SciTech Connect

Title: SHEAN (Simplified Human Error Analysis code) and automated THERP

SHEAN (Simplified Human Error Analysis code) and automated THERP One of the most widely used human error analysis tools is THERP (Technique for Human Error Rate Prediction). Unfortunately, this tool has disadvantages. The Nuclear Regulatory Commission, realizing these drawbacks, commissioned Dr. Swain, the author of THERP, to create a simpler, more consistent tool for deriving human error rates. That effort produced the Accident Sequence Evaluation Program Human Reliability Analysis Procedure (ASEP), which is more conservative than THERP, but a valuable screening tool. ASEP involves answering simple questions about the scenario in question, and then looking up the appropriate human error rate in the indicated table (THERP also uses look-up tables, but four times as many). The advantages of ASEP are that human factors expertise is not required, and the training to use the method is minimal. Although not originally envisioned by Dr. Swain, the ASEP approach actually begs to be computerized. That WINCO did, calling the code SHEAN, for Simplified Human Error ANalysis. The code was done in TURBO Basic for IBM or IBM-compatible MS-DOS, for fast execution. WINCO is now in the process of comparing this code against THERP for various scenarios. This report provides a discussion of SHEAN.
Authors:
Publication Date:
OSTI Identifier:10162198
Report Number(s):WINCO--11908; CONF-9302122--1
ON: DE93014904; TRN: 93:015325
DOE Contract Number:AC07-84ID12435
Resource Type:Conference
Resource Relation:Conference: GOCO database meeting,Augusta, GA (United States),2-3 Feb 1993; Other Information: PBD: [1993]
Research Org:Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)
Sponsoring Org:USDOE, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; HUMAN FACTORS; S CODES; REACTOR OPERATORS; RELIABILITY; ERRORS; T CODES; SAFETY ANALYSIS; REACTOR SAFETY 220900; 990200; REACTOR SAFETY; MATHEMATICS AND COMPUTERS