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Project Management for Construction of N P P

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1 Project Management for Construction of N P P
Lec. 3 (Seminar on “Sharing Experience on Nuclear Power for Development” in Vietnam) Project Management for Construction of N P P 2013 The Japan Atomic Power Company Projects Development Department 本日は、原子力プラント建設のプロジェクト管理の概要について、日本での 建設手続きを中心に講演させていただきます。 尚、我々の日本では、 に発生した東日本大震災による福島第一 原子力発電所での事故を経験し、このような手続き面についても見直しがな されていますが、まだ制度面で過渡期にあり、且つ、この新制度により原子 力発電所建設を行った実績はありません。 従って、我々の建設経験をお話する意味でも、実績のある従来の手続きを ご説明させて頂き、その後、規制がどのように見直されたかを補足させてい ただくことで、進めさせていただきます。 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.

2 Contents-1 These are contents so I skip them
【Title 】  1. About JAPC (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) 】 1. Law and Regulation for Construction of NPPs (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) These are contents so I skip them 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.

3 Contents-2 These are contents so I skip them
(10) Environmental Impact Assessment (11) 1st Public Hearing (12) Direct Dialogues with Residents (Home visits, Meeting, Newspapers, TV) 4. Preparation for Construction (1) Procedure of Reactor Installation License from NSC Viewpoint (2) Approval 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 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) 5. Stage of Construction (1) Major Activities in the construction of NPP (2) Flow of Construction Works (Example of PWR Plant) (3) Introduction of Many Tests and Inspections (4) Pre-service Inspection (Overview, Test items, Criteria, Schedule) (5) Operational Safety Program 6. Design and Construction Schedule of NPP in JAPAN These are contents so I skip them 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.

4 Construction & Operation of the First of a Kind Reactors
About JAPC Construction & Operation of the First of a Kind Reactors Capacity 表示④ 1987 (GW) 1970 70 2016, 2017 表示② 60 表示⑤ 50 55units 50GW 40 表示① 30 表示③ 1966 1978 20 10 Image This figure shows the trend of Nuclear Power Capacity in Japan. The horizontal axis means year, and the vertical axis shows total capacity of Nuclear Power Plants. The JAPC has always coped with the first of a kind reactors in Japan because our company has been expected as the pioneer of NPPs in Japan In 1966, the JAPC started commercial operation of Japan’s first NPP, Tokai Power Station, that is a gas cooled reactor with technically imported from UK. In 1970, the JAPC started commercial operation of Tsuruga Power Station Unit 1, as the first LWR in Japan. The LWR has been majority of NPPs in the world since those days. Then the JAPC built Tokai No.2 Power Station as the First BWR-5, that is the best-seller type in Japan (more than 10units) with 1100MW capacity, and Tsuruga Power Station Unit 2 as the first large-scale PWR with 4-loop and SG 1160MW capacity by domestic technology. Today, the JAPC now is preparing to build Tsuruga units 3&4 as the first APWR, which means Advanced PWR, plants. この図は、日本の原子力発電容量の年代別傾向を示しています。横軸は西暦を意味し、縦軸は、原子力発電所の総設備容量を示しています。 当社は、日本での原子力発電の開拓事業化の使命を期待されており、JAPCは、常に、日本に原子炉を導入する場合の初号機を建設しています。1966年には、JAPCは、ガス冷却炉を英国から輸入して、日本で初の商業用原子力発電所である東海発電所の運転を開始しました。  1970年には、日本で最初の軽水炉として、敦賀発電所1号機の商業運転を開始しました。 LWRは当時以来、世界における原子力発電所の大多数となっています。  その後JAPCでは、BWR-5である東海第2発電所を建設し、日本では1100MW容量として、その後の標準的な出力となっています。(10units以上) 敦賀2号機では、国産技術によって、4ループPWRを建設しました。 今日、JAPCはAPWR初号機(アドバンスドPWR)となる敦賀3&4号機の建設準備を進めている。 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 (Year) 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.

5 Outline of Tsuruga Units 3&4
About JAPC Outline of Tsuruga Units 3&4 This slide shows the summary of Tsuruga Power Station Units 3 and 4 construction plan. The Tsuruga Power Station is located in Fukui Prefecture in Japan. Here, the green colored area, the top of the Tsuruga Peninsula, is the Site of the Tsuruga Power Station. Now, we are operating Tsuruga unit 1, the first BWR in Japan, and unit 2, the 4 loop PWR here. The Tsuruga units 3&4 are the first APWRs in Japan. The electric power output is 1,538MWe for each, and they will be built as twin-type plants. We have been conducting preparation work for construction since 2004, and planning to start full-scale construction work, and originally to start commercial operation in around 2016 for unit 3 and 2017 for unit 4. But unfortunately, after 3/11 in 2011 Fukushima accident, Our construction is actually temporarily stopped. JAPC will restart the construction of those plants as faster as we can when the society condition allow it. このスライドは、敦賀発電所3,4号機の概要と建設計画を示しています。    敦賀発電所は、日本の福井県に位置しています。ここでは、緑色のエリア、敦賀半島の上部には、敦賀発電所のサイトです。   今、私たちは敦賀ユニット1、日本で最初のBWR、及び4ループPWRの2基を運用しています。  敦賀3&4は、日本で初めてのAPWRです。    発電出力は、それぞれに1538万kWであり、ツインプラントとして建設します。     我々は2004年以来、建設のための準備作業を実施し、本格的な工事を開始し、当初はユニット3とユニット4の2017、2016年頃に商業運転を開始する予定としていました。 しかし、残念なことに、2011年福島の事故で3月11日後、建設計画は実際に一時中断しています。社会的に建設が認められれば、我々はできる限りJAPCが速くとしてこれらのプラントの建設を再開します。 ■ Type : APWR (Twin Type) ■ Location : Tsuruga City, Fukui Prefecture ■ Electrical Output : 1,538MWe x 2 ■ Operation Start (Target) : Unit 3; Mar.2016, Unit 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.

6 Current Status of Site Preparation Work
Mountain-side Tsuruga-3&4(image) Sea-side These Photos show the status of the preparation work for the construction last summer. The above photo shows the mountain-side work, and the image of the Tsuruga units 3 and 4 after finishing construction is shown on the right hand. As for the sea-side work, the reclamation work inside the seawall has been almost completed. The reclamation area is bout 20 hectare, and the reclamation volume is about 1.8 million cubic meters. これらの写真は去年の夏の準備工事の状況を示します。          上の写真は山の側の作業を示しており、敦賀3,4号機の画像は建設を終えた後、右側に表示されます。     海側の作業としては、護岸内側の埋め立て工事がほぼ完了しました。埋め立て面積は20ヘクタールの試合であり、埋め立て量は約180万立方メートルです。 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.

7 APWR Main Specifications
About JAPC APWR Main Specifications This table shows the main specifications of APWR, compared to those of current 4-loop PWR. The power output is rated to about 1.3 times of the current 4-loop PWR. Also the number of fuel assemblies is increased by about 1.3times. But the specification of the one fuel assembly is same as current fuel assembly. The reactor vessel is scaled up according to the increase of fuel assemblies. The steam generator heat transfer area is also increased according to the power increase. The containment vessel type is a PCCV (Pre-stressed Concrete Containment Vessel), the same type as the current 4-loop PWRs in Japan. The length of the low pressure turbine final blades is about 54 inches. このテーブルには、従来型4ループPWRとAPWRの主な仕様比較を示す。     電気出力は、従来型4ループPWRの約1.3倍程度です。    また、燃料集合体の数は約1.3timesずつ増加します。しかし、一つの燃料集合体の仕様は、現在の燃料集合体と同じです。     原子炉容器は、燃料集合体の増加に応じてスケールアップしています。蒸気発生器の伝熱面積は、出力増加に応じて増加します。     格納容器の種類は、PCCV(プレストレストコンクリート格納容器)は、日本の現在の4ループPWRと同じ型です。     低圧タービン最終翼の長さは、約54インチである。 (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. 2

8 APWR Design Features About JAPC 3
This slide shows the main design features of the APWR. The first feature is reliability enhancement of reactor internal structures adopting “a neutron reflector”, which is located around core and has simple rings structure to reduce neutrons leaking to outside of the core, then it contributes to improve neutron economy, and simplify the structure with eliminating bolts around the core region. The second feature is safety enhancement with improvement of engineered safeguard systems. For example, 4 redundant subsystems are applied, and the emergency water source is located inside the containment. Also, the low pressure injection system is eliminated by a design improvement of accumulator tanks which have the same function of conventional low pressure injection and accumulator. The third one is operation enhancement by improved Main Control Board. Of course, APWR adopts many other improvements by reflecting the experiences of operations and maintenance. このスライドは、APWRの主な設計の特徴を示しています。     第一の特徴は、炉心周りに設置し、外部に漏れる中性子を削減する単純なリング構造を持った “中性子反射体”を採用した炉内構造物の信頼性の向上である。 それは中性子経済向上と、炉心領域の周りのボルトを排除することによる構造簡素化です。     第二の特徴は、 4つの冗長サブシステム適用による安全性の向上である。たとえば、緊急時の水源は、格納容器内部に設置している。また、低圧注入系は、従来の低圧注入とアキュムレータと同じ機能を持っているアキュムレータタンクの設計の改善によって解消されています。     三つ目は、総合ディジタル式新型中央制御盤による操作機能です。もちろん、APWRは運用·保守の経験を反映することによって、その他の多くの改良を採用しています。 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. 3 Quotation of the above pictures in this document has been allowed by MHI

