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DOE-DP-STD-3016-99
are already in place to prevent or mitigate accidents and the need for any additional safety controls.
The HA shall provide assurance that the safety features of the nuclear explosive are not compromised.
Acceptable methods of HA include combinations of what-if/checklist analysis, process HA, hazard
and operability analysis, failure modes and effects analysis, fault tree and event tree analysis, and
human reliability analysis. In many cases, a combination of these techniques should be employed for
the NEO HA.
The HA evaluates potential hazards associated with specific NEOs and associated activities. The HA
shall consider hazards specific to the operation, including failure of equipment, tooling, support
systems, and human actions. The HA shall also address hazards external to the facility where the
operations are conducted (e.g., natural phenomena, transportation accidents, explosions or accidents at
neighboring facilities), and hazards internal to the facility but external to the operation (e.g., fires and
floods). Based on these analyses, the HA identifies and evaluates the effectiveness of relevant safety
controls including systems, structures, components, tooling, and equipment that are necessary to
prevent accidents or mitigate consequences. Due in part to the large uncertainty associated with
accident scenario likelihood, selection of controls should use safety conservative expert judgment.
Human reliability is an important element in nuclear explosive safety and needs to be considered in
both the HA and controls development. NEOs primarily entail hands-on tasks involving direct work
with the nuclear explosive; as a result, the potential for human error must be considered in the
development of hazard scenarios.
Generally, rare events have large uncertainties in accident frequency estimates due to a lack of data
concerning occurrence frequency, accident progression, and phenomenology; therefore, qualitative
estimates are sufficient for hazard scenario likelihoods. While quantitative uncertainty analysis is not
required, the magnitude of the uncertainties and the potential impact of large uncertainties on the
results should be discussed and documented in qualitative terms. Additional deterministic or
probabilistic calculations should be employed to provide a better understanding of the largest
consequence accident scenarios.
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