Semantic search

Jump to navigation Jump to search
 Issue dateTitle
IR 05000483/198600329 April 1986Safety Insp Rept 50-483/86-03 on 860211-0414.No Violation or Deviation Noted.Major Areas Inspected:Tmi Action Plan Requirements,Surveillance,Maint,Operational Safety & Cycle 1 Refueling Outage
IR 05000483/198800912 July 1988Insp Rept 50-483/88-09 on 880606-09.No Violations, Deficiencies or Deviations Noted.Major Areas Inspected: Emergency Preparedness Program,Emergency Response Facility Appraisal & Review of Radioactive Release Assessment
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
ML02249010326 August 2002Emergency Plan Implementing Procedure
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0331600393 November 2003Transmittal of Revisions to Emergency Plan Implementing Procedures for Callaway Plant
ML0407010903 March 2004Defense-in-Depth and Diversity Assessment (Non-Proprietary)
ML0407204404 March 2004Callaway Plan, DEFENSE-IN-DEPTH and Diversity Assessment for Digital Upgrade of Callaway'S Instrumentation and Control Systems (License Amendment Request OL-1249), Enclosure 2, Non-Proprietary
ML05202042725 October 2005Issuance of License Amendment 169 Deletion or Revision of Licensing Conditions (Revision of TS Tables 5.5.9-2 and 5.5.9-3)
ML0616401577 June 2006Document Transmittal; J-26060A, Rev. 3, NRC Emergency Response Data System Data Point Library
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML0806704197 March 2008CDBI Findings
ML11187028327 June 20112011-06-Final Written Retake Exam
ML11361014227 June 20112011-06-Draft Written Exam
ML13247A23427 August 2013CW-2013-08 Final Op Test
ML14311A64031 March 2004Radiological Emergency Response Plan, Revision 026
ML14311A64131 August 2014Radiological Emergency Response Plan, Revision 045
ML17270A17220 September 20172017-09-FINAL Op Test
ML18088B36129 March 2018EIP-ZZ-00101 Addendum 2, Emergency Action Level Technical Basis Document, Revision 008
ML18207A59119 June 2018Revision OL-23 to Final Safety Analysis Report, Chapter 18, Response to NUREG-0737 Clarification of TMI Action Plan Requirements
ML20008G25930 June 1981Forwards Response to NUREG-0737, Clarification of TMI Action Plan Requirements. Response Will Be Issued as Chapter 18 of FSAR & Will Be Incorporated in Fsar,Revision 5,currently Scheduled for Jul 1981 Publication
ML20010J01324 September 1981Forwards Response to NRC 810901 Request for Addl Info Re NUREG-0737,Item II.F.2,instrumentation for Detection of Inadequate Core Cooling.Info Will Be Incorporated in Future Revision to FSAR
ML20029D02425 April 1994Submits More Conservative Setpoint Calculation for RCS Barrier Loss Indicator Based on Containment Activity on GT-RE-59/60,in Accordance w/940425 Conversation Re Numarc/ NESP-007 EAL Submittal.Revised Annunciator EALs Encl
ML20065N46120 April 1994EALs Indications Bases
ML20073L51515 April 1983Forwards Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737 Re Requirements for Emergency Response Capability.Due to Const & Licensing Status at Time TMI Requirements Were Issued,Requirements Were Addressed in Chapter 18 of FSARs
ML20080U16518 July 1983Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EIP-ZZ-00101 Re Classification of emergencies,EIP-ZZ-00102 Re Emergency Implementing Actions & EIP-ZZ-00201 Re Notifications
ML20084C20310 April 1984Rev 0 to Procedure EDP-ZZ-00005, Assessing Core Damage
ML20086U38230 December 1991Forwards Listing of Plant Attribute Library & Data Point Library Required for Implementation of Emergency Response Data Sys.Addl Critical Safety Function Parameters Recommended for Facility Listed
ML20092A9996 February 1992Forwards Changes to 911230 Plant Attribute Library,Critical Safety Function Parameter List & Data Point Library,As Required for Implementation of Emergency Response Data Sys
ML20092H31416 May 1984Rev 1 to Engineering Departmental Procedure EDP-ZZ-00005, Assessing Core Damage
ML20101F33115 June 1992Rev 0 to NRC ERDS Data Point Library
ML20101M45926 June 1992Rev 1 to J-26060A, Critical Safety Function Parameters
ML20154F83129 September 1998Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump
ML20198J73015 May 1997Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant
ML20205M1047 April 1986Informs That Listed post-accident Monitoring (Reg Guide 1.97) Instruments Declared Inoperable at Time of Cycle 2 Startup Following First Refueling Outage
ML20207F48027 May 1999Proposed Improved TSs & ITS Bases
ML20207L1069 March 1999Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0