Using　the　MELCOR　code,　we　simulated　and　analyzed　a　severe　accident　at　a　Chinese　pressurized　reactor　1000-MW　(CPR1000)　power　plant　caused　by　station　blackout　(SBO)　with　failure　of　the　steam　generator　(SG)　safety　relief　valve　(SRV).　The　CPR1000　response　and　results　for　three　different　scenarios　were　analyzed:　(i)　seal　leakage　and　an　auxiliary　feed　water　(AFW)　supply;　(ii)　no　seal　leakage　or　AFW　supply;　and　(iii)　seal　leakage　but　no　AFW　supply.　The　results　for　the　three　scenarios　are　compared　with　those　for　a　simple　SBO　accident.　According　to　our　calculations,　the　SG　SRV　stuck　in　the　open　position　would　greatly　accelerate　the　sequence　for　a　severe　accident.　For　an　SBO　accident　with　the　SRV　stuck　open　without　seal　leakage　or　an　AFW　supply,　the　pressure　vessel　would　fail　at　9576　s　and　the　containment　system　would　fail　at　124,000　s.　If　AFW　is　supplied,　pressure　vessel　failure　would　be　delayed　nearly　30000　s　and　containment　failure　would　delay　at　least　50000　s.　When　seal　leakage　exists,　pressure　vessel　failure　is　delayed　about　50　s　and　containment　failure　time　would　delay　about　30000　s.　The　results　will　be　useful　in　gaining　an　insight　into　the　detailed　processes　involved　and　establishing　management　guidelines　for　a　CPR1000　severe　accident.　(C)　2013　Elsevier　Ltd.　All　rights　reserved.