Organizational factors influencing improvements in safety
- 1. Univ. of Minnesota, Minneapolis (United States)
- 2. Battelle Human Affairs Research Centers, Washington, DC (United States)
- 3. Wayne State Univ., Detroit, MI (United States)
- 4. American Univ., Washington, DC (United States)
Description
Results of conceptual and empirical research conducted by this research team, and published in NUREG-CR 5437, suggested that processes of organizational problem solving and learning provide a promising area for understanding improvement in safety-related performance in nuclear power plants. In this paper the authors describe the way in which they have built upon that work and gone much further in empirically examining a range of potentially important organizational factors related to safety. The paper describes (1) overall trends in plant performance over time on the Nuclear Regulatory Commission performance indicators, (2) the major elements in the conceptual framework guiding the current work, which seeks among other things to explain those trends, (3) the specific variables used as measures of the central concepts, (4) the results to date of the quantitative empirical work and qualitative work in progress, and (5) conclusions from the research
Files
Additional details
Publishing Information
- Imprint Title
- Transactions of the nineteenth water reactor safety information meeting
- Imprint Pagination
- 220 p.
- Journal Page Range
- p. 9.7-9.9.
- Report number
- NUREG/CP--0118
Conference
- Title
- 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059456
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ELECTRIC UTILITIES; FAILURES; MANAGEMENT; MITIGATION; PERFORMANCE; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR OPERATION; REACTOR SAFETY; RESEARCH PROGRAMS; SCRAM; TRANSIENTS; US NRC
- Descriptors DEC
- ACCIDENTS; ELECTRIC POWER INDUSTRY; ENRICHED URANIUM REACTORS; INDUSTRY; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; PUBLIC UTILITIES; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911079--.