Nuclear Hazard Category 1 Facilities

DOE-STD-1027-92

Consequence Analysis

Consequence analysis is the final step in the accident analysis section of the SAR.

For Category 2 facilities, the following analyses must be provided.

Source Term Analysis - Provide a reasonably conservative analysis by using

defensible realistic values of the characteristics of the release from the

building. This analysis includes the amount and form of material, the timing

of the release, energy, particle size distribution, etc.

Dose Assessment - Perform dose calculations by using conservative analysis

techniques for workers and site boundary distances.

Nuclear Hazard Category 1 Facilities

4.1.2.c

DEFINITION

Hazard Analysis shows the potential for significant off-site consequences.

INTERPRETATION

Category A reactors and facilities designated by the PSO.

Release Mechanisms

Refer to the discussion in Category 2 for release mechanism analysis techniques.

It should be noted that large reactors would probably be considered highly

complex facilities and utilize fully, integrated, quantitative ET and FT techniques.

Sequence Selection

For highly complex facilities, an extensive set of accident sequences need to be

categorized so that a reasonable spectrum of sequences is analyzed.

Engineering Analysis

Extensive engineering analysis is required for Category 1 facilities.

Consequence Analysis

The requirements are the same as the ones given for Category 2 facilities.