Japan Electric Association (JEA) Code, JEAC4201, “Method of Surveillance Tests for Structural Materials of Nuclear Reactors” s pecifies the method of surveillance test to investigate and evaluate the mechanical properties change (mainly embrittlement) o f reactor pressure vessel for LWR plants. The draft revised code was approved by the Nuclear Standards Committee of JEA last D ecember and was issued as JEAC4201-2007. This presentation introduces the summary of this code and the point of the revision....
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Revision Summary of JEAC4201 “Method of Surveillance Testsfor Structural Materials of Nuclear Reactors”

As the number of aged nuclear power plants in Japan is increasing, more importance of maintenance for those plants is being recognized. And new techniques are being developed to manage the maintenance activities foe those aged plants. In case of application of newly developed techniques for maintenance activ ities for nuclear plant facilities, verification process for the techniques shall be necessary. However, authorization process in Japan is not necessarily effective from standpoint of rapidness. The pr...
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Application of Techniques Developed for Maintenance Activities

From the engineering development to actual application of the new maintenance technique used for the maintenance activities of a nuclear reactor in operation, the JANTI Guide line, “the Guideline on the Application Process of a Maintenance Technique“ was developed to clarify activities to be checked or examined in each process. In engineering deve lopment, all activities are provided to be checked or examined at each process followed further, such as standardization process. It is important to carry out sh...
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Guideline on Application Process of Techniques Developed for Maintenance Activities

The JSME Code of Fitness for Service was established in 2000, and has been incorporated into so called “integrit y evaluation system” for nuclear power plant facilities, which was provided regulatory authority since 2003 and s hapes “Maintenance Rule” in Japan. The code includes in-service inspection and flaw evaluation. The presentation includes a current role and expected future development of the JSME FFS Code in Japanese maintenance activities....
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Activities and Rules on Maintenance for Nuclear Power Plants

While the importance of maintenance is now being well recognized in terms of robustness of safety of NPP, code and standards for maintenance phase are not necessarily well organized so far in Japan. This paper presents some issues on promoting code and standards applicable to the maintenance phase from both standpoint of technical and management....
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The Importance of promotion of Code and Standards for Maintenance Phase

１．はじめにわが国の発電用設備に関する技術規格は、産業と技術の発展と平行して、産業災害から国民の安全を保護すると同時に産業の発展を促すとの立場から、国の指導・保護のもとに、技術規格は国の法体系の中に組み入れられ、規制基準としてその整備と高度化が進められてきた。一方、発電用設備をめぐる技術革新はめざましく、この技術革新の進捗にあわせ技術規格の内容も柔軟に対応できるよう社会的要請も高まってきた。さらに1996年の世界貿易機関の貿易に関する技術的障壁の撤廃に関する同意が締結されるなど規格・基準分野における国際性......

When Repair and Replacement Process (RRP) for maintenance of facilities of operating nuclear power plants is applied based on the construction code, many difficulties may arise because of spatial or radioactive restriction compared to doing for facilities under construction. For this reason, industries have been developed maintenance technologies and provided guidelines and codes for the repair for the facilities of operating plants under those restricted conditions. But, in fact, these guidelines and ...
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Codes and Standards in Repair and Replacement Process : Status and Issues

Working Group on Application Enhancement of Repair Replacement Technology has been established since September 2015, for the purpose of studying specific measures to create an environment that Japanese utilities can easily make corrective actions such as repair replacement technology applicable to Nuclear Power Plant to improve the safety of their own plants, and meetings have been held five times until the end of April 2016. In this paper, discussions on the WG meetings so far are shown, as well as th...
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Current Status of WG on Application Enhancement of Repair Replacement Technology

軽水炉炉内構造物の点検評価ガイドラインの体系化－将来の技術課題とその改善、高度化の方向性－ 山下 裕宣,Hironobu YAMASHITA,千種 直樹,Naoki CHIGUSA,青木 孝行,Takayuki AOKI,小山 幸司,Koji KOYAMA,元良 裕一Yuuichi MOTORA,藤森 治男,Haruo FUJIMORI......