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:
nclude plan scale drawings of each floor of the plant on which all sources are shown and identified in a manner that 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. 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 exper- ience 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 appro- priate monitoring systems. Airborne radioactivity concentrations in frequently occupied areas will be a small fraction of 10 CFR Part 20, §20.103, Appendix B concentrations. The assumptions made in arriving at quantitative values for these various sources should be specified, either in this section or by refer- ence to Chapter 11 of the SAR. Shielding and ventilation design fission product source terms will be acceptable if developed using these bases: 12.2-3 Rev. 2 July 1981 (1) an offgas rate of 100,000 pCi/sec after 30 minutes delay for BWRs. (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 allow- ances 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