Document: NUREG-1555
Document ID: 07028c9f-5219-46b4-8c75-bb8fea4e2d2a
Document Type: esrp
Title: DESIGN BASIS ACCIDENTS
Source: NUREG-1555
Source URL: https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1555/initial/
Revision Date: 2007-10
Chapter: 7
Section ID: 7.1
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Content:
ty Analysis Reports for Nuclear Power Plants - LWR Edition (NRC 1978) with respect to analyses of DBAs other than loss-of- coolant accidents ` Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants (NRC 1982) with respect to information on dispersion models ` Regulatory Guide 4.2, Rev. 2, Preparation of Environmental Reports for Nuclear Power Stations (NRC 1976) with respect to the calculation of χ/Q values for determining offsite dose consequences from postulated accidents. Technical Rationale The technical rationale for evaluation of the applicant’s plant accident data is discussed in the following paragraphs: Applicants for construction permits, operating licenses, combined licenses and early site permits are required to evaluate the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from the operation of the facility. For construction-permit applications, this information is to be contained in a preliminary safety analysis report (PSAR). Applicants for operating licenses and combined licenses are required to prepare a final safety analysis report (FSAR). Events up through Class 8 accidents were previously the only accidents considered in SARs and staff SERs. They were and are currently used, together with conservative assumptions, as the design basis events to establish the performance requirements of engineered safety features. Guidance on reviewing safety analysis report submittals related to postulated accidents is in Chapter 15 of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NRC 1985). The SRP Chapter 15 contains the methodology for reviewing the models, assumptions, and parameter values used to determine the offsite releases from DBAs. However, the conservative assumptions and calculations used in NRC safety evaluations