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Released: 29.08.1977
IEEE 381-1977 - IEEE Standard Criteria for Type Tests of Class 1E Modules Used in Nuclear Power Generating Stations
IEEE Standard Criteria for Type Tests of Class 1E Modules Used in Nuclear Power Generating Stations
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50.25 EUR
Withdraw: | 14.06.1994 |
Standard number: | IEEE 381-1977 |
Released: | 29.08.1977 |
ISBN: | 978-0-7381-4198-5 |
Pages: | 32 |
Status: | Inactive |
Language: | English |
DESCRIPTION
IEEE 381-1977
This document describes the basic requirements of a type test program with the objective of verifying that a module used as Class 1E equipment in a nuclear power generating station meets or exceeds its design specifications. This document is limited to class 1E modules from and including the sensor through the logic circuitry of the. final actuation devices. Except for those that are part of a module, switchgear, cables, connections, motors, valve actuators, station batteries, and penetrations are not included and are covered by other IEEE documents.The purpose of this document is to supplement the procedures and requirements given in IEEE Std 323-1974 [24] for type testing Class 1E modules, thereby providing directions for establishment of a type test program which will obtain the required test data and yield the required documentation of test methods and results. This standard is structured to present to the user the principal performance characteristics and environmental parameters which must be considered in designing a type test program for any given Class 1E module. These modules range from tiny sensors to complete racks or cabinets full of equipment that may be located inside or outside containment. The Class 1E modules are required to perform their function before, during, or after, or all, any design basis event specified for the module. The vast variety of modules covered by this document precludes the listing here of specific requirements for each type test.
New IEEE Standard - Inactive-Withdrawn. Minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions are established. The qualification of all types of power-driven valve actuators, including damper actuators, is covered. The standard qualification cases and their environmental parameters for the usual locations of safety-related equipment in a nuclear generating station are described. Test procedures are presented.