Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
ML18221A496 | 9 August 2018 | NRR E-mail Capture - for Your Comments - State of New Jersey - Oyster Creek License Amendment Request Regarding Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition |
RA-17-049, License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme | 29 August 2017 | License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme |
RA-17-048, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E | 22 August 2017 | Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E |
ML16239A044 | 26 August 2016 | Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) |
RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure | 26 May 2016 | Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure |
ML16209A022 | 26 May 2016 | Transcript of Oyster Creek 2016 Annual Assessment Meeting, May 26, 2016, Pages 1-111 |
ML15069A112 | 17 April 2015 | G20110563 - Licensee Letter Regarding Draft Director'S Decision to Licensee'S with Mark I and II Containment Design |
ML12215A314 | 17 April 2015 | Proposed Director'S Decision - 2.206 Petition Re Boiling Water Reactors with Mark I and Mark II Containment Designs |
ML12215A283 | 17 April 2015 | G20110563 - LTR to Lochbaum -- Draft Director'S Decision Re 2.206 Petition Re Boiling Water Reactors with Mark I and Mark II Containment Designs |
ML14177A645 | 27 June 2014 | Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations |
RA-13-109, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns | 27 November 2013 | Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns |
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- |
ML13059A271 | 28 February 2013 | Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Hardened Containment Vents (Order Number EA-12-050) |
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 |
IR 05000219/2010008 | 7 October 2010 | IR 05000219-10-008, on 08/03/2010 - 08/27/2010; Exelon Energy Company, LLC, Oyster Creek Generating Station; Component Design Bases Inspection |
ML072851059 | 20 July 2007 | Oyster Creek September 2007 Evidentiary Hearing - Staff Exhibit B, NRC Staff Testimony of Hansraj G. Ashar, Dr. James Davis, Dr. Mark Hartzman and Timothy L. O'Hara Concerning Drywell Contention |
ML072040109 | 20 July 2007 | NRC Staff Initial Statement of Position on the Drywell Contention, with Attachments |
ML071510420 | 25 April 2007 | 4/25/2007 - New Jersey Department of Environmental Protection, Petitioner V. U.S. NRC; Docket No. 07-2271 |
ML070570511 | 26 February 2007 | Commission Memorandum and Order (CLI-07-08) |
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 |
ML060960568 | 7 April 2006 | 2006/04/07-Oyster Creek, License Renewal AMP-AMR Audit Questions AMP-210 Set 2 |
ML033560302 | 9 December 2003 | Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability. |
ML010110252 | 8 February 2001 | Review of Oyster Creek Nuclear Generating Station (Oyster Creek) Individual Plant Examination of External Events (IPEEE) Submittal (Tac No. M83652) |
IR 05000219/1996010 | 27 September 1996 | Insp Rept 50-219/96-10 on 960923-27.No Violations Noted. Major Areas Inspected:Radiological Source Term Assessment, Results of Exposure Reduction Initiatives & Evidence of Station ALARA Program |
ML20078E578 | 9 November 1994 | Rev 0 to Safety Evaluation SE-403037-001, Reactor Vessel Shroud Repair |
ML20072K560 | 24 August 1994 | Submits Response to NRC GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs. W/One Oversize Drawing |
ML20101H153 | 22 June 1992 | Forwards Summaries of Changes to Sys & Procedures for Period of Jan-Dec 1991,as Described in SAR |
ML20029B386 | 28 February 1991 | ASME Section Viii Evaluation of Oyster Creek for W/O Sand Case,Part I,Stress Analysis. |
ML20065M102 | 30 November 1990 | Rev 0 to Index 9-1, ASME Section Viii Evaluation of Oyster Creek Drywall Part 1 Stress Analysis |
IR 05000219/1986024 | 30 October 1986 | Insp Rept 50-219/86-24 on 860818-1005.Violation Noted: Failure to Perform Written Safety Evaluation Prior to Implementing Procedure Change Requiring Deactivation of Automatic Initiation Feature of Isolation Condenser Sys |
IR 05000219/1986012 | 24 October 1986 | Enforcement Conference Rept 50-219/86-12 on 860912.Major Items Discussed:Findings Detailed in Insp Rept 50-219/86-12 Re Inoperability of Four Snubbers Required by Tech Specs to Be Operable |
ML20028F613 | 31 August 1982 | Seismic Analysis of Reactor Vessel Internals. |
ML19296D069 | 22 February 1980 | Summarizes Results of Insp to Determine Support Capability of Seismic & Nonseismic safety-related Electrical Equipment. Some Addl Bracing Needed to Upgrade Class II Duct Supports & Class I Seismic Requirements.Addl Supports Also Required |
ML20084C712 | 16 September 1974 | Preliminary AO 50-219/74/47:on 740912,two Bergen-Paterson Hydraulic Shock & Sway Arrestor on South Core Spray Sys Found Inoperable.Caused by Component Failure.Two Snubbers Replaced W/Units Rebuilt W/Ep Seals |
ML19343C354 | 29 May 1974 | AO 50-219/74/31:on 740519,Bergen-Paterson Hydraulic Shock & Sway Arrestor Located on South Core Spray Sys Found Inoperable.Caused by Loss of Hydraulic Fluid.Units Replaced W/Units Equipped W/Emergency Preparedness Seals |
ML20084D205 | 20 May 1974 | AO 50-219/74/31:on 740519,one Bergen-Paterson Hydraulic Shock & Sway Arrestor on South Core Spray Sys Found Inoperable.Caused by Loss of Hydraulic Fluid.Seven Units Replaced W/Units Equipped W/Ep Seals |
ML20003C722 | 18 March 1974 | AO 50-219/74/18:on 740308,w/plant Shutdown,Insp of Drywell Snubbers Located Three Inoperable & Four Leaking.Caused by Loss of Hydraulic Fluid.Units Replaced W/Identical Snubbers Rebuilt W/Ethylene Propylene Seals |