05000219/LER-1998-011, :on 980914,three Small Bore Pipe Lines Did Not Meet Design Bases for Seismic & Thermal Allowables.Caused by Inadequate Structural Piping Analysis.Two 1/2 Sdcs Lines Were Modified During 17R RFO & 3rd Was Modified During 19991999-09-30030 September 1999
- on 980914,three Small Bore Pipe Lines Did Not Meet Design Bases for Seismic & Thermal Allowables.Caused by Inadequate Structural Piping Analysis.Two 1/2 Sdcs Lines Were Modified During 17R RFO & 3rd Was Modified During 1999
ML20216H5141999-09-24024 September 1999
Safety Evaluation Supporting Amend 209 to License DPR-16
ML20211P6731999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With
ML20211A7051999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With
05000219/LER-1999-001, :on 990208,prolonged Operation of TB with Condenser & Heater Bay Pressure Less than Design Was Noted. Caused by Lack of Clearly Documented Design Description. Placed Alternate Exhaust Fan in Service.With1999-07-29029 July 1999
- on 990208,prolonged Operation of TB with Condenser & Heater Bay Pressure Less than Design Was Noted. Caused by Lack of Clearly Documented Design Description. Placed Alternate Exhaust Fan in Service.With
ML20209G0631999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With
05000219/LER-1999-004, :on 990510,determined That Configurations of Two Pipe Supports in Spent Fuel Pool Cooling Sys Do Not Meet Design Requirements for Deadweight Loads.Caused by Inadequate Analysis.Pipes Upgraded.With1999-06-22022 June 1999
- on 990510,determined That Configurations of Two Pipe Supports in Spent Fuel Pool Cooling Sys Do Not Meet Design Requirements for Deadweight Loads.Caused by Inadequate Analysis.Pipes Upgraded.With
ML20212H5491999-06-18018 June 1999
Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool
ML20195C8141999-06-0202 June 1999
Safety Evaluation Supporting Amend 208 to License DPR-16
ML20195E7961999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With
ML20206U9511999-05-18018 May 1999
Safety Evaluation Supporting Amend 207 to License DPR-16
ML20206P0241999-05-13013 May 1999
Safety Evaluation Supporting Amend 206 to License DPR-16
ML20206P0881999-05-12012 May 1999
Safety Evaluation Supporting Amend 205 to License DPR-16
ML20206N7431999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With
05000219/LER-1999-003, :on 990402,cable Trays Did Not Meet Separation Criteria.Caused by Inadequate Engineering Review.Fire Watch Was Stationed Immediately Upon Discovery.With1999-04-30030 April 1999
- on 990402,cable Trays Did Not Meet Separation Criteria.Caused by Inadequate Engineering Review.Fire Watch Was Stationed Immediately Upon Discovery.With
05000219/LER-1999-002-01, :on 990330,fire Protection Deluge Sys Isolation Valve Was Found Out of Position.No Root Cause Determined. Technical Assessment Was Performed.With1999-04-29029 April 1999
- on 990330,fire Protection Deluge Sys Isolation Valve Was Found Out of Position.No Root Cause Determined. Technical Assessment Was Performed.With
ML20205P5401999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With
ML20205A7451999-03-17017 March 1999
Safety Evaluation Supporting Amend 204 to License DPR-16
05000219/LER-1999-001-02, :on 990208,noted Prolonged Operation of TB with Condenser & Heater Bay Pressure.Caused by Loss of Integrity of Ventilation Envelope (Physical Boundaries).Alternate Exhaust Fan Was Placed in Service.With1999-03-0808 March 1999
- on 990208,noted Prolonged Operation of TB with Condenser & Heater Bay Pressure.Caused by Loss of Integrity of Ventilation Envelope (Physical Boundaries).Alternate Exhaust Fan Was Placed in Service.With
ML20204C8201999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With
05000219/LER-1998-016, :on 981028,single DG Start,Occurred.Caused by Loss of One Source of Offsite Power.Generator Relay Surveillance Revised to Eliminate Possibility of Inadvertent Procedural Breaker Trips.With1999-01-0505 January 1999
- on 981028,single DG Start,Occurred.Caused by Loss of One Source of Offsite Power.Generator Relay Surveillance Revised to Eliminate Possibility of Inadvertent Procedural Breaker Trips.With
ML20195E8321998-12-31031 December 1998
10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With
ML20199E4671998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With
05000219/LER-1998-019, :on 981118,missed TS Required Surveillance Test.Caused by Inadequate Administrative Controls.Revised Related Surveillance Task Descriptions to Provide Improved Ref.With1998-12-18018 December 1998
- on 981118,missed TS Required Surveillance Test.Caused by Inadequate Administrative Controls.Revised Related Surveillance Task Descriptions to Provide Improved Ref.With
