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 Issue dateTitleTopic
ML20217A99330 September 1999NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML20211A99812 July 1999Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure
ML20196H86230 June 1999NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 ReptHigh Radiation Area
Power change
ML20155D99631 October 1998Rev 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
ML20151Q12114 August 1998Rev 0 to Control of Hazard Barriers
ML20236P2977 July 1998Rev 2 to NPPD CNS Strategy for Achieving Engineering Excellence
ML20238E92031 March 1997Geris 2000 Invessel Sys Alternate Method for Compliance to Reg Guide 1.150Weld Overlay
ML20133F45631 October 1996Engineering Self Assessment Follow-Up, for NPPD Cooper Nuclear StationTemporary Modification
Condition Adverse to Quality
ML20113B28331 May 1996USI A-46 Seismic Evaluation Rept Vol I/VSafe Shutdown
Safe Shutdown Earthquake
Internal Flooding
Emergency Lighting
Design basis earthquake
Scram Discharge Volume
Earthquake
ML20113B2897 May 1996Rev 1 to USNRC USI A-46 Resolution Ssel & Relay Evaluation Rept, Vol I of Viii
ML20101K93229 February 1996Determination of Loc for Cooper Feedwater Nozzle Fracture Mechanics Evaluation, for Feb 1996
ML20117N56023 February 1996Engineering Self Assessment 960205- 23Loop 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
ML20095G20031 December 1995Fracture Mechanics Evaluation of UT Indications Found During 1995 Reexam of FW Nozzle to Shell Welds at CnsNondestructive Examination
ML20095G09618 December 1995Stresses from Applied Loadings for Level A,B,C & D Conditions Considered in Core Spray Line Fracture Mechanics Evaluation
ML20094P27330 November 1995Internal Core Spray Line Flaw Evaluation at Cns
ML20078J4188 November 1994Rev 0 to, Cooper Nuclear Station Restart Readiness ProgramCommercial Grade Dedication
Probabilistic Risk Assessment
Temporary Modification
ML20072U7391 September 1994CNS Diagnostic Self Assessment Jul-Aug 1994Loop 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
ML20113C19231 July 1994Generation of Conservative Design & Median-Centered In-Structure Response Spectra for Cooper Nuclear Plant Control & Reactor Bldgs
ML17352A86931 May 1993Technical 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
ML20044G1704 May 1993Seismic Occurrence of 930330, Engineering EvaluationSafe Shutdown Earthquake
Earthquake
ML20086S88113 December 1991Fracture Mechanics Evaluation of UT Indications Found in Cooper Feedwater-Nozzle-to Shell Weld
ML20086Q1961 November 1991Emergency Preparedness Assessment Rept
ML20065L67630 November 1990Initial Simulator Certification SubmittalSafe Shutdown
Shutdown Margin
Squib
Scram Discharge Volume
Feedwater Controller Failure
ML20246C61031 August 1989Dcrdr Suppl III to Summary Rept
ML20151F95027 June 1988Change 1,Rev 1 to SAIC-86/1797, Summary of Human Factors Activities Related to Cooper Nuclear Station Plant Mgt Info Sys & Spds
ML20235U43123 September 1987Turbine Bypass Valve Out-of-Svc Evaluation Summary. Related Info EnclFeedwater Controller Failure
ML20235U39321 September 1987Turbine Bypass Valve Out-of-Svc Assessment. W/Records of 870921 TelconsFeedwater Controller Failure
ML20235H27431 May 1987Mechanical Level Instrument Availability AnalysisReactor Vessel Water Level
ML20209G87031 January 1987Dcrdr Suppl II to Summary Rept
ML20199C84312 June 1986Rev C to Failure Mode & Effects AnalysesMission time
ML20198H02015 May 1986Nebraska Public Power District Response to Initial Requirements of IE Bulletin 85-003
ML20154N47431 March 1986Safety Evaluation of Main Steam Line High Flow Setpoint for Cooper Nuclear Station
ML20154L32827 February 1986Dcrdr Suppl to Summary Rept
ML20107D5234 February 1985Detailed Control Room Design Review Summary ReptReactor Vessel Water Level
Scram Discharge Volume
ML20099D4841 February 1985Rev 2 to Detailed Descriptions of Displays for Cooper Nuclear Station SpdsIncorporated by reference
ML20087A9491 March 1984Safety Parameter Display Sys Safety Analysis
ML20083C61923 November 1983Containment Purge & Vent Valve Operability Rept
ML20073R20630 April 1983Wetwell-Drywell Vacuum Breaker Valves:Long-Term Program Structural EvaluationEarthquake
ML20076E86130 April 1983Nuclear Mgt Appraisal Rept for Nebraska Public Power District
ML20064C01331 December 198210CFR50,App R Supplementary Info Rept to Vols I & II Submitted to NRC 820628Safe Shutdown
Fire Barrier
Exemption Request
Fire Protection Program
ML20084Q53631 July 1982BWR Owners Group Position on NRC Reg Guide 1.97,Rev 2Safe Shutdown
Boric Acid
Grab sample
Squib
Fuel cladding
Unidentified leakage
ML20052C07430 April 1982Plant Unique Analysis Rept:Mark I Containment Program.
ML20052J00112 February 1982to IF-300 Redundant Yoke,NUREG-0612 Evaluation.Liquid penetrant
ML20038B72531 October 1981Evaluation Rept,Oct,1981.
ML20009A53526 January 1981Meteorological Monitoring Sys Development Plan for Emergency Preparedness for Ne Public Power District,Cooper Nuclear Station & Brownsville,Ne, Preliminary Rept
ML19295D80331 October 1980Master List of Class IE Equipment.Boric Acid
ML19262C38021 January 1980Proposed Process Control ProgramProcess Control Program
ML20125B99331 October 1979Voltage Drop Analysis Computations, Revision 1
ML19270G3306 June 1979Offsite Dose Assessment Manual.Grab sample
ML19270G3336 June 1979Radiological Environ Monitoring Manual.Annual Radiological Environmental Operating Report