Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
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 |
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 |
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 |
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 |
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 |
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 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
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 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
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 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 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 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
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 |
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 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 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 |
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 |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML033560302 | 9 December 2003 | Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability. |
ML051400173 | 19 May 2005 | Technical Specifications, Issuance of Amendment Hydrogen Recombiners & Hydrogen Monitors |
ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
ML13169A422 | 15 April 2013 | 2013 Braidwood Station Initial License Examination Administered RO Administrative JPMs |
ML15286A276 | 19 November 2015 | Technical Specifications |
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. |
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. |
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. |
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 |
ML20040E113 | 26 January 1982 | Forwards Notes from 810921-23,1028-29,1112-13 & 1209 Review Meetings W/Instrumentation & Control Sys Branch |
ML20076K000 | 1 July 1983 | Proposed Findings of Fact & Conclusions of Law Re Class 9 Accidents.Certificate of Svc Encl |
ML20088A456 | 2 April 1984 | Forwards marked-up Pages of Sections of Proof & Review Tech Specs.Addl Changes Will Be Submitted by 840409 |
ML20101U349 | 18 January 1985 | Forwards Proposed Tech Spec Additions & Revs for NRC Review, Per 850115 Meeting in Bethesda,Md.Changes Revise Startup Test Program & Incorporate Necessary Specs for Referencing Unit 2 OL in Next Version |
ML20129B479 | 19 October 1996 | Notifies NRC That Util Revising Commitments Made in Response to GL 87-12 |
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 |
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 |
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 |
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 |
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 |
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 |
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 |
ML20245D841 | 28 September 1988 | Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 |
ML20311A618 | 6 November 2017 | 2017 Q1-Q4 ROP Inspection Findings |
ML20311A647 | 6 November 2017 | 2017 Q1-Q4 ROP Inspection Findings |
ML21008A413 | 17 December 2020 | Technical Specification Bases |
NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |