Definitions - doe-std-3009-94_cn3

DOE-STD -3009-94

Definitions

Notes: Origins of the definitions are indicated by references shown in "[ ]" (brackets). If

no reference is listed, the definition originates in this Preparation Guide and is unique to its

application.

Accident. An unplanned sequence of events that results in undesirable consequences.

Accident analysis. Accident analysis has historically consisted of the formal

development of numerical estimates of the expected consequence and probability of

potential accidents associated with a facility. For the purposes of implementing this

Standard, accident analysis is a follow-on effort to the hazard analysis, not a

fundamentally new examination requiring extensive original work. As such, it requires

documentation of the basis for assignment to a given likelihood of occurrence range in

hazard analysis and performance of a formally documented consequence analysis.

Consequences are compared with the Evaluation Guideline to identify safety-class

structures, systems, and components.

Administrative controls (ACs). Provisions relating to organization and management

procedures, record keeping, assessment, and reporting necessary to ensure the safe

operation of a facility. [10 CFR 830]

Organization and management, procedures, recordkeeping, assessment, and reporting

necessary to ensure safe operation of a facility consistent with the technical safety

requirement. In general, the administrative controls section addresses (1) the requirements

associated with administrative controls, (including those for reporting violations of the

technical safety requirement); (2) the staffing requirements for facility positions important

to safe conduct of the facility; and (3) the commitments to the safety management

programs identified in the documented safety analysis as necessary components of the

safety basis for the facility. [10 CFR 830 Appendix A]

Beyond design basis accident. An accident of the same type as a design basis accident

(e.g., fire, earthquake, spill, explosion, etc.) but defined by parameters that exceed in

severity the parameters defined for the design basis accident. The same correlation applies

to beyond derivative design basis accidents with regard to derivative design basis

accidents.

Decommissioning. Those actions tak ing place after deactivation of a nuclear facility to

retire it from service and includes surveillance and maintenance, decontamination, and

dismantlement. [10 CFR 830]

Decontamination. The removal or reduction of residual radioactive and other

hazardous materials by mechanical, chemical, or other techniques to achieve a stated

objective or end condition. [10 CFR 830]

Design basis. The set of requirements that bound the design of systems, structures,

and components within the facility. These design requirements include consideration

of safety, plant availability, efficiency, reliability, and maintainability. Some aspects

of the design basis are important to safety, although others are not.

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