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:
activities ALARA in accordance with 10 CFR 20.1101(b), the definition of ALARA in 10 CFR 20.1003, and RGs 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 (e.g. material selection, water chemistry and decontamination connections), (4) the ability to reduce time required in radiation fields, and (5) a provision for portable 12.3-12.4-17 Draft Revision 5 – October 2012 shielding and remote handling tools. Evidence of methods to control personnel exposure from high dose rate components such as temporary storage areas for irradiated fuel and irradiated core components (e.g. storage and handling of fixed in core detectors during outage) should be considered during plant design. 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 AOOs (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 RG 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 no greater than 1 Gy per hour (100 rads per hour). All