Definitions from 10 CFR 830

Question 1

Define Administrative controls

Answer 1

Means the provisions relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility.

Question 2

Bases appendix

Answer 2

Means an appendix that describes the basis of the limits and other requirements in technical safety requirements.

Question 3

Critical assembly

Answer 3

Means special nuclear devices designed and used to sustain nuclear reactions, which may be subject to frequent core and lattice configuration change and which frequently may be used as mockups of reactor configurations.

Question 4

Criticality

Answer 4

Means the condition in which a nuclear fission chain reaction becomes self-sustaining.

Question 5

Design features

Answer 5

Means the design features of a nuclear facility specified in the technical safety requirements that, if altered or modified, would have a significant effect on safe operation.

Question 6

Document

Answer 6

Means recorded information that describes, specifies, reports, certifies, requires, or provides data or results.

Question 7

Documented safety analysis

Answer 7

Means a documented analysis of the extent to which a nuclear facility can be operated safely with respect to workers, the public, and the environment, including a description of the conditions, safe boundaries, and hazard controls that provide the basis for ensuring safety.

Question 8

Environmental restoration activities

Answer 8

Means the process(es) by which contaminated sites and facilities are identified and characterized and by which contamination is contained, treated, or removed and disposed.

Question 9

Fissionable materials

Answer 9

Means a nuclide capable of sustaining a neutron-induced chain reaction (e.g., uranium-233, uranium-235, plutonium-238, plutonium-239, plutonium-241, neptunium-237, americium-241, and curium-244).

Question 10

Graded approach

Answer 10

Means the process of ensuring that the level of analysis, documentation, and actions used to comply with a requirement in this part are commensurate with:

(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.

Question 11

Hazard

Answer 11

Means a source of danger (i.e., material, energy source, or operation) with the potential to cause illness, injury, or death to a person or damage to a facility or to the environment (without regard to the likelihood or credibility of accident scenarios or consequence mitigation).

Question 12

Hazard Category 1, 2, and 3 DOE nuclear facilities

Answer 12

means nuclear facilities that meet the criteria for their respective hazard category consistent with the provisions of DOE-STD-1027-92, Change Notice 1. Hazard Category 1, 2, and 3 DOE nuclear facilities are required to have safety bases established in accordance with Subpart B of this part. Hazard categories are based on their radioactive material inventories and the potential consequences to the public, workers, and the environment. Hazard Category 1 represents the highest potential consequence and Hazard Category 3 represents the lowest potential consequence of the facilities required to establish safety bases.

Question 13

Hazard controls

Answer 13

Means measures to eliminate, limit, or mitigate hazards to workers, the public, or the environment, including:

(1) Physical, design, structural, and engineering features;
(2) Safety structures, systems, and components;
(3) Safety management programs;
(4) Technical safety requirements; and
(5) Other controls necessary to provide adequate protection from hazards.

Question 14

Item

Answer 14

An all-inclusive term used in place of any of the following: Appurtenance, assembly, component, equipment, material, module, part, product, structure, subassembly, subsystem, system, unit, or support systems.

Question 15

Limiting conditions for operation

Answer 15

Means the limits that represent the lowest functional capability or performance level of safety structures, systems, and components required for safe operations.

Question 16

Low-level residual fixed radioactivity

Answer 16

Means the remaining radioactivity following reasonable efforts to remove radioactive systems, components, and stored materials. The remaining radioactivity is composed of surface contamination that is fixed following chemical cleaning or some similar process; a component of surface contamination that can be picked up by smears; or activated materials within structures. The radioactivity can be characterized as low-level if the smearable radioactivity is less than the values defined for removable contamination by 10 CFR part 835, Appendix D, Surface Contamination Values, and the hazard analysis results show that no credible accident scenario or work practices would release the remaining fixed radioactivity or activation components at levels that would prudently require the use of active safety systems, structures, or components to prevent or mitigate a release of radioactive materials.

Question 17

Major modification

Answer 17

Means a modification to a DOE nuclear facility that substantially changes the existing safety basis for the facility.

Question 18

New Hazard Category 1, 2, and 3 DOE nuclear facility

Answer 18

Means a Hazard Category 1, 2, or 3 DOE nuclear facility that is in design or under construction that does not yet have a DOE approved safety basis.

Question 19

Nonreactor nuclear facility

Answer 19

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.

Question 20

Nuclear facility

Answer 20

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 requirements established by this Part.

Question 21

Operating limits

Answer 21

Means those limits required to ensure the safe operation of a nuclear facility, including limiting control settings and limiting conditions for operation.

Question 22

Preliminary documented safety analysis

Answer 22

means documentation prepared in connection with the design and construction of a new Hazard Category 1, 2, or 3 DOE nuclear facility or a major modification to an existing Hazard Category 1, 2, or 3 DOE nuclear facility that provides a reasonable basis for the preliminary conclusion that the nuclear facility can be operated safely through the consideration of factors such as:

(1) The nuclear safety design criteria to be satisfied;
(2) A safety analysis that derives aspects of design that are necessary to satisfy the nuclear safety design criteria; and
(3) An initial listing of the safety management programs that must be developed to address operational safety considerations.

Question 23

Process

Answer 23

Means a series of actions that achieves an end or result.

Question 24

Quality

Answer 24

Means the condition achieved when an item, service, or process meets or exceeds the user’s requirements and expectations.

Question 25

Quality assurance

Answer 25

Means all those actions that provide confidence that quality is achieved.

