A method to integrate human factors expertise into the PRA process
Description
In response to the recognition of need, the USNRC has initiated research directed toward the integration of human factors and hardware engineering expertise throughout the PRA process. Success in this area is perceived as vital to the overall credibility of future PRAs. That is, no matter how adequate state of knowledge single task and sequence evaluation methods are, if they are not fully exploited by qualified human factors and human reliability specialists, realistic assessments of human and hardware performance separately, and in combination, will not be achieved. Also, in response to the prevailing state of PRA, the USNRC has initiated research directed toward methods for systematically applying PRA results as a technical base to: (1) retrofit/redesign equipment-centered and personnel-centered components of commercial nuclear power plants, (2) prioritize and resolve industry-wide safety issues involving human behavior, (3) establish risk-based performance measures for monitoring the effectiveness of operations, maintainability, test and surveillance programs, and (4) establish criteria for selecting, training and licensing, and subsequently evaluating the performance of plant personnel. This paper presents a method for integrating broad-based human factors expertise into the probabilistic risk assessment (PRA)/human reliability analysis (HRA) process in a standardized manner to achieve results which: (1) provide more realistic estimates of the impact of human performance on nuclear power safety, (2) can be fully audited, (3) provide a firm technical base for equipment-centered and personnel-centered retrofit/redesign of plants enabling them to meet internally and externally imposed safety standards, and (4) yield human and hardware data capable of supporting inquiries into human performance issues which transcend the individual plant
Additional details
Publishing Information
- Imprint Title
- Transactions of the seventeenth water reactor safety information meeting
- Imprint Pagination
- 186 p.
- Journal Page Range
- p. 10.1-10.2.
- Report number
- NUREG/CP--0104
Conference
- Title
- 17. water reactor safety information meeting.
- Dates
- 23-25 Oct 1989.
- Place
- Rockville, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22051908
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EQUIPMENT; ERRORS; HUMAN FACTORS; INFORMATION; MODIFICATIONS; NUCLEAR POWER PLANTS; PERFORMANCE; PERSONNEL; REACTOR SAFETY; RELIABILITY; RESEARCH PROGRAMS; RISK ASSESSMENT
- Descriptors DEC
- NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-8910222--Summs.