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Issue date | Title | Topic | |
---|---|---|---|
ML18152A281 | 12 October 1999 | Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. | Liquid penetrant |
ML20249C001 | 30 November 1997 | Reactor Vessel Fluence Analysis Methodology | |
ML20148E709 | 31 May 1997 | Vols 1 & 2 to Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Ors,Usi A-46, Per GL 87-02 | Safe Shutdown Boric Acid High Radiation Area Safe Shutdown Earthquake Probabilistic Risk Assessment Design basis earthquake Earthquake Power-Operated Valves |
ML18151A710 | 30 September 1996 | Supplemental Info for VA Power Nomad Code & Model. | Power change |
ML20249C405 | 16 May 1996 | Rev 0 to CE-0082, Review of Augmented ISI Frequency for Pressurizer Spray Lines | |
ML20249C403 | 23 April 1996 | Rev 0 to CE-0081, Review of Augmented ISI Frequency for Reactor Coolant Bypass Lines | Safe Shutdown Earthquake |
ML20092A261 | 31 August 1995 | EDG Preventive Maint Insp Outage Probabilistic Safety Assessment for August 1995 | Hydrostatic Reserve Station Service Transformer |
ML20078P926 | 26 September 1994 | Service Water System Operational Performance Assessment 940711-29 | Safe Shutdown Unanalyzed Condition Fitness for Duty High Radiation Area Ultimate heat sink Stroke time Tornado Missile Internal Flooding Coatings Zebra Mussel Emergency Lighting Missed surveillance Job Performance Measure Foreign Material Exclusion Chernobyl Biofouling Through-Wall Leak Scaffolding |
ML18153B422 | 31 July 1993 | Rev 11 to Engineering Evaluation 25, Evaluation of Existing Fire Enclosure Around Ventilation Duct,North Anna Power Station. | Safe Shutdown Fire Barrier Fire Protection Program Backfit |
ML18153B421 | 31 July 1993 | Rev 11 to Engineering Evaluation 24, Evaluation of Radiant Energy Shields,North Anna Power Station. | Safe Shutdown Fire Barrier Exemption Request |
ML20046D158 | 28 February 1993 | Virginia Power Sys Transient Analysis Using Version 1 of North Anna Retran Model. | |
ML18152A071 | 1 February 1993 | NFPA Heat & Flame Evaluation of MSA Custom 4500 SCBA Using Enriched O2 Breathing Air for VA Power,Final Rept. | Moisture barrier |
ML20116A290 | 23 September 1992 | Conceptual Engineering Final Rept NP-2653, RG 1.97 Isolation Devices Type 2,North Anna Power Station. W/One Oversize Encl | |
ML20101B033 | 30 April 1992 | Suppl to Update of Settlement Monitoring Points & Graphs NAPS - Supplement to Technical Rept CE-0019,North Anna Settlement Data Oct 1989 - Apr 1992 | |
ML20077A660 | 7 May 1991 | Summary Rept on Exam of Steam Generator Tube R11-C14,North Anna Power Station,Unit 1 | Nondestructive Examination |
ML18153C311 | 26 July 1990 | Decommisioning Financial Assurance Certification Rept for Surry Power Station & North Anna Power Station. | |
ML20011F622 | 26 February 1990 | Analysis of Small Steamline Break Performance W/O Low Pressurizer Pressure Safety Injection North Anna Units 1 & 2. | Shutdown Margin |
ML20248E864 | 19 September 1989 | Rev 0 to Evaluation of Settlement Monitoring Program for Main Plant Structures in Support of Proposed Changes to Tech Spec 3/4.7.12. W/One Oversize Figure | Finite Element Analysis |
ML20246J139 | 17 August 1989 | Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding EP-2 | |
ML20246J158 | 9 August 1989 | Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding MC-1 | |
ML20246J126 | 20 July 1989 | Rev 0 to Coordination of Load Ctr Circuit Breakers,EP-1 | |
ML20246J119 | 20 July 1989 | Rev 0 to Response to SSOMI Item IC-8 of NRC | |
