AEP-NRC-2013-25, Annual Radioactive Effluent Release Report
JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
HL-4781, Submits Addl Info Requested by NRC Re Recent Core Shroud Mod on Plant Unit 1
NG-95-0554, Notifies NRC of Changes to Plant TS Bases,Deleting Ref to Outdated Surveillance Requirements for Containment H & O Analyzers
05000277/LER-1989-011, :on 890424,scram Discharge Vol Drain & Vent Valve Stroking Surveillance Test Not Performed.Caused by Procedural Deficiency & Scheduling Error.Surveillance Test Completed Satisfactorily on 890429
05000412/LER-1989-024, :on 890815,high Radiation Alarm Caused Steam Generator Isolation Valve Closure & ESF Actuation.Caused by Flow Adjustment Dislodging Residual Activity.Radiation Monitor Flushed & Steam Generator Restored
05000338/LER-1989-012-01, :on 890626,emergency Diesel Generator Inadvertently Started During Performance of Reactor Protection & ESF Response Time Testing.Caused by Personnel Error.Personnel Counseled
A98033, Monthly Operating Repts for Mar 1998 for Zion Station,Units 1 & 2
05000275/LER-1986-019-01, :on 861212,operators Failed to Comply W/Tech Specs by Opening Containment Ventilation Isolation Valves FCV-662 & 664 While Radiation Monitor RM-14B Inoperable. Caused by Procedural Deficiency
05000328/LER-1988-022, :on 880519,10CFR Unqualified Butt Splice Found on Steam Generator Level Transmitter Causing Condition Outside Plant Design Basis.Caused by Not Changing Splice When Specs Changed.Unqualified Splice Replaced
BSEP-88-0471, Monthly Operating Rept for Apr 1988
0CAN028804, Responds to NRC Compliance Bulletin 87-002 & Provides Results of Fastener Testing to Determine Conformance W/ Applicable Matl Specs,Per Bulletin.Related Documentation Encl
05000249/LER-1985-019-07, :on 850923,observed That Reactor Not Vented at Less than 149 F.Caused by Failure of Shutdown Procedure to Completely Outline Conditions to Vent Reactor.Reactor Head Vents Opened
U-601216, Forwards Addl Info Re Main Steam Line Turbine Bldg Temp Instrument Change Request,Per NRC 880623 Telcon
05000413/LER-1985-044, :on 850622,steam Generator lo-lo Level Reactor Trip Occurred.Caused by Main Feedwater Pump Turbine Speed Increasing W/O Proper Mode Due to Miscommunication.Sys Affected Returned to Normal Alignment
05000278/LER-1992-002, :on 920117,discovered That DW Oxygen Concentration Level Exceeded Value Specified in Ts,Due to an Analyzer Failure.Round Sheets Have Been Revised to Include Instrument Nitrogen Compressor Run Times
05000483/LER-1992-011, :on 921017,four Field Contact Power Supply Output Fuses Blew Causing All Mcb Annunciators Inoperable. Caused by Short in Power Transformer.Mod Will Be Evaluated to Improve Reliability of Rk Sys
05000266/LER-1990-002-02, :on 910419,degradation of Steam Generators Tubes Occurred.Cause Unknown.Util Will Monitor Tube Integrity in Each Steam Generator & Plug Tubes Which Exceed or Approach Plugging Limit in Tech Spec
05000298/LER-1991-014, :on 911030,unplanned Actuation of Group 6 Isolation Occurred.Caused by Improper Selection of Uninsulated Metal Clip for Surveillance Testing.Uninsulated Metal Clips Replaced During Refueling Outage
05000277/LER-1991-020, :on 910607,two Diesel Generators Discovered Inoperable Due to Mispositioned Valve.Caused by Personnel Error.Valve Immediately Restored & Involved Operator & Chemist Counseled
05000341/LER-1991-009, :on 910429,loss of Power to Bus 65F Occurred Due to Mispositioned Knife Switch.Procedure 42.302.06 & Similar Electrical Surveillance Procedures Will Be Revised as Needed No Later than Sept 1991
05000029/LER-1990-007, :on 900927,incore Instrumentation Spire Failure Resulted in Pressure Boundary Leakage
05000336/LER-1981-043-03, /03L-0:on 811209,during Mode 5 W/Rcs at Atmospheric Pressure,Lpis Pump Tripped.Caused by Actuation of Trip Circuitry by Switchyard Breaker Testing.Design Basis Limitations Not Degraded
05000254/LER-1990-001, :on 891208,seven Pathways Not Included in Type B & C Local Leak Rate Testing Program.Caused by Misinterpretation of 10CFR50,App J Testing Requirements.Mod of Sys to Be Performed as Necessary
DD-80-22, Order Granting Extension Until 800811 for Commission to Review Directors Decision Under 10CFR2.206,DD-80-22. Certificate of Svc Encl
A06692, Informs of Payment to Ofc of Resource Mgt for Encl Invoices 1507A,1511A,1527A & 1532A
05000260/LER-1989-018, :on 890606,diesel Generator a Declared Inoperable Resulting in Inoperability of RHR 2A Pump & Failure to Comply W/Tech Specs.Caused by Failure to Detect Damage from Corrosion Debris