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| DOE-STD-1173-2003
c.
Define the following safety limit related terms:
Limiting conditions for operations
Limiting control settings
Risk
Safety analysis
Safety basis
Safety limits
Criticality safety limits
d.
Differentiate between the following categories of individuals who may be affected
by an accident at a Department nuclear facility:
Off-site individual
On-site individual
Public
Worker, including collocated worker
e.
Differentiate between the function of structures, systems, and components in the
following classifications:
Safety-class structures, systems, and components
Safety-significant structures, systems and components
f.
Differentiate between the function and contents of the following documents:
Safety Analysis Report (SAR)
Technical Safety Requirements (TSR)
Documented Safety Analysis (DSA)
Unreviewed Safety Question Determination (USQD)
g.
Differentiate between the plant/facility features which have the following
designations:
Mitigating features
Preventive features
h.
Differentiate between the following types of facilities:
Nuclear facility
Non-reactor nuclear facility
7.
Criticality safety personnel shall demonstrate a familiarity level knowledge of
nuclear accident analysis techniques.
Supporting Knowledge and/or Skills
8
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