ML20246J099 | 18 July 1989 | Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-2 | |
ML20246J107 | 18 July 1989 | Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-7 | |
ML20246J148 | 30 June 1989 | RCS Leakage Detection Sys | |
ML20246K346 | 5 May 1989 | Technical Evaluation & Safety Analysis:Solid State Protection Sys Slave Relay Testing REA-88-51 | Scram Discharge Volume |
ML20245K731 | 26 April 1989 | Rev 0 to 890225 Steam Generator Leak Event Rept | Boric Acid Grab sample |
ML20056A034 | 18 April 1989 | Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement | |
ML18151A966 | 18 April 1989 | Nuclear Decommissioning Trust Agreement. | |
ML20245A531 | 13 September 1988 | Simulator Certification Submittal | |
ML20148J631 | 16 March 1988 | Generator Tube Fatigue Evaluation & Remedial Actions Rept | |
ML20147F562 | 2 March 1988 | Safety Evaluation in Support of Containment Temp Increase for North Anna Power Station | |
ML20196J290 | 24 February 1988 | Rev 1 to Civil Engineering Technical Rept 0005, Differential Settlement Between Svc Bldg & Unit 2 Main Steam Valve House | |
ML20148J640 | 12 February 1988 | Rev 2 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept | |
ML20091L704 | 19 October 1987 | Generator Row 9 Column 51 Tube Failure Analysis | Flow Induced Vibration |
ML20235G244 | 25 September 1987 | Steam Generator Downcomer Mods Safety Evaluation for North Anna Units 1 & 2 | |
ML20238F616 | 15 September 1987 | Rev 1 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept | Safe Shutdown Boric Acid Health Physics Network Shutdown Margin Grab sample Post Accident Monitoring Hydrostatic Finite Element Analysis Through-Wall Leak Unidentified leakage |
ML18151A135 | 28 August 1987 | Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. | Fuel cladding |
ML20235U670 | 7 August 1987 | Loss of Inventory Event 870617-21 | |
ML20235Q066 | 5 August 1987 | Metallurgical Svcs Rept FAL-00050 | |
ML20237G979 | 29 July 1987 | Rev 0 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept. W/Pages from Facility Updated FSAR | Boric Acid Shutdown Margin Grab sample Weld Overlay Post Accident Monitoring Hydrostatic Stress corrosion cracking Eddy Current Testing Liquid penetrant Unidentified leakage |
ML20235U343 | 20 July 1987 | Rev 0 to Chronology Steam Generator Tube Rupture Event North Anna Power Station Unit 1 870715. Related Info Encl | |
ML20238E161 | 15 July 1987 | Rept of Emergency Preparedness Events Re Unit 1 Steam Generator Tube Rupture | Health Physics Network Shutdown Margin Fire Protection Program |
ML20215G547 | 17 June 1987 | Safety Evaluation for Change in Methodology & Supporting Analyses | |
ML20235Q055 | 21 May 1987 | Investigation Rept FAL-00024, Emergency Diesel Generator Floating Busing Failure | |
ML20206D672 | 31 March 1987 | Engineering Analysis Svc & Maint North Anna Power Station Fairbanks-Morse 38 TD8-1/8 Diesel Engines Phase II | Hydrostatic |
ML20207B523 | 30 November 1986 | Reactor Vessel Fluence & Rt/Pts Evaluations Suppl to WCAP 11016 | |
ML20213D777 | 31 October 1986 | RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices | Boric Acid Post Accident Monitoring Pressure Boundary Leakage |
ML20213D760 | 31 October 1986 | RCS Loads & Component Support Margins Evaluation for Elimination of Rcs,Main Loop Pipe Break Protective Devices | High Radiation Area Safe Shutdown Earthquake Earthquake |
ML20210F682 | 17 October 1986 | Reactor Protection Sys Trip Setpoint Drift Characterization |