9 Outline of Construction Procedures of Nuclear Power Plants
Next I would like to explain about the outline of construction procedures of nuclear power plants in Japan. 次に私は、日本の原子力発電所の建設手順の概要について、説明したいと思います。 なお、福島事故を教訓として、 に日本で原子力規制委員会設置法が施行され、原子力規制委員会が発足し、新安全規制体制に移行しました。 新制度で原子力発電所の建設手続きを実施した実績がないことから、本日の講義は、これまでの実績のある従来の建設手順でご説明させて頂きます。

10 Law and Regulation for Construction of Nuclear Power Plants
・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. There were several laws applied for construction of nuclear power plants. ・Atomic Energy Basic Law, that describes that nuclear power shall be developed for only peaceful use. ・The Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors, that regulates the safety aspects of nuclear power. ・Electricity Utilities Industry Law, that regulates the nuclear power as one of the electric power source. ・Law for Environmental Impact Assessment, that is for environmental protection.  ・Industrial Safety and Health Law, that is for general industrial safety. etc. Two laws colored red is very important in Japan, as the regulation of the nuclear power plants 原子力発電所の建設のために適用されるいくつかの法律がある。 原子力基本法は、原子力利用は、平和の目的に限り、安全の確保を旨として行う 核原料物質、核燃料物質及び原子炉の規制に関する法律は、原子力の安全面を規制する 電気事業法、電力源の一つとして原子力を規制している。 環境影響評価法は、環境保護のためのものです。 ·一般産業の安全のためである労働安全衛生法、等 この二つの法律(赤色)は、原子力発電所を規制する法律として、日本では非常に重要である。 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.

11 Law and Regulation for Construction of Nuclear Power Plants
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 Electricity Utilities Industry 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. The first one, the Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors, is to ensure of peaceful uses of nuclear fuel material and reactors and to secure public safety by preventing accidents, accordance with the sprits of the Atomic Energy Basic Law. The second one, Electricity Utilities Industry Law, has following three purposes - To protect the benefits of consumers of electricity - To contrive the sound development of the electric utility, - To Secure public safety and to contribute to environmental preservation by regulating its work of installing, constructing, maintaining and operating its electrical facilities. In Japan, these two laws are applied for the commercial nuclear power plants at the both construction and operation stage. 核原料物質、核燃料及び原子炉の規制に関する法律は、原子力基本法の精神に基づいて、 ・核原料物質、核燃料物質及び原子炉の利用が平和の目的に限られることを確保 ・災害を防止し、及び核燃料物質を防護して、公共の安全を図る。 電気事業法では、 - 電気の消費者の利益を保護するために、 - 電気事業の健全な発展を図ること、 -電気設備の建設、運転、メンテナンス等の規制によって、環境保全に貢献、公共の安全を確保する。  日本では、これらの2つの法律は、建設及び運転段階の両方で、商業用原子力発電所に適用されます。 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.

12 Law and Regulation for Construction of Nuclear Power Plants
Main Guidelines for Safety Examination for LWRs Site Evaluation Guidelines ECCS Performance Evaluation Guidelines Safety Evaluation Guidelines Meteorological Guidelines for Safety Analysis Reactivity Initiated Event Evaluation Guidelines PWR Core Thermal Design Evaluation Guidelines Dose-objectives Guidelines Dose Target Evaluation Guidelines Radioactive Material Emission Measurement Guidelines Safety Design Guidelines I have already showed this figure before on “Safety Design Guidelines.” Today I would like to explain those guidelines related to NPP in more detail later. In Japan, there are several guidelines for safety examination on the basic design stage, determined by the Nuclear Safety Commission. There are guidelines mainly for site evaluation, safety design and safety evaluation. All the applicants for reactor installation license should demonstrate the compliance to these guidelines. 日本では、原子力安全委員会が決定した基本設計段階での安全審査のためのガイドラインがあります。 今日、私は後で詳しく原子力発電所に関連するこれらのガイドラインを説明したいと思います。     主にサイトの評価、安全設計と安全性評価のためのガイドラインがあります。原子炉設置許可申請者は、これらのガイドラインに適合していることを証明しなければならない。 Fire Protection Guidelines Seismic Design Guidelines Radiation Measurement Guidelines Priority Classification Guidelines 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.

13 Law and Regulation for Construction of Nuclear Power Plants
Technical Standards of METI for nuclear facility, electric equipment, fossil fuel facility, etc. Endorse Academic Society and Association Codes, etc. 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. In detailed design phase, several technical standards of METI (Ministry of Economy, Trade and Industry) are applied for examination of construction plan of the plant in view point of performance, structural and seismic integrity, etc. of the system, structure and component. In the process of this examination, academic society and association codes, such as Technical codes of the Japan Society of Mechanical Engineering (JSME CODES: same as ASME of the US), are used supplementary (additionally). The applicability of these codes are endorsed by METI’s technical standards. 詳細設計の段階では、経済産業省の技術基準は、性能の観点、構造や耐震設計など、システム、構造、コンポーネントの中で工事計画認可申請書の審査に適用されます。     この審査の過程において、協会や日本機械学会(JSMEコード:米国のASMEと同じ)の規格を使用します。 これらの基準は、経済産業省の技術基準によって、エンドースされています。 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.

14 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) This slide shows the relation between Utilities, Government, and Local Community in the process of NPP construction. The entire process of construction is mainly divided into 3 stages, planning, preparation for construction, construction. After construction is completed, the plant starts commercial operation. On the planning stage, we select an adequate site for NPP construction, and then start environmental survey and its assessment. The Government assesses if our construction plan is appropriate to minimize the affect to the environment . During this environmental assessment, the Government holds the first public hearing. After environmental assessment is completed, the utility’s construction project is included into the basic program of power development of the government. このスライドは、原子力発電所の建設の過程での、電力会社、政府、地域社会との関係を示している。      建設プロセス全体は、主に3段階、計画、建設準備、建設、運転に分かれています。建設終了後、発電所は商業運転を開始します。      計画段階では、我々は、原子力発電所建設のための適切なサイトを選択し、環境調査とその評価を開始します。私たちの建設計画は、環境への影響を最小限にするために適切であるかどうか、政府は評価している。      この環境アセスメントの間に、政府は、公聴会を実施しています。      環境影響評価が完了したら、電力会社の建設プロジェクトは、政府の電源開発基本計画に組み入れられます。 Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

15 Selection of Project Site Feasibility Study for Siting
Stage of Planning Stage of Planning 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. On the site selection stage, we have to select a sites suitable for NPP construction. In order to determine the site for NPP construction, topographic(地理), geological(地質), meteorological(気象) and oceanographic(海洋学) surveys are carried out. And one of the most important conditions is acceptance of local community and local government. In Japan, the largest efforts have been made to obtain the agreement of the local communities. サイト選定の段階で、原子力発電所の建設に適したサイトを選択する必要があります。 原子力発電所の建設サイトを決定するために、地理、地質、気象、海洋等の調査を行います。 そして、最も重要な条件の一つは、地域社会や地方自治体の受け入れです。日本では、地域社会の合意が得られるよう最大限努力します。 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.

16 Important site conditions are as follows:
Stage of Planning 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 In order to construct a nuclear power plant, there are some major conditions for site selection. The typical appropriate site conditions are as follows: 1. There is a large site area with enough distance from the public. (location far away from populated areas) 2. We can obtain a large volume of sea water for condenser cooling . 3. There is a Solid bedrock under the planned point, from the view point of Earthquake-resistance. 4. It is easy to obtain plant services water (fresh water). 5.It is convenient for transportation of heavy components, and there is a large temporary area for the construction work. 原子力発電所を構築するためには、サイト選定のためのいくつかの主要な条件があります。典型的な適切なサイトの条件は次のとおりです。 1.住民から十分な距離を持つ大規模な敷地面積がある。 (人口密集地から遠く離れた場所) 2.復水器冷却用の海水を大量に取得できる。 3.耐震性の観点から、計画地点の下の岩盤が存在する。 4.プラントへの給水(淡水)を取得することが容易である。 5.重機器の輸送のための便利で、工事のための仮設用地がある。 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.

17 Procedures for Site Selection
Stage of Planning Procedures for Site Selection Basic program of power development Candidate Sites Project Scale (Number of Units & Capacity) Requirements for Plant (Area, Cooling Water, Plant Fresh Water, etc.) 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.) 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) This flow chart shows the procedures for site selection from view point of utilities. For the candidate site, project scale corresponding to the basic program of power development (for example, number and capacity of the plant), requirement for the plant (for example, area, cooling water) , topographical, geological and geographical features are considered. Then, preliminary site survey is carried out for the feasibility study. After assessing the total cost, safety, etc., the site is determined and then detailed study and the official environmental survey is carried out. このフローチャートは、電力の視点でサイト選定を行う手順を示しています。        候補地は、電源開発の為の基本的なプログラム(例えば、基数、電気出力)に対応できる規模で、プラント設計上の要求事項(例えば、必要面積、冷却水)、地形、地質や地理的特徴が考慮されます。        その後、予備サイト調査はフィージビリティ·スタディに行われる。        総建設費、安全性などを評価した後に、サイトが決定され、その後、詳細な調査と公的な環境調査が実施される。 Site Determination Plot Plan Study Survey Items, Scope, Method Geological:Bedrock/ Plant Design Parameter Environmental Survey Land, Marine, Atmospheric & Social environment 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.

