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Issue date | Title | |
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IR 05000269/1986004 | 4 April 1986 | Insp 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 05000269/1991008 | 10 April 1991 | Insp 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 Units | 23 March 1990 | Unanticipated 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 Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
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 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
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 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
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 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
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 1996-65, 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 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 |
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 |
ML023600065 | 16 December 2002 | Technical 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 |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML031681423 | 9 June 2003 | Technical Specification Bases (Tsb) Change |
ML032250127 | 31 July 2003 | Technical Specification Bases Change |
ML032731475 | 29 September 2003 | Technical Specifications Pages for Amendment Nos. 335, 335 and 336, Respectively |
ML040220176 | 12 January 2004 | Technical Specification Bases (Tsb) Change |
ML042790461 | 20 September 2004 | License Amendment Request to Eliminate the Technical Specifications Requirements for the Hydrogen Monitors and Hydrogen Recombiners Oconee Technical Specification 3.3.8 and McGuire Technical.. |
ML050810416 | 16 March 2005 | License 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 |
ML052290274 | 9 August 2005 | Technical Specification Bases (Tsb) Change |
ML063470137 | 6 December 2006 | Technical Specification Bases (Tsb) Change |
ML070080325 | 13 December 2006 | Licensee'S Handouts for Oconee, Summary of December 13, and 14, 2006 |
ML073440021 | 3 December 2007 | Technical Specification Bases (Tsb) Change |
ML073470813 | 12 December 2007 | Handout from 12/12/07 Meeting, Rps/Esps Digital LAR |
ML080670419 | 7 March 2008 | CDBI Findings |
ML080730339 | 31 January 2008 | License Amendment Request for Reactor Protective System/Engineered Safeguards Protective System Digital Upgrade, Technical Specification Change Number 2007-09 |
ML080770031 | 11 March 2008 | Revisions to Technical Specification Bases (Tsb) Change |
ML081410060 | 14 May 2008 | Technical Specification Bases (Tsb) Change |
ML083510088 | 10 December 2008 | Technical Specification Bases (Tsb) Change |
ML100220016 | 28 January 2010 | Issuance of Amendment Nos. 366, 368, and 367, Reactor Protective System and Engineered Safeguard Protection System Digital Upgrade |
ML102460015 | 31 August 2010 | Tornado Mitigation License Amendment Request - Response to Request for Additional Information |
ML12003A070 | 16 December 2011 | Tornado and High Energy Line Break (HELB) Mitigation License Amendment Requests (Lars) - Responses to Request for Additional Information, Part 1 of 6 |
ML12173A389 | 18 June 2012 | Technical Specification Bases (Tsb) Changes |
ML17118A023 | 20 April 2017 | Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2 |
ML19312C158 | 4 June 1976 | Forwards Addl Info Re Electrical Equipment Which May Become Submerged Following Postulated Loca,In Response to Question 4 of NRC 760406 Ltr Re ECCS Analysis |
ML19312C159 | 6 August 1976 | Evaluation of Post-LOCA Boric Acid Concentration Control Sys for Facility Reactors. |
ML19322B597 | 24 February 1976 | Discusses 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 |
ML20027C124 | 30 September 1982 | Public 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 |
ML20148H285 | 22 January 1988 | Summary 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 |
ML20213F064 | 10 November 1986 | Summary 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 1985-02 | 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 |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
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) |