NRC Inspection Manual 0310, Components Within the Cross-Cutting Areas
IMC 0310, Aspects within the Cross-Cutting Areas
05000412/LER-1989-013, :on 890427,svc Water Flow Through Recirculation Spray Sys HXs Discovered Below Tech Spec Requirements.Caused by Buildup of Asiatic Clams.Hx Tubes Cleaned,Limit Switches Adjusted & Task Force Developed
05000369/LER-1988-040, :on 881025,observed Air Leaking Through Penetration Into Containment Bldg.Caused by Defective Procedure Due to Mgt/Qa Deficiency & Inappropriate Action. Procedure PT/0/A-4700/48 Changed
05000424/LER-1989-005, :on 890210,main Feedwater Pump Turbine Tripped on High Vibration.Cause Cannot Be Positively Identified. Corrective Actions Include Temporarily Installing Vibration Instrumentation to Collect Vibration Data
05000440/LER-1987-061, :on 870830,Tech Specs Violated When Inner Air Lock Door Not Maintained Closed W/Outer Air Lock Door Inoperable.Caused by Bushing Failure.Bushing Replaced & Design Change for Air Lock Door Initiated
05000260/LER-1988-009-03, :on 880909 & 1002,reactor Protection Sys Bus Deenergized,Completing Initiation Logic for Listed Esfs. Caused by Lack of Preventive Maint on Breaker & Board Compartment.Maint Activities to Be Carried Out
05000327/LER-1988-041, :on 881018,turbine Trip & Feedwater Isolation Signal Occurred Due to Receipt of hi-hi Level Signal in Loop 1 Steam Generator.Caused by Inadvertent Opening of Loop 1 Valve as Result of Backfilling.Valve Closed
05000327/LER-1986-028, :on 860702,discovered Failure to Comply W/Asme Section XI Accuracy & Range Requirements for Instruments Used for Pump Testing.Caused by Personnel Error.Instruments Calibr to Required Accuracy
05000250/LER-1986-017, :on 860411,momentary Turbine Runback at 93% Power Occurred When RPI Power Supply Swapped from Normal to Alternate Supply When Inverter Failed.Caused by Component Failure of Transformer.Rpi Amplifier Adjusted
05000333/LER-1992-052, :on 921203,roving Fire Watch Tour Not Performed to Compensate for Smoke Detection Circuits Out of Svc.Caused by Personnel Error.Fire Watch Tour Reassigned & Disciplinary Action Taken
05000341/LER-1992-020, :on 911120,HPCI Sys Start Failure Occurred During Quarterly Surveillance Test.Caused by Egr Not Responding to Signal from EG-M Control Unit.Egr Replaced
05000247/LER-1983-041-03, /03L-0:on 831029,following Maint Outage,Reactor Coolant Chemical Analysis Indicated Chloride Concentration of 200 Ppb.Caused by Unflushed Anion Demineralizer Placed in Svc.Chloride Concentration Restored
05000298/LER-1991-010, :on 911002,group 3 Isolation (RWCU Sys) Occurred Due to High Temp Conditions Downstream of Nonregenerative Hxs.Caused by Hot Water Drawn Into Section of Piping.Procedure Change to Be Processed
05000445/LER-1994-002-01, :on 940510,control Room Missile Shield Door Was Declared Inoperable.Caused by Broken Missile Shield Door Latching Mechanism.Door Was Repaired & Control Room HVAC System Was Restored to Operable Status
05000324/LER-1993-012-02, :on 931204,discovered Temperature Switch Inoperable for PCIS MSL High Temperature Trip Due to Personnel Error.Operators Counseled & PT 2.1.22A/B Will Be Revised
05000339/LER-1990-009-02, :on 901028,2J 416-volt Emergency Bus Deenergized Due to Design Deficiency
AECM-82-153, Forwards Response to SER Item 1.11(17) Re post-accident Sampling & Draft Chemistry Procedure for Estimating Core Damage
0CAN039310, Forwards Objectives to Be Demonstrated by Util During Plant 1993 Radiological Emergency Exercise (REX-93)
05000321/LER-1990-009-01, :on 900522,determined That Requirements of Tech Spec 3.14.2,Actions 105 & 107 Not Met.Caused by Inadequate Procedure.Normal Range Monitoring Sys Restored to Operable Status & Procedure 64CH-SAM-005-OS Revised
05000412/LER-1993-001, :on 930126,identified That Stress on AFW Piping to C SG Exceeded Design Stress Due to Water Hammer.Station Will Perform ISI Insps of AFW Piping & Replace Mechanical Snubbers W/New Hydraulic Snubbers
05000338/LER-1991-005, :on 910209,containment Building Penetrations Breached.Caused by Inadequate Procedural Controls.Core Mapping & Cavity Pump Down Activities Secured,Air Hose Removed & Hydrolase Hose Capped
AEP-NRC-2012-83, Communications Assessment Requested by Nuclear Regulatory Commission Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulation 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3
05000254/LER-1997-020-01, :on 970519,B-train Control Room Ventilation Sys Became Inoperable When AHU Breaker Tripped When Performing Monthly Surveillance.Cause Could Not Be Determined.Circuitry Testing Completed