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:
for the extended period of time required by the long-lived radioactivity. 6. The applicant has met the requirements of TMI Action Plan items II.E.2.3, II.K.2.8 (B&W), II.K.3.5 (Generic Letters 85-012, 86-005, and 86-006 provide DRAFT Rev. 3 - April 1996 15.6.5-12 guidance on implementation of TMI Action Item II.K.3.5), II.K.3.25 (BWR, W, 92 or CE), II.K.3.30, II.K.3.31, and II.K.3.40 (B&W). The radiological consequences meet 10 CFR Part 100 requirements 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 AEBPERB resulting from the reviews detailed in Appendices A, 93 B, and D, as applicable, should be inserted in the safety evaluation report draft at this point. See Appendices A, B, and 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. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.94 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan for using this SRP section. This SRP section will be used by the