TY - CONF TI - The ENIQ pilot study: current status AB - A pilot study is currently being carried out by ENIQ (European Network for Inspection Qualification) in order to explore the issues involved in inspection qualification applied along the general principles of the European methodology. The components selected for the pilot study are austenitic pipe to pipe and pipe to elbows welds typical of those in BWR recirculation loops. A range of defect parameters has been defined. A suitable inspection procedure designed to find the designated defects will be applied to geometrically representative test pieces. The procedure/equipment will be qualified through open trials and technical justification. The personnel qualification will be done in a blind way. Once all features of the inspection system will have been qualified an in-service inspection will be simulated in order to test the feasibility of the qualification approach followed. In this paper the current status of this pilot study is discussed. (orig.) AU - "Lemaitre, P" AU - "Eriksen, B" AU - "Crutzen, S [European Commission, DG Joint Research Centre, Petten (Netherlands)]" AU - "Hansch, M [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany)]" AU - "Whittle, J [AEA Technology, Warrington (United Kingdom)]" KW - "21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS" KW - "42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES" KW - "IN-SERVICE INSPECTION" KW - "NUCLEAR POWER PLANTS" KW - "DEFECTS" KW - "PIPES" KW - "QUALITY ASSURANCE" KW - "PERSONNEL" KW - "RELIABILITY" KW - "TRAINING" KW - "EUROPE" KW - "REACTOR COMPONENTS" KW - "REACTOR SAFETY" KW - "REGULATIONS" KW - "NONDESTRUCTIVE TESTING" DO - https://doi.org/ UR - https://www.osti.gov/etdeweb/servlets/purl/667747 PB - CY - Germany PY - 1998 DA - 1998-11-01 LA - English J2 - [] VL - C1 - Stuttgart Univ. (Germany). Staatliche Materialpruefungsanstalt C2 - C3 - INIS-DE-0022; CONF-9710266- C4 - C5 - INIS; OSTI as DE99704622 L3 - Conference: 23. MPA seminar: safety and reliability of plant technology with special emphasis on nuclear technology - behaviour of pressurized components and systems at increased loading, 23. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Kerntechnik - Verhalten von druckfuehrenden Komponenten und Systemen bei erhoehten Belastungen, Stuttgart (Germany), 1-2 Oct 1997; Other Information: PBD: [1998]; Related Information: Is Part Of 23. MPA-Seminar: Safety and reliability of plant technology with special emphasis on behaviour of pressurized components and systems at increased loading. Vol. 2. Papers 27-50; PB: 431 p.; 23. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Verhalten von druckfuehrenden Komponenten und Systemen bei erhoehten Belastungen. Bd. 2. Vortraege 27-50 ER -