18 Requirement for NPP Siting
Stage of Planning Requirement for NPP Siting Nuclear 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. In order to assess the adequacy of the site from the view point of safety in the safety examination, there is the nuclear reactor site evaluation guideline determined by Nuclear Safety Commission. Considering the reactor accident, the following site conditions are required in principle. - There have not been any events which induce (occur) large accident, and no such event is expected to occur in 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. 安全審査における安全性の観点からサイトの妥当性を評価するためには、原子力安全委員会によって決定された原子炉立地評価の為の指針があります。      原子炉事故は、どこに設置しようと起こさなように設計、建設、運用を行うのは当然ですが、公衆の安全を確保する為に、万一の事故に備え、原則的に次のような立地条件が必要である。 1.大きな事故の誘因となるような事象が過去においてなかったことはもちろんであるが,将来においてもあるとは考えられないこと,また,災害を拡大するような事象も少ないこと。 2.原子炉は,その安全防護施設との関連において十分に公衆から離れていること。 3.原子炉の敷地は,その周辺も含め,必要に応じ公衆に対して適切な措置を講じうる環境にあること。 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.

19 Site Selection ( Accompanying events of earthquake )
Stage of Planning Site Selection ( Accompanying events of earthquake ) Regulatory guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities (Sep.19,2006 NSC) Consideration of the accompanying events of earthquake - inclined planes around Facilities (stability on slide) - tsunami (run-up/down) As an example that “There have also been very few events which expand disaster.”, this side explains about the accompanying events of earthquake. In Japan, we have to consider impact of the inclined planes around facilities and tsunami, as well as the impact of earthquake itself. We simulate the maximum and minimum level of the wave originated by earthquake and confirm that there is not impact on the safety of the plant. Also we calculate the stability of the inclined plates near the plant in case of the largest earthquake, and confirm that there is not impact on the safety of the plant. 日本では、地震自体の影響のみならず,原子炉周辺斜面の安定性や津波の影響を考慮する必要があります。     我々は、地震によって起きる津波の最大値と最小レベルを想定し、プラントの安全性への影響がないことを確認します。     また、最大の地震波で発電所近傍の斜面の安定性を計算し、プラントの安全性に影響がないことを確認します。 Reactor Building 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.

20 Safety Examination[Site Evaluation Guidelines]
Preparation for Construction Stage of Planning Safety Examination[Site Evaluation Guidelines] <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 Collective doses; 20,000man-Sv or less Adults thyroid exposure doses; 3Sv or less Accidents Whole body exposure doses; 0.25Sv or less Hypothetical Infants thyroid exposure doses; 1.5Sv or less accidents Major Residential Area The area where radiation hazard may occur if people stayed in the area continuously in case of a major accident. Power Station Non-residential Area High Population Area Low Population Zone (Power Station Site) In the safety examination for the reactor installation, we have to demonstrate that the site has a large area, sufficient to assure the safety of the public near the plant, under accidental conditions. In Japan, we suppose two categories of large reactor accidents for site evaluation, a major accident and hypothetical accident. The major accident(重大事故) is the accidents which may occur in the worst case from technical point of view. The hypothetical accident(仮想事故) is the accidents exceeding major accidents which may not occur from technical point of view. Around the reactor facilities, non-residential area and low population zone is required to minimize the environmental impact of such accidents and to protect the public from radiation disasters. 安全審査-原子炉立地審査指針- 原子炉設備の安全審査において,不測の事態における周辺住民の安全を確保するために十分な敷地の広さがあることを説明しなければなりません。 日本では,立地評価のために,重大事故と仮想事故の2つの原子力事故を想定しています。 本指針の基本的な目標は、 敷地周辺の事象,原子炉の特性,安全防護施設等を考慮し, 重大事故の発生を仮定しても,周辺の公衆に放射線障害を与えないこと。 さらに,重大事故を超えるような仮想事故(例えば,重大事故を想定する際には効果を期待した安全防護施設のうちのいくつかが動作しないと仮想し,それに相当する放射性物質の放散を仮想するもの)の発生を仮想しても,周辺の公衆に著しい放射線災害を与えないこと。 【重大事故】技術的見地からみて、最悪の場合には起こるかもしれないと考えられる事故 【仮想事故】技術的見地からは起こるとは考えられない事故 原子炉敷地は人口密集地帯からある距離だけ離れている(外国の例:例えば2万人Sv) The area where appropriate measures can be taken to project the public from radiation in case of a hypothetical accident. 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.) 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.

21 Requirement for NPP Siting
Stage of Planning Requirement for NPP Siting A large volume of condenser cooling water Required Cooling Water Flow : 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. As a condition for the power generation, the site must be able to intake and discharge a large volume of condenser cooling sea water. For example, a 1,100MW class nuclear power plant requires cooling water at ton/sec. As the cooling water, seawater, river water of large rivers or lake water is normally used. Since there are few large rivers in Japan, nuclear power plants are all located along the sea, and use seawater for condenser cooling. In foreign countries, there are many plants which take the cooling water from rivers or lakes. 原子力発電所立地について、復水器の熱を除去するために大量の水を取水・放水することができなければなりません。 これは、原子力発電所の熱効率が、最新の火力発電所の熱効率よりも低いためです。 1,100 MW級の原子炉の場合には、70~80ton/secの冷却水を必要とします。通常は大河川や湖水,海水を使用しています。 大きな河川がほとんどない日本では、原子力発電所はすべての海沿いに位置し、冷却水として海水を使用しています。 外国では、河川や湖から冷却水を取る原子力発電所が多くあります。 火力発電所の熱効率 約40%前後 液化天然ガス:コンバインドサイクルで約61% APWR:約34%程度 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.

22 Requirement for NPP Siting
Stage of Planning Requirement for NPP Siting 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. As you know, we have many earthquakes in Japan, so the NPP sites have solid bedrocks(固い岩盤). Because the reactor building contains heavy equipment such as the reactor vessel, reactor containment, steam generators and radiation shield concrete, the dead load on the building foundation becomes very heavy. Further, the support structures of the above equipment must be designed to be very solid and have an enough seismic margin. Accordingly, the reactor building, structures and equipment which are important for plant safety are erected(直立する) directly on a solid bedrock or be supported by an artificial bedrock, to suppress(抑制する) the amplification of vibration in case of earthquakes Hence it is desirable(望ましい) to select a site at which such solid bedrock is found at a relatively shallow(浅い) level from the ground. In Japan, it is a common practice to erect the plant on the ground made about two million years ago. ご存知のように、日本では多くの地震があり、原発は固い岩盤の上に建設する(固い岩盤)      原子炉建屋は、原子炉容器、原子炉格納容器、蒸気発生器などの機器や放射線遮蔽コンクリートが含まれているため、建物の基礎の上に死負荷は非常に大きくなります。      また、上記の機器の支持構造は非常に強固で、十分な耐震余裕を持つように設計されなければならない。したがって、原子炉建屋、安全上重要な構造物および機器は、プラントの安全性のため、直接固い岩盤上または人工岩盤によって、サポートされていることにより、地震の場合の振動の増幅を抑制されている。      したがって、このような固い岩盤が、地面から比較的浅いレベルで発見されているサイトを選択することが望ましい。     日本では、約200万年前に生成された地盤に、建設することが一般的な方法です。 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.

23 Site Selection(Site Condition)
Stage of Planning Site Selection(Site Condition) 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. The site must have an easy access to water for power plant services. Fresh water is used in nuclear power plants as;  - make-up water for reactor system - make-up water for house-boilers - water for washing insulators - water for system flushing. As the large amount of water is recycled in nuclear power plants, the amount of make-up water is small. It is about several hundred to one thousand tons per day for a 1,000 MW unit. The site must provide an easy access to water sources for such services. In Japan, fresh water is taken from a river near the power plant, or demineralization(脱塩:purring water wit salt ) units supply fresh water. サイトには、発電所に給水するための淡水(純水)を容易に確保できる必要があります。       純水は、以下のような原子力発電所での設備に使用される;   - 原子炉システムのための補給水      - 所内ボイラーの補給水      - 絶縁体の洗浄水      - 系統の洗浄水。       大量の水を原子力発電所で再利用することにより、補給水の量を削減できる。       それは、1,000 MWのユニットは、一日につき千数百トン程度である。サイトではこのような淡水源への容易なアクセスが必要です。       日本では、プラント近傍の川から取水し、脱塩した水(純水)を供給しています。 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.

