Pages that link to "NRC Form I"
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The following pages link to NRC Form I:
Displayed 50 items.
- ML20137A374 (← links)
- ML20141F755 (← links)
- ML20149M595 (← links)
- 05000313/LER-1988-022, :on 881216,identified Discrepancy Which Resulted in Potential Impact on Environ Qualification of Plant.Caused by Failure to Properly Evaluate Changes in Svc Water Flow to DHR Coolers.Plan Developed (← links)
- 05000368/LER-1989-004, :on 890301,discovered Plant Startup Procedure Inadequate Resulting in Inability to Automatically Transfer HPSI Pump Suction Prohibited by Tech Specs.Caused by Inadequate Procedure.Procedures Revised (← links)
- 05000368/LER-1988-023-01, :on 880219,inoperability of Mechanical Snubber on Main Steam Supply Piping Discovered.Caused by High Dynamic Loading of Piping & Snubber Due to Water Entrainment in Steam Piping.Snubber Replaced (← links)
- 05000368/LER-1987-010, :on 870522,plant Protection Sys Panels Seismic Qualification Compromised Due to Loose Fasteners.Caused by Personnel Error When Personnel Elected Not to Tighten All Screws.Personnel Counseled (← links)
- 05000313/LER-1988-030, :on 890620,determined That Unacceptable Modeling Technique Used in Stress Calculations,Potentially Affecting Seismic Capabilities of Eccs.Mods of Affecting Piping Completed (← links)
- 05000313/LER-1988-020-01, :on 881103,nonsafety-related Ventilation Sys Affected Penetration Room Ventilation Sys Capability to Process Penetration Leakage Following Design Basis Accident. Caused by Failure to Assess Sys Impact (← links)
- 05000368/LER-1989-009-01, :on 890420,determined That Emergency Diesel Generator 18-month Test Procedure Did Not Verify Fuel Pump Transfer Capabilities.Caused by Personnel Error.Procedure to Be Revised (← links)
- 05000368/LER-1989-015-01, :on 890809,personnel Identified Discrepancy Re Single Failure Design Criterion of Containment Hydrogen Analyzers.Caused by Inadequate Design Review Process. Evaluations Being Conducted to Correct Design (← links)
- 05000313/LER-1989-023, :on 890605,determined That Power Range Nuclear Instrumentation Calibr Required by Tech Specs Had Not Been Performed within Specified Frequency.Caused by Lack of Procedural Guidance.Procedure Revised (← links)
- 05000368/LER-1989-012-01, :on 890626,RCS Backleakage Through Safety Injection Sys Check Valve Occurred Three Times.Caused by Missing Internal Parts.Cause of Missing Rollpins Could Not Be Determined.Rollpins Replaced (← links)
- 05000368/LER-1985-028, :on 851025,procedure for Safety Injection Tanks Identified as Allowing cross-connecting of Safety Injection Tanks Via Nonseismic Piping of Nitrogen Addition Sys for Tanks.Caused by Personnel Error (← links)
- 05000368/LER-1987-012, :on 870511,discovered Low Temp Overpressure Sys Relief Valves Deviated from Configurations Shown on Piping Isometric Drawings.Caused by Lack of Programmatic Mod Controls.Snubber Clamp Replaced (← links)
- 05000313/LER-1987-003-01, :on 870808,emergency Feedwater Sys Actuation Occurred During Power Reduction.Caused by Main Feedwater Valve Fulcrum Pin Out of Position Due to Personnel Error.New Set Screws & Pin Installed (← links)
- 05000368/LER-1989-002, :on 890109,discovered That Tech Spec Required 14-day Periodic Surveillance Test for Svc Water Flow Rate to Containment Cooling Units Not Performed.Caused by Personnel Error.Personnel Counseled (← links)
- 05000313/LER-1988-009, :on 880922,three Inoperable Snubbers Discovered on safety-related Piping Sys.One Snubber Failed Due to Spec of Undersized Snubber & Other Two Found W/Inadequate Travel Remaining for Thermal Growth (← links)
