Document: NUREG-0800
Document ID: 1085af08-a4b7-4fe7-bfed-ca7a60f2022c
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070734.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
ing the requirements outlined in the references provides assurance that following a loss-of-coolant accident the reactor core will remain in a coolable geometry and offsite consequences will be within the guidelines specified in 10 CFR Part 100. 68 2. Compliance with GDC 35 requires that a means of providing abundant emergency core cooling be provided that will transfer heat from the reactor core in the event of a loss-of- 15.6.5-7 DRAFT Rev. 3 - April 1996 coolant accident, and that suitable redundancy of components and features is provided so that the safety function can be accomplished assuming a single failure. GDC 35 specifies that an emergency core cooling system be installed in all nuclear power reactors. SRP Section 15.6.5 specifies the analytical procedures that are to be followed to establish that the ECCS will function to meet acceptance criteria specified in 10 CFR 50.46. 10 CFR part 50, Appendix K and Regulatory Guide 1.157, "Best Estimate Calculations of Emergency Core Cooling System Performance," provide guidance on calculational procedures needed to demonstrate compliance with the acceptance criteria. Meeting the requirements of GDC 35 will provide assurance that following a loss-of- coolant accident that the reactor core will remain in a coolable geometry and offsite consequences will be within the guidelines specified in 10 CFR Part 100.69 3. Compliance with 10 CFR 100, Reactor Site Criteria, describes criteria which guide the Commission in its evaluation of the suitability of proposed sites for nuclear power and testing reactors. Part 100 specifies radiation dose guidelines that should not be exceeded in the event of postulated accidents including loss-of-coolant accidents. In order to satisfy the requirements of 10 CFR 100, the applicant must demonstrate that the offsite doses resulting from various accidents presented in the SAR are within the guideline values. Meeting the guideline doses is achieved by a combination of engineered safety