Semantic search
Jump to navigation
Jump to search
| Issue date | Title | |
|---|---|---|
| IR 05000395/2020002 | 4 August 2020 | Integrated Inspection Report 05000395/2020002 and Independent Spent Fuel Storage Installation Inspection (ISFSI) Report 07201038/2020001 |
| RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachment Ii: Technical Bases Document for the Proposed EALs (Marked-Up Copy) | 7 April 2014 | Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachment Ii: Technical Bases Document for the Proposed EALs (Marked-Up Copy) |
| RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. EPP-108, Enclosure 1, Revision 01 (Draft E) | 7 April 2014 | Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. EPP-108, Enclosure 1, Revision 01 (Draft E) |
| RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EA | 7 April 2014 | Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EAL |
| ML14122A157 | 7 April 2014 | License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachment Ii: Technical Bases Document for the Proposed EALs (Marked-Up Copy) |
| ML14122A158 | 7 April 2014 | License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. EPP-108, Enclosure 1, Revision 01 (Draft E) |
| RC-14-0032, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments III, IV, V & VI: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EAL Comparison.. | 7 April 2014 | License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments III, IV, V & VI: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EAL Comparison.. |
| ML080670419 | 7 March 2008 | CDBI Findings |
| RC-06-0024, 1007930 - On-Line Monitoring of Instrument Channel Performance, Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation | 31 December 2004 | 1007930 - On-Line Monitoring of Instrument Channel Performance, Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation |
| RC-02-0170, Operating License No. NPF-12, Basis Documentation for Application for Renewed Operating License, Virgil C. Summer Nuclear Station Mechanical Database AMR Query, Pages 1 to 237 | 1 October 2002 | Operating License No. NPF-12, Basis Documentation for Application for Renewed Operating License, Virgil C. Summer Nuclear Station Mechanical Database AMR Query, Pages 1 to 237 |
| 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 |
| 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 |
| 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 |
| RC-93-0310, (VCSNS) - Technical Specification Change - TSP 930011 Accident Monitoring Instrument | 17 December 1993 | (VCSNS) - Technical Specification Change - TSP 930011 Accident Monitoring Instrument |
| 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 |
| ML17349A931 | 3 November 1992 | Forwards Update to Data Point Library |
| ML20114D657 | 28 August 1992 | Forwards App B Survey Response & Data Point Library,Per NUREG-1394 |
| 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) |
| ML20102A811 | 22 July 1992 | Proposed TS 3/4.3.3.6 & Tables 3.3-10 & 4.3-7 Re Accident Monitoring Instrumentation |
| 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 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 05000395/1987014 | 15 June 1987 | Insp Rept 50-395/87-14 on 870505-31.Violations Noted:Failure to Promptly Evaluate & Classify Event & Inadequate Sys Operating Procedure for Svc Water Sys |
| ML20215K329 | 15 June 1987 | Insp Rept 50-395/87-14 on 870505-31.Violations Noted:Failure to Promptly Evaluate & Classify Event & Inadequate Sys Operating Procedure for Svc Water Sys |
| NRC-86-3095, Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified | 9 January 1986 | Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified |
| NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
| 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 |
| ML20115G423 | 15 April 1985 | Summary Rept on Reg Guide 1.97,Rev 3,Post-Accident Monitoring Sys |
| 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 |
| ML20072R031 | 11 March 1983 | Procedure PPM 13.1.1, Classifying Emergency |
| ML20002A968 | 4 December 1980 | Forwards Info Re TMI Requirement II.F.2.Discussion of Thermocouples & in-core Instrumentation,Subcooling Meter & Reactor Vessel Water Level Instrumentation Encl |