This standard identifies and discusses criteria for risk-informed categorization and treatment of electrical and electronic components that are designated by the user to be placed into safety significant categories at nuclear power generating stations and other nuclear facilities.

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This standard provides the basic principles for qualification of equipment used in nuclear facilities; it does not define the scope of equipment requiring qualification nor does it provide guidance on how to classify equipment. Other standards that present qualification methods for specific classifications of equipment, specific types of equipment, specific environments, or specific aspects of a qualification program may be used to supplement this standard, as applicable. The bibliography… read more contains a partial list of references, including other standards, related to equipment qualification. read less

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This document provides common terminology and recommended practices for initiating and conducting event investigations, analyzing data, producing results, and identifying corrective actions associated with facility personnel, processes, equipment, and systems at nuclear facilities.

定价： 65元 / 折扣价： 56 元

This standard covers qualification of Class 1E protective relays and auxiliaries to be used outside the primary containment in Nuclear Power Generating Stations and Other Nuclear Facilities . Protective relays and auxiliaries located inside the primary containment in a Nuclear Power Generating Stations and Other Nuclear Facilities present special conditions beyond the scope of this document.

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This guide provides a structured framework for the incorporation of human reliability analysis (HRA) into probabilistic risk assessments (PRAs).

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Describes the requirements and guidelines for qualifying mechanical equipment, such as pumps, valves, and dynamic restraints, used in nuclear facilities. Nuclear facilities can include nuclear power plants (NPP), small modular reactors (SMR), and advanced reactors. The requirements and guidelines presented include the principles, procedures, and methods of qualification.

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These criteria established minimum requirements for the safety-related functional performance and reliability of protection systems for stationary land-based nuclear reactors producing steam for electric power generation. Fulfillment of these requirements does not necessarily fully establish the adequacy of protective system functional performance and reliability. On the other hand, omission of any of these requirements will, in most instances, be an indication of system inadequacy. For… read more purposes of these criteria, the nuclear power generating station protection system encompasses all electric and mechanical devices and circuitry (from sensors to actuation device input terminals) involved in generating those signals associated with the protective function. These signals include those that actuate reactor trip and that, in the event of a serious reactor accident, actuate engineered safeguards such as containment isolation, core spray, safety injection, pressure reduction, and air cleaning. read less

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This standard provides general requirements and methods for qualifying electric cables, and splices for nuclear facilities. Cable, and splices within or integral to other devices (e.g., instruments, panels, motors) should be qualified using the requirements in the applicable device standard or IEEE/IEC Std 60780-323™:2016. However, this standard’s requirements may be applied to the cable and splices within these devices. For qualification of fiber optic cable refer to IEEE Std 1682™-2011.

定价： 59元 / 折扣价： 51 元

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