Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20196H0111997-07-11011 July 1997 Special Rept 97-001:on 970620,removed High Range Radioactive Noble Gas Effluent Monitor (Stack Ragems) from Service to Allow Secondary Calibr IAW Master Surveillance Schedule. Completed Calibr on 970628 & Returned Stack Ragems to Svc ML20129A3401996-10-15015 October 1996 Special Rept 96-001,rev 1:on 960806,stack Ragems High Range Monitor Was Removed from Svc & Not Restored to Svc in Seven Days.Caused by Malfunction of Interlock on Source. Interlock Components Replaced ML20117K5931996-09-0505 September 1996 Special Rept SR 96-001:on 960806,declared Stack Ragems High Range Monitor Inoperable.Caused by Difficulties Requiring Component Replacement.Developed Course of Action for Returning Stack Ragems Instrument ML20034E7741993-02-18018 February 1993 Special Rept 93-001:on 930204,HVAC Sys B Inoperable for More than 7 Days.On 930128,sys Did Not Pass Procedure Acceptance Criteria & Declared Inoperable.Caused by Broken Access Hatch.Hatch Repaired & Sys Declared Operable on 930211 ML20116B7521992-10-27027 October 1992 Special Rept 92-08:on 920929,Turbine Building High Radiation Noble Gas Monitor Declared Inoperable for Greater than Seven Days.Alternate Testing Performed Throughout Period of Inoperability ML20115G6461992-10-22022 October 1992 Special Rept 92-07:on 921015,determined That Stem & Disc Separated on Discharge Valve V-9-004 for Diesel Fire Pump P-9-102A.On 921021,fire Pumps Isolated.Redundant Fire Pump Secured & Valves Replaced ML20105A5121992-09-10010 September 1992 Special Rept 92-06:on 920807,fire Diesel Pump 1 Declared Inoperable for More than 7 Days to Perform Preventive Maint.On 920811,diesel Engine Overheated.Solenoid Valve Replaced & New Cooling Water Strainers Installed ML20104B6081992-09-10010 September 1992 Special Rept 92-05:on 920727,condenser Bay Sprinkler Sys 2 Removed from Svc After Spurious Actuation of Sprinkler Head. Hourly Fire Watch Established While Sys Out of Svc.Sprinkler Head Replaced & Sys Returned to Svc on 920814 ML20114C5191992-08-26026 August 1992 Special Rept 92-03:on 920705,electromatic Relief Valve C Inadvertently Opened While Testing Pressure Switch of Valve A.Caused by Personnel Error.Training Session Will Be Held & Engineering Work Request Submitted Re Switch Terminal Point ML20114A9701992-08-17017 August 1992 Special Rept 92-04:on 920724,fire Diesel Pump 2 Removed from Svc to Replace Battery Cables & Solenoid Valve.Correct 24 Volt Dc Coil Obtained from Mfg & Pump Returned to Svc on 920806 ML20096D4711992-05-0101 May 1992 Special Rept 92-02:on 920327,fire Diesel Pump 1 Out of Svc for More than 7 Days to Replace Pump Due to Marginal Discharge Pressure.Caused by Valve Seating Problem.Pump Replacement Expected to Be Completed by 920504 ML20100R7411992-04-10010 April 1992 Special Rept 92-01:on 920227,CO2 Fire Suppression Sys for 4,160-volt Switchgear Inoperable for More than 14 Days When Leaking Valve Stem Repaired on 920226.Possibly Caused by Moisture Intrusion.Corroded Components Replaced ML20087B8431992-01-0303 January 1992 Special Rept 91-09:on 911115,fire Diesel Pump 1-2 Failed to Meet Required Acceptance Criteria During Functional Test. Caused by Cloth Rag Becoming Lodged Inside Pump.Fire Diesel Pump 1-2 Rebuilt & Reinstalled on 911208 ML20076E2641991-08-13013 August 1991 Special Rept 91-08:on 910717,coolant Found Leaking from Cap on Heat Exchanger of Engine of Fire Diesel Pump 1-1.Caused by Wearing on HX Neck,Resulting in HX Failing to Hold Normal Pressure.Engine Secured & Work Request Initiated ML20076E3001991-08-12012 August 1991 Special Rept 91-07:on 910709,nonfunctional Fire Barrier Doors Between Fire Zones OB-FA-6 & TZ-FZ-11B Not Restored to Operable Status within 7 Days.Caused by Ventilation Flow Preventing Door from Closing.Fire Patrol Established ML20077K2271991-07-31031 July 1991 Special Rept 91-06 Re Nonfunctional Fire Barrier Door Not Repaired within 7 Days as Required by Tech Spec 3.12.E. Caused by Broken Door Closure Mechanism.Hourly Fire Watch Initiated.Door Mechanism Repaired on 910704 ML20082E1411991-07-23023 July 1991 Special Rept:On 910702,non-functional Fire Barrier Door Not Repaired within Seven Days as Required by Tech Specs. Caused by Faulty Door Closing Mechanisms.Util Evaluating Alternate Door Closing Mechanisms ML20073C9381991-04-18018 April 1991 Special Rept 91-04:on 910309,fire Detection Sys on Elevations 75 & 95 of Reactor Bldg Made Inoperable to Facilitate Maint Activities.Fire Watch Patrol Has Been Established to Compensate for Detection Sys ML20070T5341991-03-28028 March 1991 Special Rept:On 910222,inoperable Fire Hose Station 33 Not Restored to Operable Status within 14 Days as Required by Tech Specs.Caused by Maint to Angle Valve.Valve Reopened on 910312,restoring Hose Station 33 to Operability ML20070M5181991-03-14014 March 1991 Special Rept 91-02:on 901117,discovered That Fire Barrier Door Between 480-volt Switchgear Rooms a & B Nonfunctional Since 901110 & Not Repaired within 7 Days.Caused by Faulty Door Latching Mechanism.Fire Watch Established ML20058A7441990-10-16016 October 1990 Special Rept 90-04:on 900921,nonfunctional Fire Barrier Door Not Repaired within 7 Days.Fire Watch Established ML20043A7901990-05-11011 May 1990 Special Rept 90-03:on 900412,Fire Diesel Pump 1-1 Not Restored to Functional Status within 7 Days.Pump Removed from Svc to Install Mod.Mod Completed,Tested & Returned to Functional Status on 900420 ML20012F5171990-04-0303 April 1990 Special Rept 90-02:on 900309,stack Radioactive Effluent Monitoring Sys High Range Monitor Not Repaired within 7 Days,Per Tech Spec 3.13.H.Caused by Acceptance Criteria Test Procedure.Test Procedure Revised ML19351A3001989-10-11011 October 1989 Special Rept 89-03:on 890904,during Weekly Surveillance of Fire Barrier Doors,Door Between Fire Zones RB-FZ-1E & RB-FZ-1F4 Did Not Meet Acceptance Criteria.Door Unable to Latch W/O Assistance.Fire Watch Established & Door Repaired ML20245E7541989-06-0909 June 1989 Special Rept 89-02:on 890526,declared Fire Pump/Diesels 1-1 & 1-2 Inoperable.Caused by Loss of Fire Suppression Water. Pressure Switch & Associated Recorder for 1-2 Diesel Recalibrated Along W/Pump Discharge Pressure Gauge ML20247J2081989-05-22022 May 1989 Special Rept 89-01:on 890422,nonfunctional Fire Barrier Not Repaired within 7 Days as Required by Tech Spec 3.12.E. Fire Watch Established.Nonfunctional Fire Barrier Seal Plannned to Be Restored to Operable Status by 890523 ML20237C6711987-12-11011 December 1987 Special Rept 87-08:on 871112,fire Diesel Pump 1-2 Not Restored to Functional Status within 7 Days.Caused by Constraints Imposed by Increased outage-related Maint Activities.Fire Diesel Pump Restored to Functional Status ML20236S5201987-11-19019 November 1987 Special Rept 87-07:on 871020,nonfunctional Thermo Lag Fire Barrier Not Restored to Functional Status within 7 Days Per Tech Spec 3.12.E.Caused by Constraints Imposed by Increased Maint Activities.Fire Watch Established ML20236L3711987-10-29029 October 1987 Special Rept 87-06:on 870928-30,fire Barrier Penetration Seals Identified as Not Meeting Acceptance Criteria.Cause Not Stated.Fire Watch Established Immediately.Fire Barrier Seals Will Be Restored to Functional Status by 871030 ML20235B4411987-09-22022 September 1987 Ro:On 870811,spill of Reactor Bldg Closed Cooling Water Occurred.Caused by Failure to Follow Instructions on Switching & Tagging Request Form Re Valve Backseating. Procedures Will Be Revised & Training Provided ML20235G2151987-09-20020 September 1987 Ro:On 870911,w/reactor in Cold Shutdown Mode,Tech Spec Safety Limit 2.1.E Exceeded.Caused by Operator Error. Operators Received Training on Safety Limit,Applicable Procedures & Relevant Control Room Indications ML20214H9801987-05-0707 May 1987 Ro:On 870424,operator Personnel Blocked Open Two Torus to Drywell Vacuum Breaker Valves at Time When Primary Containment Integrity Was Required.Caused by Cognitive Personnel Error.Procedures Revised ML20215H3621987-04-0909 April 1987 Special Rept 87-02:on 870214,turbine Trip & Reactor Scram Occurred.Caused by Loose Wire Causing Loss of Feedwater Flow Signal.Following Reduction in Reactor Pressure All Electromatic Relief Valves Reseated Properly ML20206E3931987-04-0101 April 1987 Special Rept 87-01:on 870302,inoperable Fire Suppression Water Deluge Sys Not Restored to Functional Status within 14 Days from Time of Discovery.Caused by Long Lead Time for Procurement of Replacement Parts ML20209H2501987-01-23023 January 1987 Special Rept 86-017:on 861228,nonfunctional Fire Barrier Not Returned to Functional Status within 7 Days from Discovery.Hourly Fire Watch Established.Repairs Completed & Penetration Seal Restored to Functional Status on 870112 ML20207J2981986-12-17017 December 1986 Special Rept 86-16:on 861121,fire