Pages that link to "10 CFR 50.73(c)(2)()"
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The following pages link to 10 CFR 50.73(c)(2)():
Displayed 35 items.
- 05000316/LER-1989-010, :on 890524,control Room Operators Observed That Loop 2 delta-T Reactor Power Indication Approx 4% Lower than Remaining Loops.Caused by Replacement of Steam Generators Resulting in Change in Flow Distribution (← links)
- 05000316/LER-1989-017, :on 891019,discovered Discrepancy Between turbine-driven Auxiliary Feed Pump Test Line Flow & Process Flow Indication.Caused by Conducting Inaccurate Flow Measurements.Flow Sensing Switches Reset (← links)
- 05000315/LER-1989-002-01, :on 890303,failure of MSIVs to Meet Tech Spec Lift Setpoint Requirements Occurred.Safety Valve Setpoints Reset within Specified Ranges (← links)
- 05000316/LER-1989-019, :on 891130,discovered That Backup Sampling Pump Stopped During Surveillance of Unit Vent Effluent Monitor & Sample Not Taken.Caused by Wire Leads Rubbing on Pump Pulley.Portable Backup Pump Put Into Svc (← links)
- 05000315/LER-1989-015-01, :on 891128,pyralarm Fire Detection Zone 3 Made Inoperable When Welding in Laundry Room Caused Standing Alarm.Fire Watch Patrol Not Assigned within 1 H.Caused by Personnel Error.Event Reviewed W/Operators (← links)
- 05000316/LER-1989-008, :on 890311,reactor Cable Tunnel CO2 for Quadrants 1,3 & 4 Declared Inoperable Due to False Indication of Status (← links)
- 05000315/LER-1989-014-01, :on 891127,discovered That P-250 Computers Rod Sequence & Deviation Monitors Inoperable Since Computer Bootstrap on 891123.Caused by Inadequate Guideline to Conduct Computer Bootstrap.Program Corrected (← links)
- 05000315/LER-1989-013-01, :on 891122,determined That Between 890906 & 1003,unit East Motor Driven Auxiliary Feedwater Pump Should Have Been Declared Administratively Inoperable.Caused by Personnel Error.Continuous Fire Watch Posted (← links)
- 05000316/LER-1989-018, :on 891108,discovered That P-250 Computer Contained Incorrect Blowdown Constants for Thermal Output Program Entered on 891025.Caused by Lack of Administrative Controls.Zero Value for Blowdown Reentered (← links)
- 05000315/LER-1989-012-01, :on 890913,solid State Protection Sys Surveillance Testing Performed on Train B While Train a Safety Injection Pump Inoperable.Caused by Personnel Error. Breaker Surveillance Test Procedures Revised (← links)
- 05000315/LER-1989-011-01, :on 890901,discovered Snubber Installed on Pressurizer Spray Line Not Tested Since Aug 1987.Caused by Failure to Include Snubber on Testing Job Order.Procedure Changed to Add Two Separate Steps (← links)
- 05000316/LER-1989-015, :on 890821,inoperable Open Fire Damper Subj to Constraints of Tech Spec 3.7.10 Found Which Action Statement Requirements Not Implemented.Caused by Misconception by Person Developing Task Sheet for Maint Insps (← links)
- 05000316/LER-1989-014, :on 890814,reactor Protection Sys Actuation Occurred Due to Failure of Class 1E Power Supply Inverter. Caused by Failed Silicon Controlled Rectifier in Static Transfer Switch.Inverter Repaired (← links)
- 05000315/LER-1989-009, :on 890705,disovered That Testing Document for Valve 1-CS-443-2 Not Signed Off.Record Search Conducted & No Evidence Found to Indicate That post-maint Testing Performed.Caused by Personnel Error (← links)
- 05000315/LER-1989-004, :on 890324,leakage Found on Containment Penetrations Exceeded Tech Spec 3.6.1.2.b Requirement.Caused by Excessive Leakage Rate of Valves WCR-924,ECR-26 & ECR-31. Faulty Valves Repaired & Restested (← links)
- 05000315/LER-1989-010-01, :on 890705,determined That 414 Seismic/ Expansion Gap Seals Should Have Been Included in Formal Fire Seal Insp Program.Caused by Failure to Recognize Seals as Requiring Surveillance Per Tech Specs (← links)
- 05000315/LER-1989-009-01, :on 890705,discovered That post-maint Testing Documentation for Job Order on Valve 1-CS-442-2 Not Signed Off as Completed.Unit Entered Hot Shutdown W/Type C Testing Not Performed on 890620 (← links)
