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IR 05000280/199700129 August 1997Discusses 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
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
ML02301048019 September 2002Part 2 of 7 - GE BWR/4 Advanced Course R-504B
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0426503638 September 2004Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML09064101827 February 2009Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML11256A02330 September 2011NUREG-1953 Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models - Surry and Peach Bottom.
ML12026068131 January 2012NUREG/CR-7110 Vol 2 State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis
ML13063A18128 February 2013Overall 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)
ML13240A24231 August 2013NUREG/CR-7110 Vol 2 Rev 1 State-of-the-Art Reactor Consequence Analyses Project Volume 2: Surry Integrated Analysis
ML18136A22526 November 1979Responds to 791030 Ltr Re Implementation of short-term Requirements in NUREG-0578.Forwards Schedules for short-term Requirements W/Specified Completion Dates
ML18136A39210 January 1980Responds to NRC 790913 Request Re Status of Implementation of TMI Lessons Learned Task Force short-term Requirements. Forwards Implementation Status & Addl Info Requested by NRC at 791130 Meeting
ML18141A46820 January 1984Safety Parameter Display Sys SAR for NUREG-0696 Computer Project,North Anna & Surry Nuclear Power Stations.
ML18151A20730 June 1994Evaluation 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
ML18151A22630 June 1994Evaluation 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
ML18151A2596 June 1991Forwards Remaining Survey Info & Data Point Library for Surry Power Station as Well as Corrected North Anna Data Point Library Info for ERDS
ML18151A27511 April 1991Forwards 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
ML18151A55811 October 1991Forwards 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
ML18152A06828 January 1997Submits 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....
ML18152A54822 December 1995Responds 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
ML18153B3632 November 1993Informs 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
ML19011A1714 January 2019Enclosures 1 to 3 - EAL Scheme Revisions Enclosure Summary, Discussion of Change and Mps EAL Scheme Revisions-Supporting Documents
ML19011A1724 January 2019Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up)
ML19011A1734 January 2019Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents
ML19011A1744 January 2019Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents
ML19249B76829 August 2019Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated)
ML19249B77229 August 2019Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated)
ML19249B77429 August 2019Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated)
ML20084E50231 March 1984Monthly Operating Repts for Mar 1984
ML20128M47015 February 1993Forwards Dpl Revision Summaries for Surry Unit 1 & 2 Emergency Response Data Sys
ML20245D84128 September 1988Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920
ML20247A89716 March 1989Summary 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
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
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