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	Issue date	Title	Topic
ML17187A805	31 January 1993	Suppl 1 to GENE-770-26-1092, Long Term Containment Response to DBA-LOCA w/65 Fdegrees F Svc Water Temperature,80 Degrees F Initial Pool Temperature & Initiation of Containment Cooling at 1800 Seconds.	Reactor Vessel Water Level Fuel cladding
ML17194A063	31 May 1981	Errata & Addenda Sheet 5,replacing Pages V/VI,3-1/3-2,4-10, 4-12,4-13 & 4-14 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations.
ML17194A065	31 July 1981	Errata & Addenda Sheet 6,replacing Pages V/VI,3-1,3-2,4-3 & 4-14,to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations.
ML17252A753	30 November 1992	Lpci/Containment Cooling Sys Evaluation.	Reactor Vessel Water Level Coatings Turbine Missile Flow Induced Vibration
ML19250B999	31 December 1978	Load Line Limit Analysis License Amend Submittal.
ML19343A990	13 November 1980	Revised Page 4-8 to LOCA Analysis Rept. Supplemental Discussion of NEDO-24855 Encl
ML20039G953	31 December 1981	Cycle 8 Reload Analysis, Revision 1	Shutdown Margin Anticipated operational occurrence Feedwater Controller Failure Fuel cladding
ML20039G956	23 December 1981	3,Cycle 8 Plant Transient Analysis Rept.
ML20063C487	31 July 1982	Errata & Addenda Sheet 7,replacing Pages 4-11 & 4-14 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations
ML20065Q853	30 November 1990	Rev 0 to, Comm Ed Topical Benchmark of BWR Nuclear Design Methods
ML20069J554	30 September 1982	Errata & Addenda Sheet 8,replacing Page 4-10 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations
ML20071Q036	2 December 1982	to Dresden Unit 2 LOCA Analysis Using Exem/Bwr Evaluation Model MAPLHGR Results	FLEX
ML20071Q059	7 December 1982	Nonproprietary Version of Revision 1 to Plant Transient Analysis for Dresden Unit 2,Cycle 9	Stroke time Anticipated operational occurrence Power-Operated Valves Power change
ML20076G957	31 August 1983	Cycle 9 Plant Transient Analysis	Stroke time Anticipated operational occurrence Power Operated Valves Power change
ML20076H058	1 August 1983	Revised Mplhgr Analysis Using Exxon Nuclear Corp Exem Evaluation Model	FLEX
ML20106A605	30 April 1983	Errata & Addenda Sheet 10,replacing Page 4-11 to, LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations
ML20106A648	31 January 1985	Errata & Addenda Sheet 13,replacing Pages v/vi,3-2,4-3, 4-15 & 4-16 to, LOCA Anaysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations	Fuel cladding
ML20126J695	31 March 1981	Control Blade Exam Results & Response to Item 4 of IE Bulletin 79-26
ML20137F033	15 January 1985	Rev 1 to Criticality Safety Analysis,Dresden 2,3 Spent Fuels Storage Pool W/Exxon Nuclear Co,Inc 9x9 Reload Fuel
ML20147F410	9 February 1988	Rev 49 to CE-1-A, QA Program for Nuclear Generating Stations
ML20154A398	28 September 1984	Analysis of Dresden Units 2 & 3 Operation W/One Relief Valve Out-of-Svc	Reactor Vessel Water Level
ML20154A402	28 September 1987	LOCA-ECCS Analysis for Dresden Units During Single Loop Operation W/Advanced Nuclear Fuels Corp Fuel	FLEX Fuel cladding
ML20154A413	13 July 1988	Extended Operating Domain/Equipment Out-of-Svc Analysis for Dresden Units 2 & 3	Reactor Vessel Water Level Anticipated operational occurrence Feedwater Controller Failure Power change
ML20205F271	31 August 1985	Errata & Addenda Sheet 14,replacing Pages v/vi,3-2,4-3,4-10, 4-15 & 4-16 to, LOCA Analysis Rept for Dresden Units 2,3 & Quad Cities 1,2 Nuclear Power Stations	Fuel cladding

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