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:
ase has been considered. 3. A review of the core inventory determined by the licensee to ensure that it is consistent with the current licensing basis rated thermal power, enrichment, and burnup. 4. A review of the models, assumptions, and parameter inputs used by the licensee for the calculation of the radiological consequences. For plants applying for, or having received, approval for the use of a full implementation of an AST, this SRP section supersedes the radiological analyses assumptions, acceptance criteria, and methodologies identified in the SRP sections listed below. Provisions related to the nonradiological analyses aspects of these SRP sections remain applicable. a. Section 15.1.5, Steam System Piping Failures Inside and Outside of Containment (PWR) b. Sections 15.3.3-15.3.4, Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break c. Section 15.4.8, Spectrum of Rod Ejection Accidents (PWR) d. Section 15.4.9, Spectrum of Rod Drop Accidents (BWR) e. Section 15.6.2, Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant Outside Containment f. Section 15.6.3, Radiological Consequences of Steam Generator Tube Failure (PWR) g. 15.6.4, Radiological Consequences of Main Steam Line Failure Outside Containment (BWR) h. 15.6.5, Loss-of-Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant System Pressure Boundary 15.0.1-5 Rev. 0 -- July 2000 i. 15.7.4, Radiological Consequences of Fuel Handling Accidents. This SRP section and the referenced RG-1.183 may contain information that contradicts that provided in other SRP sections. In these cases, the most recent applicable information should be used. 5. Independent calculations by the staff, as necessary, to conclude, with reasonable assurance, 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.