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:
urance, that the licensee’s analyses are acceptable. 6. Comparison of the doses calculated by the licensee and the staff against the appropriate exposure criteria, as stated in Section II below. II. ACCEPTANCE CRITERIA An application to replace the current DBA source term with an AST is acceptable if the plant, as modified, will continue to provide sufficient margin of safety with adequate defense in depth to address unanticipated events and to compensate for uncertainties in accident progression and analysis assumptions and parameter inputs. The staff should allow licensees to pursue technically justifiable uses of an AST in the most flexible manner compatible with maintaining a clear, logical, and consistent design basis. A complete recalculation of all design basis radiological consequence analyses may not be required for an application to be acceptable. However, applications should be supported by evaluations of all significant radiological and non-radiological impacts of the proposed plant modifications in the context of the proposed AST. The scope and extent of the reanalysis effort, and the staff review, will depend on the specifics of the application. The acceptance criteria below address the implementation of an AST and the supporting radiological consequence analyses. Additional acceptance criteria may be found in other applicable SRP sections. If the application is justified, in part, on risk insights, the acceptance criteria of SRP Section 19.0 (Ref. 3) apply. In addition to the nonradiological acceptance criteria provided in other SRP sections, an acceptable implementation of an AST is required to demonstrate compliance with the following regulations: • Section 50.49, Environmental qualification of electric equipment important to safety for nuclear 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