Published 1996 | Version v1
Report Open

Core damage frequency (reactor design) perspectives based on IPE results

Description

This paper provides perspectives gained from reviewing 75 Individual Plant Examination (IPE) submittals covering 108 nuclear power plant units. Variability both within and among reactor types is examined to provide perspectives regarding plant-specific design and operational features, and C, modeling assumptions that play a significant role in the estimates of core damage frequencies in the IPEs. Human actions found to be important in boiling water reactors (BWRs) and in pressurized water reactors (PWRs) are presented and the events most frequently found important are discussed

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE97003198; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
18 p.
Report number
SAND--97-0339C

Conference

Title
24. water reactor safety information meeting.
Dates
21-23 Oct 1996.
Place
Bethesda, MD (United States).

INIS

Optional Information

Contract/Grant/Project number
Contract AC04-94AL85000
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
CONF-9610202--5.