IEEE Std 387-2017 pdf download – IEEE Standard for Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations.
1.5 Exclusions The following items are not in the scope of this standard: a) Diesel-generator unit enclosure and foundations b) External service equipment and systems that are a part of, or that are housed in, the diesel-generator unit enclosure, other than those tabulated in 1.1.1 c) The control, protection, and surveillance systems for the following: 1) Protecting the loads energized by the diesel-generator unit 2) Prevention of common-mode failure between the preferred power supply and the standby power supply d) Determination of the characteristics of the service environment e) Fire protection system 2. Normative references The following referenced documents are indispensable for the application of this document (i.e., they must be understood and used, so each referenced document is cited in text and its relationship to this document is explained). For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments or corrigenda) applies. ANS 59.51, Fuel Oil Systems for Safety-Related Emergency Diesel Generators. 2 ASME OM, Operation and Maintenance of Nuclear Power Plants (Part 16, Performance Testing and Monitoring of Standby Diesel Generator Systems in Light-Water Reactor Power Plants). IEEE Std 308™, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations. 3,4 IEC/IEEE 60780-323™, Nuclear Facilities – Electrical Equipment Important to Safety–Qualifcation.
3. Defnitions For the purposes of this document, the following terms and defnitions apply. The IEEE Standards Dictionary Online should be consulted for terms not defned in this clause. 7 acceptable: Demonstrated to be adequate by the safety analysis of the plant. continuous rating (of diesel-generator unit): The electric power output capability that the diesel- generator unit can maintain in the service environment for 8760 h of operation per year with only scheduled outages for maintenance. design basis event/accident: Postulated events used in the design to establish the performance requirements of the structures, systems, and components. A postulated event or accident that a nuclear facility shall be designed and built to withstand without loss to the systems, structures, and components necessary to improve public health and safety. design load: That combination of electric loads (kW and kvar), having the most severe power demand characteristic, which is provided with electric energy from a diesel-generator unit for the operation of engineered safety features and other systems required during and following shutdown of the reactor. Design load may include the term power factor.