24 Site Selection(Site Condition)
Stage of Planning Site Selection(Site Condition) Convenience for transportation of heavy components and a large temporary area for the construction work Unloading facilities for heavy components near the site. Transportation of spent fuel casks (about 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 : 13-17×104 (m2) Twin unit : 18-29×104 (m2) MW ~ 1,500MW class) Reactor Vessel of Tsuruga-2 (320ton) Also the site must be convenient for transportation of heavy components, and must have a large temporary area during construction. After starting the commercial operation, it is necessary to transport spent fuels contained in heavy weight casks (about tons) to the reprocessing plant. For these purpose, unloading facilities for heavy components are usually provided near the site. They are used for transportation of heavy component at the construction stage, such as the reactor vessel, steam generators, main transformers and generators. Furthermore, temporary area is needed for locating the contractor's temporary building, storage, machinery shop, etc. during construction. また、サイト内は、重機器の輸送のために利便性がなければならず、建設工事中に大規模な仮設用地を持っている必要があります。     再処理工場が商業運転を開始した後、使用済燃料をキャスク(約70 -100トン)で輸送することが必要である。     これらの目的のために、重機器の荷揚げ施設は通常、サイトの近傍に設けられている。これらは、原子炉容器、蒸気発生器、主変圧器、発電機として、供用段階での重量物輸送に使用されています。       さらに、仮設用地は、建設中に請負業者の仮設建物、倉庫、機械工作場等の場所を提供するのに必要である。 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.

25 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) After selecting the site, the utility starts environmental survey and its assessment to confirm that the site is suitable for NPP siting. After finishing the utility’s survey and assessment, the Government implements the environmental examination by three steps. The first one is for methodology, the second one is for preliminary report, and the third one is for the final report. On each stage, public opinion is collected from the inhabitants. サイト選定した後、電力会社は、サイトは原子力発電所の立地に適していることを確認するために、環境調査及び環境影響評価を実施します。     電力会社の調査と環境影響評価を終えた後、政府は、次の3つの手順で環境審査を実施します。最初のものは方法論のためであり、もう一つは予備的な報告のためであり、三つ目は、最終報告書のためのものです。各ステージでは、公衆意見が収集されます。 Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

26 Survey to Determine the Site
Stage of Planning 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 Mainly, three kinds of surveys are carried out in order to determine the site. That is topographic and geological survey (地形学及び地質学的調査), meteorological survey(気象学的調査) and Oceanographic Survey and Marine Life Survey(海洋学的調査及び海生物調査).   I will explain these surveys shortly. サイト選定の為の種々の調査は、下記の3種類について実施しています。        1.地形・地質調査(地形学及び地質学的調査)、 2.気象調査(気象学的调查) 3.海洋調査と海洋生物調査(海洋学的調査及び海生物調査)。 私はすぐにこれらの調査についてご説明します。 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.

27 Topographic and Geological Survey
Stage of Planning Topographic 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) The topography of the plant site and its surrounding area are investigated by core drilling, test pitting, aerial photogrammetric, etc. The shape, depth and strength of bedrock is investigated to confirm the adequacy of locating the important structures including the reactor building. Seismic history, geological structure and measured seismic waves are investigated to determine the seismic design inputs (for example, maximum acceleration of the foundation ground). プラントの敷地及びその周辺地域の地形は、コア掘削、試験ピット、空中写真測量等により調査される。 岩盤の形状、深さ、強度は、原子炉建屋などの重要な構造物を設置する妥当性を確認するために調査されています。       地震の歴史、地質構造と測定した地震波は、耐震設計の入力(例えば、基礎地盤の最大加速度)を決定するために調査されている。 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.

28 Topographic and Geological Survey - Geological Survey [Example] -
Stage of Planning Topographic and Geological Survey - Geological Survey [Example] -    These photos shows the geological survey for Tsuruga units 3&4. To investigate the geological property(特性、性質) of the ground, core drilling on the land and sea was performed. Also, the exploratory tunnel was made at the site for the detailed geological investigation. Through these investigations, the shape, depth and strength of bedrock is investigated. これらの写真は、敦賀3&4号機の地質調査状況を示しています。 地盤の地質学的特性(特性、性質)を調査するために、陸と海の上でコアの掘削を行った。また、試掘坑は詳細な地質調査のためのサイトで行われた。 これらの調査を通じて、形状、深さ、岩盤の強度を調べた。 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.

29 Meteorological Survey
Stage of Planning Meteorological 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 As for the meteorological survey, wind velocity, temperature, moisture, rain precipitation, salinity, etc. are investigated. The results are reflected in the building and equipment design conditions of the plant. Wind direction and velocity distributions, vertical distribution of temperature, etc. are also investigated. The results of these investigation is used to evaluate the effects of released gaseous radioactive wastes under normal and accidental conditions on the public people, as well as to evaluate the adequacy of the stack height. 気象調査としては、風速、温度、湿度、雨量、塩分などが調査されている。 結果は、プラントの建屋や設備の設計条件に反映されます。   風向と速度分布、温度等の鉛直分布についても調査されています。 これらの調査の結果は、公共の人々に正常かつ偶発的条件で、放出された気体放射性廃棄物の影響を評価するだけでなく、スタックの高さの妥当性を評価するためにも使用されます。 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.

30 Meteorological Survey [Example]
Stage of Planning Meteorological Survey [Example]    These photos shows the meteorological survey. Air quality, such as wind velocity, temperature, moisture, rain precipitation, salinity, etc. are measured by this facility.(左上) The ground meteorological condition, such as wind direction and velocity distributions, are measured by these facilities.(左下)   Vertical distribution of temperature is measured by using this type of balloon.(右上:レーウィンゾンデ) Wind vector of upper-air is measured by this equipment using ultra-sonic.(左下) これらの写真は、気象調査を示しています。         風速、温度、湿度、雨量、塩分濃度などの大気の性質を測定しました(左上) 風向と風速分布などの地上気象条件は、これらの施設で測定しています(左下) 気温の鉛直分布は、このタイプのバルーンを用いて測定されます(右上:レーウィンゾンデ)。 上空の風向風速は、超音波を使用した装置(ドップラーソーダ式風向風速計)によって測定されます(左下) 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.

31 Oceanographic Survey and Marine Life Survey
Stage of Planning Oceanographic 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   Wave height, wave direction, tidal level, depth of water, drift sand, tidal current, and marine life are investigated to use in the design of the intake and discharge facilities of the condenser cooling sea water, and to assess the impacts of the diffusion of thermal discharge on marine life. 海洋調査では、波高、波向(なみむき)、潮位、水深、漂砂、潮流、海洋生物が調査されます。 ・復水器冷却海水の取水及び排水設備での設計に使用され ・海洋生物における温排水拡散の影響を評価する。 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.

32 Oceanographic Survey and Marine Life Survey [Example]
Stage of Planning Oceanographic Survey and Marine Life Survey [Example] These photos shows the oceanographic survey and marine life survey. これらの写真は、海洋調査と海洋生物の調査を示しています。 water temperature,salt content 水温・塩分濃度測定(左上) tidal current 潮流調査(左下) bottom sampler 海底土砂調査(右上) wave direction,flow velocity波の方向・流速調査(右下) 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.

33 Reduction of Diffusion Area of Thermal Effluent
Deep layer discharge Surface layer discharge 1℃ up  2℃ up  3℃ up  After several mitigation measures had been taken into the cooling water system, to predict thermal plume diffusions resulting from effluent discharges were made with the method of hydraulics model experiment and mathematical model simulation. In this figure, blue isotherm lines indicate temperature rise when the plant adopts the deep layer discharge and red lines indicate the case of surface buoyant discharge The gross area where surface water temperature rise will be decreased with the deep layer discharge method of thermal effluent, in comparison with surface layer discharge method. 復水器冷却水系に対するミティゲーション(緩和)措置を行なった後の温排水の拡散範囲を,水理模型実験及び数値シミュレーション手法によって予測した。 この図では水中放水によって上昇する水温の等温線を青色で,表層放水によって上昇する水温の等温線を赤色で示している。温排水の水中放水を行うことによって,表層放水を行なったときよりも海面の水温上昇範囲が狭まったことを示している。 防波堤内の取水口から約214m3で取水(3,4号機合計) 防波堤の水面下約10mの位置から約4m/sの流速で水中放水 取水放水温度差7℃以下 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

34 An Image of Nuclear Power Station after EIA Review
Native tree planting 環境影響評価方法書に対する知事意見対応例 「埋立工事等の敷地造成による地形の改変を最大限抑制すること」の対応として, 右下の準備書のイメージ図から改変面積を縮小,自然の景観に溶け込み目立たないような色合いの色彩計画とした。 埋め立て面積は25万平方メートルから20万平方メートルに縮小した。 背後斜面の緑化計画についても工法を更に工夫することで,高木の植栽等を行うこととした。 Minimize reclamation area An Image of Nuclear Power Station at Basic Plan Stage

35 Environmental Impact Assessment
Stage of Planning Environmental 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. This slide summarizes the environmental 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 Law for Environmental Impact Assessment and Electricity Utilities Industry Law. EIAL:環境影響評価法、EUIL:電気事業法 In accordance with Law for Environmental Impact Assessment and Electricity Utilities Industry Law, an environmental impact report is submitted from the utility to Ministry of Economy, Trade and Industry 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 in the process of environmental examination. このスライドは、環境影響評価をまとめたものです。 電力会社は、選択したサイトの自然·社会環境を調査し、環境影響評価法及び電気事業法の両方の法律で必要とされる建設・供用期間中に環境に与える影響の予測と評価を行います。 - 環境影響評価法及び電気事業法等に関する法律に基づき、環境影響評価書は、電力会社から、経済産業省及び地方自治体に提出されています。報告書はまた、地域住民によってレビューされており、それらの意見が調査されています。経済産業省では、環境審査の過程で、地元の知事や地域住民からの意見を考慮して報告書を審査します。 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.

