Document: NUREG-0800
Document ID: 0513eafb-8911-4410-853b-e2ec7a00ee07
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070616.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
necessary quantitative source parameters. Their position should be located accurately, indicating the approximate size and shape. 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, by opening formerly closed containers, by storage of leaking fuel elements, etc., shall be identified by location and magnitude, in a manner useful for designing appropriate ventilation systems and in specifying appropriate monitoring systems. Airborne radioactivity concentrations in frequently occupied areas will be a small fraction of 10 CFR Part 20, §20.103§20.1203 and §20.1204 , Appendix B concentrations. The 11 assumptions made in arriving at quantitative values for these various sources should be specified, either in this section or by reference to Chapter 11 of the SAR. Shielding and ventilation design fission product source terms will be acceptable if developed using these bases: (1) an offgas rate of 370 MBq/sec (100,000 µCi/sec) after 30 minutes delay for BWRs. 12 (2) 0.25% fuel cladding defects for PWRs. (3) Post-accident shielding for vital area access, including work in the area, source terms from Task Action Plan Item II.B.2 of NUREG-0718 and 0737. Coolant and corrosion activation products source terms should be based on applicable reactor operating experience. The buildup of activated corrosion products in various components and systems should be addressed. Any allowances made in design source terms for buildup of activated corrosion products should be explained. Neutron and prompt gamma source terms should be based on reactor core physics calculations and applicable reactor operating experience. The tables of source parameters, which can be placed in Chapter 12 or referenced to Chapter 11,