Document: NUREG-0800
Document ID: c75a9de4-9927-49e4-b078-7f5dadd37acd
Document Type: srp
Title: DESIGN BASIS ACCIDENT RADIOLOGICAL CONSEQUENCE ANALYSES FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.3
CFR Part: 
CFR Title: 

Content:
ontainment Spray as a Fission Product Cleanup System.” 7. Review of the analysis modeling of fission product removal capability for plant systems and structures is performed under SRP Section 6.5.3, “Fission Product Control Systems and Structures.” 8. If a plant design includes an ice condenser in the containment, the review of the fission product removal capability of the ice condenser is performed under SRP Section 6.5.4, “Ice Condenser as a Fission Product Cleanup System.” 9. The review of the fission product removal capability of a BWR pressure suppression pool is performed under SRP Section 6.5.5, “Pressure Suppression Pool as a Fission Product Cleanup System.” 10. For review of DC applications, CPs and OLs, and COLs or ESPs referencing an advanced light-water reactor design, this SRP section supersedes the radiological analyses, assumptions, acceptance criteria, and methodologies identified in the SRP sections (with appendices) listed below. Provisions related to the nonradiological analysis 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” 15.0.3-5 March 2007 F. Section 15.6.3, “Radiological Consequences of Steam Generator Tube Failure (PWR)” G. Section 15.6.4, “Radiological Consequences of Main Steam Line Failure Outside Containment (BWR)” H. Section 15.6.5, “Loss-of-Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant System Pressure Boundary” I. Section 15.7.4, “Radiological Consequences of Fuel Handling Accidents” J. Section 15.7.5,