Actions for Human error model adaptation and validation for Savannah River Site nonreactor facilities [electronic resource].

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Human error model adaptation and validation for Savannah River Site nonreactor facilities [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 1993.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
7 pages : digital, PDF file
Additional Creators
Westinghouse Savannah River Company, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
As part of an overall effort to improve safety analysis methods for the Savannah River Site (SRS) nonreactor nuclear facilities, a comprehensive human reliability analysis (HRA) methodology has been developed and selectively validated. The HRA methodology covers a wide variety of human errors that may exist in risk analyses of the nonreactor nuclear facilities. Such risk analyses are an integral part of safety analysis reports (SARS) at the SRS, forming the basis for severe accident analysis and assisting in the identification of safety classes for equipment. Nonreactor nuclear facilities at the SRS include nuclear fuel fabrication and reprocessing, nuclear waste processing, and nuclear waste storage and disposal. The SRS HRA methodology improvement included both adaptation of existing human error models and validation of selected model results with SRS-specific data on actual human errors. The data were obtained from three existing SRS data bases: (1) Fuel Processing, (2) Fuel Fabrication, and (3) Waste Management. These three are part of the Risk Analysis Methodology (RAM) Fault Tree data banks. Events in these data banks are obtained from a wide variety of sources, including operator log books, occurrence reports, safety newsletters, and others. Validation of the human error models involved comparison with SRS-specific data and calibration of model results where appropriate.
Report Numbers
E 1.99:wsrc-ms--93-245
E 1.99: conf-940312--6
conf-940312--6
wsrc-ms--93-245
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
09/01/1993.
"wsrc-ms--93-245"
" conf-940312--6"
"DE93040722"
2. Probabilistic safety assessment and management conference (PSAM),San Diego, CA (United States),20-24 Mar 1994.
Olsen, L.M.; Eide, S.A.; Benhardt, H.C.; Held, J.E.; Vail, R.E.
Funding Information
AC09-89SR18035
View MARC record | catkey: 14417249