Document: NUREG-0800
Document ID: 2717fe7f-71fd-4f1e-bd08-7685b24763ba
Document Type: srp
Title: Standard Review Plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for th
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0301/ML030160606.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15
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Content:
c classes of accidents and transients will be developed in the future. Guidance to the industry is proposed in 2 Draft Regulatory Guide DG-1120, “Transient and Accident Analysis Methods” [Ref. 2]. The areas to be reviewed are: 1. Documentation The development of an evaluation model for use in reactor safety licensing calculations requires a substantial amount of documentation. This documentation includes/covers: (a) the evaluation model, (b) the accident scenario identification process, (c) the code assessment, (d) the uncertainty analysis, (e) a theory manual, (f) a user manual, and (g) the quality assurance program. 2. Evaluation Model An evaluation model is the calculation framework for evaluating the behavior of the reactor coolant system during a postulated accident or transient. It includes one or more computer programs and other information necessary for application of the calculation framework to a specific transient or accident, such as mathematical models used, assumptions included in the programs, a procedure for treating the program input and output information, specification of those portions of the analysis not included in the computer programs, values of parameters, and other information necessary to specify the calculation procedure. Evaluation models are sometimes referred to as a licensing methodology. 3. Accident Scenario Identification Process The accident scenario identification process is a structured process used to identify and rank the reactor component and physical phenomena modeling requirements based on (a) their importance to acceptable modeling of the scenario and (b) their impact on the figures of merit for the calculation (e.g., peak cladding temperature and maximum and average cladding oxidation thicknesses). It is also used to identify the key figures of merit or acceptance criteria for the accident. 4. Code Assessment The code assessment provides a complete assessment of all code models against applicable experimental data