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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• 05000397/LER-1989-007, :on 890316,discovered That Two Tech Spec Surveillance Procedures Re Fire Protection Zones for Standby Svc Water Pump Houses & Power Generation Control Cabinet Inconsistent.Action Statements Implemented  + (ML17285A412)
• IR 05000397/1989009  + (ML17285A413)
• GO2-89-065, Forwards Amends 3,4,& 5 to Offsite Dose Calculation Manual Re Tech Spec Section 6.14.2a, Administrative Controls. Amends Cover Semiannual Reporting Requirements & near-field Dilution Factor  + (ML17285A414)
• ML17285A418  + (ML17285A418)
• IR 05000397/1989010  + (ML17285A420)
• ML17285A421  + (ML17285A421)
• IR 05000397/1989008  + (ML17285A423)
• 05000397/LER-1989-009, :on 880529,full Reactor Protection Sys Actuation Occurred Twice During Performance Testing.Caused by Inadequate Preoperational Test & trouble-shooting Procedures.Preoperational Procedure Revised  + (ML17285A425)
• ML17285A427  + (ML17285A427)
• GO2-89-072, Supply Sys Nuclear Plant 2 Annual Environ Operating Rept 1988  + (ML17285A428)
• GO2-89-069, Forwards Application to Amend License NPF-21,authorizing Onsite Disposal of Very Low Level Radwaste by Burying Eight Moisture Separator Reheater Tube Bundles W/Associated Assemblies & Four Small Spools of Piping  + (ML17285A430)
• ML17285A431  + (ML17285A431)
• GO2-89-070, Part 21 Rept Re Defect in Limitorque Valve Motor Operator Model SMB-2 W/Soft Worm Shaft Clutch Gear Assembly.Caused by Failure to Install Split Spacer of Worm Shaft Clutch Gear assembly.Safety-related Valves Manually Operated  + (ML17285A432)
• 05000397/LER-1988-030, :on 880825 & 26,full Reactor Protection Sys (RPS) Actuations Occurred.Caused by Switch Overtravel.Rps Power Supply Select Switch Returned to Normal Position & Scram Reset  + (ML17285A433)
• ML17285A434  + (ML17285A434)
• ML17285A438  + (ML17285A438)
• ML17285A445  + (ML17285A445)
• ML17285A447  + (ML17285A447)
• GO2-89-074, Radiological Environ Monitoring Program 1988 Annual Rept for Nuclear Plant 2  + (ML17285A448)
• ML17285A449  + (ML17285A449)
• 05000397/LER-1988-030-01, Forwards LER 88-030-01.Rept Submitted Per Commitment in Response to Violation B Noted in Insp Rept 50-397/88-24  + (ML17285A453)
• ML17285A455  + (ML17285A455)
• ML17285A457  + (ML17285A457)
• ML17285A459  + (ML17285A459)
• ML17285A460  + (ML17285A460)

• ML17285A461  + (ML17285A461)

• ML17285A462  + (ML17285A462)
• ML17285A463  + (ML17285A463)
• ML17285A465  + (ML17285A465)
• ML17285A466  + (ML17285A466)
• ML17285A467  + (ML17285A467)
• ML17285A468  + (ML17285A468)
• ML17285A470  + (ML17285A470)
• GO2-89-087, Suppls Response to NRC Re Violations Noted in Insp Rept 50-397/87-26.Corrective Actions:All Associated Master Data Sheets Revised  + (ML17285A471)
• ML17285A472  + (ML17285A472)
• ML17285A474  + (ML17285A474)
• GO2-89-095, Part 21 Rept Re Defects in Target Rock Actuator Kits (Part 300562-1).Initially Reported on 890516.Defects Noted in Cold Solder Condition,Insufficient Solder Joints & Failed Solder Joints.Defective Kits Returned to Mfg for Repair  + (ML17285A477)
• GO2-89-089, Forwards Update of Status Sheets Used to Track Items/Issues Identified During Mar & Apr 1989 NRC SSOMI at Plant.Items Include 125-volt Dc Battery Life Calculations & Change from Automatic to Manual Intake Valve Operation in Control Room  + (ML17285A478)
• ML17285A479  + (ML17285A479)
• ML17285A480  + (ML17285A480)
• ML17285A482  + (ML17285A482)
• ML17285A483  + (ML17285A483)
• 05000397/LER-1989-008, :on 890419,discovered That on 881202,Tech Spec Amend Request Submitted to NRC Describing Diesel Generator Trip Bypass Verification That Had Not Been Performed W/Ler Not Issued within 30 Days After Determination  + (ML17285A485)
• GO2-89-092, Forwards Info Re Implementation of Improvement Programs in Each of Functional Areas Reviewed by NRC in 1988 SALP Rept & Summary of Accomplishments & Status of All Commitments from Util 880917 Response to Subj Rept,Per 890105 Meeting  + (ML17285A486)
• GO2-89-096, Requests Addl 30 Days for Responding to Generic Ltr 89-06. Response Would Be Due to NRC by 890810.Ltr Not Received Until 890512  + (ML17285A487)
• GO2-89-081, Forwards Status Rept for Apr 1989 in Response to Generic Ltr 88-14 Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. W/Six Oversize Drawings  + (ML17285A488)
• ML17285A492  + (ML17285A492)
• 05000397/LER-1989-014, :on 890509,full Reactor Protection Sys Actuation Occurred.Caused by Accidental Movement of Local Power Range Monitor Cables.Scram Reset & Importance of Tying Cables Away from Working Area Stressed  + (ML17285A496)
• GO2-89-097, Advises That No Tech Spec Change to Table 3.12-1 Re Location of Direct Radiation Station Necessary Per Review of Amend 6 to Offsite Dose Calculation Manual  + (ML17285A497)
• GO2-89-098, Requests That 21 Addl Days Be Granted for Response to Generic Ltr 89-08, Erosion/Corrosion-Induced Pipe Wall Thining, Due to Util Not Receiving Ltr Until 890523  + (ML17285A498)
• GO2-89-104, Part 21 Rept Re Defect Discovered in Valve Motor Operator of RCIC Inboard Containment Isolation Valve RCIC-V-63.Upper Housing Cover Will Be Machined to Remove Excess Matl to Provide Required Recess  + (ML17285A500)