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 Issue dateTitle
ENS 40357Reactor Manually Scrammed from 23% Due to Decreasing Reactor Vessel Water Level
ENS 42526Invalid Emergency Diesel Generator Start
ENS 43333Invalid Eccs Actuation During Refueling Outage
IR 05000037/20230072 November 2007IR 050003723-07-004 & 05000374-07-004, on 07/01/2007 - 09/30/2007, LaSalle County Station, Units 1 & 2; Surveillance Testing and Radioactive Material Processing and Transportation Report
IR 05000373/198501718 July 1985Insp Repts 50-373/85-17 & 50-374/85-17 on 850514-0619. Violations Noted:Inadequate Administrative Controls for Review & Authorization of Planned Testing,Failure to Follow Procedures & to Have Adequate Control of Design Drawings
IR 05000373/198501913 August 1985Insp Repts 50-373/85-19 & 50-374/85-21 on 850620-0724. Violation Noted:Inadequate Procedures Causing Inadvertent Equipment/Sys Operations & Failure to Have Procedures for Shutdown of CRD Pump
IR 05000373/198502426 September 1985Insp Repts 50-373/85-24 & 50-374/85-25 on 850725-0906. Violation Noted:Failure to Follow Procedure LIP-GM-09 When Returning Instrument to Svc,Causing Unit 1 to Trip & Failure to Have Adequate Document Control
IR 05000373/198503726 November 1985Insp Rept 50-373/85-37 on 851104-06.No Violation or Deviation Noted.Major Areas Inspected:Licensee Actions on Refueling Preparations & Activities & Spent Fuel Pool Activities
IR 05000373/198600728 April 1986Insp Repts 50-373/86-07 & 50-374/86-08 on 860213-0312. Violation Noted:Failure to Follow Procedures,Inadequate Procedures & Failure to Perform Required Tech Spec Surveillance
IR 05000373/198603523 October 1986Insp Repts 50-373/86-35 & 50-374/86-36 on 860903-1007. Violation Noted:On 860916 Reactor Not in at Least Hot Shutdown & PWR Svc Water Temp Indicator on Remote Shutdown Panel Inoperable 7 Days After Indicator Made Inoperable
IR 05000373/198603727 January 1987Insp Repts 50-373/86-37 & 50-374/86-37 on 860929-1003.No Violation or Deviation Noted.Major Areas Inspected:Control Room Activities,Effectiveness of Shift Supervision & Mgt Involement in Operations
IR 05000373/198604428 January 1987Insp Repts 50-373/86-44 & 50-374/86-44 on 861118-1229.No Violations Noted.Problems W/Verifications Identified. Observation of Switch Activities Continuing.Major Areas Inspected:Maint,Training Lers,Unit Trips & Investigations
IR 05000373/198700619 March 1987Insp Repts 50-373/87-06 & 50-374/87-06 on 870128-0309.No Violations Noted.Major Areas Inspected:Operational Safety Surveillance,Maint Training,Lers,Unit Trips,Outages,Generic Ltr Followup & Info Notices
IR 05000373/198703310 December 1987Insp Repts 50-373/87-33 & 50-374/87-32 on 871103-30. Violation Noted.Major Areas Inspected:Previous Insp Findings,Operational Safety,Surveillance,Maint,Training, LERs & Regional Requests
IR 05000373/198703526 January 1988Insp Repts 50-373/87-35 & 50-374/87-34 on 871201-880106. Violation Noted.Major Areas Inspected:Operational Safety, Surveillance,Maint,Training,Lers,Regional Requests,Unit Trips & Part 21 Notifications,
IR 05000373/19880011 June 1988SALP Insp Repts 50-373/88-01 & 50-374/88-01 for 861116- 880315.Overall Performance Acceptable
IR 05000373/198800713 June 1988Insp Repts 50-373/88-07 & 50-374/88-07 on 880316-0603.No Violations or Deviations Noted.Major Areas Inspected: Inservice Insp Activities,Including Review of Programs, Procedures,Data Review & Actions on Info Notice 88-003
IR 05000373/19880258 November 1988Insp Repts 50-373/88-25 & 50-374/88-24 on 880924-1031. Violations Noted Re Thoroughness of Surveillance Procedure Reviews.Major Areas Inspected:Operational Safety,Lers, Outages,Security,Esf Walkdowns & Emergency Preparedness
