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	Issue date	Title	Topic
ML20206T477	31 May 1999	Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology	Boric Acid Shutdown Margin Loop seal Fuel cladding Coast down Affidavit Manual Operator Action
ML20205L234	5 April 1999	SFP Criticality Analysis
ML20199E965	24 November 1998	Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility
ML20203J858	31 January 1998	Rev 2 to Catawba Nuclear Station PRA Summary Rept, for Jan 1998.W/one Diskette	Safe Shutdown Boric Acid High winds Mission time Fire Barrier Tornado Missile Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Large early release frequency TORMIS Earthquake Fuel cladding Coast down Fatality
ML20117J049	8 May 1996	At&T Round Cell Nuclear Util User'S Council Charter
ML20094N075	31 October 1995	Validation of Crest, Interim Rept	Earthquake
ML20094N064	31 July 1995	Computer Program for Coupled Response Spectrum Analysis of Secondary Sys
ML20117M802	31 July 1995	CNS Standby Nuclear SW Pond Analysis
ML20086F471	30 June 1995	Interim Plugging Criteria 90 Day Rept	Non-Destructive Examination Nondestructive Examination Stress corrosion cracking Eddy Current Testing
ML20098A451	30 April 1995	Stations Replacement SG Topical Rept
ML20083N754	24 April 1995	Rn Sys Corrosion in Stainless Steel Welds Metallurgical Analysis Rept
ML20117M791	28 February 1995	Standby Nuclear SW Pond Physical Testing Conducted During Feb 1995	Grab sample
ML20077S609	31 December 1994	1994 Annual Insp of Snsw Dam & Wwcb Dikes
ML20077R710	20 December 1994	CNS Units 1 & 2 10CFR50.59 Evaluation of FSAR Change Related Edsfi Deviation 50413,414/92-01-02 (IEEE 308-1974)	Safe Shutdown Emergency Lighting
ML20077C577	3 November 1994	1 Cycle 7 Interim Plugging Criteria Assessment & Projected EOC-8 Slb Leakage	Stress corrosion cracking
ML20072T444	31 August 1994	Selected Licensee Commitments	Boric Acid Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change
ML20063E280	31 January 1994	Duke Power Co Catawba Nuclear Station Special Rept RHR Pump Vibration	Loop seal Probabilistic Risk Assessment Operability Determination Scaffolding
ML20071A929	25 January 1994	Nonproprietary McGuire Units 1 & 2 Kinetic Sleeve Evaluation	Exclusive Use
ML20059J277	18 January 1994	Non-proprietary Document 51-1228707-01, Evaluation of Bwnt Kinetic Sleeving Process	Safe Shutdown Non-Destructive Examination Stress corrosion cracking Exclusive Use
ML18010B084	5 May 1993	NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.	Safe Shutdown Boric Acid Shutdown Margin Loop seal Stroke time Temporary Modification Stress corrosion cracking Liquid penetrant Overspeed trip
ML20126A067	9 December 1992	Snubber Elimination at McGuire Nuclear Station Using Limit Stops, Interim Rept	Earthquake
ML18010A952	30 November 1992	NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.	Nondestructive Examination Liquid penetrant
ML20101F181	18 November 1991	Rev 0 to Overtemp Delta Temp Scaling,Westinghouse NSSS Process Control Sys
ML20079N401	11 November 1991	Mixed Waste Characterization & Processing	Eddy Current Testing
ML20062G727	19 November 1990	Eddy Current Exam Rept Catawba Unit 2 June 1990 Refueling Outage 3	Stress corrosion cracking
ML20043E810	28 February 1990	Rev 0 to Catawba Unit 1 Cycle 5 Core Operating Limits Rept.
ML20043E770	28 February 1990	Rev 0 to Catawba Unit 2 Cycle 3 Core Operating Limits Rept.
ML17347B462	31 December 1989	App a to USI A-46 & Generic Ltr 87-02.	Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Earthquake Backfit
ML20246D687	14 August 1989	Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks
ML20011E253	31 July 1989	Arrotta Validation & Verification - Std Benchmarks Set.	Safe Shutdown
ML19327B401	31 July 1989	Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel.
ML18008A031	31 July 1989	NTH-TR-01 Decrease in Heat Removal by Secondary Sys.	Safe Shutdown Rod Drop Event
ML20246A679	30 June 1989	Description of Additions to & Deviations from Generic Emergency Response Guidelines
ML20247H071	30 June 1989	Description & Verification Summary of Computer Program, Gappipe	Earthquake
ML20246D671	30 June 1989	Criticality Analysis of Byron/Braidwood Fresh Fuel Racks
ML20247H079	22 June 1989	App to Description & Verification Summary of Computer Program,Gappipe
ML20247N062	31 May 1989	Production Training Dept,Braidwood,Malfunctions & Initial Conditions
ML20246J357	31 May 1989	Evaluation of Degradation of Tube R18C25 & Justification for Return to Power	Boric Acid Stress corrosion cracking Eddy Current Testing
ML20247L184	12 May 1989	Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2	Packing leak Safe Shutdown Earthquake Liquid penetrant Flow Induced Vibration
ML20244B334	12 May 1989	Rev 3 to Final Design Description of ATWS Mitigation Sys Actuation Circuitry	Loss of condenser vacuum
ML20247K301	12 May 1989	Leak-Before-Break Evaluation for Carbon Steel Piping	Safe Shutdown Earthquake Hydrostatic Finite Element Analysis Earthquake Flow Induced Vibration
ML18094A355	30 April 1989	Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles.	Safe Shutdown Earthquake
ML20247F132	23 March 1989	Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment
ML17251A481	28 February 1989	Ultrasonic Indication Sizing Technique Development. Related Info Encl	Hydrostatic
ML20005G421	28 February 1989	Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation.	Hydrostatic
ML20206C745	30 November 1988	ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5
ML20205T750	4 November 1988	Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination
ML20206K310	31 October 1988	Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1
ML20206K302	31 October 1988	Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3
ML20154N608	30 September 1988	Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations	Nondestructive Examination

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