LEADER 01543nam 2200385Ia 450 001 9910699743003321 005 20101130140641.0 035 $a(CKB)5470000002405517 035 $a(OCoLC)688251044 035 $a(EXLCZ)995470000002405517 100 $a20101130d1996 ua 0 101 0 $aeng 135 $aurbn||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 00$aPotential for high post-accident closed-cycle cooling water temperatures to disable equipment important to safety$b[electronic resource] 210 1$aWashington, D.C. :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation,$d[1996] 215 $a1 online resource 225 1 $aNRC information notice ;$v96-01 300 $aTitle from HTML title screen (viewed on Nov. 30, 2010). 300 $a"January 3, 1996." 606 $aNuclear power plants$zUnited States$xEquipment and supplies 606 $aNuclear power plants$zUnited States$xSafety measures 606 $aNuclear reactors$xCooling 615 0$aNuclear power plants$xEquipment and supplies. 615 0$aNuclear power plants$xSafety measures. 615 0$aNuclear reactors$xCooling. 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Reactor Regulation. 801 0$bGPO 801 1$bGPO 906 $aBOOK 912 $a9910699743003321 996 $aPotential for high post-accident closed-cycle cooling water temperatures to disable equipment important to safety$93188499 997 $aUNINA