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| Issue date | Title | Topic | |
|---|---|---|---|
| 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 | |
| ML20059K508 | 14 September 1990 | Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990 | |
| 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 | |
| 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 | |
| ML20059A399 | 15 August 1990 | Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp Program | Boric Acid VT-2 Scaffolding |
| 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 |
| 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 | |
| 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 | |
| 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 | |
| ML20055H763 | 25 July 1990 | Forwards Financial Info Re Decommissioning of Plants | |
| ML20055H029 | 17 July 1990 | Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990 | |
| ML20044A962 | 13 July 1990 | Forwards Rev 0 to Topical Rept NFSR-0081, Comm Ed Topical Rept on Benchmark of PWR Nuclear Design Methods Using PHOENIX-P & Advanced Nodal Code (Anc) Computer Codes, in Support of Implementation of PHOENIX-P & Anc | |
| ML20055G463 | 13 July 1990 | Responds to NRC Re Violations Noted in Insp Repts 50-456/90-08 & 50-457/90-08.Corrective Actions:Discrepancy Record for Cable Generated & Cable That Had Been Previously Approved for Use on Solenoid Obtained & Installed | |
| ML20044B141 | 12 July 1990 | Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request | |
| ML20044B214 | 11 July 1990 | Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification | |
| ML20044B287 | 9 July 1990 | Forwards Brief Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,Per NUREG-1002 & Util 900629 Original Submittal | Shutdown Margin |
| 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. | |
| ML20044A799 | 29 June 1990 | Forwards Description of Change Re Design of Containment Hydrogen Monitoring Sys,Per 900517 Request.Util Proposing Alternative Design Ensuring Containment & Hydrogen Monitoring Sys Operability in Event of Power Loss | Post Accident Monitoring |
| ML20058K352 | 22 June 1990 | Requests Withdrawal of 900315 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,changing Tech Specs 3.8.1.1 & 4.8.1.1.2 to Clarify How Gradual Loading of Diesel Generator Applied to Minimize Mechanical Stress on Diesel | Safe Shutdown Offsite Circuit |
| ML20056A036 | 15 June 1990 | Responds to NRC Re Violations Noted in Insp Repts 50-456/90-10 & 50-457/90-11.Corrective Action:Valve 2CS021b Returned & Locked in Throttle Position & Out of Svc Form Bwap 330-1T4 Modified | |
| ML20043G585 | 8 June 1990 | Forwards Repts Re Valid & Invalid Test Failures Experienced on Diesel Generator (DG) 1DG01KB,1 Valid Test Failure on DG 2DGO1KA & 2 Invalid Test Failures Experienced on DG 2AGO1KB | |
| ML20043D323 | 1 June 1990 | Forwards Rev 31 to Security Plan.Rev Withheld (Ref 10CFR73.21) | |
| ML20043D314 | 1 June 1990 | Forwards Rev 18 to Security Plan.Rev Withheld (Ref 10CFR73.21) | |
| ML20043E314 | 31 May 1990 | Withdraws 880302 Application for Amend to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,changing Tech Spec 4.6.1.6.1.d to Reduce Containment Tendon Design Stresses to Incorporate Addl Design Margin,Due to Insufficient Available Data | Operating Basis Earthquake |
| ML20043C818 | 30 May 1990 | Forwards Rev 1 to Core Operating Limits Rept,Dresden Station Unit 2,Cycle 12. Rev Reflects MCPR Limit Adjustment for Cycle 12 Due to Number of Reused Channels,Per Discussion of Channel Bow Effects in BWRs in NRC Bulletin 90-002 | |
