RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
BVY 13-078, Submittal of Snubber Program for the Fifth Ten-Year Inservice Inspection Interval
RA-12-004, Revised Annual Radioactive Effluent Release Report for 2008
RA-12-004, Oyster Creek, Revised Annual Radioactive Effluent Release Report for 2007
RA-12-004, Oyster Creek - Revised Annual Radioactive Effluent Release Report for 2006
RA-10-002, Oyster Creek, Revised 2008 Annual Radioactive Effluent Release Report
RA-10-002, Oyster Creek, Annual Radioactive Effluent Release Report for 2009
RA-09-033, Annual Radioactive Effluent Release Report, January 1 Through December 31, 2008
RA-08-017, Independent Spent Fuel Storage Facility, Annual Radioactive Effluent Release Report for 2007
HL-4587, Application for Amends to Licenses DPR-57 & NPF-5,lowering ATWS-RPT Setpoint & Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained
B17393, Withdraws 960702 Proposed License Amend Request Re Changes to TS 3.6.E, Safety Relief Valves. No New Commitments Are Contained in Ltr
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
05000333/LER-1998-002, :on 980311,determined That Two of Four SRVs Were Outside Tolerance Allowed by TS SR 4.6.E.Caused by Corrosion Bonding Between SRV Pilot Disc & Seat.Removed Four Pilot Assemblies & Replaced W/Steam Certified Assemblies
05000282/LER-1982-020-03, /03L-0:on 821026,during Surveillance Test, Auxiliary Bldg Special Vent Sys Pac Filter 121 Exhibited DOP Removal Efficiency of 98.6%,less than Tech Specs Requirement.Caused by Loose Filters.Filters Tightened
05000333/LER-1982-037-03, /03L-0:on 820730,during Ascension to Power, Abnormally High Tail Piece Temps Indicated on Interim Target Rock Model Safety Relief Valve F.Probably Caused by Valve Leakage from Pilot Seat.Daily Surveillance Initiated
05000321/LER-1993-013, :on 931022,trip of Condensate Pump Resulted in Decrease in Reactor Water Level & Manual Scram.Caused by Spurious Actuation of Hotwell Level Instrument Due to Intermittent Vibration.Mod Implemented
NG-93-2104, Application for Amend to License DPR-49,consisting of Request for TS Change (RTS-197A),correcting Errors & Improving Consistency of Rewrite of TS Section 3.6, Primary Sys Boundary
05000282/LER-1981-027-03, /03L-0:on 811116,discovered That Pre,Absolute & Charcoal Filter Test Not Done on 11 Shield Bldg Ventilation Sys Replacement on 811112.Caused by Procedural Inadequacies & Poor Communications
05000306/LER-1980-034-03, /03L-0:on 801031,auxiliary Bldg Special Vent Exhaust Fan 122 Tripped.Caused by Actuation of Thermal Overload Protective Device.Device Replaced
05000282/LER-2002-001, Condition Prohibited by Technical Specifications Due to Potential Auxiliary Building Special Vent Zone Boundary Degradation