Document: NUREG-0800
Document ID: b8d2b8f5-432a-4c0a-81ab-20231f7d0f28
Document Type: srp
Title: PROBABILISTIC RISK ASSESSMENT AND SEVERE ACCIDENT EVALUATION FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1508/ML15089A068.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.0
CFR Part: 
CFR Title: 

Content:
e a separate document entitled “Applicant’s Environmental Report - Standard Design Certification,” which must address the costs and benefits of the severe accident mitigation design alternatives (SAMDA), and the bases for not incorporating SAMDAs in the design to be certified. 2. 10 CFR 52.47(a)(1) states that each DC application must include the site parameters postulated for the design, and an analysis and evaluation of the design in terms of those site parameters. 3. 10 CFR 52.47(a)(2) states that it is expected that the standard plant will reflect through its design, construction, and operation an extremely low probability for accidents that could result in the release of radioactive fission products. 4. 10 CFR 52.47(a)(4) states that each DC application must contain an FSAR that includes an analysis and evaluation of the design and performance of SSCs with the objective of assessing the risk to public health and safety resulting from operation of the facility and including determination of the margins of safety during normal operations and transient conditions anticipated during the life of the facility, and the SSCs provided for the prevention of accidents and the mitigation of the consequences of accidents. 5. 10 CFR 52.47(a)(8) states that a DC application must contain an FSAR that provides the information necessary to demonstrate compliance with any technically relevant portions 19.0-6 Revision 3 – December 2015 of the Three Mile Island requirements set forth in 10 CFR 50.34(f), except paragraphs 10 CFR 50.34(f)(1)(xii), 10 CFR 50.34(f)(2)(ix), and 10 CFR 50.34 (f)(3)(v). 6. 10 CFR 52.47(a)(23) states that a DC application for light-water reactor (LWR) designs must contain an FSAR that includes a description and analysis of design features for the prevention and mitigation of severe accidents, e.g., challenges to containment integrity caused by core-concrete interaction, steam explosion, high-pressure core melt ejection, hydrogen combustion, and