Published October 1989 | Version v1
Report

A method to integrate human factors expertise into the PRA process

  • 1. Lawrence Livermore National Lab., CA (USA)

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.