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	Issue date	Title	Topic
ML20198R233	30 April 1997	Rev 2 to Quad Cities Unit 2 Cycle 145 Reload Analysis	Anticipated operational occurrence Feedwater Controller Failure Fuel cladding
ML20198T325	18 April 1997	Non-proprietary Rev 1 to EMF-96-180, Quad Cities Unit 2 Cycle 15 Plant Transient Analysis	Safety Limit Minimum Critical Power Ratio Stroke time Anticipated operational occurrence Feedwater Controller Failure Power change
ML20078E517	25 January 1995	Correction to Encl 3, Equivalent Margin Analysis Plant Applicability Verification Form of Topical Rept NEDO-32205-A,Rev 1
ML20078D861	5 January 1995	Shroud Repair Seismic Analysis	Operating Basis Earthquake Finite Element Analysis Design basis earthquake Earthquake
ML20078A745	30 June 1994	Evaluation of Indications Found at H5 Weld Location in Quad Cities Unit 1 Shroud
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
ML17252A753	30 November 1992	Lpci/Containment Cooling Sys Evaluation.	Reactor Vessel Water Level Coatings Turbine Missile Flow Induced Vibration
ML20065Q853	30 November 1990	Rev 0 to, Comm Ed Topical Benchmark of BWR Nuclear Design Methods
ML19332E407	16 October 1989	Errata & Addendum 1 to, Safety Evaluation to Justify Operation W/Loss of Jet Pump Flow Indication for Quad Cities 1 & 2.
ML19325C913	31 March 1989	Safety Evaluation to Justify Operation W/Loss of Jet Pump Flow Indication for Quad Cities,Units 1 & 2.
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
ML20147F410	9 February 1988	Rev 49 to CE-1-A, QA Program for Nuclear Generating Stations
ML20154A402	28 September 1987	LOCA-ECCS Analysis for Dresden Units During Single Loop Operation W/Advanced Nuclear Fuels Corp Fuel	FLEX Fuel cladding
ML20235C487	31 July 1987	Extended Operating Domain & Equipment Out-of-Svc for Quad Cities Nuclear Power Station Units 1 & 2. B Wolfe Affidavit Also Encl	Abnormal operational transient Feedwater Controller Failure Fuel cladding
ML20235C433	30 June 1987	Rev 0 to Suppl Reload Licensing Submittal for Quad Cities Nuclear Power Station Unit 1,Reload 9
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
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
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
ML20154A398	28 September 1984	Analysis of Dresden Units 2 & 3 Operation W/One Relief Valve Out-of-Svc	Reactor Vessel Water Level
ML20245F290	30 June 1984	Hpci/Rcic Room Leak Detection,Phase II & III
ML20245F271	31 January 1984	Hpci/Rcic Room Leak Detection,Phase I Rept
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
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
ML20071Q036	2 December 1982	to Dresden Unit 2 LOCA Analysis Using Exem/Bwr Evaluation Model MAPLHGR Results	FLEX
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
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
ML20065L871	31 July 1982	GE BWR Extended Load Line Limit Analysis for Quad Cities Nuclear Power Station,Unit 1,Cycle 7 & Unit 2,Cycle 6	Feedwater Controller Failure
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.
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.
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.
ML20126J695	31 March 1981	Control Blade Exam Results & Response to Item 4 of IE Bulletin 79-26
ML19343C375	28 February 1981	Generic Info for Barrier Fuel Demonstration Bundle Licensing, Approved Version	Fuel cladding Power change Coast down
ML19343A990	13 November 1980	Revised Page 4-8 to LOCA Analysis Rept. Supplemental Discussion of NEDO-24855 Encl
ML19343A983	31 August 1980	Plant:Extended Burnup Fuel Program.	Abnormal operational transient Fuel cladding
ML19250B999	31 December 1978	Load Line Limit Analysis License Amend Submittal.

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