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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
ML20006A823	10 January 1990	Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1
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.
ML19351A419	30 September 1989	Mark-BW Reload LOCA Analysis for Catawba & McGuire Units.	Boric Acid
ML19325C913	31 March 1989	Safety Evaluation to Justify Operation W/Loss of Jet Pump Flow Indication for Quad Cities,Units 1 & 2.
ML20235M911	20 February 1989	Nonproprietary Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue	Flow Induced Vibration
ML20207L778	6 October 1988	Nonproprietary WCAP 11936, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue	Finite Element Analysis Flow Induced Vibration
ML20154M242	30 September 1988	Simulate-3 Validation & Verification
ML20207L926	30 September 1988	Nonproprietary Addendum 2 to COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions)
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
ML20154J983	30 April 1988	RCS Flow Anomaly Investigation Rept
ML20147F410	9 February 1988	Rev 49 to CE-1-A, QA Program for Nuclear Generating Stations
ML20237C409	30 November 1987	Nonproprietary Rev 2 to Byron/Braidwood T-Hot Reduction Final Licensing Rept	Boric Acid Loop seal Turbine Missile Fuel cladding Flow Induced Vibration
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
ML18149A512	30 November 1986	Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code.
ML20207H976	30 November 1986	Nonproprietary Resistance Temp Detector Bypass Elimination Licensing Rept for Byron 1 & 2 & Braidwood 1 & 2	Hydrostatic Nondestructive Examination
ML20210A605	5 September 1986	Addendum a to Vol II of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification
ML20155J491	31 May 1986	Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block	Anticipated operational occurrence
ML20155J523	31 May 1986	Rev 1 to Functional Design Requirement for Core Protection Calculator	Anticipated operational occurrence
ML20155J505	31 May 1986	Rev 1 to Functional Design Requirements for Control Element Assembly Calculator	Anticipated operational occurrence
ML20203G548	31 March 1986	Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs	Power change
ML20151Z064	31 January 1986	Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines
ML20151Z052	31 January 1986	Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure
ML20140A682	31 December 1985	Reactor Vessel Fluence & Ref Temp for Pressurized Thermal Shock Evaluations
ML20138M421	30 September 1985	Justification for Raising Setpoint for Reactor Trip on High Pressure, Transient Assessment Program
ML20135H949	31 August 1985	Rev 1 to Reload Nuclear Design Methodology	Boric Acid Shutdown Margin
ML20135A557	31 August 1985	B&W Owners Group Cavity Dosimetry Program
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
ML20134N302	31 July 1985	Rev 00 to Functional Design Requirement for Core Protection Calculator	Anticipated operational occurrence
ML20134N294	31 July 1985	Rev 00 to Functional Design Requirement for Control Element Assembly Calculator	Anticipated operational occurrence
ML17346B171	31 July 1985	Retran Code Transient Analysis Model Qualification.	Anticipated operational occurrence Fuel cladding Coast down
ML20133H359	31 July 1985	Statistical DNBR Evaluation Methodology
ML20138P154	2 July 1985	Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation, Topical Rept
ML20127K138	30 June 1985	Nuclear Physics Methodology for Reload Design
ML20128Q275	31 May 1985	Revised Nomad Code & Model
ML20129E988	30 May 1985	VEPCO Reactor Sys Transient Analysis Using Retran Computer Code	Boric Acid
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
ML20111C117	31 January 1985	Rev 1 to Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 1 (Sys 80 Prototype),Evaluation of Predictions & Pre-Core Hot Functional Measurement & Insp Programs	Flow Induced Vibration
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
ML18142A153	31 December 1984	Nonproprietary Version of Revised VEPCO Evaluation of Control Rod Ejection Transient.	Shutdown Margin
ML17298B540	30 November 1984	Summary Rept on Operability of Shutdown Cooling Sys Relief Valves for Palo Verde Units 1,2 & 3.

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