Liliana Yetta Pandi danBudi Rohnian; Bapeten. Based on .theconsideration' of t,hehuman and environ!1J€mtal safetY and toensure thai the NPP will beoperated safely,'a saiety analysis is need 'tobe performed by tHelicensing applicant andverified by the regulatory body. The safety analysis is intended to calculate the reactoroperation par~meters having effects on the reactor operation, safety during transient,and these parameters are then is compared to the acceptance criterir;t; This paperdiscusses the analysis assessing thefulfillment of a four-loop 1100-MWe PWR plant incase of the occiirrenc,e of complete loss of reaCtor coolantjlow accident, to theacceptance criteria. The anqlysis is conducted by using Relap5/M0(i2 and Cobra-IVI/Jins code. The results of the analysis show thatfollowing 10ss'afreaCtor coolantjlow,the minimum DNBRreaches 1,6366,while the max.imum reactor' coolemt pressure" reaches 164,05 kg/cm2 g. These value meet the acceptance criteria, i.e. minimum DNBR1.17 and rea(;{orpressure .20W2 MPa g'or 210 kg/cm2g, therefoe, the integrity of,the core and reactor pressure' boundarie~are not challenged during this ~ccident 'Kevwords: PWR, accident, loss ofreactor coolantjlow, acceptance,criteria, DNBR
