Document: NUREG-0800
Document ID: e1fb2732-c7c9-4bbf-99dc-ee2469f9ed6f
Document Type: srp
Title: - 12.4  RADIATION PROTECTION DESIGN FEATURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070617.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
radiation protection aspects of General 49 Design Criteria 19 and 61, and 10 CFR 50.34. This includes evidence that major exposure accumulating functions (maintenance, refueling, radioactive material handling, processing, etc., in-service inspection, calibration, decommissioning, and recovery from accidents) have been considered in plant design and that potential radiation exposure from these activities will be kept ALARA in accordance with 10 CFR Part 20.1(c)20.1101(b) and the definition of ALARA in 20.1003 and Regulatory Guides 8.8 and 8.10 by radiation protection features incorporated in 50 the design. Such features may include (1) ease of accessibility to work and inspection and sampling areas, (2) the ability to reduce source intensity, (3) design measures to reduce the production, distribution, and retention of activated corrosion products, (4) the ability to reduce time required in radiation fields, and (5) provision for portable shielding and remote handling tools. Access control will be judged for acceptability in accordance with the requirements of 10 CFR 20.20320.1601, 20.1602, 20.1901, 20.1902, and 20.1903 or access control alternatives 51 in Standard Technical Specifications (NUREGs-0103, 0123, 0212, and 04521430, 1431, 1432, 1433, and 1434).52 Access controls to the spent fuel transfer tube or canal should be more stringent than 10 CFR 20.20320.1601, 20.1602, 20.1901, 20.1902, and 20.1903. All accessible portions of 53 the spent fuel transfer tube or canal which are capable of having radiation levels greater than 1 Gy per hour (100 rads per hour) shall be shielded during fuel transfer. Use of removable 54 shielding for this purpose is acceptable. This shielding shall be such that the resultant contact radiation levels shall be no greater than 1 Gy per hour (100 rads per hour). All accessible 55 portions of the spent fuel transfer tube shall be clearly marked with a sign stating that potentially lethal radiation fields are possible during fuel