1 Project Management for Construction of N P P 2013 The Japan Atomic Power Company Projects...

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Project Management for 　Construction of N P P

2013The Japan Atomic Power CompanyProjects Development Department

The following materials may contain JAPC’s proprietary proprietary and confidential information; and all of or any part of these materials or information contained herein may NOT be used for any purposes other than originally intended or may NOT be reproduced, disclosed, transferred, distributed or in any manner transmitted in any tangible, electronic or any other form to any third party without prior written consent thereto by JAPC.

Lec. 3(Seminar on “Sharing Experience on Nuclear Power for Development” in Vietnam)

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Contents-1【 Title 】　 ----------------------------------------------------------------------------------------------------------------------------------------

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1. About JAPC ------------------------------------------------------------------------------------------------------------------------------ - 4(1) Construction & Operation of the First of a Kind Reactors(2) Outline of Tsuruga Units 3&4 　（ Current Status, APWR Main Specification / Design Features)

【 Outline of Construction Procedures of Nuclear Power Plants (NPPs) 　】 ------------------------------------------------------------- 9

1. Law and Regulation for Construction of NPPs ---------------------------------------------------------------------------------- ----10(1) Two Important Laws as the regulation of NPPs in Japan(2) Main Guidelines for Safety Examination for LWRs(3) Endorsement of Academic Society and Association Codes, etc by Government

2. Procedural Steps for NPP Construction ---------------------------------------------------------------------------------- ------------ 　14

3. Stage of Planning ------------------------------------------------------------------------------------------------------------------------ 　 15(1) Site Selection (Important site conditions)(2) Procedures for Site Selection(3) Requirement for NPP Siting (Nuclear Reactor Site Evaluation Guidelines)(4) Site Selection (Accompanying events of earthquake)(5) Safety Examination(6) Requirement for NPP Siting (A large volume of condenser cooling water)(7) Requirement for NPP Siting (Solid bedrock for Earthquake-resistance)(8) Site Selection (Service Water, transportation, large temporary area)(9) Environmental Survey (Determine the Site, Topographic , Geological, Meteorological, Oceanographic and Marine Life Survey)

May　contain　JAPC’s　proprietary　information.　Subject　to　JAPC’s　prior　written　consent　before　using　for　any　other　purposes　than　originally　intended　or　before　disclosing　to　any　third　party.

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(10) Environmental Impact Assessment(11) 1st Public Hearing(12) Direct Dialogues with Residents (Home visits, Meeting, Newspapers, TV)

4. Preparation for Construction -------------------------------------------------------------------------------------------------------- 40(1) Procedure of Reactor Installation License from NSC Viewpoint(2) Approval Criteria for Reactor Installation LicenseApproval Criteria for Reactor Installation License(3) Application Document for Reactor Installation License (Application Text, Appendix documents)(4) Law and Regulation for Construction of Nuclear Power PlantsLaw and Regulation for Construction of Nuclear Power Plants(5) Safety Examination (Site Evaluation Guidelines)(6) Safety Design Guidelines (7) Dose-objective Guidelines(8) 2nd Public Hearing(9) Construction permit (Examination of Detailed Design, Approval of Construction Plan) Approval of Construction Plan)

5. Stage of Construction ---------------------------------------------------------------------------------------------------------------- 55(1) Major Activities in the construction of NPPMajor Activities in the construction of NPP(2) Flow of Construction Works (Example of PWR Plant) Flow of Construction Works (Example of PWR Plant) (3) Introduction of Many Tests and Inspections (4) Pre-service Inspection (Overview, Test items, Criteria, Schedule)Pre-service Inspection (Overview, Test items, Criteria, Schedule)(5) Operational　Safety　Program

6. Design and Construction Schedule of NPP in JAPANDesign and Construction Schedule of NPP in JAPAN--------------------------------------------------------------------------- 64

Contents-2


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Construction & Operation Construction & Operation of the First of a Kind Reactorsof the First of a Kind Reactors

About JAPCAbout JAPC

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1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015

(GW)

(Year)

ImageImage


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Outline of Tsuruga Units 3&4Outline of Tsuruga Units 3&4

■　■　Type　:　APWR　(Twin　Type)Type　:　APWR　(Twin　Type)

