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Standard [WITHDRAWN]
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Electrical equipment in nuclear facilities shall meet its functional safety requirements over its total service life. This is achieved through a complete program of quality assurance, design, qualification, manufacture, transportation, storage, installation, maintenance, periodic testing and monitoring. The standard specifically addresses qualification with respect to environmental conditions. It applies to electrical equipment with safety significance and its interfaces that are necessary for the performance of a safety function or whose failure could adversely affect the safety function of other equipment. It describes the general qualification process, the qualification procedures to be applied and the associated documentation. It also includes recommended procedures in various combinations, as well as information on the level of testing rigor during the qualification process. In this context, "device" is used as a generic or collective term within the meaning of equipment, device. "Equipment" may be a single device or consist of a smaller or larger number of interconnected individual devices with different functions. The standard replaces DIN IEC 60780:2000-12 and has the following main changes: the title of the standard has been changed; the practices of qualification already cited in IEC 60780:1998 and IEEE 323:2003 have been merged and at the same time updated within this framework. These essentially include: - the need to design equipment for loads from beyond-design-basis accidents, - consideration of the behavior of I&C equipment under radioactive radiation; the need to re-evaluate and extend the Qualified Life of electrical equipment in projects to extend the operating life of nuclear facilities has been included; the need to design equipment for loads from beyond-design-basis accidents has been included; condition monitoring; the topic "Extension of life" (6. 2) has been renamed to "Reassessment of qualified life"; the topic "Operational experience" (originally 7.5) has been assigned to 6.1 "Qualification methods"; the topic "Analytical evidence" (originally 7.6) has been assigned to 7.4 "Implementation of the qualification program"; the topic "Modifications" (originally 7.7) has also been assigned to 7.4 "Implementation of the qualification program"; the designation "Qualified condition" is now written in capital letters because this condition represents a reference criterion within the scope of in-service verification for which the accident resistance has been experimentally verified. The necessity of determining a "qualified lifetime" can thus be dispensed with; due to the approximate comparability and significance of the terms "qualified condition" and "qualified lifetime" with regard to their use, it appeared advisable to also capitalize the term "Qualified lifetime"; the term "abnormal operation" has been replaced throughout by the term "disturbed operation" used in German plants; editorial revision. The responsible committee is DKE/UK 967.1 "Leittechnik für kerntechnische Anlagen" ("Instrumentation and control of nuclear facilities") of the DKE (German Commission for Electrical, Electronic and Information Technologies) at DIN and VDE.
This document replaces DIN IEC 60780:2000-12 .
This document has been replaced by: DIN EN 60780-323:2018-03; VDE 0491-80:2018-03 .