Nuclear Safety Regulation Research Articles

Codes on the Safety of Nuclear Power Plants in Relation to Seismic Design

Study on the nuclear Safety laws and regulations, and good grasp of relevant definitions are essential prerequisites for Seismic and geologic siting of nuclear power plants. It can be too strongly emphasized that laws or decrees of issue by government and legislature have profound mandatory binding force. The guides and regulations related nuclear safety belong to directing documents of the specific rules, they have not been mandatory in the law significance, and allow some adaptability to a certain degree. Professionally technical specification is merely the inherent stipulations, besides; it must meet the codes demands in the concrete practice. Finally, the assessment of the capability for surface faulting at nuclear power plant sites belongs to the mandatory claims but not in assessment of active fault.

A Study of the EU Common Policy for Guaranteeing Nuclear Security and Nuclear Safety

This study examines the history and structure of EU"s nuclear energy policy and intra system. Up to recently, EU Commission has supported a foreign policy for nuclear energy management to form nuclear energy related systems. Also the Community has promoted an active participation in international-assistance system in relation to nuclear safety, nuclear security and Safeguard.<BR> Thus This study aims to analyze how EU has responded to overall environment changes and promoted its nuclear policies recently. It also takes a look at what relationship exits in international community and how EU"s nuclear policies and nuclear energy related systems has progressed.<BR> And this paper conducts an evaluation of the structure of the European Nuclear Safety Regulators Group (ENSREG) and European Nuclear Energy Forum(ENEF). ENSREG is an independent, authoritative expert body created in 2007 following a decision of the European Commission. It is composed of senior officials from the national nuclear safety, radioactive waste safety or radiation protection regulatory authorities from all 27 Member States in the European Union and representatives of the European Commission. ENEF is a unique platform for a broad discussion, free of any taboos, on transparency issues as well as the opportunities and risks of nuclear energy. Founded in 2007, ENEF gathers all relevant stakeholders in the nuclear field: governments of the 27 EU Member States, European Institutions including the European Parliament and the European Economic and Social Committee, nuclear industry, electricity consumers and the civil society.

Manufacturing preparations for the European Vacuum Vessel Sector for ITER

Abstract The contract for the seven European Sectors of the ITER Vacuum Vessel, which has very tight tolerances and high density of welding, was placed at the end of 2010 with AMW, a consortium of three companies. The start-up of the engineering, including R&D, design and analysis activities of this large and complex contract, one of the largest placed by F4E, the European Domestic Agency for ITER, is described. The statutory and regulatory requirements of ITER Organization and the French Nuclear Safety regulations have made the design development subject to rigorous controls. AMW was able to make use of the previous extensive R&D and prototype work carried out during the past 9 years, especially in relation to advanced welding and inspection techniques. The paper describes the manufacturing methodology with the focus on controlling distortion with predictions by analysis, avoiding use of welded-on jigs, and making use of low heat input narrow-gap welding with electron beam welding as far as possible and narrow-gap TIG when not. Further R&D and more than ten significant mock-ups are described. All these preparations will help to assure the successful manufacture of this critical path item of ITER.

原子力安全規制の国と地方の役割分担に関する制度設計案の検討

In this paper, we consider the concept and the concrete direction of the institutional design concerning role-sharing between national and local governments with respect to nuclear safety regulation, and propose the following four institutional options: 1) strengthen the regulatory body's independence and clarify its accountability, 2) establish a local information committee in reference to the French CLI (Commission Locale d'Information), 3) institutionalize the environmental monitoring of local governments, and 4) institutionalize consultation among the regulatory body and local governments. Options 2, 3, and 4 are designed on the assumption that option 1 is implemented, because it is thought to be essential for fundamental improvements to enhance the regulatory body's ability as well as to reinforce bridges between safety regulation and society. Each option has some advantages and disadvantages, so there is room for further research into achieving reforms. However, it is believed that these institutional options can lead to the development of a trusting relationship between organizations responsible for safety regulation and siting areas and to the reduction in consensus-building costs in local areas.