■　■　Location　:　Tsuruga　City,　Fukui　Prefecture　Location　:　Tsuruga　City,　Fukui　Prefecture　

■　■　Electrical　Output　:　1,538MWe　x　2Electrical　Output　:　1,538MWe　x　2

■　■　Operation　Start　(Target)　:　Unit　3;　Mar.2016,　Operation　Start　(Target)　:　Unit　3;　Mar.2016,　Unit　4;　Mar.2017Unit　4;　Mar.2017 May　contain　JAPC’s　proprietary　information.　Subject　to　JAPC’s　prior　written　consent　before　using　for　any　other　purposes　than　originally　intended　or　before　disclosing　to　any　third　party.


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Current Status of Site Preparation WorkCurrent Status of Site Preparation Work

Tsuruga-3&4(image)Tsuruga-3&4(image)Mountain-sideMountain-side

Sea-sideSea-side

May contain JAPC’s proprietary information. Subject to JAPC’s prior written consent before using for any other purposes than originally intended or before disclosing to any third party.

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APWR Main SpecificationsAPWR Main Specifications

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(PCCV: Pre-stressed Concrete Containment Vessel)

May contain JAPC’s proprietary information. Subject to JAPC’s prior written consent before using for any other purposes than originally intended or before disclosing to any third party.


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APWR Design FeaturesAPWR Design Features

3May contain JAPC’s proprietary information. Subject to JAPC’s prior written consent before using for any other purposes than originally intended or before disclosing to any third party. Quotation of the above pictures in this document has been allowed by MHI


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Outline of Construction Procedures Outline of Construction Procedures of Nuclear Power Plantsof Nuclear Power Plants

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LawLaw・ Atomic Energy Basic Law

・ The Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors 　

・ Electricity Utilities Industry Law

・ Law for Environmental Impact Assessment 　

・ Industrial Safety and Health Law, etc.


Law and RegulationLaw and Regulationfor Construction of Nuclear Power Plantsfor Construction of Nuclear Power Plants

Law and RegulationLaw and Regulation

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Electricity Utilities Industry Law

The Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors

-Ensure of peaceful uses of nuclear fuel material and reactors

-Secure public safety by preventing accidents

-Accordance with the sprits of the Atomic Energy Basic Law

-Protect the benefits of consumers of electricity

-Contrive sound development of the electric utility

-Secure public safety / contribute to environmental preservation by

regulating its work of installing, constructing, maintaining and operating its

electrical facilities.




12May　contain　JAPC’s　proprietary　information.　Subject　to　JAPC’s　prior　written　consent　before　using　for　any　other　purposes　than　originally　intended　or　before　disclosing　to　any　third　party.

Main Guidelines for Safety Examination for LWRsMain Guidelines for Safety Examination for LWRs

Site Evaluation Guidelines

Safety Evaluation Guidelines

Safety Design Guidelines

Dose-objectives Guidelines

Priority Classification Guidelines

ECCS Performance Evaluation Guidelines

Meteorological Guidelines for Safety Analysis

Reactivity Initiated Event Evaluation Guidelines

PWR Core Thermal Design Evaluation Guidelines

Dose Target Evaluation Guidelines

Radioactive Material Emission Measurement Guidelines

Fire Protection Guidelines

Seismic Design Guidelines

Radiation Measurement Guidelines



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- Technical Guideline and Rules of the Japan Electric Association (JEA)

- Technical codes of the Japan Society of Mechanical Engineering (JSME)

- Technical Standards of the Atomic Energy Society of Japan (AESJ), etc.


Technical Standards of METI for nuclear facility, Technical Standards of METI for nuclear facility, electric equipment, fossil fuel facility, etc.electric equipment, fossil fuel facility, etc.

Academic Society and Association Codes, etc.Academic Society and Association Codes, etc.

