ISMS GUIDELINES FOR FACILITY DISPOSITION AND
Safety basis documents that exists from previous phases of facility or environmental restoration
operation or disposition is evaluated and used only when the following information is provided:
(1) a description of the site and location, including current facility and site boundaries; (2)
design criteria for those safety structures, systems, or components (for nuclear facilities, safety
class and safety-significant equipment are defined by DOE-STD-3009-94) needed to support
safe facility disposition work; (3) normal and emergency operating procedures based on a
hazard analysis that is still representative of planned future work; and (4) operational limitations
to address existing facility vulnerabilities.
environmental permits (e.g., RCRA and CAA) has been determined and the needed permits
have been obtained and mechanisms are in place to ensure that the work complies with the
For decommissioning and environmental restoration projects, the need for required
environmental permits (e.g., RCRA and CAA) has been determined and the substantive aspects
of applicable permits have been incorporated into the set of ARARs that are determined for the
PERFORM THE WORK
A readiness evaluation is conducted that ensures all hazards have been identified, S&H
requirements have been met, and safety systems and controls are in place and functional.
Workers are qualified to perform the required task(s) and understand the associated hazards and
Applicable environmental permits and procedures are in place and controls are operable.
Work authorization is obtained.
Verification of the resolution of applicable readiness assessment findings is completed.
Management of Change
A change control process should be employed that evaluates changes to work plans, procedures,
and effects from unforeseen hazards. The process should encompass screening all changes, the
evaluation of changes to hazards and controls, verification that the changes are within the
existing safety basis, and specification of actions necessary if a change is outside of the safety
For category 2 or 3 nuclear facilities, tasks are screened against the seven questions defined in
DOE G 4242.1-1 to determine whether they represent a potential USQ.
FEEDBACK AND EVALUATION
Feedback mechanisms are in place and include monitoring and self-assessment.
Performance monitoring reflects appropriate and measurable ES&H indicators and measures
that encompass integrated safety management activities.
Self-assessment of the ES&H program is performed periodically and includes an evaluation of
both management commitments and worker involvement.