ML20198D2091998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With
05000219/LER-1998-017, :on 981027,discovered That Station Battery Racks Did Not Comply with Seismic Design Basis.Caused by Inadequate Engineering Review.Restored Battery Rack Retainer Plates to Appropriate Configuration.With1998-11-25025 November 1998
- on 981027,discovered That Station Battery Racks Did Not Comply with Seismic Design Basis.Caused by Inadequate Engineering Review.Restored Battery Rack Retainer Plates to Appropriate Configuration.With
05000219/LER-1998-018, :on 981023,DG 2 Failed to Start from App R Local Shutdown Panel During Functional Test.Caused by Incorrectly Designed Wiring.Incorrect Wiring Was Modified & Demonstrated by Testing to Be Correct.With1998-11-23023 November 1998
- on 981023,DG 2 Failed to Start from App R Local Shutdown Panel During Functional Test.Caused by Incorrectly Designed Wiring.Incorrect Wiring Was Modified & Demonstrated by Testing to Be Correct.With
ML20195J8591998-11-12012 November 1998
Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan
ML20195C4271998-11-0606 November 1998
Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle
ML20155G9311998-11-0404 November 1998
Safety Evaluation Supporting Amend 201 to License DPR-16
ML20155J3021998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With
05000219/LER-1998-014, :on 980928,noted Failure of Isolation Condenser Tube Bundles.Caused by Thermal Stresses/Tgscc Due to Leaky Valve.Replaced Failed Tubes Bundles & Repaired Condensate Return Valve.With1998-10-29029 October 1998
- on 980928,noted Failure of Isolation Condenser Tube Bundles.Caused by Thermal Stresses/Tgscc Due to Leaky Valve.Replaced Failed Tubes Bundles & Repaired Condensate Return Valve.With
05000219/LER-1998-015, :on 980929,SDC Isolation Occurred Due to Equipment Failure.Caused by Damaged Conduit That Appeared to Have Been Damaged by Personnel Error.Instrument Was Repaired & Bypass Was Removed.With1998-10-28028 October 1998
- on 980929,SDC Isolation Occurred Due to Equipment Failure.Caused by Damaged Conduit That Appeared to Have Been Damaged by Personnel Error.Instrument Was Repaired & Bypass Was Removed.With
05000219/LER-1998-013-01, :on 980926,LLRT Results Indicated That MSIV NS03B Exceeded TS Leak Rate Limit.Caused by Component Wear. Maint Was Performed on Subject Valve to Restore Seat Integrity & as-left LLRT Was Acceptable.With1998-10-26026 October 1998
- on 980926,LLRT Results Indicated That MSIV NS03B Exceeded TS Leak Rate Limit.Caused by Component Wear. Maint Was Performed on Subject Valve to Restore Seat Integrity & as-left LLRT Was Acceptable.With
ML20154R4981998-10-20020 October 1998
Core Spray Sys Insp Program - 17R
05000219/LER-1998-012-01, :on 980916,unplanned Actuation of Esfs Occurred.Caused by Written Communication.Procedure Revised to Include Signature Verifications to Install & Subsequently Remove Ohmmeter1998-10-16016 October 1998
- on 980916,unplanned Actuation of Esfs Occurred.Caused by Written Communication.Procedure Revised to Include Signature Verifications to Install & Subsequently Remove Ohmmeter
ML20154M6311998-10-15015 October 1998
Safety Evaluation Supporting Amend 200 to License DPR-16
05000219/LER-1998-011-01, :on 980914,discovered That Three Small Bore Piping Lines Did Not Meet Design Basis Seismic &/Or Thermal Allowables.Caused by Design Deficiency.Subject Lines Will Be Modified During Present Refueling Outage.With1998-10-15015 October 1998
- on 980914,discovered That Three Small Bore Piping Lines Did Not Meet Design Basis Seismic &/Or Thermal Allowables.Caused by Design Deficiency.Subject Lines Will Be Modified During Present Refueling Outage.With
ML20154L3051998-10-14014 October 1998
Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage
ML20154Q3371998-09-30030 September 1998
Rev 8 to Oyster Creek Cycle 17,COLR
ML20154L5571998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With
ML20237D5691998-08-31031 August 1998
Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification
ML20151V6311998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Oyster Creek Nuclear Generating Station.With
05000219/LER-1998-010, :on 980724,DG Switchgear Was Found Beyond Design Bases.Caused by Inadequate Installation During Original Construction.Evaluated Temporary Mod to Determine If It Should Be Reclassified as Permanent Mod1998-08-24024 August 1998
- on 980724,DG Switchgear Was Found Beyond Design Bases.Caused by Inadequate Installation During Original Construction.Evaluated Temporary Mod to Determine If It Should Be Reclassified as Permanent Mod