EndorseEndorse


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Procedural Steps for NPP ConstructionProcedural Steps for NPP ConstructionP

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Utilities Government

Site SelectionEnvironmentalExamination

Opinions ofinhabitants

1st PublicHearing

Advisory Committee for Resource & Energy

Decision on basic program of power development

Local Governor’s

Consent

Application for Reactor Installation

License

Safety Examination 2nd PublicHearing


Reactor Installation LicenseApplication for

Construction Plan Construction Permit (approval of Construction Plan)

Start ofConstruction

WeldingInspection

Pre-serviceInspection

Fuel Inspection

Start ofOperation

PeriodicalInspection

SafetyInspection

PeriodicalSafety Review

EnvironmentalSurvey

EnvironmentalAssessment

May contain JAPC’s proprietary information. Subject to JAPC’s prior written consent before using for any other purposes than originally intended or before disclosing to any third party

Local Community

Approval of Operational Safety Program

Application for Operational

Safety Program

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Stage ofStage of 　　 PlanningPlanning

Site Selection

– Selection of Project Site– Feasibility Study for Siting

In order to determine the site, topographic, geological, meteorological and oceanographic surveys have to be carried out.

– One of the most important conditions is acceptance of local community and local government.



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Site Selection

Important site conditions are as follows:


1. A large site area with enough distance from the public

2. A large volume of sea water for condenser cooling

3. Solid bedrock from the view point of Earthquake-resistance

4. Easy to obtain plant services water

5. Convenience for transportation of heavy components 　 and a large temporary area for the construction work


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Procedures for Site SelectionProcedures for Site Selection

Candidate SitesBasic program of power development

Project Scale (Number of Units & Capacity)

Topographical Feature : Scale of Environmental Modification and Civil Work

Geological Feature : Bedrock Depth, Ground Stability, Earthquake History, etc.

Geographical Feature: Social & Environmental Features (Separation form public, etc.)

Plot PlanStudy

Site Determination

Survey Items, Scope, MethodGeological:Bedrock/ Plant Design Parameter

Environmental Survey

Requirements for Plant (Area, Cooling Water, Plant Fresh Water, etc.)

Infrastructure (Power-line / Access Road / Harbor Facilities, etc.)

Preliminary Site Survey (Geological Feature: Solid Bedrock/ quantity of Plant Fresh Water etc. )

Assessment (Total Cost, Safety)

Land, Marine, Atmospheric & Social environment



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Nuclear Reactor Site Evaluation GuidelineNuclear Reactor Site Evaluation Guideline(by Nuclear Safety Commission)

From the view point of public safety in case of accident, the following siting conditions are required in principle.

– There have not been any events which induce large accident, and no such event is expected to occur in the future.There have also been very few events which expand disaster.

– Nuclear reactors shall be located at a sufficient distance from the public.

– The environment of the nuclear reactor site shall be such that appropriate measures for the public protection can be implemented as required.

Requirement for NPP SitingRequirement for NPP Siting



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Consideration of the accompanying events of earthquake

- inclined planes around Facilities (stability on slide)- tsunami (run-up/down)

Reactor Building

Regulatory guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities (Sep.19,2006 NSC)


Site Selection （ Accompanying events of earthquake ）


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• <Site Evaluation Guidelines>

• Purpose To confirm Adequacy of isolation between Reactor and Public in Accident

• Criteria

– Major Accident accidents which may occur in the worst case from technical point of view

– Hypothetical Accident accidents exceeding major accidents which may not occur from technical point of view

Safety ExaminationSafety Examination ［［ Site Evaluation GuidelinesSite Evaluation Guidelines ］］

Power Station

The area where radiation hazard may occur if people stayed in the area continuously in case of a major accident.

Non-residential Area

Low Population Zone(Power Station Site)

The area where appropriate measures can be taken to project the public from radiation in case of a hypothetical accident.

Residential Area

High Population Area

The non-residential area and low population zone are included in the site of the power station.(There are no residents in these areas in Japan.)

Collective doses; 20,000man-Sv or less

Adults thyroid exposure doses; 3Sv or lessAccidents

Whole body exposure doses; 0.25Sv or lessHypothetical

Infants thyroid exposure doses; 1.5Sv or lessaccidents

Whole body exposure doses; 0.25Sv or lessMajor


Preparation for ConstructionPreparation for Construction

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A large volume of condenser cooling water

• Required Cooling Water Flow : 70 - 80 ton/sec (1,100MW class)

• Cooling Water Candidates: Seawater, Large River Water, Lake Water, etc.

• Because there are not large rivers in Japan, all the NPP sites are located beside the sea and use seawater for condenser cooling.



