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 Issue dateTitle
ML18221A4969 August 2018NRR 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 Scheme29 August 2017License 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 E22 August 2017Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E
ML16239A04426 August 2016Seventh 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 Disclosure26 May 2016Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure
ML16209A02226 May 2016Transcript of Oyster Creek 2016 Annual Assessment Meeting, May 26, 2016, Pages 1-111
ML15069A11217 April 2015G20110563 - Licensee Letter Regarding Draft Director'S Decision to Licensee'S with Mark I and II Containment Design
ML12215A31417 April 2015Proposed Director'S Decision - 2.206 Petition Re Boiling Water Reactors with Mark I and Mark II Containment Designs
ML12215A28317 April 2015G20110563 - LTR to Lochbaum -- Draft Director'S Decision Re 2.206 Petition Re Boiling Water Reactors with Mark I and Mark II Containment Designs
ML14177A64527 June 2014Applications 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 Walkdowns27 November 2013Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13120A1869 April 2013Enclosure 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-
ML13059A27128 February 2013Overall 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)
ML12359A0086 November 2012Rev. 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 05000219/20100087 October 2010IR 05000219-10-008, on 08/03/2010 - 08/27/2010; Exelon Energy Company, LLC, Oyster Creek Generating Station; Component Design Bases Inspection
ML07285105920 July 2007Oyster 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
ML07204010920 July 2007NRC Staff Initial Statement of Position on the Drywell Contention, with Attachments
ML07151042025 April 20074/25/2007 - New Jersey Department of Environmental Protection, Petitioner V. U.S. NRC; Docket No. 07-2271
ML07057051126 February 2007Commission Memorandum and Order (CLI-07-08)
ML06265005921 September 2006IR 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
ML07261061421 September 2006Oyster Creek - Staff Exhibit 5 to the NRC Staff Response to Rebuttal Presentations
ML0609605687 April 20062006/04/07-Oyster Creek, License Renewal AMP-AMR Audit Questions AMP-210 Set 2
ML0335603029 December 2003Exelon/Amergen 180-Day Response to NRC Generic Letter 2003-01, Control Room Habitability.
ML0101102528 February 2001Review of Oyster Creek Nuclear Generating Station (Oyster Creek) Individual Plant Examination of External Events (IPEEE) Submittal (Tac No. M83652)
IR 05000219/199601027 September 1996Insp 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
ML20078E5789 November 1994Rev 0 to Safety Evaluation SE-403037-001, Reactor Vessel Shroud Repair
ML20072K56024 August 1994Submits Response to NRC GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs. W/One Oversize Drawing
ML20101H15322 June 1992Forwards Summaries of Changes to Sys & Procedures for Period of Jan-Dec 1991,as Described in SAR
ML20029B38628 February 1991ASME Section Viii Evaluation of Oyster Creek for W/O Sand Case,Part I,Stress Analysis.
ML20065M10230 November 1990Rev 0 to Index 9-1, ASME Section Viii Evaluation of Oyster Creek Drywall Part 1 Stress Analysis
IR 05000219/198602430 October 1986Insp 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 05000219/198601224 October 1986Enforcement 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
ML20028F61331 August 1982Seismic Analysis of Reactor Vessel Internals.
ML19296D06922 February 1980Summarizes 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
ML20084C71216 September 1974Preliminary 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
ML19343C35429 May 1974AO 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
ML20084D20520 May 1974AO 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
ML20003C72218 March 1974AO 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