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:
REVIEW RESPONSIBILITIES Primary – various (see text) Secondary – various (see text) The NRC expects that most operating reactors will implement an alternative source term (AST) only as a means to justify desirable plant modifications. (In the text that follows the phrase, “implementation of an AST” includes any associated plant modifications.) These modifications may be to systems or procedures identified in the final safety analysis report (FSAR) or changes to the technical specifications. The review of the affected structures, systems, components, and accident analyses is covered in other sections of the Standard Review Plan (SRP). Those sections identify the branches responsible for the review of the modifications, as well as the acceptance criteria, areas of reviews, and evaluation documentation associated with those reviews. The review of the radiological consequences of the proposed modification as described in this SRP section is performed by the SPSB with the assistance of other technical review branches in the NRC’s Office of Nuclear Reactor Regulation (NRR), as deemed necessary. The nature of the licensee’s request will determine which technical branch will serve as the primary review branch for the overall proposed amendment request. This primary review branch has overall responsibility for leading the technical review, drafting the staff safety evaluation report (SER) or other appropriate regulatory document, and coordinating input from other technical review organizations. • Probabilistic Safety Analysis Branch (SPSB) holds the responsibility for reviewing the impact of the proposed plant modification on the radiological consequences of design basis accidents (DBAs). It assists the primary review branch by reviewing probabilistic risk analysis (PRA) information submitted by the licensee. It reviews issues related to severe accidents for operating reactors • Reactor Systems Branch (SRXB) holds the responsibility for issues related to