36 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) 一次公開ヒアリング 環境影響評価の間に開かれる During the Environmental Examination, the 1st public hearing is held. 環境審査の間に、第一公開ヒアリングが開催されます。 Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

37 - Necessity and outline of the construction plan
Stage of Planning 1st 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 During the environmental examination, METI holds the 1st Public hearing to achieve a deeper understanding of local communities concerning the necessity and outline of the construction plan, environmental impacts of the nuclear power plant installation and the basic policy of safety measures and environmental protection of the planned nuclear power plant. This is a special procedure for nuclear power plant construction, based on the guideline of METI. The public opinions are reflected in the administrative process. 環境審査の期間に、経済産業省では、増設計画の概要と必要性、安全対策、環境対策について、地域社会のより深い理解を達成するために、第一次公聴会を実施しています。 これは,第1次公開ヒアリングの写真です。 2002年2月に経済産業省が開催し,800名以上の方々にお集まりいただきました。 事前に意見公募された約20名の市民から質問やコメントがあり、当社から回答するという内容で進められました。 意見としては,安全性,電力需要,核燃料サイクル,原子力防災,地域振興など幅広い分野にわたりました。 これらに対して,当社としてもできる限り分かりやすい,丁寧な説明に務め, 県をはじめ,関係自治体からの評価をいただきました。 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.

38 Direct Dialogues with Residents
Stage of Planning Direct Dialogues with Residents (Home visits) In the process of Tsuruga units 3&4 project, the JAPC employees visited all households in Tsuruga city, about 26,000 houses, for direct dialogue. It was necessary for us JAPC to directly communicate with citizens in order to obtain the agreement of the local community. 訪問対話活動について 当社社員による敦賀市全世帯訪問対話活動: この活動は、 1995年の阪神淡路大震災後に地元議員や地元有力者に対して行われた。その後も、数年かけて敦賀市内26000世帯全ての世帯に広げて訪問しました。活動は、2002年と2003年に特に強化されました。 関心を示してもらえるように,発電所の状況やその他の話題を含めたパンフレットを作成しました。 Visiting all 26,000 households in Tsuruga 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.

39 Meetings with the Residents
Stage of Planning Meetings with the Residents Also JAPC held meetings to explain the necessity of the construction plan of Tsuruga units 3&4, and gathered about 5,000 people in total. People's opinions and questions were collected and analyzed to utilize in the future communication activities. (Non-governmental activity) 当社が主催するご意見をお聞きする会・ふれあい講演会について 合計で2600のあまりの住民の方が集まりました。 住民の意見や質問は,それぞれの自治体の中で最も関心があるものは何かを分析しました。 At echizen At takahama 5000 participants 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.

40 Newspaper Advertisements TV Commercials
Stage of Planning Newspaper Advertisements TV Commercials The JAPC also conducted advertising campaigns in newspapers and TV programs in Fukui Prefecture. JAPCまた、福井県の新聞やテレビ番組での広告キャンペーンを実施しました。

41 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) 地元の建設への同意 If the utility can obtain the local governor’s consent( agreement:同意), the utility’s Construction project is included into the electric energy development program of the government. It is the official start of the construction project in Japan and the project can step to the next stage “preparation of construction”. 地元の建設への同意が得られたら、国の電源開発基本計画に組入れられます。  これで、日本において公式に建設プロジェクトが開始されることなり、プロジェクトは次の段階“建設の準備”段階に入ります。 Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

42 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) 原子炉設置許可申請:submission of the application for reactor installation license At the beginning of the preparation of construction, the Utility submits the application for reactor installation license. In this procedure, the safety examination by government is carried out. during this safety examination, the second public hearing is held by the Nuclear Safety Commission. 工事認可申請: submission of the application for construction permit After the reactor installation license was obtained, the utility submits the application for construction permit. In this process, more detailed design is examined. 原子炉設置許可申請:原子炉の設置許可の申請書の提出      建設の準備の開始時に、ユーティリティーは、原子炉設置許可の申請を提出します。この手順では、政府による安全審査が行われる。      この安全審査中に、第二次公聴会は、原子力安全委員会が開催します。 工事計画認可申請:建設許可のための申請書の提出      原子炉設置許可を取得した後、電力会社は、建設許可申請を提出します。このプロセスでは、より詳細な設計が審査されます。 Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

43 Procedure of Reactor Installation License from NSC Viewpoint
Preparation for Construction Procedure of Reactor Installation License from NSC Viewpoint Double Check This slide shows the procedure of reactor installation license from view point of the Nuclear Safety Commission. After submission of the application for reactor installation, primary investigation by METI is carried out. After examination by METI, Nuclear Safety Commission reviews the application documents related to technical competence of the utility and adequacy of the disaster prevention measures. This process is called “Double Check”. After double check by NSC and agreement by the Minister of Education, Culture, Sports, Science and Technology, METI issues the license for reactor installation. ダブルチェック        このスライドは、原子力安全委員会の観点からの、原子炉設置許可手続きを示しています。       原子炉設置許可申請書の提出後は、経済産業省による一次調査が行われる。       経済産業省による審査を経て、原子力安全委員会が災害防止と技術的能力について、審査します。このプロセスは、 “ダブルチェック”と呼ばれています。      NSCによる ダブルチェックと、文部科学省同意後に、経済産業省は設置を許可します。 (Source:NSC Annual Report) 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.

44 Approval Criteria for Reactor Installation License
Preparation for Construction Approval Criteria for Reactor Installation License Approval Criteria 1st Examination 2nd Examination (Double check) 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. Atomic Energy Commission METI 3. The applicant has technological ability and financial position sound enough to establish reactor, and has such technical ability to operate them competently. This slide shows the approval criteria for the reactor installation license.(設置許可の許可基準) There are four criterions. The first one is that the reactor will not be used for non-peaceful purpose. The second one is that the permission will not prevent the planned development and utilization of atomic energy.(原子力開発利用計画に沿ったもの) The third one is that the applicant has technological ability and financial position sound enough to establish reactor, and has such technical ability to operate them competently.(技術的能力) The last one is that the location, structure and equipment of reactor facilities are such that they will cause no hindrance(障害) to the prevention from the hazard by reactor fuel material and by reactors. The first, second and third points are examined by METI and the Atomic Energy Commission, and the last point is examined by METI and the Nuclear Safety Commission, which is called ”safety examination”. (安全審査) このスライドでは、原子炉設置許可の許可基準を示しています 安全審査について ○平和利用  原子炉が平和の目的以外に利用されるおそれがないこと。 ○計画的遂行  許可をすることによって原子力の開発及び利用の計画的な遂行に支障を及ぼすおそれがないこと。 ○技術的能力  申請者が原子炉を設置するために必要な技術的能力と原子炉の運転を適確に遂行するに足りる技術的能力があること。 ○経理的基礎  工事に要する資金が調達可能であること ○災害防止  原子炉施設の位置、構造及び設備が核燃料物質、核燃料物質によって汚染された物又は原子炉による災害の防止上支障がないものであること。 これらが審査の対象となります。 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. Nuclear Safety Commission 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.

45 Application Document for Reactor Installation License (1)
Preparation for Construction Application Document for Reactor Installation License (1) Application Text 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 (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 設置許可申請書の本文目次概略 This slide shows the contents of the application document for reactor installation license. The main text is No.5 “location, structure and equipment”, which describes the basic safety design policy and basic design, such as location of reactor facilities, structure of reactor facilities, structure and equipment of reactor, fuel handling and storage facilities, reactor cooling system, etc. このスライドでは、原子炉設置許可の申請書類の内容を示しています。     本文の「 (5)原子炉及びその付属設備の位置、構造及び設備」では、基本的な安全設計方針及び原子炉施設の位置、原子炉施設、構造及び原子炉の機器の構造、燃料取扱及び貯蔵設備など記載しています。 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.

46 Application Document for Reactor Installation License (1)
Preparation for Construction Application Document for Reactor Installation License (1) Appendix documents (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 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 (設置許可申請書の添付書類概要) More detailed appendix documents are attached to the application. There are ten appendix documents in total. For example, chapter 6 describes about site condition, such as meteorological condition, geological condition, earthquake and social environment. The data obtained by environmental survey is put into this chapter. The chapter 8 supports the application text by describing detail of the basic safety design and its policy of reactor facilities. The chapter 9 describes the radiation protection measures and waste treatment. In this chapter, annual release of radioactive waste and public exposure is calculated to confirm that the public exposure during normal operation is low enough. The chapter 10 describes the safety analysis. Anticipated transient during operation, accidents, major accidents and hypothetical accidents are analyzed to confirm that the location and facility design is adequate from view point of disaster prevention. より詳細な付録書類が、申請書に添付されています。     合計で10章分の添付書類があります。     たとえば、第6章では、このような気象条件、地質条件​​、地震、社会環境など、サイトの状態について説明しています。環境調査によって得られたデータは、この章に記載されています。     第8章では、基本的な安全設計及び原子炉施設の方針の詳細を記載することで、申請書本文を補足しています。     第9章では、放射線防護対策や廃棄物の処理について記載します。この章では、放射性廃棄物の年間放出量と公衆被ばくを計算し、通常運転時の公衆被ばくが十分に低いことを分析しています。       第10章では、安全評価について記載しています。運転時の異常な過渡変化、事故、重大事故及び仮想事故において、設置場所や施設の設計、防災の観点から適切であることを確認される。 (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 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.

