Document: NUREG-0800
Document ID: 81955d2c-b3de-4ce3-a132-7f798c711260
Document Type: srp
Title: INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070675.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
CFR Part: 
CFR Title: 

Content:
The review branches in the Division of Systems Integration Divisions of Systems Safety and Analysis, Technical Support, Reactor Controls and Human Factors, and Engineering that have 1 some responsibility for review of anticipated operational occurrences and postulated accidents listed in this chapter are as follows: Reactor Systems Branch (RSBSRXB) - reviews analyses of anticipated operational occurrences 2 and postulated accidents from the viewpoint of systems operation, transient dynamics, analytical methodology, and meeting defined acceptance criteria. In addition, SRXB reviews analyses of core physics and fuel behavior core thermal-hydraulic performance; it also performs generic reviews of thermal-hydraulic computer codes and topical reports. 3 Core Performance Branch (CPB) - reviews analyses of core physics, fuel behavior core thermal-hydraulic performance, and performs generic reviews of thermal-hydraulic computer codes and topical reports.4 Emergency Preparedness and Radiation Protection Branch (PERB) - reviews analyses of postulated spills of radioactive material outside containment, and evaluates possible radiological consequences of transients and accidents.5 Effluent Treatment Systems Branch (ETSB) - reviews analyses of postulated spills of radioactive material outside containment.6 Accident Evaluation Branch (AEB) - evaluates possible radiological consequences of the transients and accidents.7 Instrumentation and Controls Systems Branch (ICSBHICB) - reviews and evaluates the reactor 8 protection and safety instrumentation and control instrumentation. DRAFT Rev. 3 - April 1996 15.0-2 Power Systems Branch (PSB) Plant Systems Branch (SPLB) - reviews and evaluates emergency 9 onsite power, evaluates the operation and performance of the auxiliary systems (e.g., auxiliary feedwater systems) after anticipated operational occurrences and postulated accidents, and reviews the operability of reactor primary system components.10 Auxiliary Systems Branch (ASB) -