The effects of local control station design variation on plant risk
- 1. Brookhaven National Lab., Upton, NY (USA)
Description
A human factors analysis was performed to assess how selected modifications to local control stations (LCSs) in nuclear power plants affect both human performance and plant risk. Modifications in the design of individual control panels and changes in functional centralization were considered. The analysis methodology was accomplished in four stages. First, a list of LCS human engineering design deficiencies was developed using data collected from a variety of sources including visits to nuclear power plants. From these data, a set of potential upgrades were defined to correct the deficiencies. Second, the effects of the upgrades on human error probabilities (HEPs) were determined using a computer-based methodology for soliciting expert judgment. Third, the HEPs were propagated through a plant probabilistic risk assessment, and new core melt frequencies were established. A preliminary, scoping value-impact assessment was performed to evaluate the regulatory need for further review of possible action to improve the human factors engineering aspects of local control stations. The results indicated that implementation of both types of upgrades would improve human performance and lower risk, but that only the panel design improvements would be cost beneficial
Additional details
Publishing Information
- Imprint Title
- Seventeenth water reactor safety information meeting. Proceedings: Volume 1, Luncheon and dinner talks; Equipment qualification of valves; Generic safety issues resolution; Human/system interface and personnel research; Organization and reliability research
- Imprint Pagination
- 489 p.
- Journal Page Range
- p. 295-306.
- Report number
- NUREG/CP--0105-Vol.1
Conference
- Title
- 17. water reactor safety information meeting.
- Dates
- 23-25 Oct 1989.
- Place
- Rockville, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23005560
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BATTELLE PACIFIC NORTHWEST LAB; BWR TYPE REACTORS; CONTROL ROOMS; ENGINEERING; ERRORS; EXPERT SYSTEMS; HUMAN FACTORS; MANAGEMENT; MODIFICATIONS; PROBABILITY; PUBLIC HEALTH; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR CORE DISRUPTION; REACTOR OPERATORS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SPECIFICATIONS; US NRC
- Descriptors DEC
- ACCIDENTS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; MEDICINE; NATIONAL ORGANIZATIONS; PERSONNEL; POWER REACTORS; PREVENTIVE MEDICINE; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8910222--Vol.1.