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Regulatory decision making by decision analyses

Abstract

The Technical Research Centre of Finland (VTT) has studied with the Finnish Centre for Radiation and Nuclear Safety (STUK) the applicability of decision analytic approach to the treatment of nuclear safety related problems at the regulatory body. The role of probabilistic safety assessment (PSA) in decision making has also been discussed. In the study, inspectors from STUK exercised with a decision analytic approach by reoperationalizing two occurred and solved problems. The research scientist from VTT acted as systems analysts guiding the analysis process. The first case was related to a common cause failure phenomenon in solenoid valves controlling pneumatic valves important to safety of the plant. The problem of the regulatory body was to judge whether to allow continued operation or to require more detailed inspections and in which time chedule the inspections should be done. The latter problem was to evaluate design changes of external electrical grid connections after a fire incident had revealed weakness in the separation of electrical system. In both cases, the decision analysis was carried out several sessions in which decision makers, technical experts as well as experts of decision analysis participated. A multi-attribute value function was applied as a decision model so that attributes  More>>
Authors:
Holmberg, J; Pulkkinen, U [1] 
  1. Technical Research Centre of Finland, Espoo (Finland). Lab. of Electrical and Automation Engineering
Publication Date:
Nov 01, 1993
Product Type:
Technical Report
Report Number:
STUK-YTO-TR-61
Reference Number:
SCA: 210000; PA: AIX-25:036980; EDB-94:080297; ERA-19:018480; NTS-94:022093; SN: 94001207878
Resource Relation:
Other Information: PBD: Nov 1993
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; REACTOR SAFETY; DECISION TREE ANALYSIS; ELECTRICAL FAULTS; FAILURES; INSPECTION; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; RISK ASSESSMENT; SOLENOIDS; VALVES; 210000; NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
OSTI ID:
10152740
Research Organizations:
Finnish Centre for Radiation and Nuclear Safety (STUK), Helsinki (Finland)
Country of Origin:
Finland
Language:
English
Other Identifying Numbers:
Other: ON: DE94624678; ISBN 951-47-8424-3; TRN: FI9400024036980
Availability:
OSTI; NTIS; INIS
Submitting Site:
FIN
Size:
34 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Holmberg, J, and Pulkkinen, U. Regulatory decision making by decision analyses. Finland: N. p., 1993. Web.
Holmberg, J, & Pulkkinen, U. Regulatory decision making by decision analyses. Finland.
Holmberg, J, and Pulkkinen, U. 1993. "Regulatory decision making by decision analyses." Finland.
@misc{etde_10152740,
title = {Regulatory decision making by decision analyses}
author = {Holmberg, J, and Pulkkinen, U}
abstractNote = {The Technical Research Centre of Finland (VTT) has studied with the Finnish Centre for Radiation and Nuclear Safety (STUK) the applicability of decision analytic approach to the treatment of nuclear safety related problems at the regulatory body. The role of probabilistic safety assessment (PSA) in decision making has also been discussed. In the study, inspectors from STUK exercised with a decision analytic approach by reoperationalizing two occurred and solved problems. The research scientist from VTT acted as systems analysts guiding the analysis process. The first case was related to a common cause failure phenomenon in solenoid valves controlling pneumatic valves important to safety of the plant. The problem of the regulatory body was to judge whether to allow continued operation or to require more detailed inspections and in which time chedule the inspections should be done. The latter problem was to evaluate design changes of external electrical grid connections after a fire incident had revealed weakness in the separation of electrical system. In both cases, the decision analysis was carried out several sessions in which decision makers, technical experts as well as experts of decision analysis participated. A multi-attribute value function was applied as a decision model so that attributes had to be defined to quantify the levels of achievements of the objectives. The attributes included both indicators related to the level of operational safety of the plant such as core damage frequency given by PSA, and indicators related to the safety culture, i.e., how well the chosen option fits on the regulatory policy. (24 refs., 6 figs., 9 tabs.).}
place = {Finland}
year = {1993}
month = {Nov}
}