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:
d decay heat is removed for the extended period of time required by the long-lived radioactivity. 2. The radiological consequences of the most severe LOCA are within the guidelines of 10 CFR Part 100. Appendices A, B and D to this SRP section provides the results of the LOCA analysis. 3. The TMI Action Plan (Ref. 6 and 7) requirements for II.E.2.3, II.K.2.8, II.K.3.5, II.K.3.25, II.K.3.30, II.K.3.31, and II.K.3.40 have been met. Technical Rationale 66 The technical rationale for application of these acceptance criteria to the analysis of the consequences of loss-of-coolant accidents is discussed in the following paragraphs:67 1. Compliance with 10 CFR 50.46 requires that light water cooled nuclear power reactors be equipped with an emergency core cooling system designed so that core performance following postulated loss-of-coolant accidents conforms to specified criteria related to limiting core damage. The requirements specified in 10 CFR 50.46 provide an acceptable and conservative means of calculation of the consequences of loss-of-coolant accidents from a spectrum of pipe break sizes and locations that have been subject to careful review and experimental verification. If the calculations of the performance of the emergency core cooling system are conducted in accordance with these methods, there is a high level of probability that the acceptance criteria on core performance will not be exceeded and damage to the core and offsite consequences will be minimized. Regulatory Guide 1.157, "Best Estimate Calculations of Emergency Core Cooling System Performance," and Appendix K to 10 CFR Part 50, provide guidance on evaluation models needed to demonstrate compliance with the acceptance criteria. Appendix K also specified documentation required for evaluation models. Meeting 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