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	Issue date	Title	Topic
ML20210L436	2 August 1999	Cycle 9 12-Month SG Insp Rept
ML20210L445	31 July 1999	Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20211F903	30 June 1999	Cycle 9 Refueling Outage
ML20196H862	30 June 1999	NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept	High Radiation Area Power change
ML20205B663	28 February 1999	Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys
ML20198S730	31 December 1998	Cycle 10 Voltage-Based Repair Criteria 90-Day Rept
ML20199J257	31 January 1998	Cycle 9 Voltage-Based Repair Criteria 90-Day Rept
ML20199J244	29 January 1998	Snp Unit 2 Cycle Refueling Outage Oct 1997
L-97-215, SG Secondary Side Loose Object Safety Evaluation	23 October 1997	SG Secondary Side Loose Object Safety Evaluation
ML20203B959	18 September 1997	Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn
ML20210J176	31 July 1997	Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept	Flow Induced Vibration
ML20138D199	4 April 1997	Special Project97-928S, Sequoyah Nuclear Plant Assessments
ML20138C537	24 March 1997	Rev 0 to Pressurizer Level Event	Time of Discovery Scaffolding
ML20217G240	3 March 1997	Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow	Shutdown Margin Ultimate heat sink Safe Shutdown Earthquake Fuel cladding Flow Induced Vibration Coast down
ML20117J361	1 August 1996	SE of Safety Valve Setpoint Tolerance Relaxation	Ultimate heat sink Deep Dose Equivalent Fuel cladding
ML20117K946	5 March 1996	Reliability Study
ML20117K951	29 February 1996	Reliability Common Cause Assessment, for Feb 1996
ML20095J189	5 October 1995	Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds	Weld Overlay
ML20081D383	12 March 1995	Simulator Four Yr Test Rept for 950312	Fuel cladding
ML20083N952	16 November 1994	10CFR50.59 Rept to Nrc	Safe Shutdown Boric Acid Shutdown Margin High Radiation Area Safe Shutdown Earthquake Operating Basis Earthquake Nondestructive Examination Temporary Modification Condition Adverse to Quality
ML20024H849	19 July 1993	Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles.
ML20118D194	21 September 1992	Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment
ML20114A664	15 August 1992	920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period	Fire Barrier Coatings Condition Adverse to Quality Job Performance Measure Foreign Material Exclusion Systematic Assessment of Licensee Performance Fire Watch Downpower
ML20141M134	27 March 1992	Spent Fuel Pool Mod for Increased Storage Capacity	Operating Basis Earthquake Design basis earthquake Control of Heavy Loads Fuel cladding
ML20029C201	12 March 1991	Initial Simulator Certification.	Stroke time Emergency Lighting Fuel cladding
ML20028H859	7 September 1990	Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues.	Condition Adverse to Quality
ML20136J043	30 June 1990	Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks
ML20043B606	11 May 1990	Diesel Generator Voltage Response Improvement Rept.
ML20006E577	5 February 1990	Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis.	Safe Shutdown Earthquake
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
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
ML20246D671	30 June 1989	Criticality Analysis of Byron/Braidwood Fresh Fuel Racks
ML20247H071	30 June 1989	Description & Verification Summary of Computer Program, Gappipe	Earthquake
ML20247H079	22 June 1989	App to Description & Verification Summary of Computer Program,Gappipe
ML20247N062	31 May 1989	Production Training Dept,Braidwood,Malfunctions & Initial Conditions
ML20247K301	12 May 1989	Leak-Before-Break Evaluation for Carbon Steel Piping	Safe Shutdown Earthquake Hydrostatic Finite Element Analysis Earthquake Flow Induced Vibration
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
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
ML20246D535	28 February 1989	Steam Generator Tubing Insp Results
ML20005G421	28 February 1989	Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation.	Hydrostatic
ML17251A481	28 February 1989	Ultrasonic Indication Sizing Technique Development. Related Info Encl	Hydrostatic
ML20206C745	30 November 1988	ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5
ML20247H130	30 November 1988	Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns	Operating Basis Earthquake Earthquake
ML20236D195	18 November 1988	HVAC Damping Values
ML20205T750	4 November 1988	Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination
ML20206K302	31 October 1988	Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3
ML20206K310	31 October 1988	Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1

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