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
CFR Part: 
CFR Title: 

Content:
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 and/or exact solutions in order to demonstrate that the code is adequate for analyzing the chosen scenario. 5. Uncertainty Analysis Uncertainty analyses are performed to confirm that the combined code and application uncertainty is less than the design margin for the safety parameter of interest when the code is used in a licensing calculation. Examples of safety parameters are Peak Cladding Temperature (PCT), cladding oxidation thickness, Departure From Nucleate Boiling Ratio (DNBR), and Critical Power Ratio (CPR). 6. Quality Assurance Plan The quality assurance plan covers the procedures for design control, document control, software configuration control and testing, and error identification and corrective actions used in the development and maintenance of the evaluation model. The program also 3 ensures adequate training of personnel involved with code development and maintenance, as well as those who perform the analyses. II. ACCEPTANCE CRITERIA The acceptance criteria are based on meeting the requirements of the regulations in 10 CFR Part 50 that govern the evaluation models for the specific accident under consideration (e.g., 10 CFR 50.46 for a LOCA). The specific criteria are as follows: 1. Documentation The submittal must identify the specific accident scenarios and plant configurations for which the codes will be used. The evaluation model documentation must be scrutable, complete, unambiguous, accurate, and reasonably self-contained. Consistent nomenclature must be used throughout the entire model documentation. Any referenced material must be readily available from a technical library. Copies of any referenced documents that are not readily obtainable from a technical library or the NRC Public Document Room, including proprietary reports, must be included