Document: NUREG-0800
Document ID: 55e187c7-8e17-41ed-a88e-0205d1317fb6
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A475.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
ation of the applicant’s method. The applicant’s shielding design is acceptable if the methods are comparable to commonly accepted shielding calculations and if assumptions regarding source terms, cross sections, shield and source geometries, and transport methods are realistic, and specified radiation zones are consistent with the assumed source term and shielding specified in the design. Labyrinth shielded access ways and penetrations should be used to minimize radiation streaming and scatter around shields. Composition of the shielding material should be selected to minimize, to the extent practicable, the potential for the shield itself to become a radiation source (either from activation of the shield material or production of secondary radiation resulting from interactions with the primary radiation). Effective shield design is essential to meeting the criteria that ORE will be ALARA. In addition, RG 1.69 and ANSI/ANS-6.4-1997 provide guidance on the fabrication and installation of concrete shields for occupational radiation protection at nuclear power plants. Acceptability of the shield construction will be based on an indication that the guidance of these documents have been implemented in facility construction, or that acceptable alternatives have been proposed. RG 8.8 provides additional acceptance criteria regarding shielding and isolation in radiation protection design. 12.3-12.4-19 Revision 5 – September 2013 3. Ventilation The ventilation system will be acceptable for radiation protection purposes if the criteria and bases for ventilation rates within the plant will ensure that air will flow from areas of low potential airborne radioactivity to areas of higher airborne radioactivity and then to filters or vents, that the concentrations of radioactive material in areas normally occupied can be maintained in accordance with the requirements 10 CFR 20.1701, and that the dose limits of 10 CFR 20.1201 are met consistent with the requirements of 10 CFR