Document: NUREG-0800
Document ID: 8940dd69-2a01-4786-bbe6-f71794a60643
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF POSTULATED PIPING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350156.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
rements for the postulated spectrum of loss-of-coolant accidents (LOCA) which were evaluated from the viewpoint of site acceptability. For the purposes of this analysis, large fractions of the fission products were assumed to be released from the core even though these releases would be precluded by the performance of the ECCS. The evaluation findings of the AEB resulting from the reviews detailed in Appendices A, B, and D, as applicable, should be inserted in the safety evaluation report draft at this point. See Appendices A - D for typical findings and conclusions. The staff concludes that the calculated performance of the emergency core cooling system following a postulated loss-of-coolant accident and the conservatively calculated radiological consequences of such an accident conform to the Commission's regulations and to applicable regulatory guides and staff technical positions and, accordingly, the ECCS is considered acceptable. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan for using this SRP section. EUcept in those cases in which the applicant proposes an acceptable alternative method for complying with the specific portions of the Commission's regulations, the methods described herein will be used by the staff in its evaluation of conformance with Commission regulations. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 35, "Emergency Core Cooling." 2. 10 CFR Part 50, §50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors," and Appendix K to 10 CFR Part 50, "ECCS Evaluation Models." 3. Standard Review Plan Section 6;3, "Emergency Core Cooling System." 15.6.5-8 Rev. 2 - July 1981 4. 10 CFR Part 100, "Reactor Site Criteria." 5. NUREG-0609, "Asymmetric Blowdown Loads on PWR Primary Systems: Resolution of Generic Task Action Plan A-2." 6. NUREG-0718, "Licensing Requirements for Pending Applications for Construction