Technical
Standards for Nuclear Power Plants |
-Facilities, fences and so on,
functions of which are ensured by routine
checks -Facilities, fire extinguisliing
systems and so on, which are required to be checked under other
legislations or regulations
-Vessels
-Piping
-Pumps
-Valves
-Support structures
Periodical Inspections"!—
Safety-important systems
defined in the Electricity Utilities Industry Law
-AM systems
-Reactor water level gauge
(PWR) -Dew-point hygrometer (BWR) -Other equipment necessary for
power generation plant management
Technical Standards of
S'—
the Thermal and Nuclear
Power Engineering Society
Technical Standards for
Electric Equipment
-Associated equipment of steam
turbines (PWR)
-Auxiliary boilers
-Steam turbines
-Emergency standby power
generation devices
-Turbine-generators -Main
transformers
[Source] Material distributed
at the “11th
Study committee on proper inspection systems” (Nov.14,2003)
Figure
5.2.3 Scope of applicable systems of the maintenance management
rules (JEAC4209-2003)
5~
17
NSRA,
Japan
!
Critical path |
1 20 40 60 i i i i |
Reactor vessel etc. |
Tie-out Tie-in V V j ^^d^^est [ Reactor vessel opening Reactor vessel reassembling i A 1 i A 1 1 |
Fuel |
i I ; y Fuel removal Fuel loadingi 1 i 1 Fuel handling ■ J system check ' Fuel inspection | J J, ■ 1 ! ! J i |
Reactor coolant system |
RCS depressurization, ! 1 coolinp HptjaAsinp' i * J Kenctor coolant i 81 8 V RCS valve and pump check1 V system leak test 1 ! 1 1 [ J |
Steam generator |
11 ■ 1 ' ! V Steam generator tube inspection • i J ! i , 1 ; | i |
Instrumentation and control system |
I Instrumentation and control system check ' 1 ! ; ; ■ i • ■ ! < |
Reactor containment vessel |
J t , . Airlock check Containment vessel air purging; , > Containment vessel leak-rate testing * 1 ~J u r 1 |
Radiation control system |
i i ; Radiation control system check ; 1 1 1 |
Emergency standby power generation device |
; Emergency standby power generating device check ; : 1 : = 1 -i |
Steam turbine |
Turbine
overhaul r T |