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| Issue date | Title | |
|---|---|---|
| NMP1L3095, License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03 | 1 August 2016 | License Amendment Request - Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03 |
| ML15016A152 | 13 May 2014 | Final Outlines (Folder 3) |
| ML14163A386 | 13 May 2014 | Final Written Examination with Answer Key (405-5 Format) (Folder 3) |
| ML14167A368 | 2 April 2014 | Draft Written Exam (Folder 2) |
| ML14167A298 | 2 April 2014 | Draft Outlines (Folder 2) |
| ML112130528 | 6 July 2011 | Final Written Examination with Answer Key (401-5 Format) (Folder 2) |
| ML111870274 | 26 May 2011 | Draft Written Exam (Folder 2) |
| IR 05000219/2009009 | 26 September 2009 | IR 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 |
| ML102020371 | 25 June 2009 | Assignment Report #00907846 |
| IR 05000219/2008003 | 31 July 2008 | IR 05000219-08-003; Amergen Energy Company, LLC; 04-01-08 - 06-30-08; Oyster Creek Integrated Inspection Report |
| ML080670419 | 7 March 2008 | CDBI Findings |
| IR 05000219/2007004 | 29 October 2007 | |
| PNO-I-07-006, A - NRC Resident Inspector - Update - Reactor Scram on Low Reactor Vessel Water Level Due to a Trip of the 'C' Reactor Feed Pump | 23 July 2007 | PNO-I-07-006A - NRC Resident Inspector - Update - Reactor Scram on Low Reactor Vessel Water Level Due to a Trip of the 'C' Reactor Feed Pump |
| ML071990428 | 17 July 2007 | PNO-I-07-006: Reactor Scram on Low Reactor Vessel Water Level Due to a Trip of the C Reactor Feed Pump |
| IR 05000219/2007006 | 6 July 2007 | IR 05000219-07-006, on 04/17/2007 - 05/24/2007; Amergen Energy Company, LLC; Oyster Creek Generating Station; Component Design Bases Inspection |
| ML063540086 | 14 December 2006 | Oyster Creek - Exelon/Amergen Supplement to Submittal to Revise Plant Emergency Action Levels Developed from NEI 99-01 |
| ML063460121 | 7 December 2006 | Attachment 7, Amergen Response to the Request for Additional Information Regarding the Oyster Creek Generating Station EAL Revision, EP-OC-1010 |
| ML052650388 | 8 September 2005 | Submittal of Revised Emergency Response Data Library |
| IR 05000219/2004005 | 31 January 2005 | IR 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 |
| RS-04-160, Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports | 21 October 2004 | Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports |
| ML033560302 | 9 December 2003 | Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability. |
| ML032600009 | 4 September 2003 | Revision 5 to 1820-IMP-1720.01, Emergency Public Information Implementing Procedure. |
| ML20211B901 | 18 August 1999 | Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure |
| Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
| NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
| ML20203B278 | 16 February 1998 | 10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures |
| Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
| Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
| Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
| ML20129C061 | 10 October 1996 | Application for Amend to License DPR-16,clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization |
| Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
| Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
| Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
| ML20091R699 | 31 August 1995 | Requests That NRC Review Encl Status of Resolution of Nuclear Industry Safety Issues Re Nuclear Plants in Nj |
| Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
| ML20057D997 | 29 September 1993 | Informs That Licensee 930922 Submittal of Revised Schedule for Installing Mod to Reactor Vessel Water Level Instrumentation,Per GL 92-04 & NRC Bulletin 93-03, Acceptable |
| ML20057C748 | 22 September 1993 | Informs That Util Will Make Reactor Vessel Water Level Instrumentation Mod During Planned Outage Scheduled to Begin in Sept 1994,in Accordance W/Gl 92-04 & Requests NRC Concurrence |
| ML20057B684 | 20 September 1993 | Discusses 930614 Response to GL 92-04 & NRC Bulletin 93-03 Re Resolution of Issues Re Reactor Vessel Water Level Instrumentation in Bwrs.Util Response to GL Unacceptable. Subj Instrumentation Should Be Modified During Next Outage |
| ML20056H132 | 31 August 1993 | Forwards Summary of Changes to Sys & Procedures Described in SAR for Period Jan 1992 - Mar 1993,per 10CFR50.59(b) |
| Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
| ML20056E091 | 4 August 1993 | SE Re Util 930614 Response to Bulletin 93-03, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs. Util Justification for Not Implementing Addl Short Term Actions Acceptable |
| ML20056E086 | 4 August 1993 | Forwards SE Re Util 930614 Response to Bulletin 93-03, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs. Short Term Actions Requested by Bulletin Do Not Apply to Plant Configuration & Not Needed |
| ML20046B153 | 30 July 1993 | Addresses Long Term Corrective Actions in Response to Generic Ltr 92-04 |
| ML20056C545 | 14 June 1993 | Responds to NRC Bulletin 93-003, Resolution of Issues Related to Rv Water Level Instrumentation in Bwrs, Including Summary of Rv Water Level Measurement Capability & Plans Re Errors in Rv Water Level Indication |
| Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
| ML20128P405 | 18 February 1993 | Ack Receipt of 920929 Response to GL 92-04, Resolution of Issues Re Rv Water Level Instrumentation in Bwr. Lists What Staff Finds Acceptable |
| PNO-I-93-006, on 930125,licensee Notified NRC That Reactor Vessel Core Temp Exceeded 212 Degrees F During Shutdown Cooling Operations.No Core Damage or Radioactive Release Occurred.Inspectors Reviewing Event.State of Nj Notified | 26 January 1993 | PNO-I-93-006:on 930125,licensee Notified NRC That Reactor Vessel Core Temp Exceeded 212 Degrees F During Shutdown Cooling Operations.No Core Damage or Radioactive Release Occurred.Inspectors Reviewing Event.State of Nj Notified |