Document: NUREG-0800
Document ID: 49aefb86-1adb-4b3c-826f-480e32947595
Document Type: srp
Title: Radiological Consequence Analyses Using Alternative Source Terms
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0037/ML003734190.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.1
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Content:
power plants, of 10 CFR Part 50, as it relates to qualification of safety-related equipment with regard to integrated radiation dose during normal and accident conditions. • Section 50.67, Accident source term, of 10 CFR Part 50, as it relates to the implementation of an AST in current operating nuclear power plants. For plants applying for, or having received, approval for the use of an AST, the radiological criteria in § 50.67 supersede the radiological criteria of Section 100.11, Determination of exclusion area, low population zone, and population center distance, of 10 CFR Part 100. • General Design Criterion (GDC) 19, Control Room, of Appendix A to 10 CFR Part 50, as it relates to maintaining the control room in a safe, habitable 2 The radiological criteria in these provisions reference GDC-19 or specify criteria derived from GDC-19. These criteria are generally specified in terms of whole body dose, or its equivalent, to any body organ. For facilities applying for, or having received, approval for the use of an AST, the applicable criterion should be updated for consistency with the TEDE criterion in 10 CFR 50.67.b.2.iii. 15.0.1-6 Rev. 0 -- July 2000 condition under accident conditions by providing adequate protection against radiation and toxic gases. • Title 10, CFR Part 51, Environmental protection regulations for domestic licensing and related regulatory functions, as it relates to environmental assessments of radioactive material releases during normal and accident conditions. • Paragraph IV.E.8 of Appendix E, to 10 CFR Part 50, Emergency Planning and Preparedness for Production and Utilization Facilities, as it relates to maintaining emergency facilities in a safe, habitable condition under accident conditions by providing adequate protection against radiation and toxic gases. An acceptable implementation of an AST should demonstrate compliance with plant-specific licensing commitments made in response to the NUREG-0737 (Ref. 2). Specific