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100   $a20210402d1980      ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 00$aEB 80-04 analysis of a PWR main steam sine break with continued feedwater addition
210  1$aWashington, D.C. :$cUnited States Nuclear Regulatory Commission, Office of Inspection and Enforcement,$d1980.
215   $a1 online resource
225 1 $aGeneric letter ;$v80-12
300   $a"February 8, 1980."
606   $aPressurized water reactors$xLoss of coolant
606   $aFeed-water
615  0$aPressurized water reactors$xLoss of coolant.
615  0$aFeed-water.
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Inspection and Enforcement,
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910715970403321
996   $aEB 80-04 analysis of a PWR main steam sine break with continued feedwater addition$93351939
997   $aUNINA