IR 05000373/198900720 March 1989Insp Repts 50-373/89-07 & 50-374/89-07 on 890303-04.No Violations Noted.Major Areas Inspected:Unit 2 Loss of Sys Auxiliary Transformer,Unit 1 Reactor Scram,Review of Unit 2 Ocb 4-6 Failure & Unit 1 & 2 Reactor Bldg Ventilation
IR 05000373/199300410 February 1993Insp Repts 50-373/93-04 & 50-374/93-04 on 921228-930208.No Violations Noted.Major Areas Inspected:Followup on Previously Identified Items & Lers,Review of Operational Safety,Monthly Maint & Surveillance Activities
IR 05000373/19980012 July 1998Insp Repts 50-373/98-01 & 50-374/98-01 on 980423-0605. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plan Support
IR 05000373/199801924 September 1998Insp Repts 50-373/98-19 & 50-374/98-19 on 980716-0831.No Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering & Plant Support
IR 05000373/199900110 March 1999Insp Repts 50-373/99-01 & 50-374/99-01 on 990106-0216.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support
IR 05000373/19990156 October 1999Insp Repts 50-373/99-15 & 50-374/99-15 on 990729-0916.One Violation Noted & Being Treated as Ncv.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support
IR 05000373/200300522 January 2004IR 05000373-03-005, and IR 05000374-03-005; on 10/01/03-12/31/03 for Exelon Nuclear Generation Company; LaSalle County Generating Station, Units 1 & 2; Maintenance Effectiveness
IR 05000373/200400216 April 2004IR 05000373-04-002, 05000374-04-002, on 01/01/2004 - 03/31/2004; LaSalle County Station, Units 1 & 2; Operator Workarounds and Access Control to Radiologically Significant Areas Report
IR 05000373/200600923 March 2006IR 05000373-06-009; 02/20 - 27/2006; LaSalle County Station, Unit 1: Special Inspection for Unit 1 Scram with Loss of Normal Heat Sink and Site Area Emergency Declaration Due to Multiple Unknown Control Rol Positions Following the Scram on
IR 05000373/200700227 April 2007IR 05000373-07-002, 05000374-07-002, 01/01/2007 - 03/31/2007; LaSalle County Station, Units 1 & 2, NRC Integrated
IR 05000373/201100211 May 2011IR 05000373-11-002, 05000374-11-002, 07200070-11-001, on 1/1/2011 - 3/31/2011; LaSalle County Station, Units 1 & 2; Maintenance Risk Assessments and Emergent Work Control; and Operability Evaluations
IR 05000373/201700817 August 2017NRC Design Bases Assurance Inspection (Programs); Inspection Report 05000373/2017008; 05000374/2017008 (Gmh)
IR 05000373/20220111 November 2022County Station Design Basis Assurance Inspection (Teams) Inspection Report 05000373/2022011 and 05000374/2022011
IR 05000374/198502023 July 1985Insp Rept 50-374/85-20 on 850624-28 & 0701-02.No Violation or Deviation Noted.Major Areas Inspected:Licensee Actions Required by Confirmatory Action Ltr CAL-RIII-85-07,Items 1-5
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
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
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
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 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
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 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
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
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 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent 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, & FitzPatrick5 May 1999Unanticipated 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 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
ML0036906073 March 2000Improved Technical Specifications, LaSalle County Station, Volume 13: Unit 2 CTS Markup in CTS Order
ML02135061519 April 2002Initial RO Examination 04/2002
ML0221301578 April 2002NRC-Authored Outline for the LaSalle Initial Examination - April 2002
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