Document: NUREG-0800
Document ID: bfe08773-10ce-45c6-9767-3cbe51c1726f
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070720019.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
cludes 12.3-12.4-9 Revision 3 - March 2007 evidence that major exposure accumulating functions (maintenance, refueling, radioactive material handling and processing, inservice inspection, calibration, decommissioning, and recovery from accidents) have been considered in plant design and that radiation protection features incorporated into the design will keep potential radiation exposure from these activities ALARA in accordance with 10 CFR 20.1101(b), the definition of ALARA in 10 CFR 20.1003, and Regulatory Guides 8.8 and 8.10. Such features may include (1) the ease of accessibility to work, 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) a provision for portable shielding and remote handling tools. Access control will be judged for acceptability in accordance with the requirements of 10 CFR 20.1601, 10 CFR 20.1602, 10 CFR 20.1901, 10 CFR 20.1902, and 10 CFR 20.1903 or access control alternatives in Standard Technical Specifications (NUREG-1430, NUREG-1431, NUREG-1432, NUREG-1433, and NUREG-1434). Facility design, to the extent practicable, should minimize the potential for creating a very high radiation area during normal operations, including abnormal operational occurrences (such as dropping a fuel bundle during fuel handling operations). High and very high radiation areas should be remote from normally occupied rooms and corridors such that personnel access to these areas can be controlled in accordance with 10 CFR 20.1601 and 10 CFR 20.1602 and the guidance in Regulatory Guide 8.38. All accessible portions of the spent fuel transfer tube or canal that are capable of having radiation levels greater than 1 gray (Gy) per hour (100 rads per hour) should be shielded during fuel transfer. This shielding should be such that the resultant contact radiation levels are