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
CFR Part: 
CFR Title: 

Content:
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 provisions2 of interest to this SRP section include the following: • NUREG-0737 II.B.2, Post-accident Access Shielding, as it relates to post- accident radiation exposure incurred while performing necessary plant operations outside of the control room. • NUREG-0737 II.B.3, Post-accident Sampling Capability, as it relates to post- accident radiation exposure during sampling operations. • NUREG-0737 II.F.1, Additional Accident-Monitoring Equipment, as it relates to the ability of the monitors to operate during and following an accident and perform the intended function in the accident environment. • NUREG-0737 III.D.1.1, Leakage Control, as it relates to post-accident radiation exposure. • NUREG-0737 III.A.1.2, Emergency Response 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. • NUREG-0737 III.D.3.4, Control Room Habitability, as it relates to maintaining the control room in a safe, habitable condition under accident conditions by providing adequate protection against radiation and toxic gases. An implementation of an AST is acceptable with regard to the radiological consequences of analyzed DBA if the calculated TEDE at the EAB and the LPZ outer boundaries do not exceed the exposure criteria listed in Table 1. The methodology and assumptions for calculating the radiological consequences should reflect the regulatory positions of RG-1.183. 3 For PWRs with steam generator alternate repair criteria, different dose criteria may apply to SGTR and MSLB analyses. 15.0.1-7 Rev. 0 -- July 2000 Table 1 Accident Dose Criteria3 Accident or Case EAB and LPZ Dose Criteria Analysis Release Duration LOCA 25 rem TEDE 30 days for CNMT,