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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20059L034 | 20 September 1990 | Forwards Addl Station Blackout Info Re Diesel Loading & Alternate Ac Analysis,Per 900404 Meeting.Info Will Be Helpful When Evaluating Unit O Diesel Generator cross-tie Mod | |
| ML20059K674 | 17 September 1990 | Suppls Responses to Violations Noted in Insp Repts 50-454/89-11,50-455/89-13,50-456/89-11 & 50-457/89-11. Corrective Actions:Procedures Changed & Valve Tagging Status Provided | |
| ML20065D051 | 17 September 1990 | Forwards Objectives & Scope of 901205 Emergency Plan Exercise | High Radiation Area |
| ML20059K508 | 14 September 1990 | Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990 | |
| ML20064A709 | 14 September 1990 | Forwards Endorsement 133 to Nelia Policy NF-187 & Endorsement 116 to Maelu Policy MF-54 | |
| ML20059H532 | 11 September 1990 | Requests Withdrawal of Application for Amend to Licenses NPF-11 & NPF-18,per 891215 & s.Amend Would Have Removed Applicability of Tech Spec (TS) 3.0.4 to TS 3.6.5.2, Secondary Containment Automatic Isolation Dampers | |
| ML20059L661 | 10 September 1990 | Forwards Byron Station Units 1 & 2 Inservice Insp Program | |
| ML20059H427 | 7 September 1990 | Provides Supplemental Response to NRC Bulletin 90-001.Plant Initial Review of Calibr Records Completed on 900831 | |
| ML20059G161 | 6 September 1990 | Submits Supplemental Response to Generic Ltr 89-06, Certifying That SPDS Satisfies or Will Be Modified to Satisfy Requirements of Suppl 1 to NUREG-0737.Classroom Instruction on SPDS Incorporated Into Program | |
| ML20059G094 | 5 September 1990 | Forwards LaSalle County Station Unit 2 Third Refueling Outage,Asme Section XI Summary Rept for Spring 1990 Insp | |
| ML20059F489 | 4 September 1990 | Forwards Listing of Changes,Tests & Experiments Completed During Month of Aug 1990 for Plant | |
| ML20059G175 | 31 August 1990 | Provides Results of Util Reevaluation of Response to NRC Bulletin 85-003.Util Believes That Previous Testing Results & Subsequent Submittals Provide Assurance of Continued Operability of Sys motor-operated Valves | |
| ML20059C689 | 30 August 1990 | Forwards LaSalle County Nuclear Power Station Unit 2,Cycle 4 Startup Test Rept & Test Rept Summary | Shutdown Margin |
| ML20059B972 | 28 August 1990 | Forwards Reactor Head & Upper Shell Insp Plan,Per 900419 Meeting.Insp Plan Does Not Encompass Uppermost shell-to- Shell Weld Due to Technological Limitations | Liquid penetrant |
| ML20059F031 | 27 August 1990 | Provides Schedule for Completion of Installation of Mods to Plants Reactor Water Level Instrumentation,Per Generic Ltr 84-23.Penetrations Will Be Installed During Outage 13 for Dresden & During Outage 12 for Quad-Cities | |
| ML20059E953 | 27 August 1990 | Forwards Summary of Fabrication History for Upper Reactor Vessel,Per 900419 Technical Meeting.Summary Indicates That Fabrication Mismatches,Considered to Be Significant for Development of Insp Plan,Identified at head-to-flange Weld | Hydrostatic |
| ML20064A375 | 24 August 1990 | Forwards Revised Pages to Operating Limits Rept for Cycle 2, Correcting Fxy Portion of Rept,Per Tech Spec 6.9.1.9, Operating Limits Rept | |
| ML20064A368 | 24 August 1990 | Forwards Response to 900517 Request for Addl Info Re Design of Containment Hydrogen Monitoring Sys.Util Proposes Alternative Design That Ensures Both Containment Isolation & Hydrogen Monitoring Sys Operability in Event of LOCA | |
| ML20059C720 | 23 August 1990 | Forwards Effluent & Waste Disposal Semiannual Rept,Jan-June 1990 Gaseous Effluents-Summation of All Releases & Rev 8 to Quad-Cities Station Process Control Program for Processing of Radioactive Wet Waste | Process Control Program |
| ML20059D827 | 23 August 1990 | Provides Written Communication Re Util Intentions & Commitments,Per 900808 Telcon W/M Wallace.Standing Order 90-24 Issued to Provide Administrative Controls Beyond Tech Spec Requirements to Assure Svc Water Pump Availability | |
| ML20059C078 | 22 August 1990 | Submits Supplemental Info to Util 900412 Response to Notice of Violation in Insp Repts 50-295/89-40 & 50-304/89-36.Info Regards Requalification program,180 H of Required Training Through SAT Process & Policy for Remediation of Individual | |
| ML20056B406 | 21 August 1990 | Submits Supplemental Response to Generic Ltr 88-14 Re Design & Verification of Instrument Air Sys.Mfg Purchase Specs & Vendor Manuals Reviewed for Air Quality Requirements | |
| ML20056B433 | 20 August 1990 | Forwards Errata,To Radioactive Effluent Rept for Jan-June 1990 & Gaseous Effluent Errata Sheet | |
| ML20064A018 | 16 August 1990 | Submits Supplemental Response to NRC Bulletin 88-008,Suppls 1 & 2.Surveillance Testing Revealed No Leakage,Therefore Charging Pump to Cold Leg Outage Injection Lines Would Not Be Subjected to Excessive Thermal Stresses | Nondestructive Examination Liquid penetrant |
