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:
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 developed using these bases: • An offgas rate of 370 MBq/s (100,000 μCi/s) after a 30-minute delay for BWRs. • 0.25-percent fuel cladding defects for PWRs. • Postaccident shielding (for vital area access, including work in the area) source terms from NUREG-0737, Item II.B.2, or RG 1.183. 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 the 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 source term used for determining shielding and ventilation design of PWR components provided for purification of secondary coolant, should consider isotopic concentrations associated with operation at the TSs allowed limits for primary-to-secondary leakage and/or the secondary coolant specific activity concentrations. The tables of source parameters, which can be placed in SAR Chapter 12 or referenced to SAR Chapter 11, will be acceptable if the accompanying text either in this section or other referenced sections makes it clear how the values are used in a shield design calculation, equipment qualification or in a ventilation system design during normal operation, AOOs as defined in 10 CFR Part 50, Appendix A “General Design Criteria for Nuclear Power Plants,” and DBEs, as defined in Section (b)(ii) of 10 CFR 50.49 “Environmental qualification of electric equipment important to safety for nuclear power plants.“ In addition, the quantities will be acceptable if the specific values given in the tables are