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Administrative Controls - doe-std-3009-94_cn3_3-30-060097
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Criticality Infraction Reporting and Follow-Up


DOE-STD -3009-94
requirements for committee members. This summary may be provided in this
chapter or Chapter 17, "Management, Organization, and Institutional Safety
Provisions."
6.5.2
Criticality Safety Plans and Procedures
This section summarizes the criticality safety plans and procedures for
governing operations involving fissile materials. Discuss the document control
measures employed to ensure that plans and procedures, including changes, are
reviewed for adequacy, approved for release by authorized personnel, and
distributed to and used at the locations where fissile materials are used,
processed, or stored.
Include in the summary abstracts of procedures for posting criticality safety
limits, material and operational controls, review of operations, emergency
evacuation, and guidelines for permitting fire fighting water or other
moderating materials used to suppress fires within or adjacent to moderation
control areas. These guidelines on fire fighting are based on comparisons of
risks and consequences of accidental criticality with the risks and
consequences of postulated fires for the respective areas. The bases for
guidelines for fire fighting are to be referenced or documented here. This
section is interdependent with Chapter 11, "Operational Safety" and Chapter
17, "Management, Organization, and Institut ional Safety Provisions."
6.5.3
Criticality Safety Training
This section summarizes the scope of facility wide criticality safety training as
well as the specific training requirements for personnel associated with the
operation of the facility. Discuss specifically the training of personnel on the
configuration of the equipment used to store, handle, transport, or process
fissile material. Reference, as appropriate, Chapter 12, "Procedures and
Training" if that chapter presents requested information.
6.5.4
Determination of Operational Nuclear Criticality Limits
This section summarizes the analytical approach (i.e., methods, codes, and
analysis techniques) used to derive operational nuclear criticality limits,
including the error contingency criteria or margin of error (uncertainty), the
use of contingency analyses, and the basic justification of the appropriateness
of such an approach (i.e., bases and design criteria). This section should not
include detailed calculations and limits for the facility.
This section explains and demonstrates the relationship between operational
nuclear criticality limits and their TSR designations.
6.5.5
Criticality Safety Inspections/Audits
This section summarizes the criticality safety inspection and audit programs
that verify the established procedures used for preventing inadvertent
criticalities. This includes their responsibilities and authorizations and the
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