| ML20059A399 | 15 August 1990 | Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program | Boric Acid VT-2 Scaffolding |
| ML20059B896 | 14 August 1990 | Documents Approval of Schedular Extension & Accepts Human Engineering Discrepancies Discussed | |
| ML20058P779 | 13 August 1990 | Provides Supplemental Response to NRC Bulletin 89-001 Re Mechanical Plugs Supplied by Westinghouse,Per .All Mechanical Plugs from Heats NX-3513 & NX-4523 Removed from Hot Legs of Plant Steam Generators | |
| ML20059D173 | 10 August 1990 | Responds to NRC Re Exercise Weaknesses Noted in Insp Repts 50-373/90-05 & 50-374/90-06.Corrective Actions: LOA-FP-01, Fire Alarm Response Will Be Revised to Alert Control Room Operators to Refer to Emergency Action Levels | |
| ML20063Q105 | 10 August 1990 | Forwards Monthly Operating Repts for Jul 1990 for Byron Units 1 & 2 & Corrected Monthly Operating Rept for June 1990 for Unit 2 | |
| ML20058P348 | 9 August 1990 | Forwards Summary of Fuel Performance,End of Cycle 10,May 1990. No Leakage or Fuel Failure Noted | |
| ML20058M822 | 7 August 1990 | Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions | Scram Discharge Volume |
| ML20058N055 | 7 August 1990 | Provides Supplemental Response to NRC Bulletin 88-008, Suppls 1 & 2.Surveillance Testing Performed Revealed No Leakage,Therefore,Charging Pump to Cold Leg Injection Lines Would Not Be Subjected to Excessive Thermal Stresses | Nondestructive Examination Liquid penetrant |
| ML20058N065 | 7 August 1990 | Responds to NRC Bulletin 88-009 Re Incore Neutron Monitoring Sys Thimble Tube Integrity.Thimble Tube Insps Will Be Performed at Every Refueling Outage Until Sufficient Data Accumulated on Thimble Tube Wear | |
| ML20058N297 | 6 August 1990 | Forwards Rev 34 to Security Plan.Rev Details Addl Gate Position for Security Testing & Maint.Rev Withheld (Ref 10CFR73.21) | |
| ML20058M804 | 6 August 1990 | Advises That W/Completion of Operator Training Program,Plant SPDS Meets Requirements Delineated in NUREG-0737,Suppl 1 | |
| ML20058M859 | 6 August 1990 | Forwards Rept of Metallurgical Exam That Revealed No Evidence of Defects,Porosity or Slag in Weld Overlay. Rept Responds to IGSCC Insp Performed on Facility IGSCC Susceptible Piping | Weld Overlay Stress corrosion cracking |
| ML20056A335 | 2 August 1990 | Responds to NRC Bulletin 88-009 Requesting That Addressees Establish & Implement Insp Program to Periodically Confirm in-core Neutron Power Reactors.All Timble Tubes Used at Plant Inspected & 18 Recorded Evidence of Degradation | |
| ML20058M410 | 1 August 1990 | Forwards Listing of Changes,Tests & Experiments Completed During Month of Jul 1990 for Plant | |
| ML20058M829 | 31 July 1990 | Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements of Corrective Actions. Status of Implementation of Generic Safety Issues Encl | Scram Discharge Volume |
| ML20056A027 | 30 July 1990 | Provides Addl Info Re Resolution of Number of Older Licensing Issues,Including Containment Isolation Valve Position Indication,Per NRC | |
| ML20056A074 | 27 July 1990 | Forwards Justification for Rev to Installation Schedules for Two Commitments Re Safeguards Inadequacies & Program Concerns.Encl Withheld | |
| ML20056A703 | 27 July 1990 | Responds to NRC Re Violations Noted in Insp Repts 50-373/90-13 & 50-374/90-14.Corrective actions:LRP-1250-3 Revised to Include Addl Requirement for Extremity Monitoring | Overexposure |
| ML20064A549 | 27 July 1990 | Responds to NRC Re Violations Noted in Insp Repts 50-373/90-12 & 50-374/90-13.Corrective Actions:Program Implemented Identifying & Correcting Repetitive Local Leak Rate Failures Through Testing & LER Investigation | |
| ML20055J223 | 26 July 1990 | Requests Withdrawal of Proposed Amend Re Deletion of Confirmatory Order | |
| ML20055J119 | 26 July 1990 | Responds to Generic Ltr 90-04, Request for Info Re Status of Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions. Current Status of Issues Encl | |
| ML20055J163 | 26 July 1990 | Forwards Reactor Containment Bldg Integrated Leak Rate Test Quad-Cities Nuclear Power Station Unit 2,900427-28, & Related Apps Describing Type a Test,Per 10CFR50,App J, Section V.B.1.Next Test Scheduled for Fall 1991 | |
| ML20055J122 | 25 July 1990 | Notifies That Plants Current Outage Plannings Will Not Include Removal of Snubbers.Removal of Snubbers Scheduled for Future Outages.Completion of Review by NRC by 900801 No Longer Necessary | |
| ML20055J126 | 25 July 1990 | Notifies That Replacement of 13 Snubbers w/8 Seismic Stops on Reactor Coolant Bypass Line Being Deferred Until Later Outage,Per Rl Cloud Assoc Nonlinear Piping Analyses | |
| ML20055H763 | 25 July 1990 | Forwards Financial Info Re Decommissioning of Plants | |
| ML20055H766 | 24 July 1990 | Forwards Supplemental Response to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions |