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| Issue date | Title | |
|---|---|---|
| JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position | 27 September 2021 | Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position |
| ML21008A413 | 17 December 2020 | Technical Specification Bases |
| RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) | 28 February 2020 | Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) |
| RS-17-170, Company Emergency Plan Annex and Addendum Revisions | 19 December 2017 | Company Emergency Plan Annex and Addendum Revisions |
| ML20311A618 | 6 November 2017 | 2017 Q1-Q4 ROP Inspection Findings |
| ML20311A647 | 6 November 2017 | 2017 Q1-Q4 ROP Inspection Findings |
| ML16280A402 | 6 October 2016 | License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. |
| ML16209A218 | 26 July 2016 | Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. |
| ML16021A423 | 31 January 2016 | NUREG-2187, Vol. 1, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Byron Unit 1. Chapters 1 to 8, Appendices a to C. |
| ML15286A276 | 19 November 2015 | Technical Specifications |
| RS-14-192, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process | 14 July 2014 | Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process |
| ML13169A422 | 15 April 2013 | 2013 Braidwood Station Initial License Examination Administered RO Administrative JPMs |
| RS-08-161, Technical Specification Bases | 15 December 2008 | Technical Specification Bases |
| ML051400173 | 19 May 2005 | Technical Specifications, Issuance of Amendment Hydrogen Recombiners & Hydrogen Monitors |
| IR 05000454/2005003 | 4 May 2005 | IR 05000454-05-003; IR 05000455-05-003 on 01/01/2005-03/31/2005 for Byron Station, Units 1 and 2; Post Maintenance Testing, Surveillance Testing, Access Control to Radiologically Significant Areas, Event Followup, Other Activities |
| RS-04-160, Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports | 21 October 2004 | Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports |
| RS-04-141, Amergen Request for Amendment to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process | 15 September 2004 | Amergen Request for Amendment to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process |
| ML033560302 | 9 December 2003 | Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability. |
| Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
| ML20196K673 | 31 December 1998 | 10CFR50.59 Summary Rept for 1998 |
| ML20198N204 | 29 December 1998 | Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements |
| ML20195J670 | 23 November 1998 | Forwards Comments of Draft NRC SE Re Proposed Amend to Convert Byron & Braidwood Stations Current Tech Specs (CTS) to Improved Tech Specs (Its),Per NRC .Certified ITS & ITS Bases Encl |
| NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
| Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
| Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
| Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
| ML20129B479 | 19 October 1996 | Notifies NRC That Util Revising Commitments Made in Response to GL 87-12 |
| Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
| Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
| Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
| Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
| Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
| Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
| NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
| Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
| Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
| ML20006F716 | 16 February 1990 | LER 90-001-00:on 900118,determined That Containment Purge Isolation Sys Not Demonstrated Operable 100 H Prior to Start of Core Alterations.Caused by Cognitive Personnel Error. Task Force Formed to Review Tech Specs.W/900109 Ltr |
| IR 05000454/1989010 | 5 June 1989 | Insp Repts 50-454/89-10 & 50-455/89-12 on 890401-0517.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety,Event Followup,Mud Buildup in Essential Svc Water Lines,Security & LERs |
| ML20207L186 | 13 October 1988 | Confirms 881021 Enforcement Conference in Glen Ellyn,Il Re Loss of Train of RHR Sys While Lowering Water Level in RCS on 880919.Util Should Be Prepared to Discuss Lack of Procedural Spec to Monitor Reactor Vessel Water Level |
| ML20245D841 | 28 September 1988 | Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 |
| IR 05000454/1988011 | 19 August 1988 | Safety Insp Repts 50-454/88-11 & 50-455/88-11 on 880701- 0815.Violation Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,Lers,Bulletin Followup,Operations Summary,Training,Refueling,Surveillance & Maint |
| ML20151Q405 | 27 July 1988 | Forwards Info Re Compliance W/Reg Guide 1.97 Re RHR Sys Flow,Rhr HX Outlet Temp & Accumulator Tank Level.Esf Status Monitoring Lights,Component Status Indication & Pump Motor Ammeters safety-related & Comply W/Reg Guide |
| IR 05000454/1988006 | 11 April 1988 | Safety Insp Repts 50-454/88-06 & 50-455/88-06 on 880212-0331.No Violations Noted.Major Areas Inspected: Licensee Action on Previous Insp Findings,Lers,Bulletins, Generic Ltrs,Operations Summary,Training & Surveillance |
| ML20235J271 | 25 September 1987 | Forwards Info Assessing Safe Operation of PWRs When RCS Water Level Below Top of Reactor Vessel,Per Generic Ltr 87-12 |
| ML20206J937 | 9 February 1987 | Forwards Quarterly Status Rept for Fourth Quarter of Calendar Year 1986,in Response to Direction Given in House Rept 97-850.NRC Licensing Activity During Period of Rept Includes Issuance of full-power License for Perry Unit 1 |
| ML20210L956 | 5 February 1987 | Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1 |
| ML20211G936 | 6 June 1986 | Summary of Operating Reactor Events Meeting 86-18 on 860602 Re Events Occurring Since 860519 Meeting.Attendee List, Events,Significant Elements of Events & Completion Dates for Assignments Encl |