Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

Conference · Wed Oct 01 04:00:00 EDT 1997

OSTI ID:537341

Korsah, K; Wood, R T ^[1]; Tanaka, T J ^[2]; Antonescu, C E ^[3]

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1. Oak Ridge National Lab., TN (United States)
2. Sandia National Labs., Albuquerque, NM (United States)
3. Nuclear Regulatory Commission, Rockville, MD (United States)

This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program.

• Research Organization: Oak Ridge National Lab., TN (United States); Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-96OR22464; AC04-94AL85000
• OSTI ID: 537341
• Report Number(s): CONF-970607--37; ON: DE97008464; BR: 40-100106
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CERTIFICATION
COMPUTERIZED CONTROL SYSTEMS
DIGITAL SYSTEMS
ENGINEERED SAFETY SYSTEMS
HUMIDITY
INTERFERENCE
NUCLEAR POWER PLANTS
SMOKES
TEMPERATURE DEPENDENCE
WATER COOLED REACTORS