A Step Closer to EU Law on the Management of Radioactive Waste and Spent Fuel

On 3 November 2010, the European Commission (the ‘Commission’) proposed a Directive on the Management of Spent Fuel and Radioactive Waste. The proposed Directive builds on the standards contained in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and the International Atomic Energy Agency (IAEA) 1995 Principles of Radioactive Waste Management. The Commission hopes that the Directive will be adopted sometime in 2011.Euratom and all European Union (EU) Member States (except Malta, Portugal and Cyprus) are parties to the Joint Convention. The Joint Convention is an ‘incentive’ instrument containing no mechanism for enforcement or sanction in case of a breach of its terms. Unlike the Joint Convention, the proposed Directive seeks to impose binding and enforceable obligations in EU law concerning the management of radioactive waste and spent fuel. With the aim of contributing to the ongoing discussion concerning the scope and the terms of the Directive, this article discusses its key provisions as well as those of the Commission’s previous proposals and the proposal of the European Nuclear Safety Regulators Group from March 2010. By way of background, the article outlines the existing EU law concering radioactive waste and spent fuel as well as the international framework for the management thereof.

W251003 福島原子力発電所の過酷事故の教訓と安全規制・規格の重要性([W25100](標準事業委員会企画),安全に関わる標準・規格)

The 2011 off the Pacific coast of Tohoku Pacific Earthquake and the Tsunami gave the serious damage to the Fukushima-Daiichi Nuclear Power Plants (NPPs). The accidents occurred in Unit 1, 2, 3 and 4. It is said that the height of tsunami attacked Fukushima NPP was more than 14m. After 50 minutes from the automatic shut-down, tsunami attacked the NPPs in Fukushima Daiichi NPPs. For example, the Unit 1 lost A/C power caused the loss of water injection function; it made the core meltdown and unusual increase of PCV pressure in the midnight of March 11th to 12th morning. Though the Unit one has the Isolation Condenser Core Cooling system, it was stopped by the operator to keep the cooling rate of 55℃/h. Finally, the isolation signal was transmitted from the control room to the motor driven isolation valves when the control room's battery discharged. It was the initiation of the core meltdown. The lessons from the acidents, we should improve the nuclear safety regulation through the innovatuion of regulatory rules and safety standars.

フランス地域情報委員会の原子力規制ガバナンス上の役割

In France, there exist organizations called “Commission Locale d'Information” (CLI) in all the siting areas where nuclear facilities located. Previously, the CLI organizations were established voluntarily by some local governments or nuclear utilities. Since 2006, however, the Nuclear Transparency and Safety Act has obliged the establishment of CLI in all the siting areas in conjunction with reforming the nuclear regulatory agencies. This means that the concerned local governments are officially part of nuclear safety regulation. In this study, we investigated present conditions of the CLI organizations through some interviews in France and consider their roles from the standpoint of nuclear regulatory governance. As a result, we found that the CLI plays the following roles: (1) medium of communication among concerned parties (not only between nuclear utilities and local habitants but also between the national nuclear regulatory agency and various local governments) and (2) implementing various activities in accordance with each local condition through the participation of local assembly members. In addition, we clarified that CLI's activities are supported by related institutional infrastructures, such as cost burden between central and local governments, and some other systems of citizen participation in building or expanding nuclear facilities.

原子力発電所の規制手法の分類と選択方法

Several new regulatory approaches have been introduced to Japanese nuclear safety regulations, in which a prescriptive and deterministic approach had traditionally predominated. However, the options of regulatory approaches that can possibly be applied to nuclear safety regulations as well as the methodology for selecting the options are not systematically defined. In this study, various regulatory approaches for nuclear power plants are categorized as prescriptive or nonprescriptive, outcome-based or process-based, and deterministic or risk-informed. 18 options of regulatory approaches are conceptually developed and the conditions for selecting the appropriate regulatory approaches are identified. Current issues on nuclear regulations regarding responsibilities, transparency, consensus standards and regulatory inspections are examined from the viewpoints of regulatory approaches to verify usefulness of the categorization and selection concept of regulatory approaches. Finally, some of the challenges at the transitional phase of regulatory approaches are discussed.

原子力の安全規制の最適化に関する研究会の活動 : 格納容器漏えい率試験(原子力の安全規制の最適化に関する研究会,&lt;特集&gt;第13回動力・エネルギー技術シンポジウム)

As a part of the study group's work on Optimization of Nuclear Safety Regulation of JSME, we studied the current experience and information about Containment Leakage Rate Testing (CVLRT) in the U.S. and European countries. After that, we compared their methods with the methods of CVLRT used in Japan. The results of our studies were summarized as follows: 1) In the U.S., NRC de-regulated the CVLRT methods so that the utilities could select the most efficient and the safest method. 2) In France and Belgium, the OLM (Online Leakage Monitoring) is used.

