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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 | |
| ML20059L661 | 10 September 1990 | Forwards Byron Station Units 1 & 2 Inservice Insp Program | |
| 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 | |
| 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 Intergranular Stress Corrosion Cracking Stress corrosion cracking Scaffolding |
| 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 | |
| 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 | |
| ML20055H763 | 25 July 1990 | Forwards Financial Info Re Decommissioning of Plants | |
| 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 | |
| ML20055H029 | 17 July 1990 | Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990 | |
| ML20055G325 | 16 July 1990 | Responds to SALP Board Repts 50-454/90-01 & 50-455/90-01 for Reporting Period Nov 1988 - Mar 1990.Effort Will Be Made to Continue High Level of Performance in Areas of Radiological Controls,Plant Operations,Emergency Preparedness & Security | |
| 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 | |
| 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 | |
| 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 | |
| ML20044B208 | 11 July 1990 | Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation Encl | Scram Discharge Volume |
| ML20044A952 | 10 July 1990 | Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage | |
| 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 |
| 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 Manual Operator Action |
| ML20055D481 | 29 June 1990 | Discusses Revised Schedule for Implementation of Generic Ltr 89-04 Re Frequently Identified Weaknesses of Inservice Testing Programs.All Procedure Revs Have Either Been Approved or Drafted & in Onsite Review & Approval Process | |
| 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 Overspeed trip |
| ML20055D295 | 22 June 1990 | Discusses Results of 900529-0607 Requalification Exam.Based on Results of Exam,Station Removed/Prohibited Both Shift & Staff Teams & JPM Failure from License Duties.Shift Team Placed in Remediation Program from 900611-14 | |
| 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 | |
| ML20043D315 | 1 June 1990 | Forwards Rev 30 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 |
| 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 High Energy Line Break Missed surveillance Annual Radiological Environmental Operating Report Process Control Program Grace period Power change Overspeed trip |
| ML20043C864 | 29 May 1990 | Forwards Rept of Local Leakage Rate Test Results for Third Refueling Outage.Leakage Rates of Six Valves Identified as Contributing to Failure of Max Pathway Limit | |
| 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 | |
| ML20043B769 | 23 May 1990 | Forwards Endorsement 11 to Nelia & Maelu Certificates N-93 & M-93 & Endorsement 9 to Nelia & Maelu Certificates N-101 & M-101 | |
| 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 | |
| ML20043A639 | 11 May 1990 | Submits Revised Schedule for Implementation of Generic Ltr 89-04 Guidance.Rev to Procedures for Check Valve & Stroke Time Testing of power-operated Valves Will Be Completed by 900629 | Stroke time Power-Operated Valves |
| ML20043A289 | 10 May 1990 | Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for Byron Nuclear Power Station | |
| 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 | |
| ML20042E960 | 30 April 1990 | Forwards Response to NRC 900327 Ltr Re Violations Noted in Insp Repts 50-454/90-09 & 50-455/90-08.Response Withheld (Ref 10CFR73.21) | |
| ML20042G359 | 30 April 1990 | Forwards Errata to Radioactive Effluent Rept for Jul-Dec 1989,including Info Re Sr-89,Sr-90 & Fe-55 Analysis for Liquid & Gaseous Effluents Completed by Offsite Vendor | |
| ML20055C576 | 30 April 1990 | Forwards Results of Investigation in Response to Allegation RIII-90-A-0011 Re Fitness for Duty.W/O Encl | Fitness for Duty |
| 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 | |
| ML20012E108 | 21 March 1990 | Forwards Calculations Verifying Operability of Facility Dc Battery 111 W/Only 57 of 58 Cells Functional & Onsite Review Notes,Per Request | |
| ML20012D867 | 21 March 1990 | Reissued 900216 Ltr,Re Changes to 891214 Rev 1 to Updated Fsar,Correcting Ltr Date |