Document: NRC Regulatory Guide
Document ID: 4d46a966-d280-43da-9b03-8b0abe7b29ce
Document Type: regulatory_guide
Title: Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2120/ML21204A065.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.183
CFR Part: 
CFR Title: 

Content:
(3150-0011, 3150-0151 and 3150-0155) Office of Management and Budget, Washington, DC, 20503. Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number. DG-1389, Page 4 TABLE OF CONTENTS A. INTRODUCTION ................................................................................................................................... 1 B. DISCUSSION .......................................................................................................................................... 6 C. STAFF REGULATORY GUIDANCE .................................................................................................... 9 1. Implementation of Accident Source Term .......................................................................... 9 1.1 Generic Considerations ....................................................................................................... 9 1.2 Scope of Implementation .................................................................................................. 11 1.3 Scope of Required Analyses ............................................................................................. 11 1.4 Risk Implications .............................................................................................................. 14 1.5 Submittal Requirements and Information ......................................................................... 15 1.6 Final Safety Analysis Report Requirements ..................................................................... 16 2. Attributes of an Acceptable Accident Source Term ......................................................... 16 3. Accident Source Term ...................................................................................................... 17 3.1 Fission Product Inventory