47 Law and Regulation for Construction of Nuclear Power Plants
Main Guidelines for Safety Examination for LWRs Site Evaluation Guidelines ECCS Performance Evaluation Guidelines Safety Evaluation Guidelines Meteorological Guidelines for Safety Analysis Reactivity Initiated Event Evaluation Guidelines PWR Core Thermal Design Evaluation Guidelines Dose-objectives Guidelines Dose Target Evaluation Guidelines Radioactive Material Emission Measurement Guidelines Safety Design Guidelines The application documents are investigated based on these guidelines for safety examination for LWRs determined by NSC. 設置許可申請書は、安全審査の中で、原子力安全委員会によって決定された次のガイドラインに基づいて審査されている。 Fire Protection Guidelines Seismic Design Guidelines Radiation Measurement Guidelines Priority Classification Guidelines 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.

48 Safety Examination[Site Evaluation Guidelines]
Preparation for Construction Safety Examination[Site Evaluation Guidelines] <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 Collective doses; 20,000man-Sv or less Adults thyroid exposure doses; 3Sv or less Accidents Whole body exposure doses; 0.25Sv or less Hypothetical Infants thyroid exposure doses; 1.5Sv or less accidents Major Residential Area The area where radiation hazard may occur if people stayed in the area continuously in case of a major accident. Power Station Non-residential Area High Population Area Low Population Zone (Power Station Site) (立地審査指針) For example, adequacy(妥当性) of the site is examined by the site evaluation guidelines, as I explained before. 私は前に説明したように、たとえば、サイトの妥当性(妥当性)、サイト評価ガイドラインで検証されます。 The area where appropriate measures can be taken to project the public from radiation in case of a hypothetical accident. 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.) 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.

49 Preparation for Construction
Safety Design Guidelines (1) Safety Design Examination Guideline for Power-generating LWR Facilities No Requirement Compliance to Codes & Standards Consideration of Natural Phenomena (Earthquake, Flooding, Tsunami, Wind,Snow, etc.) Consideration of External Events (Physical Protection, Airplane, etc. ) Internally Generated Missile (Pipe Break, Rotating Equipment, Explosion, Fall, etc.) Fire Protection (Prevention, Detection, Extinguish, Mitigation of damage) Environmental Conditions for Equipment Sharing Facilities (Maintain safety when facilities are shared by two or more reactors) Man-machine Interface (Proper measures to prevent operators’ errors) Reliability of Safety Facilities (Redundancy or diversity and Independency, Emergency Power Supply) Testability The safety design guidelines were established to specify the foundation for judging the validity of design in the safety examination of LWRs. They are based on IAEA’s Nuclear Safety Standard and the 10CFR50 appendix A “General Design Criteria” of US NRC.  The lessons learned from TMI accident were reflected into these guidelines in 1990.  There are 59 requirements for reactor facilities in total. The first 10 items are general requirements. I have already explained the safety guidelines as part of “outline of LWR design” January 20, so I would like to skip this guidelines 安全設計審査指針は、軽水炉の安全審査で設計の妥当性を判断するための基本を指定するために設立された。    それらは、IAEAの原子力安全基準と米国NRCの10CFR50付録“一般的な設計基準”に基づいています。 TMI事故から学んだ教訓は、1990年に、これらのガイドラインに反映されている。 指針1.準拠規格及び基準(適切な規格に基づく) 指針2.自然現象に対する設計上の考慮(適切な設計用地震力、自然現象に耐える) 指針3.外部人為事象に対する設計上の考慮 指針4.内部発生飛来物に対する設計上の考慮 指針5.火災に対する設計上の考慮 指針6.環境条件に対する設計上の考慮 指針7.共用に関する設計上の考慮 指針8.運転員操作に対する設計上の考慮 指針9.信頼性に関する設計上の考慮 指針10.試験可能性に関する設計上の考慮 最初の10項目は、原子炉施設全般的な必要条件です。 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.

50 Preparation for Construction
Safety Design Guidelines (2) Safety Design Examination Guideline for Power-generating LWR Facilities No Requirement Reactor & Reactor Shutdown System (Fuel Integrity, One Rod Stack Margin, Diversity of Shutdown System, etc.) Reactor Coolant System (Integrity of RCPB, RCPB Leak Detection, Reactor Make-up, Residual Heat Removal, Emergency Core Cooling, Heat sink, Station Black Out, etc.) Reactor Containment System (Integrity of Containment Boundary, Isolation Valves, Containment Heat Removal, In-containment Atmosphere Control, etc.) Safety Protection System (Redundancy and Independency, Fail-safe, Separation from Normal Control System, etc.) Control room & Technical Support Center (Plant Monitoring & Control Function, Remote Shutdown from other place, Comfortableness of control room, Technical Support Center, Communication Equipment, etc.) Skip 11-18 原子炉及び原子炉停止系(燃料健全性、ワンロッドスタックマージン、シャットダウンシステムの多様性など) 19-27 原子炉冷却系(RCPBの整合性、RCPBリーク検出、原子炉メイクアップ、残留熱除去、緊急炉心冷却、ヒートシンク、ステーションブラックアウトなど) 28-33 原子炉格納容器(封じ込め境界の整合性、隔離弁、格納容器熱除去は、In-封じ込め大気制御等) 34-40 安全保護系(ノーマル制御システムから冗長性と独立性、フェールセーフ、分離等) 41-46 制御室及び緊急時施設(プラント監視·制御機能、他の場所からのリモートシャットダウン、制御室の快適性、テクニカル·サポート·センター、通信機器等) (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.

51 Preparation for Construction
Safety Design Guidelines (3) Safety Design Examination Guideline for Power-generating LWR Facilities No Requirement Control System & Electric System Fuel Storage System & Fuel Handling System Radioactive Waste Treatment System Radiation Protection & Control Skip 47-48 計測制御系及び電気系統 49-51 燃料取扱系(貯蔵) 52-55 放射性廃棄物処理施設 56-59 放射線管理 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.

52 Preparation for Construction Natural Radiation 2.4mSv/y
Dose-objective Guidelines Guideline 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 (About 1/50 of annual exposure from natural radiation sources) Target for dose reduction effort of Utilities 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)   In Japan, the annual dose of the public near the NPP due to gaseous and liquid radioactive waste is kept under 0.05mSv/y, that is about 1/50 of annual exposure from natural radiation sources. Although the dose limit for public required by law is 1mSv/y, the Dose-objective Guidelines describe the dose objective of 0.05mSv/y from the view point of “ as low as reasonably achievable”. (ALARA) 通常運転時における環境への気体・液体放射性物質の放出に伴う周辺公衆の受ける線量当量を低く保つための努力目標として、施設周辺の公衆の受ける線量当量についての目標値(以下「線量目標値」という。)を実効線量当量で自然放射線源からの年間被曝量の1/50程度である年間50マイクロシーベルトとすることが定められています。 法律で義務付けられている公衆のための線量限度は、1mSv/yであるが、発電用軽水型原子炉施設周辺の線量目標値に関する指針では、“被曝線量は容易に達成できる限り低く保つことが望ましいとするいわゆる「 as low as reasonably achievable 」”の考え方に立って年間50マイクロシーベルトの線量目標があります。 Natural Radiation 2.4mSv/y ≦0.05mSv/y 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.

53 Preparation for Construction
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. In the period of the safety examination by Nuclear Safety Commission (NSC), NSC holds the 2nd public hearing to consider the opinions of local communities on the safety examination of the plant. In this event, METI explains how they examined the safety of the planned NPP, and answers to the questionnaires on safety aspect from the inhabitants. 原子力安全委員会(NSC)による安全審査中に、NSCは、プラントの安全審査に地域社会の意見を考慮する第二次公聴会を開催します。 この公開ヒアリングの制度は、地元住民等に対する施設内容などの説明とそれに対する意見を聴くための公開ヒアリング及びその結果を当該原子力施設の設置計画に反映するための制度  です。 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.

54 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) After the 2nd public hearing and safety examination, a reactor installation license is issued to the utility. Then utility submits the next application for construction permit. In this process, more detailed design is examined such as structural integrity and seismic design of each component. As I mentioned briefly before. 第二次公聴会と安全審査後、原子炉設置許可は、電力会社に発行されます。      その後、電力会社は建設許可申請(工事計画認可申請)を提出する。 Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

55 Examination of Detailed Design
Preparation for Construction Examination 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. The utility is required by EUIL (Electricity Utilities Industry Law) to obtain an approval for detailed design and the construction plan of the plant from METI, before fabrication and construction. This is called “Approval of Construction Plan” or “Construction Permit” (建設許可) 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. In this process, more detailed design is examined such as structural integrity and seismic design of each component. 電力会社は、EUIL(電気事業法)により、電気工作物変更許可及び原子炉設置許可を受けた後、工事計画認可申請を行います。 この工事計画認可申請は、機器の製作・据付などの本格的な建設工事を開始するために原子力発電所の詳細な設計の内容について認可を受けることです。    これらの申請は、通常、サイトの各設備と建設工程に従って、分割申請します。       一般的に、第1回の申請は、原子炉建屋と原子炉格納容器の設置工事に関して、申請がなされます。      このプロセスでは、各々の設備ごとに、構造設計や耐震設計と通じて、より詳細な設計が審査されます。 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.

