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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

• 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)
• GO2-89-102, Suppls 890303 & 0420 Applications for Amend to Tech Specs Re Reload Requirements for (Cycle 5).Figures 3.2.1-6,3.2.3-1, 3.2.4-2 & 3.2.4-3 Encl  + (ML17285A503)
• ML17285A504  + (ML17285A504)
• GO2-89-103, Forwards Addl Info Re Insp Rept 50-397/86-12 Concerning Equipment Qualification of Limitorque Motor Operators Toward Resolution of Remaining Open Item on Subj Audit.Grease Relief Valve Test Data & T-drain Technical Analysis Encl  + (ML17285A507)

• ML17285A508  + (ML17285A508)

• IR 05000397/1989012  + (ML17285A510)
• GO2-89-101, Forwards Supplemental Info to 890331 Application for Amend to License NPF-21,revising Tech Specs 3/4.2.6, Power Flow Instability & 3/4.2.7, Neutron Flux Noise Monitoring, Per 890515 & 22 Telcons W/Nrc  + (ML17285A513)
• ML17285A514  + (ML17285A514)
• GNRO-2017/00068, Response to Official Requests for Additional Information (RAI) for RR GG-ISI-020 to Use BWRVIP Guidelines  + (ML17285A516)
• ML17285A517  + (ML17285A517)
• ML17285A521  + (ML17285A521)
• ML17285A523  + (ML17285A523)
• 05000397/LER-1989-012, :on 890505,unplanned Reactor Scram Occurred During Performance of Reactor Protection Sys Logic Sys Functional Test.Caused by Procedural Inadequacy.Procedure Will Be Revised to Provide Specific Resetting  + (ML17285A528)
• 05000397/LER-1989-013, :on 890508,preliminary Calculations Indicated Potential Common Mode Failure of Redundant 120-volt safety- Related Devices.Caused by Less than Adequate Design Criteria to Limit Voltage Drops.Procedure Revised  + (ML17285A539)
• ML17285A541  + (ML17285A541)
• 05000397/LER-1989-015, :on 890512,three-quarter-inch High Point Vent Line Failed During Performance of HPCS Sys Operability Procedure.Caused by Reverse Bending Fatigue Caused by Vibration.Design Change Implemented  + (ML17285A542)
• GO2-89-106, Responds to NRC Re Violations Noted in Insp Rept 50-397/88-40.No Tech Spec Change to Section 4.7.2.d Will Be Submitted as Part of Corrective Action to Be Taken  + (ML17285A544)
• IR 05000133/2017003  + (ML17285A546)
• ML17285A551  + (ML17285A551)
• ML17285A553  + (ML17285A553)
• ML17285A554  + (ML17285A554)
• ML17285A556  + (ML17285A556)
• ML17285A557  + (ML17285A557)
• 05000397/LER-1989-016, :on 890514,reactor Operator Inadvertently Tripped Div 1 & 2 Offsite Power Supply Feeders Resulting in Loss of Power to Buses SM-7 & SM-4.Caused by Inadvertent Removal of Transformer Fuses.Fuses Reinserted  + (ML17285A559)
• GO2-89-109, Advises NRC That Requirement of Reg Guide 1.97,Rev 2 to Provide Qualified Wide Range Neutron Monitor Satisfied. Requests That Deferral Contained in Be Withdrawn  + (ML17285A560)
• ML17285A561  + (ML17285A561)
• 05000397/LER-1989-005, :on 890311,34 of 185 Control Rods Drifted Inward from One to Seven Notches.Caused by Main Steam Line Radiation Monitor Design Deficiency.Desired Rod Pattern Reestablished  + (ML17285A564)
• 05000397/LER-1989-017, :on 890520,outboard RHR Shutdown Cooling Valve Automatically Isolated,Causing Loss of Shutdown Cooling. Caused by Removal of Relay by Contractor Maint Electrician Installing Mod to Leak Detection Sys  + (ML17285A565)
• 05000397/LER-1989-018, :on 890522,reactor Protection Sys (RPS) a motor-generator Set Failed Resulting in Loss of Power to RPS Bus A.Caused by Component Failure.Motor Replaced  + (ML17285A566)
• 05000397/LER-1989-019, :on 890524,inboard RHR Shutdown Cooling Supply Valve Automatically Isolated When Electrician Lifted Wire Deenergizing Valve Control Relay.Personnel Counseled & Training in Plant Procedures Initiated  + (ML17285A567)