Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ST-HL-AE-3578, Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda20 September 1990Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda
ST-HL-AE-3577, Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule18 September 1990Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule
ML20059K67417 September 1990Suppls 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
ML20059K50814 September 1990Forwards Tj Kovach to E Delatorre Re Visit by Soviet Delegation to Braidwood Nuclear Station in May 1990
ST-HL-AE-3570, Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan14 September 1990Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan
ST-HL-AE-3567, Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel Nozzles14 September 1990Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel NozzlesNondestructive Examination
ST-HL-AE-3565, Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested10 September 1990Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested
ST-HL-AE-3553, Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept10 September 1990Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept
ML20059L66110 September 1990Forwards Byron Station Units 1 & 2 Inservice Insp Program
ST-HL-AE-3546, Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 198928 August 1990Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 1989
ST-HL-AE-3540, Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure Rotor28 August 1990Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure RotorTurbine Missile
ST-HL-AE-3550, Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d)28 August 1990Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d)Fitness for Duty
ST-HL-AE-3551, Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach Encl26 August 1990Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach EnclProbabilistic Risk Assessment
ML20064A36824 August 1990Forwards 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
ML20064A37524 August 1990Forwards Revised Pages to Operating Limits Rept for Cycle 2, Correcting Fxy Portion of Rept,Per Tech Spec 6.9.1.9, Operating Limits Rept
ML20064A01816 August 1990Submits 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 StressesNondestructive Examination
Liquid penetrant
ML20059A39915 August 1990Forwards Response to NRC 900521 Request for Addl Info Re Plant Inservice Insp ProgramBoric Acid
VT-2
Scaffolding
ML20063Q10510 August 1990Forwards Monthly Operating Repts for Jul 1990 for Byron Units 1 & 2 & Corrected Monthly Operating Rept for June 1990 for Unit 2
ML20058N0557 August 1990Provides 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 StressesNondestructive Examination
Liquid penetrant
ML20056A3352 August 1990Responds 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
ML20055J12225 July 1990Notifies 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
ML20055J12625 July 1990Notifies 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
ML20055H76325 July 1990Forwards Financial Info Re Decommissioning of Plants
ML20055H02917 July 1990Forwards Revised Monthly Performance Rept for Braidwood Unit 2 for June 1990
ML20055G32516 July 1990Responds 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
ML20044A96213 July 1990Forwards 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
ML20055G46313 July 1990Responds 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
ML20044B14112 July 1990Forwards Addl B&W Rept 77-1159832-00 to Facilitate Completion of Reviews & Closeout of Pressurized Thermal Shock Issue,Per NRC Request
ML20044B20811 July 1990Responds to Generic Ltr 90-04 Re Status of GSI Resolved W/ Imposition of Requirements or Corrective Actions.Status of GSI Implementation EnclScram Discharge Volume
ML20044B21411 July 1990Withdraws 891003 Amend Request to Allow Sufficient Time to Reevaluate Technical Position & Develop Addl Technical Justification
ML20044A95210 July 1990Provides Supplemental Response to NRC Bulletin 88-001. Remaining 48 Breakers Inspected During Facility Spring Refueling Outage
ML20044B2879 July 1990Forwards Brief Description of Calculations Performed in Accordance W/Facility Procedure Used to Make Rod Worth Measurements,Per NUREG-1002 & Util 900629 Original SubmittalShutdown Margin
ML20044A79929 June 1990Forwards 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 LossPost Accident Monitoring
ML20055D48129 June 1990Discusses 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
ML20055D29522 June 1990Discusses 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
ML20058K35222 June 1990Requests 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 DieselSafe Shutdown
Offsite Circuit
ML20043H61921 June 1990Forwards 1989 Annual Financial Repts for Licensees for Plant
ML20043H59719 June 1990Forwards Responses to Open Items Resulting from Sandia Draft Rept on Probabilistic Safety Assessment.Dominant Sequence Model Encl,Per NRC Reviewers Request
ML20043H77818 June 1990Forwards Rev 1 to SER Commitment Status for Plant,Per NUREG-0781.List of Action Items Completed But Not Incorporated Into Sser & List of Items for Actions Not Completed Also EnclStroke time
Post Accident Monitoring
Internal Flooding
Hydrostatic
ML20056A03615 June 1990Responds 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
ML20043F62611 June 1990Forwards Rev 0 to Unit 1 Cycle 3 Core Operating Limits Rept.
ML20043G5858 June 1990Forwards 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
ML20043F3194 June 1990Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-498/90-01 & 50-499/90-01.Corrective Actions:Compressed Gas Cylinders Removed from Power Block & Nashua 357 Tape Returned to Nuclear Purchasing Matl Mgt Co
ML20043D3241 June 1990Forwards Rev 10 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21)
ML20043D3141 June 1990Forwards Rev 18 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20043D3151 June 1990Forwards Rev 30 to Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20043E31431 May 1990Withdraws 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 DataOperating Basis Earthquake
ML20043F47330 May 1990Forwards 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 ShutdownsSafe Shutdown
Boric Acid
Shutdown Margin
Offsite Dose Calculation Manual
Missed surveillance
Annual Radiological Environmental Operating Report
Process Control Program
Grace period
Power change
ML20043C86429 May 1990Forwards 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
ML20043B77723 May 1990Forwards Endorsement 9 to Nelia & Maelu Certificates N-108 & M-108 & Endorsement 8 to Nelia & Maelu Certificates N-115 & M-115
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BCategory:UTILITY-20TO-20NRC-5D-5D-20-5B-5BSite::Byron-7C-7CBraidwood-7C-7CSouth-20Texas-7C-7C05000000-7C-7C05000545-5D-5D/-3FIssue-20date/-3FTitle/-3FTopic/mainlabel%3D/order%3D-20descending/sort%3D-20Issue-20date/offset%3D0/format%3Dtable/searchlabel%3D-5BTable-20view-5D"