Published February 1985 | Version v1
Report

Methodology for the analysis of dynamic human actions

  • 1. Pickard, Lowe and Garrick, Inc., Newport Beach, CA

Description

A methodology for the analysis of human actions under accident conditions has been developed, which uses information from plant simulator runs, plant procedures, and plant systems information. The objective is to enhance the completeness of the event sequence model (event trees) with respect to both favorable and unfavorable operator actions. Routine human actions that impact the plant at or below the systems level, such as test and maintenance actions, are handled in the systems analysis. Types of dynamic operator actions analyzed in this paper are actions taken during an event sequence that: supplement the automatic response of plant systems for event mitigation, change or detract from the automatic response of plant systems, or lead to recovery of failed systems. The derived results can be used directly in a probabilistic risk assessment. It is judged that the major cause of possible error is misdiagnosis, which can lead to either errors of omission or errors of commission. Operator mistakes may occur when a situation is misclassified or when inappropriate decisions and response selections are made in the operator action sequences. The operator action sequences are modeled in a natural progression of human response, including observation of plant parameters and the diagnosis of the event or the decision to take action

Additional details

Publishing Information

Imprint Title
International topical meeting on probabilistic safety methods and applications: proceedings. Volume 2. Sessions 9-16
Journal Page Range
p. 93.1-93.9.
Report number
EPRI-NP--3912-SR-Vol.2

Conference

Title
International ANS/ENS topical meeting on probabilistic safety methods and applications.
Dates
24 Feb - 1 Mar 1985.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19023381
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ERRORS; FAILURE MODE ANALYSIS; HUMAN FACTORS; NUCLEAR POWER PLANTS; PROBABILITY; REACTOR ACCIDENTS; REACTOR OPERATORS; REACTOR SAFETY; RISK ASSESSMENT; SYSTEMS ANALYSIS; VALVES
Descriptors DEC
ACCIDENTS; CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; NUCLEAR FACILITIES; PERSONNEL; POWER PLANTS; SAFETY; SYSTEM FAILURE ANALYSIS; THERMAL POWER PLANTS