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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

• 05000413/LER-1987-031, :on 870729,vent Gas Radiation Monitor Found Inoperable.Caused by non-conservative High Radiation Alarm Setpoint.Setpoint Returned to Original Setting & Policy Will Be Clarified  + (ML20238E972)
• PLA-2913, Monthly Operating Repts for Aug 1987  + (ML20238E974)
• ML20238E975  + (ML20238E975)
• 05000440/LER-1987-058, :on 870815,control Rods Withdrawn Prior to Performing Source Range Monitors Signal to Noise Ratio Verification.Caused by Operator Error.Operators Involved Counseled.Tech Specs Rounds Will Be Revised  + (ML20238E976)
• ML20238E978  + (ML20238E978)
• ML20238E979  + (ML20238E979)
• 05000245/LER-1987-001-01, :on 870113,insp on All Model 4160 Vac Load Ctrs Revealed Cracking Along Horizontal Noryl Insulators. Caused by GE Mfg Defect.Plant Replaced Cracked Insulation W/Bayblend Insulation to Preclude Recurrence  + (ML20238E982)
• B12661, Proposed Tech Specs,Allowing Positive Moderator Temp Coefficient at Reactor Power Levels Less than 100% to Support Cycle 2 Reload  + (ML20238E984)
• 05000413/LER-1987-030, :on 870726,failure to Perform Type C Leak Rate Test on Valve 1NI-120B Following Replacement of Torque Switch Occurred.Caused by Inadequate Retest Policy.Retest Performed.Memo Re Leak Rate Tests to Be Issued  + (ML20238E987)
• ML20238E989  + (ML20238E989)
• TXX-6677, Forwards Response to NRC Requesting Addl Info on Groundwater Withdrawal Rates from 1979 to Present,Per Util 870429 Request for Extension of CP CPPR-127.Info Suppls Table 5.1 of Plant Fes (NUREG-0775)  + (ML20238E991)
• ML20238E992  + (ML20238E992)
• ML20238E993  + (ML20238E993)
• B12648, Proposed Tech Specs,Changing Limiting Condition for Operation 3.4.6.2(c) on Page 3/4 4-9 from 0.5 Gpm to 0.15 Gpm for Any One Steam Generator  + (ML20238E995)
• TXX-6716, Interim Deficiency Rept CP-87-18 Re Errors Identified During Review of Struther-Wells Qualification Documentation for Component Cooling Water Hxs.Initially Reported on 870608. Evaluation Continuing.Next Rept Will Be Provided by 871106  + (ML20238E999)
• ML20238F000  + (ML20238F000)
• ML20238F001  + (ML20238F001)
• ML20238F002  + (ML20238F002)
• ML20238F003  + (ML20238F003)
• 3F0987-10, Forwards Rev 4 to Modified Amended Security Plan,Per 10CFR50.54(p).Rev Withheld (Ref 10CFR73.21)  + (ML20238F005)
• 05000271/LER-1987-007, :on 870812,18 & 23,while Performing Type C Leak Rate Testing,Listed Valves Found to Have Seat Leakage Above Tech Spec Requirements.Util Will Perform Maint on Valves to Determine Cause of Failure  + (ML20238F006)
• B12663, Forwards Nonproprietary WCAP-11497 & Proprietary WCAP-11496, Resistance Temp Detector Bypass Elimination Licensing Rept for Millstone Unit 3. Proprietary Rept Withheld (Ref 10CFR2.790)  + (ML20238F007)
• 05000265/LER-1998-005, Forwards LER 98-005-00,per 10CFR50.73(a)(2)(vii)B. Commitments Made by Util,Listed  + (ML20238F009)
• 05000321/LER-1987-014-01, :on 870808,10 & 13 Main Control Room Environ Control Sys Went Into Pressurization Mode of Operation. Caused by Geiger-Mueller Tube Failures.Equipment Replaced & Recalibr  + (ML20238F010)
• ML20238F011  + (ML20238F011)

• 05000265/LER-1998-005-07, :on 980729,HPCI Subsystem Turning Gear Failed to Engage Automatically Rendering HPCI Subsystem Inoperable. Caused by Failed Limit Switch in Tgr Logic.Limit Switch & Pressure Switch Were Replaced  + (ML20238F013)

• 05000327/LER-1985-031, :on 850729,auxiliary Bldg Isolation Occurred Due to High Radiation Levels from Cracked Chemical & Vol Control Sample Line Weld.Caused by Fatigue of Metal in Weld. Brace Will Be Installed by Next Outage  + (ML20238F016)
• 05000245/LER-1987-032-01, :on 870811,first Stage Bypass Switches Failed to Meet Tech Spec Requirements.Caused by Setpoint Drift from Extended Periods of Depressurization.Switches Recalibrated to Conform to Tech Specs  + (ML20238F017)
• ML20238F019  + (ML20238F019)
• 05000414/LER-1987-022-01, :on 870728,main Feedwater Isolation Occurred Due to hi-hi Steam Generator Water Level.Caused by Debris in Feedwater Control Valve Positioner.Valve Positioner Replaced & Calibr Check Completed  + (ML20238F020)
• TXX-6676, Forwards Rev 0 to QA Dept Procedure Nqa 3.07-1.01, Technical Audit Program & Rev 3 to Engineering Assurance Program Engineering Functional Evaluation,Comanche Peak Steam Electric Station  + (ML20238F022)
• ML20238F025  + (ML20238F025)
• ML20238F026  + (ML20238F026)
• B12601, Proposed Tech Spec 5.4, Containment, Deleting General Statements Made About Containment Penetrations & Associated Basis  + (ML20238F029)
• ML20238F030  + (ML20238F030)
• ML20238F033  + (ML20238F033)
• IR 05000445/1998004  + (ML20238F035)
• ML20238F036  + (ML20238F036)
• ML20238F038  + (ML20238F038)
• ML20238F039  + (ML20238F039)
• NRC-87-0129, Submits Info Re Facility Operation W/Reduced Feedwater Temp & Operation W/Moisture Separator Reheater out-of-svc,per 870814 Request.Util Believes That Other Aspects of Two Issues Require Resolution & Proposes to Meet W/Nrc Staff  + (ML20238F040)
• ML20238F043  + (ML20238F043)
• 05000461/LER-1998-022, :on 980729,discovered That Surveillance Testing of Div 2 DG Fuel Oil Transfer Pump & Div 2 DG Fuel Oil Storage Tank Had Not Been Performed.Caused by Data Input Error.Will Update & Verify Completion Dates in Database  + (ML20238F046)
• PNO-III-87-105, on 870807,reactor Manually Scrammed.Caused by Variations in Feedwater Flow to Reactor & Leakage from Feedwater Sys.Ndt Performed Small Diameter Feedwater Piping & Other High Stress Areas  + (ML20238F047)
• ML20238F048  + (ML20238F048)
• ML20238F049  + (ML20238F049)
• ML20238F052  + (ML20238F052)
• ML20238F053  + (ML20238F053)
• ML20238F056  + (ML20238F056)
• ML20238F057  + (ML20238F057)
• 05000413/LER-1987-032, :on 870729,engineer Determined That Battery Banks in 125 Volt Dc Vital Instrumentation & Control Power Sys Inoperable.Caused by Mgt/Qa Deficiency.Intercell Resistance Readings Taken  + (ML20238F059)