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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

• ML19354E006  + (ML19354E006)
• ML19354E007  + (ML19354E007)
• 05000278/LER-1989-011-03, :on 891213,discovered That Two Surveillance Tests of Turbine Stop & Control Valve Encl Not Performed Per Tech Specs.Caused by Incorrect Std Practice of Surveillance Testing.Programmatic Controls Established  + (ML19354E009)
• 05000277/LER-1989-015, :on 890721,while Attempting to Remove Malfunctioning Reactor Pressure Vessel Regulator Set,Bypass & Control Valves Opened,Causing Steam Line Pressure to Increase to 480 Psig.Components Replaced  + (ML19354E010)
• LIC-89-1206, Forwards Rev to Response to Deviations Noted in Insp Rept 50-285/89-09.Corrective Action:Water Curtains Currently Installed to Protect Doorway Opening from Fan Room Into Turbine Bldg  + (ML19354E011)
• 05000277/LER-1989-032-02, :on 891218,discovered That Weekly Surveillance Test Not Performed within Surveillance Interval.Caused by Inappropriate Action Based on Failure to Follow Procedure. Surveillance Test Coordinator Counseled  + (ML19354E012)
• 05000457/LER-1989-008-10, :on 891228,equipment Attendant Discovered Refueling Water Storage Tank Vent Line Temp Less than 35 F. Caused by Preservice Deficiency.Storage Tank Vent Path Temp Verified at 36 F  + (ML19354E013)
• 05000456/LER-1989-020-04, :on 891223,failure to Verify Safety Injection Accumulator Boron Concentration within Specified Time.Caused by Programmatic Deficiency.Procedure Revised to Include Action Requirement Sheet  + (ML19354E014)
• 05000295/LER-1989-026-02, :on 891214,security Officer Failed to Perform 2,400 Firewatch Surveillance on Svc Water Pump.Caused by Misunderstanding Between Offgoing & Oncoming Officers. Personnel Counseled & Action Taken  + (ML19354E016)
• 05000382/LER-1989-023, :on 890927,MSIV 2MS-124B,determined to Have Broken Stem.Caused by MSIV Hydraulic Control Unit Thermal Valve Leakage.Replacement MSIV Stems W/Increased Blend Radius Designed to Decrease Stress Installed  + (ML19354E017)
• 05000414/LER-1989-020, :on 891118,Tech Spec 3.0.3 Entered & 5-month Auxiliary Bldg Ventilation Sys Inoperability Occurred as Result of Low Filter Exhaust Flow Condition on 891111.Caused by Design Oversight.Duct Will Be Cleaned  + (ML19354E019)
• ML19354E021  + (ML19354E021)
• ML19354E024  + (ML19354E024)
• JPN-90-008, Forwards Application for Amend to License DPR-59,revising Tech Spec Section 4.7.A.2 & Associated Bases Re Primary Containment Leak Rate Testing Requirements  + (ML19354E032)
• ML19354E033  + (ML19354E033)
• JPN-90-011, Forwards Application for Amend to License DPR-59,revising Tech Spec 4.11.B.2, Crescent Area Ventilation to Require Calibr of Existing Temp Indicator Controllers or New Temp Control Switches  + (ML19354E034)
• ML19354E035  + (ML19354E035)
• ML19354E037  + (ML19354E037)
• ML19354E038  + (ML19354E038)
• ML19354E039  + (ML19354E039)
• ML19354E040  + (ML19354E040)
• JAFP-90-0032, Monthly Operating Rept for Dec 1989 for Ja Fitzpatrick Nuclear Power Plant  + (ML19354E041)
• JPN-90-009, Forwards Application for Amend to License DPR-59,revising Tech Specs Re Augmented Inservice Insp of Main Steam & Feedwater Piping Welds.Spec 4.6.F.2, Structural Integrity & Associated Bases on Pages 144 & 153 Deleted  + (ML19354E042)
• ML19354E043  + (ML19354E043)
• ML19354E044  + (ML19354E044)

• ML19354E048  + (ML19354E048)

• ML19354E052  + (ML19354E052)
• JPN-90-007, Forwards Application for Amend to License DPR-59,revising Tech Spec 3.6.A, Pressurization & Thermal Limits, to Comply W/Generic Ltr 88-11 & Reg Guide 1.99,Rev 2  + (ML19354E053)
• ML19354E054  + (ML19354E054)
• ST-HL-AE-3323, Responds to NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors & Discusses Insp of Bottom Mounted Instrumentation.No Detectable Defects Found on Any of 58 Thimbles  + (ML19354E057)
• ML19354E058  + (ML19354E058)
• ML19354E059  + (ML19354E059)
• 05000213/LER-1989-023, :on 891223,fire Barrier Separating Switchgear Room a & Cable Spreading Room Declared Inoperable When Breach in Floor/Ceiling Assembly Discovered.Caused by Inadequate Design Control.Fire Watch Initiated  + (ML19354E068)
• IR 05000298/1989036  + (ML19354E069)
• ML19354E077  + (ML19354E077)
• ML19354E079  + (ML19354E079)
• ML19354E080  + (ML19354E080)
• ML19354E082  + (ML19354E082)
• ML19354E084  + (ML19354E084)
• 05000278/LER-1989-010-03, :on 891211,monthly Surveillance Test ST 9.7 Not Performed within Surveillance Interval Established by Tech Spec Table 4.1.1.Caused by Combination of Programmatic Weaknesses.Review Performed  + (ML19354E085)
• ML19354E090  + (ML19354E090)
• 05000413/LER-1989-025, :on 890922,power Lost to Condenser Circulating Water Cooling Tower Fans Due to Deenergization of 13.8 Kv Auxiliary Switchgear.Caused by Weather Conditions.Reactor Power Reduced to Maintain Condenser Vacuum  + (ML19354E093)
• IR 05000271/1988099  + (ML19354E094)
• 05000440/LER-1989-032, :on 891228 & 900105,HPCS Sys Declared Inoperable Due to Inoperability of Div 3 Battery.Caused by Low Pilot Cell Voltage,Cell W/Slow Electrolyte Leak & Blown Power Fuse.Fuse & Hydromotor Pump Replaced  + (ML19354E096)
• ML19354E098  + (ML19354E098)
• 05000341/LER-1989-037, :on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed.Caused by Personnel Error. Critique of Event Being Developed  + (ML19354E102)
• 05000461/LER-1989-042, :on 891219,false RCIC Div I Steam Line Differential Pressure High Signal Caused RCIC Turbine Steam Supply Isolation Valve to Shut & RCIC Sys to Trip.Caused by Sensor Design Error.Field Alteration Begun  + (ML19354E103)
• PNO-V-90-003, on 900116,earthquake of 5.1 Magnitude Occurred Approx 45 Miles from Facility.Facility Shut Down Since Jul 1976 & Reactor Vessel Defueled.No Damage Identified  + (ML19354E104)
• 05000334/LER-1989-016-01, :on 891215 & 16,erratic Level Transmitter Behavior Caused Steam Generator B hi-hi Level Feedwater Isolation.Caused by Inner Plugs Remaining Partially Inserted After Valves Opened.Plugs Freed from Seats  + (ML19354E107)
• ML19354E111  + (ML19354E111)
• 0CAN019014, Forwards Revised Re long-term Hydrogen Monitoring Capabilities & Relief Requests,Correcting Typos  + (ML19354E112)