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| Issue date | Title | |
|---|---|---|
| NEI 99-04, Oyster Creek Nuclear Generating Station - Commitment Change Summary Report - 2017 | 21 December 2017 | Oyster Creek Nuclear Generating Station - Commitment Change Summary Report - 2017 |
| RA-17-086, Commitment Change Summary Report - 2017 | 21 December 2017 | Commitment Change Summary Report - 2017 |
| 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 |
| ML14275A162 | 25 September 2014 | Notification of Potential Part 21 Report - Electromatic Relief Valve Excessive Wear |
| ML14065A232 | 16 June 2014 | Staff Assessment of Response to Enclosure 4 of the March 12, 2012, 10 CFR 50.54(F) Information Request - Flooding Walkdowns |
| ML14084A110 | 23 April 2014 | Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac MF0152) |
| RA-14-016, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.. | 31 March 2014 | Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.. |
| ML13277A223 | 9 January 2014 | Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident TAC No. MF0256) |
| RS-12-177, E Plan for Future Seismic Walkdown of Inaccessible Equipment | 26 April 2013 | E Plan for Future Seismic Walkdown of Inaccessible Equipment |
| ML13120A185 | 26 April 2013 | Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident |
| ML13120A186 | 9 April 2013 | Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal # 1 for the Oyster Creek Generating Station Correspondence No. RS- |
| RA-12-117, Company, Llc'S 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 19 November 2012 | Company, Llc'S 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident |
| ML12359A008 | 6 November 2012 | Rev. 1 to Report 12Q0108.80-R-001,Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Oyster Creek Generating Station Unit 1. Part 1 of 4 |
| ML12056A050 | 12 March 2012 | Enclosure 4 - Recommendation 2.3: Flooding |
| ML12056A049 | 12 March 2012 | Enclosure 3 - Recommendation 2.3: Seismic |
| ML12053A340 | 12 March 2012 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident |
| 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 |
| ML062650059 | 21 September 2006 | IR 05000219-06-007; Amergen Energy Company; 03/13-17/2006 03/27-31/2006; Oyster Creek Generating Station; Inspection of the Scoping of Non-Safety Systems and the Proposed Aging Management Procedures for Application for Renewed License |
| ML072610614 | 21 September 2006 | Oyster Creek - Staff Exhibit 5 to the NRC Staff Response to Rebuttal Presentations |
| IR 05000219/2006006 | 20 June 2006 | IR 05000219-06-006, on 04/24/2006 - 05/19/2006, Oyster Creek; Biennial Baseline Inspection of the Identification and Resolution of Problems |
| RS-05-006, Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License | 25 February 2005 | Nuclear/Amergen, Proposed Changes to Delete the Reporting Requirement Section of the Facility Operating License |
| RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program | 29 November 2004 | Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program |
| Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures | 9 July 1997 | Inadequate or Inappropriate Interim Fire Protection Compensatory Measures |
| ML20129J588 | 25 October 1996 | Memorandum & Order (Ruling on Intervention Petition).* NRC Denies Citizens Awareness Network & Oyster Creek Nuclear Watch Request & Petition to Intervene Seeking to Challenge Proposed TS Change.W/Certificate of Svc.Served on 961025 |
| ML20129B009 | 7 August 1996 | Intervenor Exhibit I-NIRS-1,consisting of Comments Before ASLB Prehearing Conference on Behalf of Petitioners Nirs, Ocnw & Can.Sumitted by Petitioner |
| ML20116A921 | 18 July 1996 | Supplemental Petition of Nuclear Info & Resources Svc,Oyster Creek Nuclear Watch & Citizens Awareness Network.* Petitioners Assert That NUREG-0612 Can Be Relied on to Support Allegations.W/Certificate of Svc |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| IR 05000219/1993081 | 22 December 1993 | Insp Rept 50-219/93-81 on 930927-1015.Violations Noted.Major Areas Inspected:Engineering,Maint,Surveillance & Mgt & Corrective Actions |
| NRC Generic Letter 1992-02 | 6 March 1992 | NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown. |
| ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability |
| Information Notice 1991-38, Thermal Stratification in Feedwater System Piping | 13 June 1991 | Thermal Stratification in Feedwater System Piping |
| ML20248C912 | 27 September 1989 | Responds to Violations Noted in Insp Rept 50-219/89-16. Corrective Actions:Containment Analysis Performed to Ascertain Impact of 90 F Intake Canal Water Temp on Containment Response Curves |
| ML20246J596 | 24 August 1989 | Forwards Safety Insp Rept 50-219/89-16 on 890702-29 & Notice of Violation.Attention Required to Ensure Engineering Evaluations of Potential Safety Problems Performed |
| ML20246J610 | 24 August 1989 | Notice of Violation from Insp on 890702-29.Violations Noted: from Jul 1988 to Jul 1989,plant Operated W/Intake Canal Water Temp Above 85 F & Failure to Take Action to Prevent Uncontrolled/Unguarded High Radiation Areas |
| ML20246J626 | 18 August 1989 | Insp Rept 50-219/89-16 on 890702-29.Violations Noted.Major Areas Inspected:Plant Operational Events,Control of High Radiation Areas,Evaluation of Plant Operation W/High Canal Water Temps & Security Response to Vital Area Door Problem |
| Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break | 30 June 1989 | Degradation of Containment Isolation Capability by a High-Energy Line Break |
| ML20247R212 | 31 May 1989 | Responds to NRC Re Violations Noted in Insp Rept 50-219/88-202 Concerning Safety Sys Outage Mod Insp. Corrective Actions:Calculation 1302-826-5360-001 Revised to Include Transmission Loads from Adjacent Areas |
| IR 05000219/1988202 | 1 February 1989 | SSOMI Rept 50-219/88-202 on 881017-20 & 1031-1104.Major Areas Inspected:Detailed Design & Engineering Required to Support Mods Implemented During Outage.Weakness Noted Re Design Input for HVAC Sys Heat Loads |
| ML20206G755 | 31 October 1988 | Monthly Operating Rept for Oct 1988 for Oyster Creek Nuclear Generating Station |
| IR 05000219/1988080 | 28 October 1988 | Augmented Insp Team Rept 50-219/88-80 on 881005-13.Major Areas Inspected:Circumstances Surrounding Steaming Phenomenon on Both Isolation Condensers in Late Aug & Sept 1988 & Electrical Fault on Diesel Generator 2 on 881002 |
| ML20207M077 | 5 October 1988 | Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl |
| ML20148G748 | 29 February 1988 | Monthly Operating Rept for Feb 1988 |
| Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 |
| Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 |
| ML20236P284 | 5 November 1987 | Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl |
| ML20235J180 | 22 September 1987 | Responds to Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $205,000.Corrective Actions: Temporary Variation Revoked & Vacuum Breaker Valves Restored to Operable Status.Penalty Paid |
| ML20238A004 | 24 August 1987 | Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $80,000.Noncompliance Noted:On 870424,change Made at Facility as Described in Updated SAR Resulted in Condition Contrary to Tech Specs |
| ML20237L789 | 24 August 1987 | Discusses Insp on 870424-0506 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty |
| NRC Generic Letter 1987-12 | 9 July 1987 | NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled |