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Contents cont'd - doe-std-3009-94_cn3_3-30-060017
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Preparation Guide for U
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Evaluation Guideline (EG)


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.
Page xviii


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