Document: NUREG-0800
Document ID: c857bf88-7f70-4d0a-a004-bb765dcfa21b
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710496.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
th Regulatory Guide 1.112. 12.2-8 Revision 3 - March 2007 The source terms used to develop these airborne concentration values are comparable to estimates by other applicants with similar designs, and are acceptable. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced regulatory guides contain the implementation schedules for conformance to parts of the method discussed herein. VI. REFERENCES 1. 10 CFR Part 20, “Standards for Protection Against Radiation.” 2. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 3. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 4. General Design Criterion 61, “Fuel Storage and Handling and Radioactivity Control.” 5. Regulatory Guide 1.3, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors.” 6. Regulatory Guide 1.4, “Assumptions Used for Evaluating the