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:
e effluent release points (from ESRP 2.7). II. ACCEPTANCE CRITERIA Acceptance criteria for the review of environmental impacts of postulated accidents involving radioactive material and related to the plant are based on the relevant requirements of the following: ` 10 CFR 50.34 with respect to the applications for construction permits and operating licenses. This includes an analysis and evaluation of 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 operation of the facility. ` 10 CFR 52.17 with respect to applications for early site permits ` 10 CFR 52.79 for combined licenses with regard to requirements in 10 CFR 50.34 for the analysis and evaluation of 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 operation of the facility Regulatory positions and specific criteria necessary to meet the regulations identified above are as follows: ` Regulatory Guide 1.3, Rev. 2, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors (NRC 1974), with respect to evaluating the potential radiological consequences of a loss-of-coolant accident for boiling-water reactors (BWRs) October 1999 7.1-3 NUREG-1555 ` Regulatory Guide 1.4, Rev. 1, Assumptions used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors (NRC 1973), with respect to evaluating the potential radiological consequences of a loss-of-coolant accident for pressurized-water-reactors (PWRs) ` Regulatory Guide 1.70, Rev. 3, Standard Format and Content of Safety 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