Document: NUREG-0800
Document ID: f9721491-7ec5-4df0-a6d4-e76111e0ff41
Document Type: srp
Title: RADIATION PROTECTION AND EMERGENCY PREPAREDNESS (Tier 1)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070668.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.8
CFR Part: 
CFR Title: 

Content:
esign description. Examples of its application could be to the radiological shielding and ventilation design of the reactor building, turbine building, control building, service building, and radwaste building. The implementation of the process and the design is the responsibility of the COL applicant or licensee. DRAFT Rev. 0 - April 1996 14.3.8-4 The acceptance criteria in the DAC may be taken from the acceptance criteria in the applicable sections of Chapter 12 of the SRP. The analysis methods and source term assumptions specified in the DAC should be consistent with approved methods and assumptions listed in the SRP. The SRP is the basis for the staff's safety review of the standard design. Therefore, demonstrating that the final design meets these DAC with the methods and assumptions specified in Tier 1 ensures that the as-built design meets the applicable acceptance criteria of the SRP and the associated regulations and staff technical positions. The DAC in Tier 1 should address the verification of the plant radiation shielding design and the plant airborne concentrations of radioactive materials (e.g., the ventilation system and airborne monitoring system designs). The DAC should require the COL applicant to calculate radiation levels and airborne radioactivity levels within the plant rooms and areas to verify the adequacy of these design features during plant construction (concurrently with the verification of the ITAAC). The plant rooms and areas to which the DAC apply may be given in figures in Tier 1. Detailed supporting information for the DAC should be contained in appropriate sections of DCD Tier 2 Chapter 12. The criteria in Tier 1 should ensure that the radiation shielding design (either that provided for by the plant structures, or design permanent or temporary shielding) is adequate to ensure that the maximum radiation levels in plant areas are commensurate with the area's access requirements so radiation exposures to plant personnel can be