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Solid bedrock for Earthquake-resistance

• In Japan, the important buildings, structures and equipment has been erected directly on a solid bedrock or been supported by an artificial bedrock placed on a solid bedrock to suppress the amplification of vibration in case of earthquakes.

• It is desirable to select a site at which such solid bedrock is found at a relatively shallow level from the ground surface.




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Easy to obtain plant services water• Fresh water for plant services

Reactor make-up water, House-boiler, Washing insulators, System Flushing, etc.

• Quantity of make-up water about several hundred to one thousand tons per day (1,000 MW Plant)

• In Japan, fresh water is taken from a river near the power plant, or demineralization units supply fresh water.



Site SelectionSite Selection （（ Site ConditionSite Condition ））

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•Unloading facilities for heavy components near the site. – Transportation of spent fuel casks (about 70 - 100 tons) – Transportation of heavy components, such as the

reactor pressure vessel, steam generators, main transformers and generators in construction work

•Temporary area for construction is needed to use for locating the contractor's temporary building, construction materials and machinery storage yards, etc. during construction period.

– Single unit : 13-17×10 ４ (m2) – Twin unit : 18-29×10 ４ (m2) (@1,000 MW ～ 1,500MW class)


Convenience for transportation of heavy components and a large temporary area for the construction work

Reactor Vessel of Tsuruga-2 (320ton)

Site SelectionSite Selection （（ Site ConditionSite Condition ））Stage ofStage of 　　 PlanningPlanning

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1st PublicHearing



Local Governor’s

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WeldingInspection


Fuel Inspection

Start ofOperation


SafetyInspection




EnvironmentalSurvey

Procedural Steps for NPP ConstructionProcedural Steps for NPP Construction



License



Safety Program

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Survey to Determine the Site Survey to Determine the Site

In order to determine the site, several kinds of surveys have to be carried out as follows:

1. Topographic and Geological Survey

2. Meteorological Survey

3. Oceanographic Survey and Marine Life Survey



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Topographic and Geological SurveyTopographic and Geological Survey

the topography of the plant site and its surrounding area are investigated :

<core drilling, test pitting, seismic prospecting, aerial photogrammetric etc.>

(shape, depth and strength of bedrock, etc.)– to locate important structures including the reactor building

(seismic history, geological structure, measured seismic waves)– to determine the seismic design inputs (ex. maximum

acceleration of the foundation ground)



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Topographic and Geological SurveyTopographic and Geological Survey - Geological Survey - Geological Survey ［［ ExampleExample ］］ --



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Meteorological SurveyMeteorological Survey

Wind velocity, temperature, moisture, rain precipitation, salinity, etc. are investigated :

– To be reflected in the building and equipment design conditions

Wind direction and velocity distributions, vertical distribution of temperature, etc. are investigated :

– To evaluate the effects of released gaseous radioactive wastes under normal and accidental conditions on the public

– To evaluate the adequacy of the stack height



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Meteorological Survey ［ Example ］



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Oceanographic Survey and Marine Life SurveyOceanographic Survey and Marine Life Survey

Wave height, wave direction, tidal level, depth of water, drift sand, tidal current, and marine life are investigated :

– to design of the intake and discharge facilities of the condenser cooling sea water

– to assess the impacts of the diffusion of thermal discharge on marine life



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OceanographicOceanographic 　　 Survey and Marine Life Survey and Marine Life Survey Survey [Example][Example]



Deep layer discharge

Surface layer discharge

1℃ up

　2℃ up

　

3℃ up

　

Reduction of Diffusion Area of Thermal Effluent

May　contain　JAPC’s　proprietary　information.　Subject　to　JAPC’s　prior　written　consent　before　using　for　any　other　purposes　than　originally　intended　or　before　disclosing　to　any　third　party

An Image of Nuclear Power Station after EIA Review

Native tree planting

Minimize reclamation area

An Image of Nuclear Power Station at Basic Plan Stage

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Environmental Impact AssessmentEnvironmental Impact Assessment

- The utility surveys the natural and social environment of the selected site and makes environmental impact forecasts and assessments both during the period of construction and operation as required in EIAL and EUIL.

- In accordance with EIAL and EUIL, an environmental impact report is submitted from the utility to METI and the local government. The report is also reviewed by local residents, and their comments are invited. METI examine the report considering the comments from the local governor and local residents.



