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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

• 05000346/LER-1985-005, :on 850321,erroneous Signal in Integrated Control Sys Led to Reactor Trip on Low once-through Steam Generator Level.Caused by Faulty Controller in Feedwater Level Control Circuit.Controller Replaced  + (ML20116D584)
• 05000254/LER-1985-005-08, :on 850306,fuel Pool Radiation Monitor 1A Failed Downscale.On 850307,monitor 1B Spiked High & Monitor 1A Spiked High 13 Times.Caused by Electrical Noise Interference  + (ML20116D588)
• BSEP-85-0690, RO 1-85-016:on 850406,Type C Leakage Limits Exceeded for RHR Subsystem a Suppression Pool Suction Valve 1-E11-F020A. LER Will Be Submitted within 30 Days Following Completion of Test  + (ML20116D591)
• 05000362/LER-1985-007-02, :on 850317,safety Injection Tank Valves Pressure Tested in Closed Position W/Rcs at 351 F.Caused by Personnel Error.Briefings Will Emphasize Necessity of Monitoring & Controlling RCS Temp  + (ML20116D593)
• 05000261/LER-1985-011, :on 850318,unit Received Reactor Trip & Safety Injection from Steam Line Differential Pressure Signal A. Caused by Ground Which Tripped Bus IB-9 Due to Leak on Blowdown Valve.Valve Repaired  + (ML20116D598)
• 05000265/LER-1985-006-07, :on 850318,during Local Leak Rate Testing,Two MSIVs Leaked in Excess of Tech Specs.Cause Not Yet Determined.No Corrective Action Taken.Rept Detailing Cause Will Be Submitted Following Repair of Valves  + (ML20116D601)
• ML20116D603  + (ML20116D603)
• U-602062, Provides Addl Response to SBO Rule 10CFR50.63, Loss of All AC Power, Re Recommendation on Condensate Inventory for Decay Heat Removal  + (ML20116D605)
• ML20116D606  + (ML20116D606)
• 05000285/LER-1985-003, :on 850321,ventilation Isolation Actuation Signals Occurred.Caused by Increasing Activity Levels as Monitored by Vent Stack Particulate Monitor RM-061.Ion Exchanger Isolated,Decreasing Activity Levels  + (ML20116D614)
• ML20116D626  + (ML20116D626)
• ML20116D631  + (ML20116D631)
• ML20116D640  + (ML20116D640)
• ML20116D646  + (ML20116D646)
• ML20116D649  + (ML20116D649)
• ML20116D657  + (ML20116D657)
• ML20116D662  + (ML20116D662)
• ML20116D664  + (ML20116D664)
• ML20116D667  + (ML20116D667)
• ML20116D668  + (ML20116D668)
• ML20116D669  + (ML20116D669)
• 05000395/LER-1985-005, :on 850317,reactor Trip Occurred from 100% Power Due to lo-lo Level in Steam Generator A.Caused by Burned Contact in MSIV Test Switch.Msiv Switch Replaced & All MSIVs Tested  + (ML20116D671)
• ML20116D673  + (ML20116D673)
• 05000280/LER-1984-001, :on 840106,reactor Trip Occurred W/Unit at 100% Power.Caused by Over Temp delta-t Signal.Feedwater to Steam Generator a Isolated & Source Range Channels Manually Reinstated  + (ML20116D674)
• ML20116D683  + (ML20116D683)

• B14272, Application for Amend to License NPF-49,revising TS 4.3.2 to Further Clarify Footnote in Table 4.3-2 Re ESFAS Instrumentation Surveillance Requirements  + (ML20116D706)

• ML20116D714  + (ML20116D714)
• ML20116D730  + (ML20116D730)
• ML20116D734  + (ML20116D734)
• 05000286/LER-1985-004-01, :on 850320,control Power Fuses for Nuclear Instrumentation Range Channel 36 Failed,Resulting in Three Reactor Trips.Caused by Current Leakage Across Test Switch. Testing Performed.Investigation Continuing  + (ML20116D746)
• ML20116D747  + (ML20116D747)
• 05000275/LER-1985-012, :on 850321,automatic Reactor & Turbine Trips Occurred.Caused by Technicians Inadvertently Shorting 115-volt Vital Power Supply While Testing Level Channels. Personnel Reinstructed  + (ML20116D757)
• ML20116D768  + (ML20116D768)
• ML20116D772  + (ML20116D772)
• LD-92-106, Forwards Level 1 PRA Rev of Sys 80+ Std Design PRA, Including Chapters 1-6,9 & 10.Rev Closes 16 Open & Confirmatory Issues in Sys 80+ Dser & Specific Sections of Encl Rept Will Be Provided by 921115  + (ML20116D773)
• 05000423/LER-1992-123, :on 921003,determined That Surveillance Testing for Emergency 4,160 Volt Undervoltage Relays Did Not Satisfy Requirements of Ts,Due to Incorrect Survillance Procedure. Procedures Will Be Revised Per TS Requirements  + (ML20116D776)
• HL-5207, Forwards Non-proprietary SNCH-9501 & Proprietary SNCH-9501-P, BWR Steady State & Transient Analysis Methods Benchmarking Licensing Topical Rept, Per GL 83-11. Proprietary Encl Withheld (Ref 10CFR2.790)  + (ML20116D778)
• ML20116D781  + (ML20116D781)
• ML20116D786  + (ML20116D786)
• 05000286/LER-1985-003-01, :on 850319,reactor Trip Breaker Opened, Initiating Unit Trip.Possibly Caused by Inadvertent Actuation of Manual Trip Lever.Testing & Preventive Maint Found No Irregularities  + (ML20116D789)
• ML20116D792  + (ML20116D792)
• 05000278/LER-1985-008-01, :on 850313,suppression Pool Water Level Rose to 15.3 ft,0.4 Ft Above Tech Spec Limit.Caused by Operator Mistakenly Opening Torus Test Bypass Valve.Torus Pump Used to Lower Water Level & Operator Disciplined  + (ML20116D795)
• ML20116D802  + (ML20116D802)
• 05000395/LER-1985-006, :on 850320,discovered Senior Reactor Operator License Number SOP-20001 Expired 850203 W/O Submitting Renewal Application.Caused by Personnel Oversight.Licensee Will Provide Better Administrative Control  + (ML20116D807)
• ML20116D812  + (ML20116D812)
• ML20116D813  + (ML20116D813)
• ML20116D816  + (ML20116D816)
• ML20116D824  + (ML20116D824)
• ML20116D828  + (ML20116D828)
• ML20116D831  + (ML20116D831)
• 05000366/LER-1992-019-01, :on 920928,personnel Notified That Test Results for SRV Exhibited Drift in Mechanical Setpoint Due to corrosion-induced Bonding.C/A Includes Installing Sys That Will Provide Electrical Signals to SRV  + (ML20116D835)