Document: NUREG-0800
Document ID: faf774de-7226-41f8-ba11-7cf612907af6
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1306/ML13065A119.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
trative Controls, Section 5.5, , proposed by the applicant for process and effluent controls will be evaluated as part of the review identified in SRP Section 11.5, and SRP Chapter 16, as adopted from standard technical specifications (NUREG-1430, NUREG-1431, NUREG-1432, NUREG-1433, and NUREG-1434). The reviewer will determine whether the content of the SREC and ODCM, calculation methods, and scope of the programs identified in the Administrative Controls section of the TS are in agreement with the requirements identified as a result of the staff’s review. The review will include the evaluation or development of appropriate controls and the limiting conditions for operation and their bases as being consistent with the plant design. The ODCM, SREC, and TS are reviewed with respect to the requirements of 10 CFR 50.36a using GL 89-01 and guidance contained in NUREG-1301 (BWR) or NUREG-1302 (BWR) and NUREG-0133 for either type of plant. Alternatively, a COL applicant may incorporate by reference NEI 07-09A as the basis of the ODCM until a plant and site-specific ODCM is developed before fuel load as described in SRP Section 13.4. 10. BTP 11-5 describes acceptable methods to evaluate the consequences associated with the postulated release of radioactive noble gases and radioiodines following the failure of a waste gas system component. The associated exposure pathways include direct radiation exposures and inhalation for a receptor assumed to be located at the EAB. Supporting information on the staff’s evaluation of the site’s atmospheric dispersion characteristics in transporting radioactivity into unrestricted areas is discussed in SRP Section 2.3.4. The use of proposed short-term EAB atmospheric dispersion parameters in support of dose calculation is based on the acceptability of the information evaluated as part of the review of SRP Section 2.3.4. The reviewer will evaluate the type of event leading to the assumed component failure and release; the assumed