Document: NUREG-0800
Document ID: 968e9bbe-e8ca-4639-a8d2-f96483377bae
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1219/ML12191A219.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
n current operating experience and on predictions being made for new plant designs, it is expected that the plant shielding can be designed, the plant can be zoned, and sufficient radiation protection design features can be incorporated, such that individuals in shielded areas would receive a small fraction of the 10 CFR Part 20 limits. All vital areas, in which radiation may unduly limit personnel occupancy during operations following an accident resulting in a degraded core, should be identified. Personnel access to these areas under accident conditions should be demonstrated in accordance with 10 CFR 50.34(f)(2)(vii), using the methods listed in Section II.B.2 of NUREG-0737. The analysis should consider access to, stay time in, and egress from these vital areas. 12.3-12.4-18 Draft Revision 5 – October 2012 Consistent with the guidance contained in RGs 8.8 and 1.143, BTP 11-3 and SECY 94-198, “Review of Existing Guidance Concerning the Extended Storage of Low- Level Radioactive Waste,” SSCs that are described in the application, should be designed to control leakage and facilitate access, operation, inspection, testing, and maintenance in order to maintain radiation exposures to operating and maintenance personnel as low as is reasonably achievable. Structures housing radioactive waste processing systems or components should be classified using the guidance for potential exposure to site personnel, contained in RG 1.143. 2. Shielding The staff will evaluate the shielding design in terms of the assumptions used to calculate shield thickness, the calculational methods used, and the parameters chosen. A number of acceptable shielding calculational codes are available that are effective for determining the necessary shield thickness for gamma ray and combination neutron- gamma sources. The code description file of the Radiation Safety Information Computational Center (formerly the Radiation Shielding Information Center) at Oak Ridge National Laboratory includes