Question 26

Quality Assurance Program (QAP)

Answer 26

Means the overall program or management system established to assign responsibilities and authorities, define policies and requirements, and provide for the performance and assessment of work.

Question 27

Reactor

Answer 27

Means any apparatus that is designed or used to sustain nuclear chain reactions in a controlled manner such as research, test, and power reactors, and critical and pulsed assemblies and any assembly that is designed to perform subcritical experiments that could potentially reach criticality; and, unless modified by words such as containment, vessel, or core, refers to the entire facility, including the housing, equipment and associated areas devoted to the operation and maintenance of one or more reactor cores.

Question 28

Record

Answer 28

Means a completed document or other media that provides objective evidence of an item, service, or process.

Question 29

Safety basis

Answer 29

Means the documented safety analysis and hazard controls that provide reasonable assurance that a DOE nuclear facility can be operated safely in a manner that adequately protects workers, the public, and the environment.

Question 30

Safety class structures, systems, and components

Answer 30

Means the structures, systems, or components, including portions of process systems, whose preventive or mitigative function is necessary to limit radioactive hazardous material exposure to the public, as determined from safety analyses.

Question 31

Safety evaluation report

Answer 31

means the report prepared by DOE to document: (1) The sufficiency of the documented safety analysis for a Hazard Category 1, 2, or 3 DOE nuclear facility; (2) The extent to which a contractor has satisfied the requirements of Subpart B of this part; and (3) The basis for approval by DOE of the safety basis for the facility, including any conditions for approval.

Question 32

Safety limits

Answer 32

means the limits on process variables associated with those safety class physical barriers, generally passive, that are necessary for the intended facility function and that are required to guard against the uncontrolled release of radioactive materials.

Question 33

Safety management program

Answer 33

Means a program designed to ensure a facility is operated in a manner that adequately protects workers, the public, and the environment by covering a topic such as: Quality assurance; maintenance of safety systems; personnel training; conduct of operations; inadvertent criticality protection; emergency preparedness; fire protection; waste management; or radiological protection of workers, the public, and the environment.

Question 34

Safety management system

Answer 34

Means an integrated safety management system established consistent with 48 CFR 970.5223-1, Integration of environment, safety, and health into work planning and execution.

Question 35

Safety significant structures, systems, and components

Answer 35

Means the structures, systems, and components which are not designated as safety class structures, systems, and components, but whose preventive or mitigative function is a major contributor to defense in depth and/or worker safety as determined from safety analyses.

Question 36

Service

Answer 36

Means the performance of work, such as design, manufacturing, construction, fabrication, assembly, decontamination, environmental restoration, waste management, laboratory sample analyses, inspection, nondestructive examination/testing, environmental qualification, equipment qualification, repair, installation, or the like.

Question 37

Surveillance requirements

Answer 37

Means requirements relating to test, calibration, or inspection to ensure that the necessary operability and quality of safety structures, systems, and components and their support systems required for safe operations are maintained, that facility operation is within safety limits, and that limiting control settings and limiting conditions for operation are met.

Question 38

Technical safety requirements (TSRs)

Answer 38

Means the limits, controls, and related actions that establish the specific parameters and requisite actions for the safe operation of a nuclear facility and include, as appropriate for the work and the hazards identified in the documented safety analysis for the facility: Safety limits, operating limits, surveillance requirements, administrative and management controls, use and application provisions, and design features, as well as a bases appendix.

Question 39

Unreviewed Safety Question (USQ)

Answer 39

Means a situation where: (1) The probability of the occurrence or the consequences of an accident or the malfunction of equipment important to safety previously evaluated in the documented safety analysis could be increased; (2) The possibility of an accident or malfunction of a different type than any evaluated previously in the documented safety analysis could be created; or (3) The documented safety analysis may not be bounding or may be otherwise inadequate.

Question 40

Unreviewed Safety Question process

Answer 40

Means the mechanism for keeping a safety basis current by reviewing potential unreviewed safety questions, reporting unreviewed safety questions to DOE, and obtaining approval from DOE prior to taking any action that involves an unreviewed safety question.

Question 41

Use and application provisions

Answer 41

Means the basic instructions for applying technical safety requirements.

Question 42

§ 830.4 General requirements.

Answer 42

(a) No person may take or cause to be taken any action inconsistent with the requirements of this part. (b) A contractor responsible for a nuclear facility must ensure implementation of, and compliance with, the requirements of this part. (c) The requirements of this part must be implemented in a manner that provides reasonable assurance of adequate protection of workers, the public, and the environment from adverse consequences, taking into account the work to be performed and the associated hazards. (d) If there is no contractor for a DOE nuclear facility, DOE must ensure implementation of, and compliance with, the requirements of this part.

Question 43

§ 830.5 Enforcement.

Answer 43

The requirements in this part are DOE Nuclear Safety Requirements and are subject to enforcement by all appropriate means, including the imposition of civil and criminal penalties in accordance with the provisions of 10 CFR part 820.

Question 44

§ 830.6 Recordkeeping.

Answer 44

A contractor must maintain complete and accurate records as necessary to substantiate compliance with the requirements of this part.

Question 45

§ 830.7 Graded approach.

Answer 45

Where appropriate, a contractor must use a graded approach to implement the requirements of this part, document the basis of the graded approach used, and submit that documentation to DOE. The graded approach may not be used in implementing the unreviewed safety question (USQ) process or in implementing technical safety requirements.