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:
ion hazards. American National Standard ANSI N13.1-1969199372 provides detailed guidance on sampling airborne radioactive materials in nuclear facilities and may be used for acceptance criteria on the actual sampling process and certain techniques involved. Regulatory Guide 8.8 provides further guidance on monitoring systems. 12.3-13 DRAFT Rev. 3 - April 1996 e. Instrumentation to monitor for accidental criticality will be acceptable if it meets the criteria of 10 CFR Part 70.24 (a)(1), Regulatory Guide 8.12, and ANSI Standard N16.2.73 5. DOSE ASSESSMENT The dose assessment will be acceptable if it documents in appropriate detail the assumptions made, calculations used, the results for each radiation zone, including numbers and types of workers involved in each, expected and design dose rates, and projected person-Sievert (person-Sievert) doses, in accordance with Regulatory 74 Criteria 8.19. Technical Rationale75 The technical rationale for application of the above acceptance criteria is discussed in the following paragraphs.76 1. The referenced sections of 10 CFR Part 20 specify that the licensee shall use sound radiation protection principles to control occupational doses from radioactivity that may be received from both internal and external sources, and maintain security of licensed radioactive materials that are stored in controlled or unrestricted areas. The referenced sections of 10 CFR Part 20 apply to this Standard Review Plan (SRP) because they establish limits on radioactive doses that may be received by individuals in restricted areas, provide guidance on external and internal exposure and combinations of the two, specify requirements that must be included in a licensee's operational radiation protection program to ensure that occupational exposures are ALARA, and provide requirements for storage security of licensed radioactive materials. Meeting the requirements of the referenced sections of 10 CFR Part 20 will provide a level of assurance that