Kevin O'Kula and Jackie East
Westinghouse Safety Management Solutions, LLC

Chris Steele
Department of Energy/Los Alamos Operations Office

.5 IH CM point

Since the publication of DOE-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, safety analysts have had guidance in performing accident and consequence analyses for DOE nuclear facilities. Recently, Appendix A (Evaluation Guideline) to the Standard has been released, augmenting earlier guidance. Together with Regulatory Guide 1.145 and other resources, definitive recommendations for the calculation of radiological exposures from postulated accident events are available. This training session will discuss appropriate methods, computer models, and user input to assist the preparation and execution of radiological dispersion and consequence analyses for DOE Authorization Basis documents against the current regulatory perspective.

Several key topics will be covered, including:

1. Overview of Requirements for Authorization Basis Consequence Analyses

2. Applicable Methods, Focusing on Gaussian Methodology

3. Computer Model Evaluation 4. "Best Practices"

5. Sample Analyses

6. Modeling Detonation and Deflagration Events.

The training will also discuss minimum Software Quality Assurance criteria for dispersion and consequence models in light of the Defense Nuclear Facilities Safety Board staff Technical Report 25, Quality Assurance for Safety-Related Software at Department of Energy Defense Nuclear Facilities. Participants will receive copies of the Accident Phenomenology and Consequence (APAC) Methodology Evaluation Working Group 5 report on Radiological/Dispersion Computer Models.