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Issue date | Title | |
---|---|---|
IR 05000397/2022004 | 23 January 2023 | Integrated Inspection Report 05000397/2022004- 4th Quarter |
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 |
ML022120154 | 2 May 1995 | Wppss Project No. 2, License Amendment 137, Increasing Authorized Maximum Power Level of Reactor from Current Limit of 3323 Megawatts Thermal (Mwt) to 3486 Mwt & Modifies TSs to Incorporate Increased Power Limit in Plant Operating Limits |
ML022660035 | 20 September 2002 | Generation Station, 4 TS Pages (Overleaf) for Amendment 179 (Tac. MB3881) TS Changes for Extension of Instrumentation Channel Surveillance Test Intervals |
ML030160139 | 30 December 2002 | Request for Amendment to TS 2.1.1.2, MCPR Safety Limit & SR 3.3.1.3.2, Oscillation Power Range Monitor-LPRM Calibration Frequency |
ML030940328 | 27 March 2003 | CGS - Init Exam - 03-2003 - Draft Outline |
ML030940336 | 27 March 2003 | CGS - Init Exam - 03-2003 - Final Outline |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML031540755 | 2 June 2003 | TS Pages for Columbia Generating Station |
ML040140447 | 13 January 2004 | Meeting Slides (1/13/04) and Letter - Shutdown Cooling Isolation Reportability and a Letter from Dennis Allison to Christina Perino Dated 11/24/2003 |
ML040300619 | 30 January 2004 | IR 05000397-03-007, on 10/05/03 Through 12/31/03, Columbia Generating Station |
ML050140432 | 30 September 2004 | Init Exam - 09/2004 - Draft RO Written Examination |
ML050420426 | 30 September 2004 | Init Exam - 09/2004 - Draft RO Written Exam |
ML050620513 | 3 March 2005 | Technical Specifications, Elimination of Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process. |
ML051290107 | 6 April 2005 | Emergency Response Data System Change to Data Point Library |
ML052280259 | 4 August 2005 | Energy Northwest Response to Request for Additional Information Regarding License Amendment Request: Control Rod Drop Accident Analysis |
ML052620411 | 30 September 2004 | AST Amendment 9/30/04 - Attachments and Calculations |
ML061320272 | 12 May 2006 | IR 05000397-06-002 on 1/1/06 - 3/31/06 for Columbia Generating Station; Operability Evaluations, Other Activities |
ML090440307 | 13 February 2009 | Correction to Pages Issues with Amendment Nos. 208, 209, and 210 |
ML091700146 | 18 August 2009 | License Amendment No. 214, Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation |
ML093020205 | 29 October 2009 | Email, Request for Additional Information, Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems |
ML110600678 | 18 March 2011 | Issuance of Amendment No. 220, Revise Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation, Related to Traversing In-Core Probe Containment Isolation Valve Instrumentation |
ML11159A144 | 1 June 2011 | Response to Request for Additional Information Regarding Emergency Action Level Scheme Change |
ML12011A152 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant |
ML12011A159 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems |
ML12011A160 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features |
ML12011A161 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Chapter 7, Instrumentation and Control Systems |
ML12011A163 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Chapter 9, Auxiliary Systems |
ML12011A169 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Chapter 15, Accident Analyses |
ML12011A172 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Appendix B, Response to Regulatory Issues Resulting from TMI-2 |
ML12011A173 | 14 December 2011 | Amendment 61 to Final Safety Analysis Report, Appendix F, Fire Protection Evaluation |
ML120800078 | 30 March 2012 | Issuance of Amendment No. 223, Administrative Changes to Facility Operating License to Modify Existing License Conditions or Delete Obsolete License Conditions |
ML12089A043 | 22 May 2012 | Issuance of Renewed Facility Operating License No. NPF-21 for Columbia Generating Station. Columbia Lr Ltr to Applicant |
ML13317B623 | 31 January 2014 | Redacted - Issuance of Amendment No. 226, Technical Specification Changes to Support Installation of GE Hitachi Power Range Neutron Monitoring System; Implementation of Arts/Mellla |
ML13337A266 | 29 January 2014 | Interim Staff Evaluation and Audit Report Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) |
ML13357A322 | 21 December 2013 | Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Columbia Generating Station, TAC No.: MF0796 |
ML14010A293 | 30 December 2013 | Final Safety Analysis Report, Amendment 62, Chapter 1 - Introduction and General Description of Plant |