| ML20043F473 | 30 May 1990 | Forwards Suppl to 881130 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77.Changes Requested Per Generic Ltr 87-09,to Remove Unnecessary Restrictions on Operational Mode Changes & Prevent Plant Shutdowns | Safe Shutdown Boric Acid Shutdown Margin Offsite Dose Calculation Manual Missed surveillance Annual Radiological Environmental Operating Report Process Control Program Grace period Power change |
| ML20043B777 | 23 May 1990 | Forwards Endorsement 9 to Nelia & Maelu Certificates N-108 & M-108 & Endorsement 8 to Nelia & Maelu Certificates N-115 & M-115 | |
| ML20043A916 | 16 May 1990 | Provides Advanced Notification of Change That Will Be Made to Fire Protection Rept Pages 2.2-18 & 2.3-14 | Fire Barrier |
| ML20043C281 | 15 May 1990 | Responds to NRC 900416 Ltr Re Violations Noted in Insp Repts 50-456/90-09 & 50-457/90-09.Corrective Actions:Gas Partitioners Tested Following Maint During Mar 1990 & Tailgate Training Session Will Be Held | |
| ML20042G711 | 7 May 1990 | Responds to NRC Questions Re leak-before-break Licensing Submittal for Stainless Steel Piping.Kerotest Valves in Rh Sys Will Be Replaced in Byron Unit 2 During Next Refueling Outage Scheduled to Begin on 900901 | |
| ML20042F685 | 4 May 1990 | Requests Resolution of Util 870429,880202 & 0921 & 890130 Submittals Re Containment Integrated Leak Rate Testing in Response to Insp Repts 50-454/86-35 & 50-455/86-22 by 900608 | |
| ML20042F677 | 3 May 1990 | Advises NRC of Util Plans Re Facility Cycle 2 Reload Core. Plant Cycle 2 Reload Design,Including Development of Core Operating Limits Has Been Generated by Util Using NRC Approved Methodology,Per WCAP-9272-P-A | |
| ML20042E911 | 25 April 1990 | Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants. | Stroke time |
| ML20042F268 | 18 April 1990 | Provides Supplemental Response to Violation Noted in Insp Repts 50-456/89-21 & 50-457/89-21 Re Safeguards Info.Util Request Extension of 891010 Commitment Re Reviews of Plants. List of Corrective Actions Will Be Submitted by 900601 | |
| ML20042F024 | 28 March 1990 | Forwards Part 3 of 1989 Operating Rept.W/O Rept | |
| ML20012D867 | 21 March 1990 | Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date | |
| ML20042G464 | 20 March 1990 | Responds to NRC 900216 Ltr Re Violations Noted in Insp Repts 50-456/90-02 & 50-457/90-02.Corrective Actions:Existing safety-related Temporary Alterations Will Be Reviewed to Determine Which Alterations Include Installation of Parts | Temporary Modification |
| ML20012D871 | 19 March 1990 | Forwards Corrected No Significant Hazards Consideration to 890814 Application for Amends to Licenses NPF-72 & NPF-77 | |
| ML20012C086 | 14 March 1990 | Forwards Response to Insp Repts 50-456/90-03 & 50-457/90-03 on 900122-26.Encl Withheld (Ref 10CFR73.21) | |
| ML20012E922 | 13 March 1990 | Forwards Final Version of Action Plan for post-accident Sample Sys QC Program,Per Insp Repts 50-456/90-05 & 50-457/90-05 | Grab sample |
| ML20012C547 | 12 March 1990 | Provides Results of Completed Util Reviews & Addresses Addl Info Requested by NRC Re 890317 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Change Tech Spec 4.5.2,supplemented on 890825 & 890925-27 Meetings | Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
| ML20012C506 | 12 March 1990 | Forwards Braidwood Nuclear Station Unit 1 Inservice Insp Summary Rept,Interval 1,Period 1,Outage 1. | |
| 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 | |
| ML20011F621 | 21 February 1990 | Forwards Revised PHOENIX-P/ANC Benchmark Scope to Replace Existing Ark & 2D Codes Used to Perform Neutronic Analyses for PWR Reload Designs.Codes Expected to Be Used in Dec 1990 for Cycle 3 Design Calculations | |
| 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 |