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1st Public Hearing1st Public Hearing

During the environmental examination, METI holds the 1st Public hearing to gain a deeper understanding of local communities concerning :

- Necessity and outline of the construction plan - Environmental impacts of the NPP installation - Basic policy of safety measures & environmental

protection



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Direct　Dialogues　with　Residents　(Home　visits)

Visiting　all　26,000　households　　in　Tsuruga　　



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At　takahama At　echizen

Meetings　with　the　Residents

5000　participants　



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Newspaper　Advertisements　

TV　Commercials　Stage ofStage of 　　 PlanningPlanning

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Procedure of Reactor Installation License from NSC Viewpoint

(Source:NSC Annual Report)



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Approval Criteria for Reactor Installation LicenseApproval Criteria for Reactor Installation License

1. The Reactors will not be used for non-peaceful purpose.

2. The permission will cause no hindrance to the planned development and utilization of atomic energy.

3. The applicant has technological ability and financial position sound enough to establish reactor, and has such technical ability to operate them competently.

4. The location, structure and equipment of reactor facilities are such that they will cause no hindrance to the prevention from the hazard by reactor fuel material and by reactors.

1st Examination 2nd Examination(Double check)

METI

Atomic Energy

Commission

NuclearSafety

Commission

Approval Criteria



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Application Document for Reactor Installation License (1)

Application Text

(1) name & address of applicant

(2) purpose

(3) type, thermal output and number

(4) name & address of facility

(5) Location, structure and equipment

(6) Construction Plan

(7) Fuel material and estimated annual consumption

（８） Method of disposing of spent fuel

A. location of reactor facilities

B. structure of reactor facilities a. seismic structure b. other main structure

C. structure and equipment of reactor a. reactor core b. fuel c. coolant & reflector d.reactor vessel e. radiation shield f. others

D. fuel handling & storage facilities

E. reactor cooling system a. primary cooling system b. secondary cooling system c. emergency cooling system d. others

F. instrumentation and control system

F. radioactive waste treatment facilities

G. radiation control system

H. other facilities



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Application Document for Reactor Installation License (1)

Appendix documents

chapter 1 : purpose of reactor establishment

chapter 2 : reactor thermal output calculation

chapter 3 : economic plan for construction

chapter 4 : nuclear fuel acquisition plan

chapter 5 : technical ability of applicant to establish and operate reactor

chapter 6 : siting condition

chapter 7 : topographical map around reactor

chapter 8 : safety design of reactor facilities

chapter 9 : radiation protection and waste treatment

chapter 10 : safety analysis

(1) site outline(2) meteorological condition(3) geological condition(4) sea & water condition(5) earthquake(6) social environment

(1) safety design philosophy (2) facility layout (3) reactor & core (4) reactor cooling system (5) reactor containment system (6) turbine system (7) instrumentation & control system (8) electricity facility (9) fuel handling & storage system(10) radioactive waste treatment system(11) radiation control system(12) plant support facilities(13) emergency control center(14) operation & maintenance(15) quality assurance

(1) radiation protection policy (2) radiation control(3) peripheral radiation monitored area & environmental radiation monitoring (4) radioactive waste treatment (5) dose evaluation of public around site

(1) safety assessment policy (2) anticipated transient analysis(3) accident analysis (4) major accident & hypothetical accident analysis



47May　contain　JAPC’s　proprietary　information.　Subject　to　JAPC’s　prior　written　consent　before　using　for　any　other　purposes　than　originally　intended　or　before　disclosing　to　any　third　party.

Main Guidelines for Safety Examination for LWRsMain Guidelines for Safety Examination for LWRs

Site Evaluation Guidelines

Safety Evaluation Guidelines

Safety Design Guidelines

Dose-objectives Guidelines

Priority Classification Guidelines

ECCS Performance Evaluation Guidelines

Meteorological Guidelines for Safety Analysis

Reactivity Initiated Event Evaluation Guidelines

PWR Core Thermal Design Evaluation Guidelines

Dose Target Evaluation Guidelines

Radioactive Material Emission Measurement Guidelines

Fire Protection Guidelines

Seismic Design Guidelines

Radiation Measurement Guidelines



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<Site Evaluation Guidelines>Purpose To confirm Adequacy of isolation between Reactor and Public in AccidentCriteria

Major Accident accidents which may occur in the worst case from technical point of viewHypothetical Accident accidents exceeding major accidents which may not occur from technical

point of view

Safety ExaminationSafety Examination ［［ Site Evaluation GuidelinesSite Evaluation Guidelines ］］

Power Station

The area where radiation hazard may occur if people stayed in the area continuously in case of a major accident.

