Review of Quantitative Software Reliability Methods
Description
The current U.S. Nuclear Regulatory Commission (NRC) licensing process for digital systems rests on deterministic engineering criteria. In its 1995 probabilistic risk assessment (PRA) policy statement, the Commission encouraged the use of PRA technology in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data. Although many activities have been completed in the area of risk-informed regulation, the risk-informed analysis process for digital systems has not yet been satisfactorily developed. Since digital instrumentation and control (I and C) systems are expected to play an increasingly important role in nuclear power plant (NPP) safety, the NRC established a digital system research plan that defines a coherent set of research programs to support its regulatory needs. One of the research programs included in the NRC's digital system research plan addresses risk assessment methods and data for digital systems. Digital I and C systems have some unique characteristics, such as using software, and may have different failure causes and/or modes than analog I and C systems; hence, their incorporation into NPP PRAs entails special challenges. The objective of the NRC's digital system risk research is to identify and develop methods, analytical tools, and regulatory guidance for (1) including models of digital systems into NPP PRAs, and (2) using information on the risks of digital systems to support the NRC's risk-informed licensing and oversight activities. For several years, Brookhaven National Laboratory (BNL) has worked on NRC projects to investigate methods and tools for the probabilistic modeling of digital systems, as documented mainly in NUREG/CR-6962 and NUREG/CR-6997. However, the scope of this research principally focused on hardware failures, with limited reviews of software failure experience and software reliability methods. NRC also sponsored research at the Ohio State University investigating the modeling of digital systems using dynamic PRA methods. These efforts, documented in NUREG/CR-6901, NUREG/CR-6942, and NUREG/CR-6985, included a functional representation of the system's software but did not explicitly address failure modes caused by software defects or by inadequate design requirements. An important identified research need is to establish a commonly accepted basis for incorporating the behavior of software into digital I and C system reliability models for use in PRAs. To address this need, BNL is exploring the inclusion of software failures into the reliability models of digital I and C systems, such that their contribution to the risk of the associated NPP can be assessed.
Availability note (English)
Available from http://www.bnl.gov/isd/documents/74267.pdf; PURL: https://www.osti.gov/servlets/purl/1013511-OJPSKn/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 98 p.
- Report number
- BNL--94047-2010
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 42061073
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BNL; COMPUTER CODES; DEFECTS; DESIGN; DIGITAL SYSTEMS; FUNCTIONALS; LICENSING; NUCLEAR POWER PLANTS; PROGRAMMING; RELIABILITY; RESEARCH PROGRAMS; RISK ASSESSMENT; SAFETY; SIMULATION
- Descriptors DEC
- FUNCTIONS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Contract/Grant/Project number
- AC02-98CH10886
- Notes
- doi 10.2172/1013511
- Funding organization
- Nuclear Regulatory Commission/Non-Nureg (United States)