Document: NUREG-0800
Document ID: 49aefb86-1adb-4b3c-826f-480e32947595
Document Type: srp
Title: Radiological Consequence Analyses Using Alternative Source Terms
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0037/ML003734190.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.1
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CFR Title: 

Content:
ance to licensees on performing evaluations and reanalyses in support of the implementation of an AST. Although, this SRP section is written primarily for the review of the application for the initial implementation of an AST at operating power reactors, it is expected to be of use in reviewing applications for subsequent license amendment requests from these plants. A complete recalculation of all design basis radiological consequence analyses may not be required for an application to be acceptable. However, applications should be supported by evaluations of all significant radiological and nonradiological impacts of the proposed plant modifications in the context of the proposed AST. The scope and extent of the reanalysis effort, and the staff review, will depend on the specifics of the application. RG-1.183 provides guidance on required reviews. An AST is characterized by radionuclide composition and magnitude, chemical and physical form of the radionuclides, and the timing of the release of these radionuclides. An accident source term is a fundamental assumption upon which a large portion of the plant design is based. Ideally, the licensee would update all design basis analyses based on the previous 15.0.1-3 Rev. 0 -- July 2000 source term to reflect all five characteristics of the proposed AST. However, evaluations performed by the staff have indicated that this level of reanalysis may not be necessary for some AST implementations. There are potential implementations of an AST for which only limited reanalyses may be necessary. Some implementations may involve only one AST characteristic. Two categories of implementations, full and selective, are defined. ÿ A full implementation is a modification of the plant design basis that addresses all characteristics of an AST, that is, the composition and magnitude of the radioactive material, its chemical and physical form, and the timing of its release. A full implementation replaces the previous accident source term