Non-residential Area

Low Population Zone(Power Station Site)

The area where appropriate measures can be taken to project the public from radiation in case of a hypothetical accident.

Residential Area

High Population Area

The non-residential area and low population zone are included in the site of the power station.(There are no residents in these areas in Japan.)

Collective doses; 20,000man-Sv or less

Adults thyroid exposure doses; 3Sv or lessAccidents

Whole body exposure doses; 0.25Sv or lessHypothetical

Infants thyroid exposure doses; 1.5Sv or lessaccidents

Whole body exposure doses; 0.25Sv or lessMajor



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Safety Design Guidelines (1)Safety Design Examination Guideline for

Power-generating LWR Facilities

No. Requirement

1 Compliance to Codes & Standards

2 Consideration of Natural Phenomena (Earthquake, Flooding, Tsunami, Wind,Snow, etc.)

3 Consideration of External Events (Physical Protection, Airplane, etc. )

4 Internally Generated Missile (Pipe Break, Rotating Equipment, Explosion, Fall, etc.)

5 Fire Protection (Prevention, Detection, Extinguish, Mitigation of damage)

6 Environmental Conditions for Equipment

7 Sharing Facilities (Maintain safety when facilities are shared by two or more reactors)

8 Man-machine Interface (Proper measures to prevent operators’ errors)

9 Reliability of Safety Facilities (Redundancy or diversity and Independency, Emergency Power Supply)

10 TestabilityMay　contain　JAPC’s　proprietary　information.　Subject　to　JAPC’s　prior　written　consent　before　using　for　any　other　purposes　than　originally　intended　or　before　disclosing　to　any　third　party.


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No. Requirement

11-18 Reactor & Reactor Shutdown System (Fuel Integrity, One Rod Stack Margin, Diversity of Shutdown System, etc.)

19-27 Reactor Coolant System(Integrity of RCPB, RCPB Leak Detection, Reactor Make-up, Residual Heat Removal, Emergency Core Cooling, Heat sink, Station Black Out, etc.)

28-33 Reactor Containment System (Integrity of Containment Boundary, Isolation Valves, Containment Heat Removal, In-containment Atmosphere Control, etc.)

34-40 Safety Protection System(Redundancy and Independency, Fail-safe, Separation from Normal Control System, etc.)

41-46 Control room & Technical Support Center(Plant Monitoring & Control Function, Remote Shutdown from other place, Comfortableness of control room, Technical Support Center, Communication Equipment, etc.)

(RCPB : Reactor Coolant Pressure Boundary)May　contain　JAPC’s　proprietary　information.　Subject　to　JAPC’s　prior　written　consent　before　using　for　any　other　purposes　than　originally　intended　or　before　disclosing　to　any　third　party.


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No. Requirement

47-48 Control System & Electric System

49-51 Fuel Storage System & Fuel Handling System

52-55 Radioactive Waste Treatment System

56-59 Radiation Protection & Control



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Dose-objective GuidelinesGuideline for Dose-objective in the Vicinity of

LWR Facilities for Power Generation

Basic Philosophy Dose Limit for Public : 1mSv/y (← prescribed in the Law)

As low as reasonably achievable

Dose Objective : 0.05mSv/y

Assessment Condition

- Public near the P/S (considering future community formation)

- Radiation Source : Gaseous radioactive waste (noble-gas, iodine) Liquid radioactive waste - External Dose / Internal Dose (Food Chain)

(About 1/50 of annual exposure from natural radiation sources)

Target for dose reduction effort of Utilities


≦0.05mSv/yNatural Radiation 2.4mSv/y


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2nd Public Hearing

In the period of the safety examination by Nuclear Safety Commission (NSC), called the second examination (the double check), NSC holds the 2nd public hearing to consider the opinions of local communities on the safety examination of the plant.



