Document: NUREG-0800
Document ID: fabdf65c-d299-4b3a-a971-ae5b21a97177
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A413.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
, and after shutdown inside the containment, the primary sources of personnel exposure are fission products from fuel clad defects, and activation products, including activated corrosion products. The coolant and corrosion activation product source terms are based on operating experience from reactors of similar design; allowances are included for the buildup of activated corrosion products. Neutron and prompt gamma source terms are based on reactor core physics calculations and operating experience from reactors of similar design. Chapter 11 contains other parameters used, as well as a complete description of the routine operation source term development. The accident source terms are based on the NRC short-term lessons learned recommendation in NUREG-0737 and the alternate accident source term in RG 1.183. The source terms presented are comparable to estimates by other applicants with similar designs. Almost all of the airborne radioactivity within the plant results from equipment leakage. The applicant has provided a tabulation of the maximum expected routine radioactive airborne concentrations in equipment cubicles, corridors, and operating areas because of equipment leakage. The bases for these leakage calculations are in accordance with RG 1.112. The 12.2-13 Revision 4 – September 2013 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