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:
erly accounted for in the LOCA analyses. 15.6.5-6 Rev. 2 - July 1981 c. II.K.3.5. The reviewer evaluates the assumptions made regarding reactor coolant pump trip to assure that they are consistent and conservatively modeled with respect to the final pump trip criteria which result from resolution of TMI action plan item II.K.3.5. d. II.K.3.25 and I.K.3.40. If, as a result of a LOCA, or as a result of loss of A/C power, containment isolation is indicated to occur, the reactor coolant pump component cooling water may be lost. The reviewer evaluates the applicant's submittal to determine that the reactor coolant pump seal integrity is not lost. If it cannot be established that seal integrity is assured, the reviewer assures that the evaluation of this event correctly accounts for seal failure. e. II.K.3.30 and II.K.3.31. The reviewer evaluates the small-break LOCA model verification performed by. the applicant and assures that any modifications required are incorporated into the specific plant analyses. Upon request from the primary reviewer, other review branches will provide input for the areas of review stated in subsection I. The primary reviewer obtains and uses such input as required to assure that this review procedure is complete. The review of fission product releases and radiological consequences of design bas~is (most severe) LOCA is performed by AEB as described in the appendix to this SRP section. IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and that. the review supports the following kinds of statements and conclusions, which should be included in the staff's safety evaluation report: The staff concludes that the loss-of-coolant analysis resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary is acceptable and meets the relevant requirements of 10 CFR Part 50, §50.46 and Appendix K, GDC 35, and 10 CFR Part 100. This conclusion is based on the following: The applicant