Published October 1989 | Version v1
Report

User involvement in system design of an advanced safety parameter display system for the Forsmark 2 nuclear power plant

  • 1. Swedish State Power Board, Vaellingby (Sweden)
  • 2. Forsmark Nuclear Power Plant, Oesthammar (Sweden). Forsmark 2 Operational Dept.

Description

A safety parameter display system is being developed for the Forsmark 2 nuclear power plant. The system should support the plant accident management strategy ranging from handling of transients to severe accidents. This paper summarizes the guiding principles behind the SPDS system development. The system will support the operators decision-making by presenting information in a concentrated form. The system will primarily be a tool for the shift supervisor and closely connected to the emergency operating procedures (EOP). The system will monitor the four critical safety functions; reactivity, core cooling, heat sink and radioactive release barriers. A successful implementation of an SPDS system must in the early design process involve the end users, a new information system must also be strongly connected to existing work routines at the NPP. Human needs and limitations must be carefully considered in the development of computerized operator aids, human factors experts must also be involved in the early design process. Our intention in the Forsmark projects is to use an accurate model of the system end user while developing an SPDS system. This will be done by using a multidisciplinary project group and through active involvement of the end users in the design process. (author). 7 refs

Part of:
User requirements for decision support systems used for nuclear power plant accident prevention and mitigation

Additional details

Publishing Information

Imprint Title
User requirements for decision support systems used for nuclear power plant accident prevention and mitigation
Imprint Pagination
207 p.
Journal Page Range
p. 97-102.
Report number
IAEA-TECDOC--529

Conference

Title
Technical committee on user requirements for decision support systems.
Dates
28 Nov - 1 Dec 1988.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
21072043
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL ROOMS; DISPLAY DEVICES; FORSMARK-2 REACTOR; MAN-MACHINE SYSTEMS; REACTOR MONITORING SYSTEMS; REACTOR OPERATORS; REACTOR SAFETY
Descriptors DEC
BWR TYPE REACTORS; COMPUTER-GRAPHICS DEVICES; ENRICHED URANIUM REACTORS; PERSONNEL; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information