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Issue date | Title | Topic | |
---|---|---|---|
ML20217A993 | 30 September 1999 | NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data | |
ML20211A998 | 12 July 1999 | Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure | |
ML20196H862 | 30 June 1999 | NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept | High Radiation Area Power change |
ML20155D996 | 31 October 1998 | Rev 0 to GE-NE-B13-01980-24, Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station | |
ML20151Q121 | 14 August 1998 | Rev 0 to Control of Hazard Barriers | |
ML20236P297 | 7 July 1998 | Rev 2 to NPPD CNS Strategy for Achieving Engineering Excellence | |
ML20238E920 | 31 March 1997 | Geris 2000 Invessel Sys Alternate Method for Compliance to Reg Guide 1.150 | Weld Overlay |
ML20133F456 | 31 October 1996 | Engineering Self Assessment Follow-Up, for NPPD Cooper Nuclear Station | Temporary Modification Condition Adverse to Quality |
ML20113B283 | 31 May 1996 | USI A-46 Seismic Evaluation Rept Vol I/V | Safe Shutdown Safe Shutdown Earthquake Internal Flooding Emergency Lighting Design basis earthquake Scram Discharge Volume Earthquake |
ML20113B289 | 7 May 1996 | Rev 1 to USNRC USI A-46 Resolution Ssel & Relay Evaluation Rept, Vol I of Viii | |
ML20101K932 | 29 February 1996 | Determination of Loc for Cooper Feedwater Nozzle Fracture Mechanics Evaluation, for Feb 1996 | |
ML20117N560 | 23 February 1996 | Engineering Self Assessment 960205- 23 | Loop seal Probabilistic Risk Assessment Coatings Anchor Darling Temporary Modification Condition Adverse to Quality Feedwater Controller Failure Operability Determination Maintenance Rule Program Fire Protection Program Operability Assessment |
ML20095G200 | 31 December 1995 | Fracture Mechanics Evaluation of UT Indications Found During 1995 Reexam of FW Nozzle to Shell Welds at Cns | Nondestructive Examination |
ML20095G096 | 18 December 1995 | Stresses from Applied Loadings for Level A,B,C & D Conditions Considered in Core Spray Line Fracture Mechanics Evaluation | |
ML20094P273 | 30 November 1995 | Internal Core Spray Line Flaw Evaluation at Cns | |
ML20078J418 | 8 November 1994 | Rev 0 to, Cooper Nuclear Station Restart Readiness Program | Commercial Grade Dedication Probabilistic Risk Assessment Temporary Modification |
ML20072U739 | 1 September 1994 | CNS Diagnostic Self Assessment Jul-Aug 1994 | Loop seal Half scram Stroke time Probabilistic Risk Assessment Temporary Modification Job Performance Measure Foreign Material Exclusion Scram Discharge Volume Systematic Assessment of Licensee Performance Scaffolding |
ML20113C192 | 31 July 1994 | Generation of Conservative Design & Median-Centered In-Structure Response Spectra for Cooper Nuclear Plant Control & Reactor Bldgs | |
ML17352A869 | 31 May 1993 | Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. | Boric Acid Coatings Operating Basis Earthquake Tornado Missile Protection Earthquake |
ML20044G170 | 4 May 1993 | Seismic Occurrence of 930330, Engineering Evaluation | Safe Shutdown Earthquake Earthquake |
ML20086S881 | 13 December 1991 | Fracture Mechanics Evaluation of UT Indications Found in Cooper Feedwater-Nozzle-to Shell Weld | |
ML20086Q196 | 1 November 1991 | Emergency Preparedness Assessment Rept | |
ML20065L676 | 30 November 1990 | Initial Simulator Certification Submittal | Safe Shutdown Shutdown Margin Squib Scram Discharge Volume Feedwater Controller Failure |
ML20246C610 | 31 August 1989 | Dcrdr Suppl III to Summary Rept | |
ML20151F950 | 27 June 1988 | Change 1,Rev 1 to SAIC-86/1797, Summary of Human Factors Activities Related to Cooper Nuclear Station Plant Mgt Info Sys & Spds | |
ML20235U431 | 23 September 1987 | Turbine Bypass Valve Out-of-Svc Evaluation Summary. Related Info Encl | Feedwater Controller Failure |
ML20235U393 | 21 September 1987 | Turbine Bypass Valve Out-of-Svc Assessment. W/Records of 870921 Telcons | Feedwater Controller Failure |
ML20235H274 | 31 May 1987 | Mechanical Level Instrument Availability Analysis | Reactor Vessel Water Level |
ML20209G870 | 31 January 1987 | Dcrdr Suppl II to Summary Rept | |
ML20199C843 | 12 June 1986 | Rev C to Failure Mode & Effects Analyses | Mission time |
ML20198H020 | 15 May 1986 | Nebraska Public Power District Response to Initial Requirements of IE Bulletin 85-003 | |
ML20154N474 | 31 March 1986 | Safety Evaluation of Main Steam Line High Flow Setpoint for Cooper Nuclear Station | |
ML20154L328 | 27 February 1986 | Dcrdr Suppl to Summary Rept | |
ML20107D523 | 4 February 1985 | Detailed Control Room Design Review Summary Rept | Reactor Vessel Water Level Scram Discharge Volume |
ML20099D484 | 1 February 1985 | Rev 2 to Detailed Descriptions of Displays for Cooper Nuclear Station Spds | Incorporated by reference |
ML20087A949 | 1 March 1984 | Safety Parameter Display Sys Safety Analysis | |
ML20083C619 | 23 November 1983 | Containment Purge & Vent Valve Operability Rept | |
ML20073R206 | 30 April 1983 | Wetwell-Drywell Vacuum Breaker Valves:Long-Term Program Structural Evaluation | Earthquake |
ML20076E861 | 30 April 1983 | Nuclear Mgt Appraisal Rept for Nebraska Public Power District | |
ML20064C013 | 31 December 1982 | 10CFR50,App R Supplementary Info Rept to Vols I & II Submitted to NRC 820628 | Safe Shutdown Fire Barrier Exemption Request Fire Protection Program |
ML20084Q536 | 31 July 1982 | BWR Owners Group Position on NRC Reg Guide 1.97,Rev 2 | Safe Shutdown Boric Acid Grab sample Squib Fuel cladding Unidentified leakage |
ML20052C074 | 30 April 1982 | Plant Unique Analysis Rept:Mark I Containment Program. | |
ML20052J001 | 12 February 1982 | to IF-300 Redundant Yoke,NUREG-0612 Evaluation. | Liquid penetrant |
ML20038B725 | 31 October 1981 | Evaluation Rept,Oct,1981. | |
ML20009A535 | 26 January 1981 | Meteorological Monitoring Sys Development Plan for Emergency Preparedness for Ne Public Power District,Cooper Nuclear Station & Brownsville,Ne, Preliminary Rept | |
ML19295D803 | 31 October 1980 | Master List of Class IE Equipment. | Boric Acid |
ML19262C380 | 21 January 1980 | Proposed Process Control Program | Process Control Program |
ML20125B993 | 31 October 1979 | Voltage Drop Analysis Computations, Revision 1 | |
ML19270G330 | 6 June 1979 | Offsite Dose Assessment Manual. | Grab sample |
ML19270G333 | 6 June 1979 | Radiological Environ Monitoring Manual. | Annual Radiological Environmental Operating Report |