原子力の安全規制の最適化に関する研究会の活動 : 新しい保全システムと検査の実施(原子力の安全規制の最適化に関する研究会,&lt;特集&gt;第13回動力・エネルギー技術シンポジウム)

In order to make the inspection of nuclear facilities effective, mutual understanding and respect between the regulatory body and the licensees, NISA has been made considerable efforts open and yet formal relationship shall be fostered. For example, Inspection and optimization of Nuclear Safety Regulation meeting has been held at NISA from 2005, where academic, regulatory and industrial members, such as JSME had frankly discussion for the improvement of inspection system. Based on the agreed on the necessity of system renovation, the optimal inspection system, suitable plant shutdown interval for the preventive maintenance was evaluated considering the current monitoring technique. The useful conclusions were published so that each member makes efforts for the effective inspection system. And this year, NISA will start the new maintenance system, and inspection that is improved not also during outage but also the startup and rated operation.

原子力の安全規制の最適化に関する研究会の活動 : リスク情報を用いた待機除外処置(AOT)について(原子力の安全規制の最適化に関する研究会,&lt;特集&gt;第13回動力・エネルギー技術シンポジウム)

原子力の安全規制の最適化に関する研究会の活動 : リスク情報を用いた待機除外処置(AOT)について(原子力の安全規制の最適化に関する研究会,&lt;特集&gt;第13回動力・エネルギー技術シンポジウム)

原子力の安全規制の最適化に関する研究会の活動 : 研究会の概要(原子力の安全規制の最適化に関する研究会,&lt;特集&gt;第13回動力・エネルギー技術シンポジウム)

In order to make the inspection of nuclear facilities more effective, mutual understanding and respect between the regulatory body and the licensees, and a frank, open and yet formal relationship, shall be fostered. Thus the Research Section on Optimization of Nuclear Safety Regulation was established at JSME in 2005, where academic, regulatory and industrial members have frankly discussed for the improvement of inspection system. Agreed on the necessity of system renovation, the optimal inspection system was discussed. Suitable plant shutdown interval for the preventive maintenance was evaluated considering the current monitoring technique. At the same time, the U.S. and European inspection systems were reviewed to learn a lesson. The useful conclusions were published so that each member makes efforts for the effective inspection system. Some of the results have already been referred by the governmental task force on the inspection system improvement, and contributed to the system renovation.

B201 原子力の安全規制の最適化に関する研究会 : (1) 活動状況(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

B201 原子力の安全規制の最適化に関する研究会 : (1) 活動状況(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

B203 原子力の安全規制の最適化に関する研究会 : (3) 格納容器漏えい率試験(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

B203 原子力の安全規制の最適化に関する研究会 : (3) 格納容器漏えい率試験(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

B206 原子力の安全規制の最適化に関する研究会 : (6) リスク情報を用いた待機除外処置(AOT)(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

B206 原子力の安全規制の最適化に関する研究会 : (6) リスク情報を用いた待機除外処置(AOT)(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

B207 原子力の安全規制の最適化に関する研究会 : (7) 新しい保全システムと検査の実施(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

B207 原子力の安全規制の最適化に関する研究会 : (7) 新しい保全システムと検査の実施(安全規制の最適化,OS-8 軽水炉・新型炉・核燃料サイクル(2),一般講演,地球温暖化防止と動力エネルギー技術)

Lack of the Governance on the Planning Process of Nuclear Safety Regulation in Japan

Lack of the Governance on the Planning Process of Nuclear Safety Regulation in Japan

909 原子力安全規制における学協会規格の活用(社会貢献フォーラム:材料力学研究者の社会貢献と規格化・標準化)

909 原子力安全規制における学協会規格の活用(社会貢献フォーラム:材料力学研究者の社会貢献と規格化・標準化)

K10 原子力の安全規制の最適化に関する研究会の取り組み

K10 原子力の安全規制の最適化に関する研究会の取り組み

Enforcement of New Nuclear Safety Regulation

平成14年夏に, 東京電力の原子力発電所の自主点検記録や原子炉格納容器の漏えい率検査に不正があったことが発覚した。これは, 原子力発電の安全に対する社会の信頼を大きく損ねた。このため, 原子力安全・保安院では, 東京電力に対する厳正な措置を講じるとともに, 不正事案の再発防止のために, 定期事業者検査制度および健全性評価制度の導入, 罰則の強化などの安全規制を抜本的に強化する電気事業法および原子炉等規制法の改正を平成14年秋に行い, 平成15年10月から施行したところである。 本稿では, 原子力発電所の不正問題とその再発防止策としての安全規制の強化策について, 原子力安全・保安院における取組について述べることとする。