Document: NUREG-0800
Document ID: c8e72d8e-80ed-420f-9ddd-f5f19cf5989c
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350047.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
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. Other parameters used, as well as a complete description of the routine operation source term development, are contained in Chapter 11. The accident source terms are based on NRC Short-Term Lessons Learned recom- mendation in NUREG-0737. The source terms presented are comparable to esti- mates by other applicants with similar designs. Almost all of the airborne radioactivity within the plant is due to equipment leakage. The applicant has provided a tabulation of the maximum expected routine radioactive airborne concentrations in equipment cubicles, corridors, and operating areas, due to equipment leakage. The bases for these leakage calculations are in accordance with Regulatory Guide 1.112. 12.2-5 Rev. 2 July 1981 The source terms used to develop these airborne concentration values are compar- able to estimates by other applicants with similar designs, and are acceptable. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regard- ing the NRC staff's.plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 20, "Standards for Protection Against Radiation." 2. General Design Criterion 61, "Fuel Storage and Handling and