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 Issue dateTitle
LIC-17-0006, EP-FC-1001 Addendum 3 Rev 2 Issued 12/29/201611 January 2017EP-FC-1001 Addendum 3 Rev 2 Issued 12/29/2016
LIC-16-0110, Emergency Plan Update30 November 2016Emergency Plan Update
LIC-14-0098, License Amendment Request 14-06 to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors26 December 2014License Amendment Request 14-06 to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML12132A39511 May 2012IR 05000285-12-002; 01/01/2012 - 03/31/2012; Fort Calhoun Station, Integrated Resident and Regional Report; Adverse Weather Protection, Emergency Plan Biennial Exercise, Mc 0350
ML12157A39120 April 20122012-04 Draft Written Exam
ML12156A00520 April 20122012-04 Final Written Exam
ML12157A2883 April 20122012-04 Draft Written Exam Comments
IR 05000285/20030064 February 2004IR 05000285-03-006 on 09/21/2003 - 12/31/2003 for Fort Calhoun Station, Integrated Resident and Regional Report; Maintenance Rule Implementation, Nonroutine Evolutions and Events, Refueling Activities, Access Control, Event Followup
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
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
IR 05000285/19970132 October 1997Insp Rept 50-285/97-13 on 970630-0718.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering
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
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
LIC-94-0169, Notifies NRC of Rev to Post Accident Sampling Sys Licensing Basis Commitment Re Measurement of Reactor Coolant Ph. Informs of Util Intent to Delete from PASS Program Requirement to Measure Ph of Reactor Coolant1 September 1994Notifies NRC of Rev to Post Accident Sampling Sys Licensing Basis Commitment Re Measurement of Reactor Coolant Ph. Informs of Util Intent to Delete from PASS Program Requirement to Measure Ph of Reactor Coolant
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
ML20086E80822 November 1991Forwards Schedule for Implementation of Emergency Response Data Sys (Erds),Completed Site Survey Including Data Point Library (Dpl) & Plant Attribute Library (Pal)
IR 05000285/199002615 June 1990Insp Rept 50-285/90-26 on 900416-0512.Noncited Violations Noted.Major Areas Inspected:Operational Safety Verification, Monthly Maint,Surveillance,Security & Onsite Followup of Events & in-ofc Review of Repts
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
IR 05000285/19870318 December 1987Insp Rept 50-285/87-31 on 871116-19.No Violations or Deviations Noted.Major Areas Inspected:Emergency Detection & Classification,Protective Action Decisionmaking, Notifications & Communication & Shift Staffing
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0217 April 1985NRC 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 1985-0531 January 1985NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML19351D2696 October 1980Forwards Status Rept Re Implementation of NUREG-0578 Category B Tasks & Util Position Re Addl Requirements of TMI-2 Task Action Plan Per NUREG-0660.Requests Deferral Until Sept 1981 for Related Tasks Requiring Outages
ML19257A53331 December 1979Forwards Rept Implementation Methods & Schedules for NUREG- 0578, in Response to NRC 791030 Ltr.Rept Supplements 791025 & 1127 Ltrs