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 Issue dateTitle
05000219/LER-1982-023, Forwards LER 82-023/03L-0.Detailed Event Analysis Encl20 May 1982Forwards LER 82-023/03L-0.Detailed Event Analysis Encl
05000219/LER-1982-033, Forwards LER 82-033/03L-0.Detailed Event Analysis Encl13 July 1982Forwards LER 82-033/03L-0.Detailed Event Analysis Encl
05000219/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl15 February 1983Forwards LER 83-003/03L-0.Detailed Event Analysis Encl
05000219/LER-2007-001Automatic Reactor Scram Following Trip of Reactor Feed Pump
ENS 43495Automatic Reactor Scram on Low Reactor Vessel Water Level (Rvwl)
IR 05000219/198501924 July 1985Insp Rept 50-219/85-19 on 850603-30.No Violations Noted. Major Areas Inspected:Operations,Physical Security,Radiation Control,Housekeeping,Chemistry,Surveillances & Hanger Insps
IR 05000219/19850237 October 1985Insp Rept 50-219/85-23 on 850701-0818.Violations Noted: Improper Closure of Containment Isolation Valve & Failure to Follow Procedures While Inerting Drywell
IR 05000219/198502912 November 1985Insp Rept 50-219/85-29 on 850923-1020.No Violation Noted. Major Areas Inspected:Plant Operations,Physical Security, Radiation Control,Housekeeping,Equipment Surveillances & Preparations for Upcoming 1-month Outage
IR 05000219/198603524 November 1986Insp Rept 50-219/86-35 on 861026-29.No Violations or Deviations Noted.Major Areas Inspected:Preliminary Results Evaluation of Containment Integrated Leak Rate Test & Final Results Evaluation of Local Leak Rate Test
IR 05000219/19870138 July 1987Insp Rept 50-219/87-13 on 870420-23 & 0507-0618.Major Areas Inspected:Plant Operations,Radiation Control,Physical Security,Forced Shutdown Work Activities,Open Insp & NUREG-0737 Action Items & Core Spray & Svc Water Problem
IR 05000219/198702225 September 1987Insp Rept 50-219/87-22 on 870619-0809.No Violations Noted. Major Areas Inspected:Plant Operations,Radiation Control, Physical Security,Surveillance & Maint,Followup of Causes for Reactor Trip
IR 05000219/198703530 November 1987Insp Rept 50-219/87-35 on 871017-27.No Violations or Deviations Noted. Major Areas Inspected:Test Witnessing & Preliminary Results Evaluation of Containment Integrated Leak Rate Test
IR 05000219/19880046 May 1988Insp Rept 50-219/88-04 on 880207-0319.Violations Noted.Major Areas Inspected:Activities in Progress,Including Plant Operation,Physical Security,Radiation Control,Housekeeping, Fire Protection & Emergency Preparedness
IR 05000219/198801726 July 1988Insp Rept 50-219/88-17 on 880613-17.No Violations Noted. Major Areas Inspected:Previously Identified Findings,Spds & Planned Mods to Institute Corrective Measures to Satisfy ATWS
IR 05000219/199202324 December 1992Insp Rept 50-219/92-23 on 921103-1214.No Violations Noted. Major Areas Inspected:Plant Operations,Security & Safety Assessment/Quality Verification
IR 05000219/200400531 January 2005IR 05000219-04-005 on 10/01/04 -12/31/04 for Oyster Creek Generating Station; Event Follow-up and Access Control to Radiologically Significant Areas
IR 05000219/200700429 October 2007
IR 05000219/20070066 July 2007IR 05000219-07-006, on 04/17/2007 - 05/24/2007; Amergen Energy Company, LLC; Oyster Creek Generating Station; Component Design Bases Inspection
IR 05000219/200800331 July 2008IR 05000219-08-003; Amergen Energy Company, LLC; 04-01-08 - 06-30-08; Oyster Creek Integrated Inspection Report
IR 05000219/200900926 September 2009IR 05000219-09-009, on 07/16/2009 - 08/14/2009, Exelon Generation Company, LLC, Oyster Creek Nuclear Generating Station, Special Inspection for July 12, 2009, Reactor Scram, Inspection Procedure 93812, Special Inspection
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML0326000094 September 2003Revision 5 to 1820-IMP-1720.01, Emergency Public Information Implementing Procedure.
ML0335603029 December 2003Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability.
ML0526503888 September 2005Submittal of Revised Emergency Response Data Library
ML06055028514 August 1992Response to Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities (IPE)
ML0634601217 December 2006Attachment 7, Amergen Response to the Request for Additional Information Regarding the Oyster Creek Generating Station EAL Revision, EP-OC-1010
ML06354008614 December 2006Oyster Creek - Exelon/Amergen Supplement to Submittal to Revise Plant Emergency Action Levels Developed from NEI 99-01
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML07199042817 July 2007PNO-I-07-006: Reactor Scram on Low Reactor Vessel Water Level Due to a Trip of the C Reactor Feed Pump
ML0806704197 March 2008CDBI Findings
ML10202037125 June 2009Assignment Report #00907846
ML11187027426 May 2011Draft Written Exam (Folder 2)
ML1121305286 July 2011Final Written Examination with Answer Key (401-5 Format) (Folder 2)
ML14163A38613 May 2014Final Written Examination with Answer Key (405-5 Format) (Folder 3)
ML14167A2982 April 2014Draft Outlines (Folder 2)
ML14167A3682 April 2014Draft Written Exam (Folder 2)
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