Document: NUREG-0800
Document ID: e3249d77-0411-430a-9793-06aea8669075
Document Type: srp
Title: FISSION PRODUCT CONTROL SYSTEMS AND STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070474.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.3
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Accident Evaluation Branch (AEB)Plant Systems Branch (SPLB)1 Secondary - Effluent Treatment Systems Branch (ETSB)Materials and Chemical Engineering Branch (EMCB)2 Emergency Preparedness and Radiation Protection Branch (PERB)3 I. AREAS OF REVIEW The description of the fission product control systems and structures are is reviewed to 4 (a) provide a basis for developing the mathematical model for design basis loss-of-coolant accident (LOCA) dose computations, (b) verify that the values of certain key parameters are 5 within pre-established limits, (c) confirm the applicability of important modeling assumptions, and (d) verify the functional capability of ventilation systems used to control fission product releases. The parameters which must be established for use in the calculation of the radiological consequences of accidents in Chapter 15 of the safety evaluation report (SER) and the systems 6 whose functions must be reviewed are outlined below. Many of these areas are the responsibility of other branches and are reviewed by the AEBSPLB to provide a general 7 knowledge of the containment systems and their operation following a loss-of-coolant accident (LOCA). The following areas are reviewed: 8 1A. Primary Containment Design9 1. Primary containment characteristics, including of (1) the containment isolation 10 times and methods; (2) leak rates prior to nd following containment isolation if DRAFT Rev. 3 - April 1996 6.5.3-2 venting, vacuum relief, or purging of the containment is permitted (by technical specification) during operation; (3) total and mixing volumes to be assumed from the recirculation characteristics given in safety analysis reports (SARs); and 11 (4) the efficiencies of the engineered safety features (ESF) filters used for 12 postaccident ventilation. Each of the foregoing containment design and operational characteristics will influence the quantity of radioactive fission products available for release during normal