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Examination of Detailed DesignExamination of Detailed Design

-The utility is required by EUIL to obtain an approval for detailed design and the construction plan of the plant from METI before fabrication and construction.

Approval of Construction Plan (Construction Permit)

- These applications are usually submitted on the separate basis in accordance with the schedule of fabrication of each component and construction at site.

Generally, the first application that covers the construction of the reactor building and the installation of reactor containment is submitted to METI.



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Construction PermitConstruction Permit(Approval of Construction Plan)(Approval of Construction Plan)

METI(Examinations)

Application for approval of construction plan

Advisory Committee on Technical Matters

Approval of Construction(Construction Permit)

Explanations

Comments

Utility

UtilityStart of Construction

JNES(ex-NUPEC)(Audit Analysis)

Instructions

Experts



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- excavation of building foundation

- reinforced concrete works of reactor building’s base mat- primary containment Vessel works- other building works

- installation of reactor vessel

- installation of piping and equipment- installation of core internals- cold / hot function test- fuel loading

- startup test

Major Activities in the construction of NPPMajor Activities in the construction of NPP


Stage of ConstructionStage of Construction

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Phase Ⅰ Phase Ⅱ Phase Ⅲ Phase Ⅳ

▽ Start of ConstructionStart of Commercial Operation ▽

Preparatory Work(Site Preparation)

Flow of Construction Works (Example of PWR Plant) Flow of Construction Works (Example of PWR Plant)

▽ Fuel Loading



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- EUIL requires the pre-service inspection by METI at each stage of the fabrication and construction.

- METI confirms that the utility has been conducting construction works in compliance with the construction plan and technical standards, and that the plant has adequate performance as prescribed in the construction plan and other licensing documents.

Pre-service InspectionPre-service Inspection



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Pre-Service InspectionPre-Service Inspection

TEST ITEM

CRITERIA(1) Accordance with the construction plan(2) Not such that facilities do not conform to the technological standards

Stage (a)

Stage (b)

Stage (c)

Stage (d)

Stage (e)

When the situation allows to test the structure, strength, or leakage of each facilities

When the installation of the lower part of the steam turbine cabin or main unit of the auxiliary boiler is completed

When the situation allows to load fuels

When the Reactor reaches criticality

When all the works stated in the construction plan is completed



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FactoryInspection

InstallationInspection

Equipment unitexamination

SystemFunction test

Heat uptest

On powertest

Stage (a),(b) Stage (a) Stage (c) Stage (d),(e) Stage(e)

QualityManagement

WeldingInspection

FuelInspection

Pre-servicePre-serviceinspectioninspection


Major Regulatory Inspections in NPP Construction


HFTCFT

Fuel Loading

Factory Site

Major Activities of Utility & Manufacturer

64

(c)Pressurizer Safety Valve Function Test (FT)RCS Pressure/Level Control System FTChemical Volume Control System FTSafety Injection System FTResidual Heat Removal System FTComponent Cooling Water System FTMain Steam Safety Valve FTMain Steam Relief Valve FTSafety Protection System FTCore Instrumentation System FTReactor Make-up System FTFuel Handling System FTSFP Purification & Cooling System FTRadiation Monitoring Facility FTHVAC System FTRadioactive Waste Treatment System FT Containment Spray System FTContainment Isolation Valve FTReactor Containment FTMain Feedwater System FTAuxiliary Feedwater System FTEmergency Power Supply System FTTotal Facility Inspection FT

(d) Fuel Loading TestControl Rod Drive Mechanism TestPressurizer Spray TestControl Rod Control Range Confirmation TestTotal Interlock TestModerator Temperature Efficiency MeasurementMinimum Shutdown Margin Boron Concentration Measurement

Critical Boron Concentration Measurement

(e) Load Reduction TestPlant Trip TestLoss of Offsite Power TestGenerator Load Loss TestTotal Load Test




65

Prior to the startup of the reactor, the utility, pursuant to the LRNR*, establishes the operational safety program to adequately prevent accidents that may arise from the operation of the nuclear power plant. The operational safety program must be authorized by METI.