56 Construction Permit (Approval of Construction Plan)
Preparation for Construction Construction Permit (Approval of Construction Plan) Utility Application for approval of construction plan Instructions Explanations JNES(ex-NUPEC) (Audit Analysis) METI (Examinations) Advisory Committee on Technical Matters Comments Experts Approval of Construction (Construction Permit) This slide shows the flow of the construction permit. After application for approval of construction plan by the utility, METI examines it and JNES (The Nuclear Energy Safety Organization) carry out the audit analysis for the applicant’s analysis reports. Also the advisory committee checks important safety issues. After these examinations, the approval of construction, that is construction permit, is issued by METI. Then the utility can start the construction work. このスライドは、工事計画認可の流れを示しています。 電力が工事計画認可申請をした後、経済産業省では、それと原子力安全基盤機構は、(原子力安全基盤機構)、申請者の解析結果の監査分析を行う。また、諮問委員会は、重要な安全性の問題をチェックします。       これらのチェックの後、工事認可が、経済産業省が発行されます。 その後、電力会社は、建設工事を開始することができます。 Utility Start of Construction 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.

57 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) Then we can proceed to the next step “construction”. Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

58 Major Activities in the construction of NPP
Stage of Construction Major Activities in the construction of NPP - 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 This slide shows the major activities in NPP construction. - excavation of building foundation reinforced (補強) concrete works of reactor building’s base mat primary containment vessel works other building works installation of heavy components (reactor vessel, etc.) installation of piping and equipment installation of core internals cold / hot function test fuel loading startup test このスライドは、原子力発電所建設の主要な活動を示しています。   - 建物の基礎掘削  原子炉建屋の基礎マットの鉄筋コンクリート工事  格納容器構築  他建屋建築  重機器(原子炉容器等)の設置  配管や機器の据付  炉内構造物の据付  冷態/温態機能テスト  燃料装荷  起動試験 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.

59 Flow of Construction Works (Example of PWR Plant)
Stage of Construction Flow of Construction Works (Example of PWR Plant) Phase Ⅰ Phase Ⅱ Phase Ⅲ Phase Ⅳ ▽ Fuel Loading ▽ Start of Construction Start of Commercial Operation▽ Preparatory Work (Site Preparation) This slide shows the typical flow of NPP construction work. The construction work is roughly divided into four phases. In phase 1, preparatory work of the site and excavation for building basement are carried out. In phase 2, the base mat for the reactor building is assembled and then the reactor containment vessel is constructed. Other buildings, such as the auxiliary building and turbine building is constructed in parallel. In phase 3, heavy components, such as reactor vessel, steam generator, and other equipments are installed in the building. After installation of equipments, system flushing and leak test are carried out. In phase 4, cold function tests and hot function tests are carried out in case of PWR plants. After these tests, Fuels are loaded in the core to prepare for the commercial operation start. このスライドでは、原子力発電所の建設工事の一般的な流れを示しています。    建設工事は、大きく4つのフェーズに分かれています。     フェーズ1では、建物の地下のためのサイトと掘削の準備作業が行われている。     フェーズ2では、原子炉建屋のベースマットは、組み立てされ、その後、原子炉格納容器が構築されます。このような補助建屋とタービン建屋のような他の建物は、並行して構築されます。     フェーズ3では、このような原子炉容器、蒸気発生器、その他の機器など建物内に設置されています。機器の据付後、システムのフラッシングとリークテストが行われる。     フェーズ4は、冷能機能検査と温態機能検査はPWRプラントの場合に行われている。これらのテストの後、燃料が商業運転開始に備え、燃料装荷されます。 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.

60 Procedural Steps for NPP Construction
Utilities Government Local Community Site Selection Environmental Examination 1st Public Hearing Opinions of inhabitants Environmental Survey Planning Environmental Assessment Advisory Committee for Resource & Energy Local Governor’s Consent Decision on basic program of power development Application for Reactor Installation License Safety Examination 2nd Public Hearing Opinions of inhabitants Preparation for Construction Reactor Installation License Application for Construction Plan Construction Permit (approval of Construction Plan) In the construction stage, many tests and inspections are carried out, such as pre-service inspections welding inspections and fuel inspection. Also the utility establish an operational safety program for the reactor, which describes the rules for reactor operation to ensure safety. The utility applies it to METI and obtains approval for it. If the utility offends against the operational safety program, it is ordered to shutdown the reactor by METI. In the worst case, the reactor installation license is withdrawn by METI. 建設段階では、多くの試験及び検査は、使用前検査、溶接検査、燃料検査として実施されています。     また、電力会社は安全を確保するために、原子炉の運転に関する規則について定めた保安規定認可申請をし、認可を取得します。     電力会社は、保安規定に違反する場合には、経済産業省による原子炉をシャットダウンするよう命じている。最悪の場合、原子炉設置許可は、経済産業省により取り消しされる可能性があります。 Start of Construction Pre-service Inspection Welding Inspection Fuel Inspection Construction Application for Operational Safety Program Approval of Operational Safety Program Start of Operation Periodical Inspection Safety Inspection Periodical Safety Review Operation 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

61 Pre-service Inspection
Stage of Construction Pre-service Inspection - 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. - In Japan, The Electricity Utilities Industry Law 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 established by METI, and that the plant has adequate performance as prescribed in the construction plan and other licensing documents. - 日本では、電気事業法により、製造·施工の各段階で経済産業省による使用前検査が必要です。 - 経済産業省では、電力会社は、工事計画、経済産業省で定める技術基準を遵守して建設工事を実施してきたこと、及びプラントが工事計画とその他の文書に定めた十分な性能を持っていることを確認します 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.

62 Pre-Service Inspection
Stage of Construction Pre-Service Inspection TEST ITEM 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 Pre-service inspection by METI is categorized to 5 stages. The Stage (a) Tests are carried out when the situation allows to test the structure, strength, or leakage of each facilities. The Stage (b) Tests are carried out when the installation of the lower part of the steam turbine cabin or main unit of the auxiliary boiler is completed. The Stage (c) Tests are carried out when the situation allows to load fuels. The Stage (d) Tests are carried out when the reactor reaches criticality. The Stage (e) Tests are carried out when all the works stated in the construction plan is completed. There are two criterions for the pre-service inspections The first one is accordance with the construction plan, and the second one is not such that facilities do not conform to the technological standards 経済産業省による使用前検査を5段階に分類されます。 ステージ(a)構造、強度、または漏れのテストを行うことができる状況になったとき ステージ(b)蒸気タービン車室下半部の据付が完了した時及び補助ボイラ本体組立が完了したときのやメインユニットの下部の取り付けが完了した時点での試験が行われる。 ステージ(c)燃料を搬入できる状態になったとき ステージ(d)原子炉が臨界反応操作ができる状態になったとき。 ステージ(e)工事計画に規定されたすべての工事が完了したときにテストが行われている。     使用前検査には、2つのクライテリアがあります 最初のものは、工事計画に従っていること もう一つは、設備が技術基準に適合しないものでないこと。 CRITERIA (1) Accordance with the construction plan (2) Not such that facilities do not conform to the technological standards 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.

63 Pre-Service Inspection
Stage of Construction Pre-Service Inspection Major Regulatory Inspections in NPP Construction Quality Management Welding Inspection Fuel Inspection Pre-service inspection Stage (a) Stage (a),(b) Stage (c) Stage (d),(e) Stage(e) Factory Inspection Installation Inspection Equipment unit examination System Function test Heat up test On power test   This slide shows the position of the pre-service inspection in the major regulatory inspections in NPP construction. Quality Management is required in all of the major activities of the utility and manufactures. Welding Inspection is carried out at the stage of the Factory and Installation. Fuel Inspection is carried out at the stage of the Factory and heat up. Pre-service Inspections are carried out at the each activities of construction. このスライドは、原子力発電所建設の使用前検査の時期を示しています。       品質管理は、電力、メーカの主要な活動のすべてに要求されます。       溶接検査は、工場、インストールの段階で行われる。      燃料検査は、工場とヒートアップ段階で行われる。       使用前検査は、建設の各段階で行っています。 Major Activities of Utility & Manufacturer CFT HFT Fuel Loading Factory Site

64 Pre-Service Inspection
Stage of Construction Pre-Service Inspection (c) (d) Pressurizer Safety Valve Function Test (FT) RCS Pressure/Level Control System FT Chemical Volume Control System FT Safety Injection System FT Residual Heat Removal System FT Component Cooling Water System FT Main Steam Safety Valve FT Main Steam Relief Valve FT Safety Protection System FT Core Instrumentation System FT Reactor Make-up System FT Fuel Handling System FT SFP Purification & Cooling System FT Radiation Monitoring Facility FT HVAC System FT Radioactive Waste Treatment System FT Containment Spray System FT Containment Isolation Valve FT Reactor Containment FT Main Feedwater System FT Auxiliary Feedwater System FT Emergency Power Supply System FT Total Facility Inspection FT Fuel Loading Test Control Rod Drive Mechanism Test Pressurizer Spray Test Control Rod Control Range Confirmation Test Total Interlock Test Moderator Temperature Efficiency Measurement Minimum Shutdown Margin Boron Concentration Measurement Critical Boron Concentration Measurement (e) Load Reduction Test Plant Trip Test Loss of Offsite Power Test Generator Load Loss Test Total Load Test This slide shows the major items of pre-service inspection for PWR Plants. Refer to P58 As the stage C inspection, function tests for each systems, such as Chemical Volume Control System, Safety Injection System and Residual Heat Removal System, are carried out. As the stage D inspections, inspections after fuel loading, such as Control Rod Drive Mechanism Test, Pressurizer Spray Test, Total Interlock Test are carried out. As the stage E inspections, inspections of total plant performance, such as Load Reduction Test, Plant Trip Test, are carried out. After passing all of the pre-service inspections, The METI permits the commercial operation start. このスライドは、PWRプラントのための使用前検査の主な項目を示しています。 ステージC検査では、検査、そのような化学体積制御系、安全注入システムおよび残留熱除去系などの各システム用の機能テストが行われている。 ステージD検査では、燃料装荷後の検査、制御棒駆動機構、加圧器スプレイ、全インターロック試験のような検査を実施。 ステージE検査では、負荷低減、プラントトリップテストなどのプラント全体性能検査が行われているとして。     使用前検査のすべてに合格した後、経済産業省は、商業運転の開始を許可します。 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.