Barrier Door Between Monitor & Control Area Stairwell & Hallway Outside Cable Spreading Room Found Nonfunctional.Hourly Fire Watch Patrol Established.Door to Be Restored as Functional on 861222 ML20207J2821986-12-16016 December 1986 Special Rept 86-15:on 861110,penetrations Through Floor of 4160 Volt Switchgear 1D Vault & Floor of Motor Generator Set Room Found Degraded.As of 861117,penetrations Not Restored to Functional Condition.Hourly Fire Watch Patrol Initiated ML20197B1471986-10-0909 October 1986 Special Rept 86-14:on 860922 & 27,nonfunctional Fire Barrier Penetration Seals Not Restored to Functional Status within 7 Days.Hourly Fire Watch Patrol Established within 1 H. Restoration Expected by 861130 ML20212D6251986-07-10010 July 1986 Special Rept 86-03:on 860616,two Hangers Supporting Ofc Bldg Fire Water Supply Riser Found to Need Repair.Riser Consequently Isolated,Rendering Sprinkler Sys 4 & 12 & Deluge Sys 4 Inoperable.Hangers Repaired & Sys Restored ML20137U7031986-01-20020 January 1986 Fire Protection Special Rept 85-03:on 851216,insp of 14 Fire Dampers Identified Design or Installation Deficiencies Resulting in Dampers Being Determined Inoperable.Caused by Nonconforming as-found Fire Damper Configuration ML20117C7451985-04-25025 April 1985 Special Rept 85-02:on 850225,electromatic Relief Valves NR-108B,NR-108C & NR-108D Failed to Fully Reseat After Initial Actuation,Per Tech Spec 6.9.3.f.Caused by Valve Design Deficiency.Design Change Considered ML20102B8671985-02-21021 February 1985 Special Rept 85-01:on 850207,leakage Observed Around post-indication Valve V-9-13.Fire Suppression Water Sys Isolated on 850211 to Facilitate Valve Repair.Caused by Crack in Valve Body.Valve Replaced ML20092N6351984-06-15015 June 1984 Special Rept 84-01:on 840606,post-indicating Valve V-9-12 Branching Off 14-inch Fire Water Main Damaged by Maint Vehicle,Resulting in Loss of Fire Suppression Water Sys. Caused by Lack of Protection Against Physical Damage ML20083C6451983-12-0808 December 1983 RO 83-02T:on 831119,w/fire Pump 1-1 Out of Svc,Fire Pump 1-2 Failed to Start on Low Sys Pressure.Caused by Impeller Wear Rings Out of Tolerance on High End of Clearance Limits. Overspeed Trip Reset ML20082R6551983-11-21021 November 1983 RO 83-02:on 831119,fire Pump 1-2 Failed to Start on Low Sys Pressure During Demand for Fire Water to Fill Isolated Portion of Underground Fire Suppression Pool.Caused Suspected to Be Faulty Overspeed Trip Switch.Switch Tested ML20082L1491983-11-18018 November 1983 Followup RO 83-01:on 831103,fire Suppression Water Sys Declared Inoperable After Pump 1-1 Failed Testing.Mod Underway to Install New Pressure Relief Valves on Both Fire Pumps ML20082B7921983-11-0404 November 1983 RO 83-01:on 831103,fire Suppression Water Sys Declared Inoperable Due to Smoke Emitting from Under Fire Pump 1-2 Pumphead During post-maint Inservice Test & Failed Design Rated Curve for Pump 1-1.Caused by Misadjusted Impeller ML20082L5721983-09-15015 September 1983 Advises That Followup to RO 83-17 Re Diesel Generator Fast Start Surveillance Will Be Forwarded by 830921 ML20073A7071983-03-23023 March 1983 RO 83-4:on 830211,during Controlled Reactor Shutdown,One Dilution Pump Remained in Svc When Intake Canal Water Below Tech Spec Limit.Caused by Personnel Error.Procedures Will Be Revised to Provide More Explicit Directions ML20071B0911983-02-14014 February 1983 RO 83-1-1:on 830113,dilution Pump 1-2 Removed from Svc. Caused by Insufficient Seal Water flow.Long-term Corrective Action Includes Program Designed to Improve Pump Reliability 1997-07-11
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With 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
ML20196E2741998-11-30030 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-16 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 ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20151V6311998-08-31031 August 1998 Monthly Operating Rept for Aug 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 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
ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B7331998-08-13013 August 1998 Safety Evaluation Supporting Amend 196 to License DPR-16 ML20237B0131998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station 05000219/LER-1997-013, Has Been Canceled1998-06-30030 June 1998 Has Been Canceled 1999-09-30
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