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Issue date | Title | |
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LIC-17-0006, EP-FC-1001 Addendum 3 Rev 2 Issued 12/29/2016 | 11 January 2017 | EP-FC-1001 Addendum 3 Rev 2 Issued 12/29/2016 |
LIC-16-0110, Emergency Plan Update | 30 November 2016 | Emergency 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 Reactors | 26 December 2014 | 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 Reactors |
ML12132A395 | 11 May 2012 | IR 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 |
ML12157A391 | 20 April 2012 | 2012-04 Draft Written Exam |
ML12156A005 | 20 April 2012 | 2012-04 Final Written Exam |
ML12157A288 | 3 April 2012 | 2012-04 Draft Written Exam Comments |
IR 05000285/2003006 | 4 February 2004 | IR 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, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC 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 Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
IR 05000285/1997013 | 2 October 1997 | Insp 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 Shutdown | 11 December 1996 | Undetected 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 Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
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 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial 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 Coolant | 1 September 1994 | 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 Coolant |
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 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
ML071040017 | 28 April 1994 | 59 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 Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
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 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
NRC Generic Letter 1992-04 | 19 August 1992 | NRC 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 Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
ML20086E808 | 22 November 1991 | Forwards Schedule for Implementation of Emergency Response Data Sys (Erds),Completed Site Survey Including Data Point Library (Dpl) & Plant Attribute Library (Pal) |
IR 05000285/1990026 | 15 June 1990 | Insp 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 Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
IR 05000285/1987031 | 8 December 1987 | Insp 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 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
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 |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML19351D269 | 6 October 1980 | Forwards 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 |
ML19257A533 | 31 December 1979 | Forwards Rept Implementation Methods & Schedules for NUREG- 0578, in Response to NRC 791030 Ltr.Rept Supplements 791025 & 1127 Ltrs |