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:
ngs: A. The staff concludes that the information provided by the applicant with respect to radiation sources is acceptable and meets the requirements of 10 CFR Part 20 and 12.2-12 Draft Revision 4 – October 2012 GDC 61 in Appendix A to 10 CFR Part 50. This conclusion is based on the following rationale: B. The applicant has described a facility that can meet the requirements of 10 CFR 20.1101(b), 10 CFR 20.1201, 10 CFR 20.1202, 10 CFR 20.1203, 10 CFR 20.1204, 10 CFR 20.1206, 10 CFR 20.1207, 10 CFR 20.1301, 10 CFR 20.1801, 40 CFR Part 190 and 10 CFR 20.1301(e), 10 CFR 50.49 as they relate to the evaluation of source terms and the related provisions of GDC 4 and 61 in Appendix A to 10 CFR Part 50 and supplemented by the guidance of RG 1.112, RG 1.183, NUREG-0737, and ANSI/ANS Standard 18.1. C. The applicant has provided a description of contained and airborne radioactivity sources used as inputs for the dose assessment and for shielding and ventilation designs. The applicant also included its assumptions in arriving at quantitative values for these contained and airborne source terms, based on ANSI/ANS-18.1, RG 1.112, GDC 61, 10 CFR 20.1201, 10 CFR 20.1202, 10 CFR 20.1203, 10 CFR 20.1204, 10 CFR 20.1206, and 10 CFR 20.1207 and TSs. For postaccident shielding for vital area access, the applicant used the source terms in NUREG-0737 and RG 1.183. During power operation, the greatest potential for personnel dose is inside the containment from nitrogen-16, noble gases, and neutrons. Outside the containment, and after shutdown inside the containment, the primary sources of personnel exposure are fission products from fuel clad defects, 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