* The Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors

Operational Safety ProgramOperational Safety Program

66

Design and Construction Schedule of NPP in JAPANDesign and Construction Schedule of NPP in JAPAN


▼▼▼ ▼ 　▼

-　-　-　-　-　-　-　-　-　-

▼

▼

139 10 11 125 6 7 84321

Safety ExaminationEnviron.Assess.

Environ. Scope Assess.

#1 #2 #6 to 8

Construction Permit

Preparation for construction

Decision of site and start construction (Electric Power Development Coordination Council)

Basic Site Plot Plan / GA Study Examination by METI & NSC/AEC

R/B,C/B,A/B Structure Case Study

NSSS/BOP basic system design

Safety Analysis & Safety Document

Environ. Survey

R/B,A/B Seismic Analysis & Design

Detail Plot Plan / GA design

Detailed Design of NSSS / BOP system / equipment

Equipment installation (on site)

Functional Test

Excavation work

Pre-Service inspection

CommercialOperation

Fuel Loading

Bed Lock Inspection

material properties, welding, fabrication, installation and functional test, etc.

material procurement, processing, fabrication of equipment

Documents (structure design, seismic Integrity, Quality Management, etc.)

PCCV Construction

Civil ConstructionLeak Rate Test

CFT

Example

Welding Safety Management inspection

HFT


END

Appendix


　Basic Policy of the reform on Nuclear Regulatory Organizations and Lows

　 2013The　Japan　Atomic　Power　Company

The following materials may contain JAPC’s proprietary and confidential information; and all or any part of these materials or information contained herein may NOT be used for any purposes other than originally intended or may NOT be reproduced, disclosed, transferred, distributed or in any manner transmitted in any tangible, electronic or any other form to any third party without prior written consent thereto by JAPC.


Background2011/03/11 ： The Great East Japan Earthquake, tsunami and

Fukushima No.1 NPP accident 　 happened

2011/08/15 ： The Cabinet of Japanese government decided “the

basic policy of the revision on nuclear regulatory organizations

and related matters.

2012/01/31:The Cabinet decided “nuclear regulatory organizations

and lows reform act draft”

2012/06/20:The enactment of the reform act above is passed by

the Diet.

2012/09/19:The new nuclear regulatory organizations and lows

reform system were activated


Basic points of the reform on this nuclear regulatory system

1.The clear Separation between utilization and regulation

“Nuclear safety and Industrial Agency” is separated from “Ministry of Economy

Trade and Industry” and adds the function of Nuclear Safety Committee, and

“Nuclear Regulation Authority ” was established.

2. Integration

Nuclear safety regulations are divided in several organizations, so they haven’t

been worked effectively so those works are interrogated in Nuclear Regulation

Authority to enhance the function of nuclear safety

3.Crisis Management

Nuclear Regulation Authority positions crisis management in initial response for

accidents as their important task and arrange their system for that.

4.Development of Human Resources

Making much efforts to secure high quality human resource without regarded to

public or private sectors to make sure works in the new agency.

5.New safety regulation

Reviewing adequate regulations and related system such as introducing new

regulatory constructers based on the accident at Fukushima NO.1

ＮＲＡ（ Nuclear Regulation Authority ）


Cabinet

Office

Outline of the new organization System

Atomic

Energy

Commission

Nuclear

Safety

Commission

Nuclear and

Industrial Safety

Agency

ＭＥＴＩ

Ministry of

Economy

Trade Industry

The conventional Nuclear Safety regulatory organization

The new Nuclear Safety regulatory organization

Nuclear

Security

Double

Check

Ministry

of Education

Culture

Sports

Science and

Technology

Regulation

against

NPP

Regulation

against Test

Reactor

ＭＥＴＩ

Securing Independence of

Regulations

Realizing objective and

scientific Regulations

Separation Use & Regulations

Integration on Nuclear Safety

Enhancing Emergency

Ministry of Environment

TheSecretariat

of 　 the 　 NRA

Pla

nnin

gP

repa

ratio

n fo

rC

onst

ruct

ion

Con

stru

ctio

nO

pera

tion

METI

Environmental 　 Examination


Safety Examination PublicHearing

Reactor Installation License

Construction Permit (approval of Construction Plan)

Welding 　 Inspection

Fuel 　 Inspection


SafetyInspection





NRA



Construction Permit (approval of Construction Plan)

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