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The human factor in licensing and operating the next generation of nuclear plants
As human factors specialists working at the intersection of human performance and nuclear operations, we are witnessing one of the nuclear sector’s most significant transitions in decades. The emergence of small modular reactors, microreactors, and other advanced designs is reshaping the industry’s landscape. Digital instrumentation and controls, passive safety systems, and increased automation are creating opportunities for greater safety margins and more flexible operation. These same features also fundamentally redefine what it means to “operate” a nuclear plant. Interactions among human roles, automation, and passive systems shape how people maintain awareness, exercise judgment, and intervene when necessary. These developments affect both operational realities and the regulatory foundations on which nuclear safety is built.
Andrew P. Hull
Nuclear Technology | Volume 87 | Number 2 | October 1989 | Pages 383-394
Technical Paper | TMI-2: Health Physics and Environmental Release / Radiation Biology and Environment | doi.org/10.13182/NT89-A27728
Articles are hosted by Taylor and Francis Online.
Although the advance planning for it was minimal by today’s standards, a large integrated federal and state environmental monitoring response was made to the Three Mile Island Unit 2 accident. In particular, major resources were committed by the U.S. Department of Energy (DOE). They include the Brookhaven National Laboratory-based Radiological Assistance Program, the Atmospheric Release Advisory Capability, and the Aerial Measurements System, with backup personnel from other DOE national laboratories. Additional resources were provided by the Environmental Protection Agency. The monitoring effort included plume tracking, field environmental monitoring and sampling, sample analysis, and dose assessment. The ranges of the installed plant monitors having been exceeded, these data were important for establishing the nuclides and their quantities in the daily releases from the plant during the first few weeks after the accident. In particular, it was established that the continuing releases consisted almost entirely of radiogases, with very small quantities of radioiodines. The highest measured ground-level dose rate was 1.3 × 102 C/kg (50 mR/h) and the largest concentration of 131I <3.7 × 10−6 Bq/cm3 (<1 × 10−10 µCi/cm3). From DOE population dose assessment, the highest individual dose appears to have been <1 mSv/h (<100 mR/h) and the total population dose 20 person-Sv (∼2000 person-rems). This largely ad hoc response became the basic model for today’s Federal Radiological Monitoring and Assessment Program, which would be put into operation should a major accident occur at a U.S. nuclear facility.