E-3-1

Application of Preventive Maintenance Technologies: Based on the OECD/NEA SCAP Final Report

Naoto SEKIMURA (The Tokyo University)

Abstract
Application of preventive maintenance technologies requires systematic development of information basis for database, knowledge-base and commendable practice, which has been successfully accomplished in the OECD/NEA SCAP project for stress corrosion cracking and cable degradation.

Keywords
OECD/NEA SCAP, Knowledge-base, Commendable Practice, Preventive Maintenance Technology, Degradation Mechanisms, Ageing Management, Nuclear Regulatory Inspection, Strategy Maps for Research and Development

E-3-2

Coordination Among Industry, Academic Society and Regulatory Body in The Research on Aging Management

Hiroki ISHIGAKI (Nuclear and Industrial Safety Agency), Toru OSAKI, Masanori KANNO (Japan Nuclear Energy Safety Organization), Hiroshi MIYANO (Hosei University)

Abstract
Many activities for the coordinated research on aging management are reviewed, and examples of fruitful results are introduced according to the technical strategy map. Industry-Academia-Government exchanging system of the information each other on aging management was established for autonomy, diversity, collaboration. To clarify the concept of the role of industry, government and academia to address aging management without duplication algorithm is for the overall coordination of industrial and academic information and response issues, technological strategy map for aging management formulated.

Keywords
coordination, roadmap, aging management, good practice

E-3-3

Academic-Industry Partnership in R&D Activities on Aging Management and Seismic Reliability Evaluation of BWRs

Shunich SUZUKI (The Tokyo Electric Power Company, Inc.)

Abstract
In recent years, the formulation of reasonable methodologies to manage and evaluate the safety and integrity of aging nuclear power facilities is the matter of importance for Japanese power utilities to secure stable power supply in the next few decades. Among possible concerns about aging problems, stress corrosion cracking (SCC) is the one of critical problems to ensure the integrity of boiling water reactors (BWR) and extensive R&D activities are being conducted. The seismic reliability of nuclear power plants is also attracting increasing attention after Kashiwazaki-Kariwa nuclear power station suffered from Niigataken-Chuetsuoki earthquake in July 2007. Intensive seismic evaluations and reinforcements have been being conducted from then on.

This paper will provide an introductory review on research activities on SCC mechanism and seismic reliability of BWRs that are conducted in academic-industry partnership.

Keywords
academic-industry partnership, plant aging, stress corrosion cracking, SCC mechanism, seismic reliability, boiling water reactor

E-3-4

Maintenance Activities for Main Components at PWR NPPs and Expectations of Societies related to Nuclear Power

Tomoya MATSUNAGA (The Kansai Electric Power Co., INC.)

Abstract
PWSCCs have been found in Alloy 600 materials of several Japanese PWR Nuclear Power Plants. These issues have caused large amount of loss of electricity. On the other hand, new technologies on preventive maintenance and repair for Alloy 600 materials have been remarkably developed in recent years. NISA, Societies and Industries related to NPPs have played important roles for the application of the new technologies in fields. Quality of maintenance activities for main components leads to safety and high performance of NPPs.

Keywords
PWSCC, Inspection, Evaluation, Repair, Replacement, Preventive maintenance

E-3-5

Expectations of Wall Thinning Management For Development of Measurement Technology and Improvement of Prediction Technology for Progress of Wall Thinning

Tomiyasu IMAI, Toshihiro KODAKA and Michita MIZUNO (CHUBU Electric Power Co., lnc.)

Abstract
The wall thinning management program at Hamaoka Nuclear Power Station stipulate object points and test frequencies depending on wall thinning environment (flow condition, material). Currently, object points and test frequency are determined conservatively, which contribute to an increase of radiation exposure of filed workers. Development of measurement technology and improvement of prediction technology for a progress of wall thinning may enable utilities to conduct a more effective wall thinning management.

Keywords
Thinning Management