Equipment failure. Equipment failure is defined as a condition in which equipment can no longer perform
their design requirements.
Equipment database. The equipment database cross references structures, systems, and components with
their design requirements, design basis, and associated documents. It is the primary source for design
requirements. See section 4.8 of the standard.
Facility documents. Those documents that support facility operations, such as-built configuration
information (such as drawings, valve lists, etc.), the facility procedures for activities (such as operations,
maintenance, and testing), and facility operational records (such as completed tests, work requests, and
radiation survey maps).
Formal review. A process through which design information is identified and retrieved from on-hand, top-
level, summary-type design documents such as the Safety Analysis Reports, Technical Safety
Requirements, and System Design Descriptions.
Graded approach. The term graded approach, when used in this standard, means the process of ensuring
that the level of analysis, documentation, and actions used to comply with a requirement in this part are
(1) The relative importance to safety, safeguards, and security;
(2) The magnitude of any hazard involved;
(3) The life cycle stage of a facility;
(4) The programmatic mission of a facility;
(5) The particular characteristics of a facility;
(6) The relative importance of radiological and nonradiological hazards; and
(7) Any other relevant factor.
(10 CFR Part 830)
Independent design verification. Independent design verification is a verification performed by a person
other than the person who performed the original design work. It is the act of checking the design or
requirement, often by using a different calculation method, to verify that the structure, system or
component will meet established performance criteria.
Integrated Safety Management System (ISMS). See Safety Management System.
Major modification. Major modification means a modification to a DOE nuclear facility that substantially
changes the existing safety basis for the facility. (10 CFR Part 830)
Master equipment list (MEL). The master equipment list is a detailed master list of equipment,
components, and structures to be included in the maintenance program. This includes both safety-related
and non-safety-related systems and equipment. (DOE G 433.1-1)
Nonreactor nuclear facility. Nonreactor nuclear facility means those facilities, activities or operations that
involve, or will involve, radioactive and/or fissionable materials in such form and quantity that a nuclear or
a nuclear explosive hazard potentially exists to workers, the public, or the environment, but does not
include accelerators and their operations and does not include activities involving only incidental use and
generation of radioactive materials or radiation such as check and calibration sources, use of radioactive
sources in research and experimental and analytical laboratory activities, electron microscopes, and X-ray
machines. (10 CFR Part 830)
Nuclear facility. Nuclear facility means a reactor or a nonreactor nuclear facility where an activity is
conducted for or on behalf of DOE and includes any related area, structure, facility, or activity to the extent
necessary to ensure proper implementation of the applicable requirements. (10 CFR Part 830)