IEEE IEC 60980-344:2020 pdf download.NUCLEAR FACILITIES-EQUIPMENT IMPORTANT TO SAFETY -SEISMIC QUALIFICATION.
IEEE IEC 60980-344 describes methods for establishing seismic qualification procedures that will yield quantitative data to demonstrate that the equipment can meet its performance requirements. This document is applicable to electrical, mechanical, instrumentation and control equipment/components that are used in nuclear facilities. This document provides methods and documentation requirements for seismic qualification of equipment to verify the equipment’s ability to perform its specified performance requirements during and/or after specified seismic demands. This document does not specify seismic demand or performance requirements. Other aspects, relating to quality assurance, selection of equipment, and design and modification of systems, are not part of this document. As seismic qualification is only a part of equipment qualification, this document is used in conjunction with IEC/IEEE 60780-323.
The seismic qualification demonstrates equipment’s ability to perform its safety function(s) during and/or after the time it is subjected to the forces resulting from at least one safe shutdown earthquake (SSE/S2). This ability is demonstrated by taking into account, prior to the SSE/S2, the ageing of equipment and the postulated occurrences of a given number of lower intensity operating basis earthquake (OBE/Si). Ageing phenomena to be considered, if specified in the design specification, are those which could increase the vulnerability of equipment to vibrations caused by an SSE/S2.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content constitutes requirements of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.
IEC 60068-2-6, Environmental testing — Part 2-6: Tests — Test Fc: Vibration (sinusoidal)
IEC/IEEE 60780-323, Nuclear facilities — Electrical equipment important to safety — Qualification 1,2
IEEE Std 382TM, IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations
3 Terms and definitions
The terminology and definitions used in this document are consistent with IAEA Safety Glossary 3.
For the purposes of this document, the following terms and definitions apply.
ISO, IEC, and IEEE maintain terminological databases for use in standardization at the following addresses:
• lEO Electropedia: available at http://www.electropedia.org/
• ISO Online browsing platform: available at http://www.iso.org/obp
• IEEE Standards Dictionary Online: available at http://dictionary.ieee.org
The IEEE Standards Dictionary Online should be consulted for terms not defined in these databases.
3.1
acceptance criteria
specified bounds on the value of a functional indicator or condition indicator used to assess the ability of a structure, system or component to perform its design function
Note I to entry: Value(s) of performance parameters and other criteria to demonstrate that equipment can perform
the safety function(s) shall be identified.
[SOURCE: IAEA Safety Glossary, 2018]
3.2
assembly
comprising all electrical, mechanical, and structural components of the equipment including a common mounting and supporting structure.IEEE IEC 60980-344 pdf download.