- 05000313/LER-1986-005-01, :on 860612,discovered Existence of Unsealed Conduits Between Manholes 1MH05 & 1MH06 Since 841205.Caused by Apparent Oversight of Conduits During Design Change Preparation & Inadequate Insp.Conduits Capped (← links)
- 05000313/LER-1986-007-01, :on 861221,set Pressure Verification Tests Showed Pressurizer Code Safety Valves PSV-1001 & PSV-1002 W/ Incorrect Settings.Root Cause of Event Under Investigation. Valve PSV-1001 Adjusted & Other Valve Replaced (← links)
- 05000368/LER-1986-002-01, :on 860227,nonconservative Error Discovered in Analysis of Samples from Charcoal Filters in Ventilation Sys.Caused by Inadequate Technical Review of Procedure.No Corrective Actions Will Be Taken (← links)
- 05000368/LER-1985-020, :on 850919,reactor Protection Sys Actuated on Two of Four Channels,Resulting in Opening of Reactor Trip Circuit Breakers.Caused by Personnel Error.Technician Counseled Re Procedures (← links)
- 05000368/LER-1988-007, :on 880423,inadvertent Plant Protection Sys (PPS) Actuation Occurred When Maint Technician Deenergized Power Supply to Sys.Caused by Personnel Error.Technician Reset PPS & Counseled (← links)
- 05000368/LER-1988-009, :on 880501,discovered That Tech Spec Drop Time Limit for Control Element Assembly (CEA) Insertion Not Met for Certain Ceas.Caused by Deficiency in Method for Testing. Emergency Amend Request Submitted (← links)
- 05000313/LER-1988-006-01, :on 880406,potential Degradation of Environ Boundary Seal on Rosemount Instrumentation Transmitters Discovered.Cause Not Conclusively Determined But Rotation of Sensor Modules Suspected.Part 21 Related (← links)
- 05000368/LER-1985-025, :on 851118,control Element Assembly Calculator Monthly Functional Test Not Performed.Caused by Personnel Error & Conflicting Monthly Test Schedules.Schedules Restructured & Personnel Counseled (← links)
- 05000368/LER-1988-003-01, :on 880310,unplanned Automatic Actuation of ESFAS Occurred Due to Deenergizing of Electrical Distribution Sys Vital Power Panel for Maint.Caused by Drift of Time Delay Relay.Relay Recalibr (← links)
- 05000313/LER-1988-002, :on 871022,anchor Bolts for Upper North Base Plate of Instrumentation Rack R-02 Found to Be Loose & Pulling Out of Wall.Caused by Insufficient Guidance to Field Personnel During Const.Bolts Replaced (← links)
- 05000368/LER-1988-001, :on 850429,leakage Discovered in Two Solenoid Operated Valves While Performing Containment Test.Caused by Inadequate post-installation Verification Testing.Valves Removed & Reinstalled in Reverse Condition (← links)
- 05000368/LER-1985-021, :on 850925,unsealed Fire Barrier Penetration Reported During 18-month Fire Barrier Surveillance.Caused by Improper Sealing of False Wall for Cleanout Pipe from Restroom Into Turbine Bldg.Sealing Corrected (← links)
- 05000368/LER-1985-006, :on 850221,fire Watch Door Found Open.Caused by Failure to Label Door,Per New Fire Barrier & Penetration Marking Program Requirements.Door Labeled & Closed. Surveillance Verified Proper Labeling (← links)
- 05000368/LER-1985-027, :on 851217,monthly Surveillance Revealed That Armatures on Undervoltage Devices for Reactor Trip Circuit Breakers 4 & 8 in mid-position.Cause Not Stated.Procedures Changed to Require Verification of Position (← links)
- 05000368/LER-1985-012, :on 850617,core Operating Limits Supervisory Sys (COLSS) Declared Inoperable Due to Error in Calculation of DNBR Power Operating Limit.Caused by Input Error During Cycle 5 COLSS Update.Coding Error Corrected (← links)
- 05000313/LER-1985-004-01, :on 850531,intercept Valves Closed & Feedwater Pump Tripped,Causing Reactor Trip.Faulty Connection Caused Close Signal & Spurious Vacuum Trip Signal,Resulting in Pump Trip.Disconnects Realigned (← links)
