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Issue date | Title | Topic | |
---|---|---|---|
ML20065D051 | 17 September 1990 | Forwards Objectives & Scope of 901205 Emergency Plan Exercise | High Radiation Area |
ML20064A709 | 14 September 1990 | Forwards Endorsement 133 to Nelia Policy NF-187 & Endorsement 116 to Maelu Policy MF-54 | |
ML20059F489 | 4 September 1990 | Forwards Listing of Changes,Tests & Experiments Completed During Month of Aug 1990 for Plant | |
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 |
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 |
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 |
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 Intergranular Stress Corrosion Cracking |
ML20058M804 | 6 August 1990 | Advises That W/Completion of Operator Training Program,Plant SPDS Meets Requirements Delineated in NUREG-0737,Suppl 1 | |
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 Stress corrosion cracking |
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 | |
ML20055H763 | 25 July 1990 | Forwards Financial Info Re Decommissioning of Plants | |
ML20055G633 | 18 July 1990 | Responds to Generic Ltr 89-06 Re SPDS to Meet Requirements of Suppl 1 to NUREG-0737.SPDS Lesson Plan Incorporated Into Initial License Class Training Program | |
ML17202L286 | 2 July 1990 | Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. | |
ML20055D434 | 29 June 1990 | Forwards Comm Ed Rept on Evaluation of Cracking in Quad- Cities Unit 2 Reactor Head, Per Commitment Made at 900419 Meeting W/Nrr.Rept Concludes That Cracks Caused by Interdendritic Stress Corrosion Cracking Mechanism | Stress corrosion cracking |
ML20055D474 | 29 June 1990 | Forwards Annual FSAR Update for Quad-Cities Station | |
ML20055C855 | 15 June 1990 | Forwards Special Neutron Attenuation Test for High Density Spent Fuel Racks (Wet), Final Rept.Rept Provides Results of Neutron Radioassay Measurement Program Conducted During Fall,1989 Refueling Outage | |
ML20043D766 | 4 June 1990 | Responds to J Lieberman 900501 Ltr Re Rl Dickherber. Confidence in Dickherber Performance in Future for Nonlicensed Duties Can Be Based Upon Demonstrated Record of Good Past Performance | |
ML20043D769 | 4 June 1990 | Responds to 900501 Ltr Re Work Hours for Dickherber.During Outage,Dickherber Worked Extended Hours Traditionally Associated W/Refueling Activities | Fitness for Duty |
ML20043G425 | 2 June 1990 | Forwards Listing of Changes,Tests & Experiments Completed During May 1990 | |
ML20043D320 | 1 June 1990 | Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21) | |
ML20043B668 | 22 May 1990 | Forwards Proposed Changes to SER Re Hot Shutdown Repairs in Event of Fire,Per 10CFR50,App R Section Iii.G Covering Spurious Operations & High Impedance Faults & Electrical Isolation Deficiency | Safe Shutdown Exemption Request |
ML20043A468 | 10 May 1990 | Forwards Proposed Changes to 880721 SER Re App R Section Iii.G Exemption for Fire Zones 1.1.1.1S & 1.1.1.2,southern & Northern Torus Level in Unit 1 Reactor Bldg Column & Unit 1 Reactor Bldg Elevations 623 Ft & 647 Ft | Safe Shutdown Fire Barrier Exemption Request |
ML20042H001 | 3 May 1990 | Forwards Listing of Changes,Tests, & Experiments Completed During Apr 1990 | Post Accident Monitoring |
ML20042G350 | 2 May 1990 | Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-254/90-02 & 50-265/90-02.Corrective Actions:Continuous Fire Watch Initiated & Training Conducted on Procedure Rev | Continuous fire watch Fire Protection Program Fire Watch |
ML20042F122 | 1 May 1990 | Forwards Preliminary Rept of IGSCC Insp Results.Flaw Indication Detected in Weld Overlay Matl of Weld 02J-S3 & Removed by Boat Sample & Std Weld Overlay Thickness Restored.Final Rept Will Be Forwarded within 30 Days | Weld Overlay Intergranular Stress Corrosion Cracking Liquid penetrant |
ML20042F118 | 1 May 1990 | Advises of Listed Value for Secondary Containment,Per NRC Request for Addl Info Re LER 50-254/87-025.Value Based on Info Contained in Plant FSAR | |
ML20042F069 | 1 May 1990 | Responds to Generic Ltr 83-28,Item 4.5.3 Re Reactor Protection Sys on-line Functional Test Intervals.Endorses Two BWR Owners Group Topical Repts NEDC-30844 & NEDC-30851P Generic Evaluations | |
ML20042E449 | 11 April 1990 | Forwards Request for Rev to Previous NRC Exemption Approval on 860625 Re Combustible Load Values | Safe Shutdown Fire Barrier Exemption Request |
ML20042F035 | 23 March 1990 | Forwards Part 3 of 1989 Operating Rept.W/O Rept | |
ML19330D516 | 14 March 1990 | Advises That Revs to Inservice Testing Program & Implementation Procedures Will Be Completed by 900629,per Generic Ltr 89-04 | Decommissioning Funding Plan |
ML20012C072 | 8 March 1990 | Comments on SALP Board Repts 50-254/89-01 & 50-265/89-01 for Oct 1988 to Nov 1989.Util Appreciates NRC Recognition of Overall Improvements in Areas of Operation & Emergency Preparedness & Good Performance in Area of Security | |
ML20012B592 | 2 March 1990 | Forwards Listing of Changes,Tests & Experiments Computed During Month of Feb 1990 for Plant | Stress corrosion cracking |
ML17347B588 | 1 March 1990 | Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits | |
ML15217A103 | 28 February 1990 | Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals | Offsite Dose Calculation Manual Process Control Program |
ML18094B322 | 28 February 1990 | Forwards Executed Amend 14 to Indemnity Agreement B-74 | |
ML20011F382 | 26 February 1990 | Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices | |
ML20006G062 | 22 February 1990 | Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld | |
ML20006E907 | 16 February 1990 | Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures | |
ML20006E144 | 16 February 1990 | Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals | |
ML20006E420 | 14 February 1990 | Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 | |
ML20011E615 | 12 February 1990 | Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) | |
ML20012A955 | 8 February 1990 | Responds to Violations Noted in Insp Repts 50-254/89-26 & 50-265/89-26.Corrective Action:Procedure Qis 47-1 Revised to Include Requirement That Equalizing Valve Be Open During Isolation of Transmitter | Hydrostatic Excess Flow Check Valve |
ML20006F336 | 8 February 1990 | Responds to NRC Ltr 900110 Ltr Re Violations Noted in Insp Repts 50-254/89-25 & 50-265/89-25.Corrective Actions:Safety Evaluations Submitted Via 900116 Ltr & Table of Content Will Be Completed for 1989 FSAR Update to Be Submitted by 900630 | |
ML20011E713 | 6 February 1990 | Forwards Reactor Containment Bldg Integrated Leak Rate Test,Quad Cities Nuclear Power Station,Unit 1,891114-15. Next Type a Test Scheduled for Fall 1990 | Integrated leak rate test |
ML20011E499 | 6 February 1990 | Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested | |
ML20006D691 | 2 February 1990 | Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle |