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| Issue date | Title | |
|---|---|---|
| ML19249B768 | 29 August 2019 | Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) |
| ML19249B772 | 29 August 2019 | Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) |
| ML19249B774 | 29 August 2019 | Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) |
| ML19011A174 | 4 January 2019 | Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents |
| ML19011A171 | 4 January 2019 | Enclosures 1 to 3 - EAL Scheme Revisions Enclosure Summary, Discussion of Change and Mps EAL Scheme Revisions-Supporting Documents |
| ML19011A172 | 4 January 2019 | Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) |
| ML19011A173 | 4 January 2019 | Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents |
| ML13240A242 | 31 August 2013 | NUREG/CR-7110 Vol 2 Rev 1 State-of-the-Art Reactor Consequence Analyses Project Volume 2: Surry Integrated Analysis |
| ML13063A181 | 28 February 2013 | Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) |
| ML120260681 | 31 January 2012 | NUREG/CR-7110 Vol 2 State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis |
| ML11256A023 | 30 September 2011 | NUREG-1953 Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models - Surry and Peach Bottom. |
| ML090641018 | 27 February 2009 | Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors |
| ML042650363 | 8 September 2004 | Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process |
| ML023010480 | 19 September 2002 | Part 2 of 7 - GE BWR/4 Advanced Course R-504B |
| 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 |
| IR 05000280/1997001 | 29 August 1997 | Discusses Insp Repts 50-280/97-01 & 50-281/97-01 on 970113 & 17 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000 |
| ML18152A068 | 28 January 1997 | Submits Written Summary Rept of Actions Taken,Conclusions, Basis for Continued Operability & Corrective Actions to Be Implemented in Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis.... |
| 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 |
| ML18152A548 | 22 December 1995 | Responds to NRC 951019-1122 Ltr Re Violations Noted in Insp Repts 50-280/95-20 & 50-281/95-20 on Stated Date.Corrective Actions:Immediate Actions Initiated to Restore & Maintain RCS Inventory & to Ensure Outage Activities Controlled |
| 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 |
| ML18151A226 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Appendices I |
| ML18151A207 | 30 June 1994 | Evaluation of Potential Severe Accidents During LOW Power and Shutdown Operations at Surry,Unit 1.Analysis of Core Damage Frequency from Internal Events During Mid-Loop Operations.Appendices A-D |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
| ML18153B363 | 2 November 1993 | Informs of Mod Made to Instrument Range for RVLIS Dynamic Head Points to Expand Range in Order to Prevent Spurious Alarms Which Resolves North Anna Emergency Response Facility Problem Rept |
| 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 |
| ML20128M470 | 15 February 1993 | Forwards Dpl Revision Summaries for Surry Unit 1 & 2 Emergency Response Data Sys |
| 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) |
| 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 |
| ML18151A558 | 11 October 1991 | Forwards Emergency Response Data Sys (ERDS) Data Base Updates,Per NRC 901025 Ltr,Requesting Detailed Hardware, Communications,Data Point & Administrative Info to Assist Contractor in Designing ERDS Interfaces |
| ML18151A259 | 6 June 1991 | Forwards Remaining Survey Info & Data Point Library for Surry Power Station as Well as Corrected North Anna Data Point Library Info for ERDS |
| ML18151A275 | 11 April 1991 | Forwards Response to NRC 901025 Ltr Containing Survey Requesting Detailed Hardware,Communications,Data Point & Administrative Info to Assist NRC Contractor in Designing Emergency Response Data Sys Interface |
| 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 |
| ML20247A897 | 16 March 1989 | Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl |
| ML20245D841 | 28 September 1988 | Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 |
| 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 |
| 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 |
| ML20084E502 | 31 March 1984 | Monthly Operating Repts for Mar 1984 |