- 05000316/LER-1989-013, :on 890617,reactor Trip Breakers Opened When ESF Signal Initiated from Set I,Intermediate Range Nuclear Instrumentation Channel.Caused by Miscommunication. Importance of Complete Turnover Stressed (← links)
- 05000316/LER-1989-012, :on 890624,monthly Channel Checks Required by Tech Spec 3.3.3.6,Table 3.3-10 for Containment Water Level Instruments Not Included in Surveillance Procedure.Caused by Personnel Error.Procedure Revised on 890624 (← links)
- 05000316/LER-1989-011, :on 890613,discrepancies Determined to Have Rendered Sys Outside of Design Basis Error Allowances During post-accident Conditions.Caused by Failure to Install Outer Heat Shrink.Splice Boxes Corrected (← links)
- 05000315/LER-1989-008-01, :on 890420,power Range Neutron Flux Instrumentation Monthly Channel Functional Surveillance Test Procedures Do Not Satisfy Intent of Tech Spec 3.3.1.1.Caused by Lack of Specific Guidance.Rev Initiated (← links)
- 05000315/LER-1989-007-01, :on 890414,Fire Door 422 in Demineralizer Valve Gallery,High Radiation Area Not Inspected Per Tech Spec 4.7.10.2a.Cause Not Stated.All Surveillances Assigned to Personnel Reconducted for Other Discrepancy (← links)
- 05000316/LER-1989-009, :on 890331,discrepancy Noted in Westinghouse P-250 Computer Calculated Thermal Power Value Which Could Lead to Exceeding Rated Thermal Power.Caused by Not Including blowdown-mass Enthalpy Term (← links)
- 05000315/LER-1989-005-01, :on 890330,during Surveillance Testing, Containment Isolation Valve Would Not Close Per Tech Spec 3.6.3.1.Probably Caused by Flaw in Gear Tooth.Valve Operator Repaired by Replacing Defective Components (← links)
- 05000315/LER-1989-006-01, :on 890405,discovered That Flow Rates for Safety Injection Pumps Exceeded Tech Spec 4.5.2.H Allowable Flow.No Cause Identified.Flow Control Values Adjusted to Meet Required Flows (← links)
- 05000315/LER-1989-003-01, :on 890318,ESF Actuation Occurred.Caused by Standing High Flux Trip on Intermediate Range Nuclear Instrumentation Channel I Which Had Not Reset Prior to Power Dropping Below Permissive P-10 (← links)
- 05000315/LER-1989-004-01, :on 890324,discovered That Containment Type B & C Leakage Exceeded Limiting Condition for Operation.Caused by Degradation of Isolation Valve Seating Surfaces. Containment Isolation Valves Being Repaired (← links)
- 05000316/LER-1989-002, :on 890116,seismic Restraint,Located on 24-inch ECCS Suction Line,Noted to Have Significant Deformation. Probably Caused by Removal & Reinstallation of Piping During Startup.Mod Initiated to Repair Restraint (← links)
- 05000316/LER-1989-007, :on 890310,reactor Trip Signal Received Due to lo-lo Steam Generator Level.Caused by Failure of Personnel to Adequately Anticipate Required Auxiliary Feedwater Flowrate.Personnel Involved Counseled (← links)
- 05000316/LER-1989-004, :on 890210,leakage Through Pressurizer Safety Valves (EIIS/AB-RV) Detected Via Temp & Acoustic Monitor Indications.Caused Attributed to Setpoint Drift.Valve Inspected & Disc & Seat Polished & Lapped (← links)
- 05000316/LER-1989-006, :on 890224,ESF Actuation Occurred from Instrumentation Indicating Low Level Coincident W/Feedwater Flow/Steam Flow Mismatch on Steam Generator 24.Cause Unknown.Procedures Implemented (← links)
- 05000316/LER-1989-005, :on 890221,containment Type B & C Leak Rate Exceeded Limiting Condition for Operation Using Min Pathway Calculation Method,Causing Excessive Leakage in Several Valves.Valves Repaired & Retested (← links)
- 05000315/LER-1989-001-01, :on 890116,erroneous Operation of Control Switch for Condenser Air Off Takes to Startup Air Ejectors Occurred.Caused by Inadequate self-checking.Switches Labeled & Operator Training Emphasis Made (← links)
- 05000316/LER-1989-001, :on 890125,discovered Controls to Limit Access to Extreme High Radiation Area Not Implemented.Caused by Poor Communication Between Radiation Protection & Security. Design Change Approved by Plant Mgt (← links)
- 05000316/LER-1989-003, :on 890119,valve Stem Seal Leak Allows Air Into Sensor Capillary Tubing Causing Reactor Vessel Level Indication Sys Calibr Shift.Caused by Leakage of High Point Fill Valve Stem Seals (← links)