Document: NUREG-0800
Document ID: d1231348-49d9-4197-8557-69cb2e1eb62a
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1218/ML12186A009.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
rce, and special nuclear material exceeding 3.7 E+9 Bq (100 millicuries) that may warrant shielding design consideration, should be provided. For contained sources, the description should include plan scale drawings of each floor of the plant that show all sources identified so that they can easily be related to tables containing the pertinent and necessary quantitative source parameters. Their position should be located accurately, indicating the approximate size and shape. The information about neutron and gamma source terms from the core, reactor pressure vessel and irradiated components inside containment, should be described in sufficient detail to allow determination of the radiation fields that could occur in areas that may require occupancy or may contain certain electrical equipment important to safety as described in 10 CFR 50.49. Neutron and gamma streaming into containment from the annulus between the reactor pressure vessel and the biological shield should be analyzed to determine the radiation fields that could occur in areas that may require occupancy. Relevant experience from operating reactors may be used. Airborne sources that are created by leakage, opening formerly closed containers, storage of leaking fuel elements, and other mechanisms should be identified by location and magnitude so that they can be used for designing appropriate ventilation systems and in specifying appropriate monitoring systems. Airborne radioactivity concentrations in frequently occupied areas should be a small fraction of the concentrations related to 10 CFR 20.1203, 10 CFR 20.1204, and Appendix B to 12.2-9 Draft Revision 4 – October 2012 10 CFR Part 20. The assumptions made in arriving at quantitative values for these various sources should be specified, either in this section or by reference to SAR Chapter 11, and other relevant interfacing sections of the technical submittal. Shielding and ventilation design fission product source terms will be acceptable if