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Issue date | Title | |
---|---|---|
IR 05000456/1986043 | 22 September 1986 | Insp 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 |
IR 05000456/2022002 | 26 July 2022 | Integrated Inspection Report 05000456/2022002; 05000457/2022002; and 07200073/2022001 |
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. |
ML051400181 | 26 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 |
ML090270474 | 15 December 2008 | Technical Specification Bases |
ML13148A101 | 15 April 2013 | 2013 Braidwood Station Initial License Examination Proposed JPMs |
ML13169A422 | 15 April 2013 | 2013 Braidwood Station Initial License Examination Administered RO Administrative JPMs |
ML14363A062 | 21 November 2014 | 2014 Braidwood Station Initial License Examination Administered Written Examination |
ML15002A033 | 24 November 2014 | 2014 Braidwood Station Initial License Examination Proposed Written Examination |
ML15286A276 | 19 November 2015 | Technical Specifications |
ML15336A731 | 27 January 2016 | TS 50456-Bwd-AppsABC |
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. |
ML20040E113 | 26 January 1982 | Forwards Notes from 810921-23,1028-29,1112-13 & 1209 Review Meetings W/Instrumentation & Control Sys Branch |
ML20079K549 | 18 June 1991 | 10CFR50.59 Annual Rept 1990-1991 |
ML20129B479 | 19 October 1996 | Notifies NRC That Util Revising Commitments Made in Response to GL 87-12 |
ML20135B645 | 18 February 1997 | Insp 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 |
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 |
ML20198K584 | 23 December 1998 | Revised Tech Spec Pages 3/4 3-53,3/4 3-53a,6-27 & 6-27a,for Rv LI Sys |
ML20199A954 | 10 June 1986 | Forwards Proof & Review Tech Specs.Three Remaining Open Items Listed.Comments Requested by 860701 |
ML20206F166 | 18 June 1986 | Forwards 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 |
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 |
ML20210Q095 | 28 August 1997 | Discusses 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 |
ML20211G848 | 31 October 1986 | Technical Specifications for Braidwood Station,Units 1 and 2.Docket Nos. 50-456 and 50-457.(Commonwealth Edison Company) |
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 |
ML21008A417 | 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 |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |