Format and Content of Criticality Safety Evaluations

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