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IR 05000269/19860044 April 1986Insp Repts 50-269/86-04,50-270/86-04 & 50-287/86-04 on 860211-0310.No Violation Noted.Major Areas Inspected: Operations,Surveillance,Maint,Verification of ESF Lineups & Refueling Activities
IR 05000269/199100810 April 1991Insp Repts 50-269/91-08,50-270/91-08 & 50-287/91-08 on 910312-15.violations Noted.Major Areas Inspected:Maint, Control Room Operation,Planning & Scheduling Activities, Training & Procedures,Plant Physical Condition & Mgmt
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
ML02360006516 December 2002Technical Specification Bases (Tsb) Change, Revisions to Tsbs 3.3.8, 3.5.3, & 3.6.5 to Clarify & Document Interdependency Between Reactor Building Spray (RBS) & LPI System with Respect to Pump Runout
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0316814239 June 2003Technical Specification Bases (Tsb) Change
ML03225012731 July 2003Technical Specification Bases Change
ML03273147529 September 2003Technical Specifications Pages for Amendment Nos. 335, 335 and 336, Respectively
ML04022017612 January 2004Technical Specification Bases (Tsb) Change
ML04279046120 September 2004License Amendment Request to Eliminate the Technical Specifications Requirements for the Hydrogen Monitors and Hydrogen Recombiners Oconee Technical Specification 3.3.8 and McGuire Technical..
ML05081041616 March 2005License Amendment Request Applicable to Oconee Technical Specification 3.3.8, PAM Instrumentation, and 3.6.7, Hydrogen Recombiners, Using the Consolidated Line Item Improvement Process
ML0522902749 August 2005Technical Specification Bases (Tsb) Change
ML0634701376 December 2006Technical Specification Bases (Tsb) Change
ML07008032513 December 2006Licensee'S Handouts for Oconee, Summary of December 13, and 14, 2006
ML0734400213 December 2007Technical Specification Bases (Tsb) Change
ML07347081312 December 2007Handout from 12/12/07 Meeting, Rps/Esps Digital LAR
ML0806704197 March 2008CDBI Findings
ML08073033931 January 2008License Amendment Request for Reactor Protective System/Engineered Safeguards Protective System Digital Upgrade, Technical Specification Change Number 2007-09
ML08077003111 March 2008Revisions to Technical Specification Bases (Tsb) Change
ML08141006014 May 2008Technical Specification Bases (Tsb) Change
ML08351008810 December 2008Technical Specification Bases (Tsb) Change
ML10022001628 January 2010Issuance of Amendment Nos. 366, 368, and 367, Reactor Protective System and Engineered Safeguard Protection System Digital Upgrade
ML10246001531 August 2010Tornado Mitigation License Amendment Request - Response to Request for Additional Information
ML12003A07016 December 2011Tornado and High Energy Line Break (HELB) Mitigation License Amendment Requests (Lars) - Responses to Request for Additional Information, Part 1 of 6
ML12173A38918 June 2012Technical Specification Bases (Tsb) Changes
ML17118A02320 April 2017Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2
ML19312C1584 June 1976Forwards Addl Info Re Electrical Equipment Which May Become Submerged Following Postulated Loca,In Response to Question 4 of NRC 760406 Ltr Re ECCS Analysis
ML19312C1596 August 1976Evaluation of Post-LOCA Boric Acid Concentration Control Sys for Facility Reactors.
ML19322B59724 February 1976Discusses Cycle 3 Reload Licensing Concerns Expressed in NRC 751015,751015 & 760217 Ltrs Re Water Hammer in Lpis,Core Flood Tank Vent Valves,Core Boron Dilution Following Postulated LOCA & Primary Sys Flow Measurement
ML20027C12430 September 1982Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures PT/0/B/2000/04 Re Establishment & Insp of Technical Support Ctr & CP/3/A/2002/05 Re post-accident Caustic Injection Into LPIS
ML20148H28522 January 1988Summary of ACRS Subcommittee on Generic Items 871216 Meeting W/Util in Washington,Dc Re Effectiveness of NRC Process That Deals W/Generic Issues & Usis.Viewgraphs & Presentation Schedule Encl
ML20213F06410 November 1986Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
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
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
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)
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