IEEE 379-1994

379-1994 is a nuclear engineering standard titled Failure Criterion to Nuclear Power Generating Station Safety Systems. It addresses how failure should be judged for safety-related systems used in nuclear power generation, helping define consistent expectations for design review, analysis, and verification. As a superseded English-language standard, it remains relevant for understanding earlier safety-system criteria and the technical basis used to assess whether a system can still perform its protective function when needed.

379-1994 overview

This standard focuses on failure criteria for nuclear power generating station safety systems, which are central to plant protection and controlled response under abnormal conditions. In practice, 379-1994 provides a structured technical reference for evaluating when a system, component, or function is considered failed in the safety context. That makes it useful for engineers, reviewers, and compliance teams working with nuclear plant design documentation, reliability assessments, and safety analyses where clear failure definitions are important.

Typical use cases

Typical use of 379-1994 includes reviewing safety system performance expectations in nuclear plant engineering, especially where protective functions, sensing chains, logic, or actuation paths must be assessed against defined failure conditions. It may also support specification writing, design verification, maintenance planning, and test interpretation for station safety equipment. In nuclear engineering workflows, the standard can help align technical judgments across disciplines when determining whether a safety-related function has met its required criterion.

Why this standard matters

Clear failure criteria are important in nuclear safety because they support consistent decisions about system acceptability, redundancy, and operational readiness. 379-1994 helps reduce ambiguity in how failures are identified and evaluated, which can improve design control and documentation quality. For procurement and engineering review, it can also provide a common reference point for comparing equipment or system claims against expected safety performance, lowering the risk of inconsistent interpretation during analysis or testing. As 379-1994 is superseded, it is especially useful for legacy context and historical reference.

• Failure criteria for safety systems
• Nuclear power station engineering context
• Design, test, and review reference
• Safety-related performance assessment
• Superseded English-language document