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Definitions - s3007cn10011
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Guidelines For Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities
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Introduction - s3007cn10013


DOE-STD-3007-93
Criticality safety evaluations that are prepared for Department of Energy (DOE) Non-Reactor
Nuclear Facilities should conform to the format and content guidelines provided in this section.
An outline of an evaluation is given below. All evaluations used to demonstrate facility safety
shall contain, at an appropriate level of detail, the information embodied in these major sections.
These sections should appear in the specified order whenever practical. [Criticality safety
evaluations for transportation packages that are required to follow a pre-specified Nuclear
Regulatory Commission (NRC) format are exceptions.] Subsections may be used at the author's
discretion to provide order and clarity. A description of each section of an evaluation follows the
outline.
1.0
INTRODUCTION
2.0
DESCRIPTION
3.0
REQUIREMENTS DOCUMENTATION
4.0
METHODOLOGY
5.0
DISCUSSION OF CONTINGENCIES
6.0
EVALUATION & RESULTS
7.0
DESIGN FEATURES (PASSIVE & ACTIVE) AND
ADMINISTRATIVELY CONTROLLED LIMITS &
REQUIREMENTS
8.0
SUMMARY & CONCLUSIONS
9.0
REFERENCES
APPENDIX A:
MATERIALS & COMPOSITIONS
APPENDIX B:
TYPICAL INPUT LISTINGS
APPENDIX C, D,... ETC.:
OPTIONAL APPENDICES PROVIDING SUPPLEMENTAL
INFORMATION
3


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