Document: NUREG-0800
Document ID: 723c7d66-7b0b-443a-af9b-ec3026461a0c
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1130/ML113081427.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
t relates to criteria for the establishment of locations for fixed continuous area gamma radiation monitors and for design features and ranges of measurement. 20. ANSI N13.1-1999, as it relates to the principles that apply in obtaining valid samples of airborne radioactive materials, and acceptable methods and materials for gas and particle sampling. 21. ANSI/ANS-6.4-1997 (R2004), as it relates to requirements and recommended practices for the construction of concrete radiation shielding structures. 22. Memorandum from Larry W. Camper to David B. Matthews and Elmo E. Collins, dated October 10, 2006, and NUREG/CR-3587, as they relate to the design issues that need to be addressed to meet the requirements of 10 CFR 20.1406. The specific SRP acceptance criteria are: 1. Facility Design Features The acceptability of the facility design features will be based on evidence that the applicant has fulfilled the dose limiting requirements of 10 CFR 20.1201, 10 CFR 20.1202, 10 CFR 20.1203, 10 CFR 20.1204, and 10 CFR 20.1207, as well as the radiation protection aspects of GDC 19 and 61, and 10 CFR 50.34. This includes 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 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, (4) the ability to reduce time required in radiation fields, and (5) a provision for portable shielding and remote handling tools. Access control will