Document: NUREG-0800
Document ID: e1c5261f-4ef6-4478-8cf0-015611057574
Document Type: srp
Title: and 9.3.2, “Process and Post-accident Sampling Systems.”  The review addresses
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A039.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
waste to the points of controlled discharges to the environment as defined in the ODCM, or at the point of storage in holdup tanks or decay beds in accordance with the guidance of RG 1.143 for gaseous wastes produced during normal operation and AOOs. H. DC/COL-ISG-05, NUREG-0016 and NUREG-0017, as they relate to the use of the gaseous and liquid effluent (GALE) 86 Code in calculating routine radioactive releases in gaseous and liquid effluents from BWR and PWR plants. I. DC/COL-ISG-06, NEI 08-08A, and RG 4.21, as they relate to acceptable levels of detail and content required to demonstrate compliance with 10 CFR 20.1406. J. NUREG-1430, as it relates to Standard Technical Specifications - Babcock and Wilcox Plants. K. NUREG-1431, as it relates to Standard Technical Specifications - Westinghouse Plants. L. NUREG-1432, as it relates to Standard Technical Specifications - Combustion Engineering Plants. M. NUREG-1433, as it relates to Standard Technical Specifications - General Electric Plants (BWR/4). N. NUREG-1434, as it relates to Standard Technical Specifications - General Electric Plants (BWR/6). Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. 10 CFR 20.1302 requires that surveys of radiation levels in unrestricted areas and radioactive materials in effluents released to unrestricted areas be performed to demonstrate system compliance with the dose limits to individual members of the public contained in 10 CFR 20.1301. 10 CFR 20.1302 identifies two approaches, either of which can demonstrate compliance with the dose limits of 10 CFR 20.1301 and 10 CFR 20.1301(e). Each one of these approaches requires a demonstration of the following: A. That the annual average concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted area do not 11.3-18 Revision 4 – January 2016 exceed