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 Issue dateTitle
IR 05000456/202200226 July 2022Integrated Inspection Report 05000456/2022002; 05000457/2022002; and 07200073/2022001
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 Position27 September 2021Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML21008A41717 December 2020Technical Specification Bases
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)28 February 2020Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
RS-17-170, Company Emergency Plan Annex and Addendum Revisions19 December 2017Company Emergency Plan Annex and Addendum Revisions
ML16280A4026 October 2016License 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.
ML16209A21826 July 2016Application 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.
ML15336A73127 January 2016TS 50456-Bwd-AppsABC
ML15286A27619 November 2015Technical Specifications
ML15002A03324 November 20142014 Braidwood Station Initial License Examination Proposed Written Examination
ML14363A06221 November 20142014 Braidwood Station Initial License Examination Administered Written Examination
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 Process14 July 2014Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process
ML13148A10115 April 20132013 Braidwood Station Initial License Examination Proposed JPMs
ML13169A42215 April 20132013 Braidwood Station Initial License Examination Administered RO Administrative JPMs
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases15 December 2008Braidwood, Units 1 and 2 - Technical Specification Bases
ML09027047415 December 2008Technical Specification Bases
ML05140018126 May 2005Technical Specifications, Issuance of Amendment Hydrogen Recombiners & Hydrogen Monitors
RS-04-160, Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports21 October 2004Request 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 Process15 September 2004Amergen Request for Amendment to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process
ML0335603029 December 2003Exelon/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, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
ML20198K58423 December 1998Revised Tech Spec Pages 3/4 3-53,3/4 3-53a,6-27 & 6-27a,for Rv LI Sys
ML20195J67023 November 1998Forwards 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 1998-0228 May 1998NRC 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 Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
ML20210Q09528 August 1997Discusses 961019 Supplemental Response to GL 87-12 in Which Ceco Informed NRC of Rev to Commitments to Braidwood,Units 1 & 2.Rev Changes Allowable Residual Heat Removal Rate. Determined Change Acceptable
ML20135B64518 February 1997Insp Repts 50-456/96-19 & 50-457/96-19 on 961019-1129. Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected 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 Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
ML20129B47919 October 1996Notifies NRC That Util Revising Commitments Made in Response to GL 87-12
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
ML07104001728 April 199459 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 Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
NRC Generic Letter 1992-0419 August 1992NRC 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 Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
ML20079K54918 June 199110CFR50.59 Annual Rept 1990-1991
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
ML20151Q40527 July 1988Forwards 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
ML20235J27125 September 1987Forwards Info Assessing Safe Operation of PWRs When RCS Water Level Below Top of Reactor Vessel,Per Generic Ltr 87-12
ML20206J9379 February 1987Forwards 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
ML20210L9565 February 1987Forwards 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
ML20211G84831 October 1986Technical Specifications for Braidwood Station,Units 1 and 2.Docket Nos. 50-456 and 50-457.(Commonwealth Edison Company)
IR 05000456/198604322 September 1986Insp Repts 50-456/86-43 & 50-457/86-38 on 860811-0912.No Violations or Deviations Noted.Major Areas Inspected: Previous Insp Items,Preoperational Test Procedures, Verification & Results & Startup Test Procedures
ML20206F16618 June 1986Forwards Draft Tech Specs for Review.Review Should Focus on Clarity & Enforceability of Specs,Action Statements & Surveillance Requirements W/Secondary Emphasis on Technical Accuracy.Comments Needed by 860626