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:
xemptions to labeling requirements," as they relate to posting of radiation areas, high 33 radiation areas, airborne radioactivity areas, and further indications necessary to identify and quantify the presence of radioactive materials in an area. 6. 10 CFR Part 20, Section 20.207, "Storage of licensed materials"20.1801, "Security of stored material," as it relates to securing licensed materials against unauthorized 34 removal from the place of storage. 7. 10 CFR Part 50, Appendix A: a. General Design Criterion 19 - Control Room as it relates to adequate radiation protection to be provided to permit access to areas necessary for occupancy after an accident, without personnel receiving radiation exposures in excess of 50 mSv (5 rems) to the whole body or the equivalent to any part of the whole body for 35 the duration of the accident. b. General Design Criterion 61 - Fuel Storage and Handling and Radioactivity Control as it relates to occupational radiation protection aspects of fuel storage, handling, radioactive waste, and other systems designed to assure adequate safety during normal and postulated accident conditions, with suitable shielding and appropriate containment and filtering systems. 8. 10 CFR Part 70, Section 70.24, "Criticality Accident Requirements" as it relates to procedures and criteria for monitoring for criticality accidents involving special nuclear material. The following regulatory guides, NUREGs and industry standards provide information, recommendations and guidance and in general describe a basis acceptable to the staff for implementing the requirements of the regulations identified above: 1. Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant accident for Boiling Water Reactors," as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems, following a loss-of-coolant accident for BWRs. 2. Regulatory Guide 1.4,