05000338/LER-1990-002, :on 900127,fuel Bldg Ventilation Sys Not Aligned to Discharge Through Auxiliary Bldg HEPA Filter & Charcoal Adsorber Assembly During Fuel Movement.Caused by Personnel Error.Disciplinary Action Taken
RA-98-0153, Transmits Description of Rev 0 to Physical Security & Safeguards Contingency Plan, Which Contains Plant Industrial Security Plan & Safeguards Contingency Plan,Per 10CFR72.44(e)
RA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review
RBG-28777, Provides Util 120-day Response to NRC Bulletin 88-005 Including Suppls 1 & 2, Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co at Williamstown,Nj
ST-HL-AE-2683, Forwards Annotated Revs to FSAR Re Redesign of Unit Initial Core to Accomodate Revised Cycle Length of Approx 400 Efpds. Westinghouse Evaluation Concluded That LOCA Analysis Unaffected by Change
05000266/LER-1986-005-01, :on 861117,reactor Tripped Due to Loss of Power on Red Instrument Bus.Caused by Failure of Control Circuit Diode in Bus Inverter.Diodes Replaced
05000271/LER-1987-001, :on 870107,reactor Protection Sys Motor Generator Set Tripped,Resulting in Half Scram & Initiation of ECCS Sys.Caused by Failed Coil on Control Relay Due to End of Life.Coil Replaced
05000259/LER-1988-022-02, :on 880720,spurious Refuel Zone Hi Radiation Causing Containment Isolation Occurred.Caused by Failure of Upscale Logic Relay Coil.Corrective Maint Initiated to Replace Relay & Radiation Monitor Tested
05000528/LER-1986-024, :on 860207,reactor Trip Occurred Due to Low Level Condition in Steam Generator 1.Caused by Operator Error During Transition from Downcomer to Economizer Feed Paths.Event Reviewed by All Licensed Operators
05000482/LER-1985-023, :on 850501,reactor Protection Sys Trip Signal & ESFAS Initiated During Startup Test Procedure in Mode 3. Caused by Personnel Error.Plant Testing Temporarily Suspended.Personnel Counseled
05000483/LER-1990-012, :on 901003,Tech Spec 3.9.2 Violation Occurred Due to Performance of Core Alteration When Source Range Nuclear Instrument Inoperable Due to Personnel Error. W/
05000344/LER-1990-023, :on 900608,determined That Inadequate Temporary Procedure Rev Leads to Failure to Document Verification of Reactor Coolant Flow During Boron Dilution.Procedure Rev Withdrawn & Operating Instruction 3-1 Revised.W/Undtd Ltr
05000483/LER-1990-001, :on 900108,discovered That 24-month Tech Spec Required Local Leak Rate Test Surveillance for Containment Electrical Penetration Had Not Been Performed Since 870917. Caused by Personnel Error.Test Performed
05000311/LER-1989-023-02, :on 891116,radiation Monitoring Sys Channel 2R12A Failed Low Resulting in ESF Actuation Signal.Caused by Poor Pin Contact W/Control Module.Pin Found Bent & Loose. Pushed Pins & Remote Control Module Replaced
DCL-94-060, Forwards Public Version of Revised Epips,Including Rev 17 to EP G-2, Actuation & Operation of Interim Site Emergency Organization (Control Room) & Rev 26 to EP G-3, Notification of Off-Site Agencies...
05000354/LER-2007-001, Re Low Reactor Water Level Scram
NSD-NRC-97-5348, Forwards Assessment on Surge Line Flooding Effect on Low Power & Shutdown Risk in Response to 970905 Telcon Request
B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2