Abstract This study proposes the systematization of plant maintenance and establishment of Maintenology or “Maintenance Engineering“. In this paper, it is shown that “Inspection System Engineering”, which consists of a part of Maintenance En gineering, is necessary to incorporate a scientific approach or rationality into maintenance planning and can provide ho w to optimize inspection planning by considering the structural strength and aging degradation of equipment or component....
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Approach to the Construction of “Maintenance Engineering"

Che draft guideline for managing the leakage from seal portions of equipment in nuclear power plant has be en eveloped by the special research committee of Japan society of maintenology (ISM). In this paper, the o utline f this guideline is shown and the technical backgrounds and key points including leak management pr ocess, leak ate measurement methods, leak rate prediction method, acceptance criteria, etc. are discussed....
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Development of a Guideline for managing Leakage from Seal Portions of Equipment in Nuclear Power Plants

At Tokai No. 2 Power Plant, the fourth monitoring test is conducted to confirm the tendency of reactor pressure vessel steels to become brittle due to neutron irradiation. From the results of the Charpy impact test, the amount of transition of the upper shelf absorbed energy and the related temperature was evaluated, and it was confirmed that there was no significant tendency to embrittlement. We report the results of the 4th monitoring test and discuss the results. ...
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Report of the reactor pressure vessel steel material surveillance test results (the 4th) at Tokai No. 2 Power Station

It has been newly required as a regulatory standard that the blowout panel installed in the reactor building of BWR can be closed promptly when it is opened. In Tokai No. 2 Power Plant, a blowout panel closing device was developed to meet this requirement. In this report, we describe the design of blowout panel closing device and report the result of vibration test conducted in E-Defense....
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Development of reactor building blowout panel closing device for Tokai No.2 power station

At Tokai No. 2 Power Station, a special inspection is conducted in line with the application for approval of extension of operating period. In particular, for reactor pressure vessels, ultrasonic flaw inspection is performed on the base metal part of the trunk which has not been inspected during the conventional in-service inspection. For water supply nozzles, we are conducting eddy current flaw detection inspection for low alloy steel, which is the first in Japan. As a result of these inspections, no defec...
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Reactor pressure vessel inspection for extension of operation period at Tokai No. 2 power station

Tokai No.2 Power Station (Tokai II) has been operated more than 40-years. At 2018,we completed the 40-years Aging Management Technical Evaluation (AMTE), and concluded that most of component and structure would be maintained their integrity by continued existing preservation activities, even assuming the operation period of 60 years. In this paper, we explain several technical matters that were particularly discussed at AMTE, for example, thermal aging for casting stainless steel, neutron irradiation embrit...
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Aging management technical evaluation for Tokai No.2 Power Station

This study proposes a method for the evaluation of leakage from pressure retaining components. In this study, leakage from seal portion of components and leakage from flaw due to aging degradation in components are discussed. And metho ds to estimate a leak rate and its acceptance criteria in the both cases are also discussed. As a result, it was shown that it is possible to prescribe how to estimate a leak rate from seal and flaw, and how to set acceptance criteria....
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Study on a method for the evaluation of leakage from pressure retaining components

A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. Finally, an example that the proposal was applied to setting maintenance program of sodium-cooled fast reactor was presented. ...
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Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features

A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. ...
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Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (1) Basic Requirements

A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage were first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. In this paper, requirements on maintenance program of NPP at R&D stage were clarified and an example that the proposal was applie...
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Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (2) case study