Document: NUREG-0800
Document ID: 36b6a414-c2ba-46ab-ae85-e214a0f457fa
Document Type: srp
Title: COOLANT SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A022.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary- Organization responsible for the review of the coolant source terms associated with normal operations, anticipated operational occurrences, and accident conditions. Secondary- None I. AREAS OF REVIEW For a review of an application for an early site permit (ESP), construction permit (CP), standard design certification (DC), or a combined license (COL) that does not reference a DC, the U.S. Nuclear Regulatory Commission (NRC) staff reviews the information in the applicant’s Safety Analysis Report (Preliminary Safety Analysis Report (PSAR) or Final Safety Analysis Report (FSAR)) as it relates to the sources of radioactivity that are processed by radioactive waste management systems (RWMS) in treating liquid and gaseous wastes. For operating licenses (OL) or COLs that reference a DC, the staff confirms that the information accepted at the CP or standard DC stage is appropriately incorporated in the relevant sections of OL or COL applications, and that proposed departures are adequately justified and documented. 11.1-2 Revision 4 – January 2016 The Standard Review Plan (SRP) utilizes various source terms for a variety of purposes, including: 1. Normal operational source term, based on operational reactor experience, as described in American National Standards Institute/American National Standard (ANSI/ANS) N18.1. Addressed in SRP Section 11.1 for reactor coolant (primary and secondary) and reactor steam design details, and in SRP Section 11.2, “Liquid Waste Management System,” and SRP Section 11.3, “Gaseous Waste Management System,” for system design features used to process and treat liquid and gaseous effluents before being released or recycled 2. Anticipated operational occurrences (AOOs) source term, based on the technical specifications (TS), or the design basis source term, whichever is more limiting, is used to determine the effects of events like primary to secondary leaks and reactor steam source terms. This is