Published May 1999 | Version v1
Report

Procedural guidance levels in computerized plant operation

  • 1. CEA DRN, Cadarache (France)

Description

The computerization of the operation of nuclear plants tends, in some cases, to put emphasis on some problems that existed already in conventional hardwired panel-based control rooms. Among these, the search for an optimal balance between operator initiative and the prescriptive guidance provided by the operating procedures has always been a subject of concern, which is coming to the foreground with the computerization of these operating procedures.In this case, the main concern in to balance the excessive rigidity of the computerized tool that often reflects only theoretical prescriptions, by providing for some human adaptation to the actual operating conditions and to the actual operator activity. On the other hand, a minimum level of operator guidance must be maintained to avoid operating errors and missing of important constraints which may in some cases not appear clearly in the logical unfolding of the task. Thus the problem is to search for computerized guiding means realizing a good compromise between total computer responsibility (task automation) and unbounded operator initiative.The Reactor Operation Assistance Laboratory (LAER) of the CEA has launched a reflexion about this problem related to the share of decisional responsibility between the operators and the computerized operation systems. This paper resumes the basic aspects of procedural guidance, insisting upon the distinction between the strategical level (tasks structuration accounting for the plant physical constraints) and the tactical level (task carrying out respecting local constraints on plant systems).The presentation focuses on the tactical aspects, for which several guidance alternatives, (following automation level scales proposed in the literature), are analyzed on the basis of a generic system start-up task illustration. A computer prototype has been realized to put in a concrete form these various alternatives.This paper concludes with a discussion about the potential benefit of extended comparative tests on a representative testing bench (author) (ml)

Part of:
Enlarged Halden programme group meeting on man-machine systems research and high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects. Volume I

Additional details

Publishing Information

Imprint Title
Man-machine systems research and high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects
Imprint Pagination
vp.
Journal Page Range
6 p.
Report number
HPR--352/v.1

Conference

Title
Enlarged HPG meeting on man-machine systems research and high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects
Dates
24-29 May 1999
Place
Loen (Norway)

INIS

Country of Publication
Norway
Country of Input or Organization
Norway
INIS RN
38116856
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Non-conventional Literature, Conference
Descriptors DEI
COMPUTERS; CONTROL ROOMS; CONTROL SYSTEMS; DOCUMENTATION; ELECTRONIC GUIDANCE; ENGINEERED SAFETY SYSTEMS; HUMAN FACTORS; INFORMATION SYSTEMS; MAN-MACHINE SYSTEMS; NUCLEAR POWER PLANTS; REACTOR OPERATION; REACTOR SAFETY; SAFETY STANDARDS; TECHNOLOGY TRANSFER
Descriptors DEC
CONTROL SYSTEMS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; SAFETY; STANDARDS; THERMAL POWER PLANTS

Optional Information

Notes
4 refs., 5 figs