- 05000368/LER-1985-003, :on 850201,Tech Specs 4.6.1.3.c Surveillance Requirement Not Met.Caused by Inadequate Guidance & Review of Tech Specs During Procedure Writing & Rev Process.Test Procedure Revised (← links)
- 05000368/LER-1984-025, :on 840727,discovered That Incorrect Data Used to Calibr Resistance Temp Detector (RTD) 2TE-4711-4 Which Provides Cold Leg Temp Input to Channel D Core Protection Calculator.Caused by Manufacturer Error (← links)
- 05000368/LER-1984-021, :on 840728,automatic Reactor Trip Occurred Due to High Level on Steam Generator B.Main Feedwater Flow Increased in Response to Decreasing Steam Generator Level.No post-trip Anomalies Noted (← links)
- 05000368/LER-1984-017, :on 840713,fire Barrier Penetration 2124-0004 Identified as Degraded During HVAC Mods.Fire Watch Established within 1 H of Discovery.Penetration Repaired by Replacing Plastic Tubing W/Copper Tubing (← links)
- 05000368/LER-1984-013, :on 840617,reactor Tripped from Full Power on Low DNBR Due to Penalty Factors Generated by Core Protection Calculators.Caused by Dropped Control Element Assembly (← links)
- 05000368/LER-1984-024, :on 840828,reactor Trip Occurred.Caused by Dropped Control Element Assembly (Cea).Silicon Controlled Rectifiers Replaced for Cea.Power Supply fuses,opto-isolator Cards & Coil Driver Cards Replaced (← links)
- 05000368/LER-1984-011, :on 840507,reactor Turbine Trip Occurred Due to High Level on Steam Generator B.Caused by Master Controller Settings Not Being Set at Optimum Setpoints for Maneuvering at Reduced Power Levels (← links)
- 05000368/LER-1984-001, :on 840128,unit Tripped During Low Power Physics Testing.Caused by One Pin Peaking Factor Limit Being Exceeded Due to Control Element Assembly Position During Testing.Procedures Modified (← links)
- 05000293/LER-1982-021-03, /03L-0:on 820624,fire Door 153 on 37 Ft Elevation of Turbine Bldg Annex Found Blocked Opened.Caused by Door Being Blocked to Remove Matl.Faulty Lock Replaced (← links)
- 2CAN049013, LER 90-V01-00:on 900222,inadvertent Start of Emergency Diesel Generator (EDG) Occurred.Caused by Inadequate Procedural Guidance Re Air Rolling Edgs.Warning Placards Placed at EDG Control Panels (← links)
- 05000368/LER-1990-001, :on 900126,identified That Required Visual Insps of Containment Bldg After Entry Made Not Documented as Being Performed.Caused by Inadequate Procedural Guidance. Administrative Controls to Be Established (← links)
- 05000368/LER-1989-026-01, :on 891112,gaps in Piping Supports on Supply & Return Piping for Containment Coolers Identified.Caused by Inadequate Design Technique Used in Original Support Design. Shims Added Before Restart from Outage (← links)
- 05000313/LER-1989-045, :on 891210,discovered That U-bolt Supports on Two Containment Isolation Valves in Containment Bldg Not Installed & Pressurizer Sample Lines & Valves Considered Inoperable.Missing U-bolts Installed (← links)
- 05000368/LER-1989-023, :on 891117,noted That Channel a Not Responding to Change in Power Level & Declared Inoperable.Caused by Defective Preamplifier.Evaluation of Sys Design & Channel Functional Test Initiated (← links)
- 05000313/LER-1989-046, :on 891204,reactor Bldg Isolation Valves Rendered Inoperable Due to Deficient Welds on Piping Supports Which Were Installed During Initial Plant Const. Deficient Supports Repaired Prior to Restart (← links)
- 05000368/LER-1989-005, :on 890518 & 25,damping Board Removed from Penetration Containing Cable Tray.On 890531,voids Noted in Penetration Seals.Caused by Erroneous Vendor Procedures. Penetrations Restored & Procedures Revised (← links)