Document: NUREG-0800
Document ID: 643ab154-682e-480f-a57b-a5fd7390a34e
Document Type: srp
Title: REVIEW OF TRANSIENT AND ACCIDENT ANALYSIS METHODS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0535/ML053550265.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.2
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Lead Organization with Responsibility for Review of Transient and Accident Analyses Secondary - Other Organizations with Responsibility for Review of Transient and Accident Analyses I. AREAS OF REVIEW In order to establish a licensing basis, licensees must analyze transients and accidents in accordance with the requirements of 10 CFR 50.34, 10 CFR 50.46, and where applicable, per NUREG-0737, “Clarification of TMI Action Plan Requirements.” These accidents and transients are described in the Standard Review Plan (SRP) (NUREG-0800) [Ref. 1]. This section of the SRP describes the review process and acceptance criteria for analytical models and computer codes used by licensees to analyze accident and transient behavior. The purpose of the review is to verify that the evaluation model is adequate to simulate the accident under consideration. This includes methods to estimate the uncertainty in the calculation, as in the case of a best estimate loss of coolant accident (LOCA); or to ensure that the results of the analysis are demonstrably conservative, as in the case of a LOCA in Appendix K to 10 CFR Part 50. This review is independent of the type of application submitted (e.g., license amendment, topical report, design certification, or combined license application). The guidance in this section should be applicable to most of the transients and accidents described in the SRP. Appendices that provide specific information for specific classes of accidents and transients will be developed in the future. Guidance to the industry is set forth in Regulatory Guide 1.203, “Transient and Accident Analysis Methods” [Ref. 2]. The following sections discuss the areas to be reviewed. 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