65 Operational Safety Program
Stage of Construction Operational Safety Program 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. Prior to the startup of the reactor, the utility, pursuant to (に従って) “the Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors”, establishes the “operational safety program” (保安規定) to adequately prevent accidents that may arise from the operation of the nuclear power plant. It describes the organization, quality management, role of reactor chief engineer, safety education, rules for reactor operation, fuel management, radiation protection, maintenance, radioactive waste treatment, etc. The operational safety program must be authorized by METI. 原子炉の起動の前に、電力会社は、「核原料物質、核燃料物質及び原子炉の規制に関する法律”に基づいて、原子炉の災害の未然に防ぐための必要な措置を“保安規定”を定めている。 それは、組織、品質管理、原子炉主任技術者の役割は、安全教育、原子炉の運転のための規則、燃料管理、放射線防護、メンテナンス、放射性廃棄物処理などを記述している。        保安規定は、経済産業省によって認可されなければならない。 * The Law on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors 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.

66 Design and Construction Schedule of NPP in JAPAN
Example 1 2 3 4 5 6 7 8 9 10 11 12 13 Environ. Survey Decision of site and start construction (Electric Power Development Coordination Council) Environ. Scope Assess. CFT HFT Fuel Loading Commercial Environ.Assess. Operation Safety Examination Construction Permit #1 #2 #6 to 8 Basic Site Plot Plan / GA Study Examination by METI & NSC/AEC Pre-Service inspection NSSS/BOP basic system design Bed Lock Inspection Welding Safety Management inspection Safety Analysis & Safety Document R/B,C/B,A/B Structure Case Study R/B,A/B Seismic Analysis & Design Detail Plot Plan / GA design Detailed Design of NSSS / BOP system / equipment Documents (structure design, seismic Integrity, Quality Management, etc.) material properties, welding, fabrication, installation and functional test, etc. material procurement, processing, fabrication of equipment    Finally, this slide shows the example of total schedule of a PWR plant construction in Japan. It takes more than 10 years from the environmental survey to the commercial operation. 4 years for environmental survey and its assessment, 2 to 3 years for safety examination and 4 to 5 years for the construction work. Actually in Japan it takes longer in the preparation for construction than the construction itself. So it is very important for new comer countries to establish an efficient regulation system for reactor installation before construction work. 最後に、このスライドは、日本におけるPWRプラント建設の全体のスケジュールの例を示しています。         それは、環境調査から商業運転まで10年以上かかる。        4環境調査及び工事の安全審査及び4から5年間その評価、2から3年間の年。         実際に日本では建設そのものよりも建設準備に長期間かかります。 Preparation for construction Excavation work Civil Construction Leak Rate Test PCCV Construction Equipment installation (on site) Functional Test 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.

67 END 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 67

68 Appendix

69 Basic Policy of the reform on Nuclear Regulatory Organizations and Lows
I have explained the outline of construction procedure so far. But after 3/11 accident, the reform on nuclear regulatory organizations and lows have been considered by Japanese government. And recently, the basic policy of that reform was concluded. So I would like to introduce that briefly. Simply speaking, the construction procedure itself is not changed as a whole, but some regulations learned from the accident will be probably added or revised such as severe accidents and now those revises are considered specifically. And the regulatory organizations and systems are changing. The formula of new organizations and systems are established but actual work is just starting. So gradually new organizations and system would work actually. 私はこれまで従来の建設手順の概要を説明しました。 しかし、2011年3月11日の福島事故後、日本政府により、原子力規制機関と法制度の改革について検討されてきました。 私は、どのような見直しがなされたのか、簡潔にご紹介したいと思います。 単純に言えば、建設手順そのものは全体として変更されませんが、事故から学んだいくつかの教訓を反映し、昨年秋に規制の組織や制度が見直されています。 但し、実際の作業は始まったばかり。徐々に新しい組織やシステムが実際に機能しつつあります。   The 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. 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 69

70 Background 2011/03/11: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 The background is here. March 11 in 2011, the Great East Japan Earthquake, Tsunami and Fukusima No.1 NPP accident happened The conventional safety guidelines didn’t expect long-time like several days Station Black Out. So August 15 in 2011, the government decided the basic policy of the revision on nuclear regulatory organizations and related matters such as laws. Then January 31 in 2012, the government showed that reform act draft. And June 20 in 2012 the act above was passed by the Diet. Then formally the reform will be activated. 2011年3月11日に、東日本大震災、津波、福島第一原子力発電所事故が発生した。 従来の安全設計審査指針では、数日間続くような長期SBOが発生することを予期していなかった。 2011年8月15日に、政府は、原子力安全規制に関する組織などの改革の基本方針を決めた(閣議決定)。 その後、2012年1月31日で、政府は改革法の草案を決定、国会に上程。 そして、2012年6月20日、国会で可決、成立。 その後、2012年9月19日に正式に施行されました。 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 70

71 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 The basic points of the reform is here, 5 items. So I would like to explain it using the next slide. この原子力規制システムの改革の基本的なポイント 1.推進と規制の間の明確な分離     “原子力安全・保安院”を “経済産業省”から分離し、原子力安全委員会の機能が追加され、“原子力規制局が” 2012年以内に確立されている 2.統合      原子力安全規制はこれまでいくつかの組織に分かれていて、効果的に働いていなかった。そこで原子力安全規制を強化するため、原子力規制委員会に業務を集約した。 3.危機管理  原子力規制委員会の重要な業務として、緊急事態の初期対応に関すること(発生の認定、報告、応急処置等)があります。 4.優秀な人材の確保 原子力推進に係る行政事務を所掌する行政組織への配置転換を認めない 5.福島第一原子力発電所事故を教訓とした適切な規制や新たな規制を導入するなど、関連制度見直し 1.独立性の確保  原子力規制委員会を新設。 2.関連事務の一元化      規制に関する事務が原子力安全保安院、原子力安全委員会、文部科学省等に分散していたことから、これらを一元化(原子力の利用に関する事務は、従来通り) 3.安全規制の強化   1F事故のような重大事故を想定した対策の義務付け   バックフィット制度(最新知見を既設に反映)   運転期間を40年に制限   会議は原則公開 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 71

72 Outline of the new organization System
The conventional Nuclear Safety regulatory organization The new Nuclear Safety regulatory organization METI Ministry of Environment Cabinet Office METI Ministry of Economy Trade Industry Ministry of Education Culture Sports Science and Technology NRA (Nuclear Regulation Authority) Atomic Energy Commission TheSecretariat of the NRA Nuclear and Industrial Safety Agency Regulation against NPP Regulation against Test Reactor Nuclear Security 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 safety Agency” (provisional name) will be established within 2012 2. Integration Nuclear safety regulations are divided in several organizations, so they haven’t been worked effectively so those works are interrogated in Nuclear safety Agency to enhance the function of nuclear safety 3.Crisis Management Nuclear safety Agency 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 1.独立性の確保    “原子力安全・保安院”を “経済産業省”から分離し、原子力規制委員会を新設。 2.関連事務の一元化      規制に関する事務が原子力安全保安院、原子力安全委員会、文部科学省等に分散していたことから、これらを一元化(原子力の利用に関する事務は、従来通り) 3.安全規制の強化   1F事故のような重大事故を想定した対策の義務付け   バックフィット制度(最新知見を既設に反映)   運転期間を40年に制限   会議は原則公開 Realizing objective and scientific Regulations Nuclear Safety Commission Double Check Separation Use & Regulations Integration on Nuclear Safety Enhancing Emergency Securing Independence of Regulations 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 72

73 Procedural Steps for NPP Construction
METI NRA Environmental Examination Planning Decision on basic program of power development Safety Examination Public Hearing Preparation for Construction Reactor Installation License Construction Permit (approval of Construction Plan) Construction Permit (approval of Construction Plan) Pre-service Inspection Pre-service Inspection Fuel  Inspection Construction Welding Inspection Approval of Operational Safety Program Periodical Inspection Safety Inspection Periodical Safety Review Operation 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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