ML19247A067
From kanterella
Revision as of 11:38, 8 October 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
| ML19247A067 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/20/1979 |
| From: | Quintenz T JERSEY CENTRAL POWER & LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19247A048 | List: |
| References | |
| NUDOCS 7907270202 | |
| Download: ML19247A067 (2) | |
Similar Documents at Oyster Creek | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20029A5461991-02-12012 February 1991
[Table view]Special Rept 91-01:on 910113,inoperable Condenser Bay Sprinkler Sys 2 Not Restored within 14 Days.Caused by Steam Leak in Vicinity of Sprinkler Head.Sprinkler Will Be Replaced During Refueling Outage 13R 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 ML20028D6511983-01-0707 January 1983 RO 82-9:on 821208,temp Sensor Instrumentation Located Upstream of Us Route 9 Bridge Did Not Meet Overall Sys Accuracy Limits.Caused by Downdrift of Temp Transmitter Zero & Span Adjustments.Temp Transmitter Recalibr ML20028D6631983-01-0707 January 1983 RO 82-10:on 821210,during shutdown,364 Dead or Severely Stressed Fish Collected.Caused by Temp in Discharge Canal Below Lethal Temp for Affected Species ML20050D9991982-04-0202 April 1982 RO 50-219/82-20/01P:on 820401,abnormal Degradation of Primary Containment Identified,Based on MSIV Leak Rates Outside of Acceptable Limits.Cause Under Investigation.Msivs Adjusted & Repaired ML20050D5471982-04-0101 April 1982 RO 50-219/82-19/01P:on 820331,results of Leak Rate Testing on Main Steam Isolation Drain Valves Identified Abnormal Degradation of Primary Containment.Cause Unknown.Valve V-1-106 Repaired & Valve V-1-111 Will Be Replaced ML20049H4711982-02-19019 February 1982 RO 82-10/01P:on 820218,determined Apparent Deficiency in Safety Evaluation 218.77-81 Re safety-related Sys.Electrical Fire on 820109 Caused Deluge Sys to Actuate.Ac & Dc Ground Faults Occurred Due to Water Damage ML20041A9821982-02-11011 February 1982 RO 82-06/01P:on 811203,control Power Fuses 16F301A,16F302A, 16F303A & 16F304A Removed from Svc for Maint on Electromatic Relief Valve Pressure Switch,Rendering Valve a & Automatic Depressurization Sys Inoperable.Switch Replaced ML20040F4981982-02-0101 February 1982 RO 82-01:on 820117,fire Suppression Water Sys Declared Inoperable.Caused by Inoperability of Fire Diesels Due to Extremely Low Temps.Space Heaters Repaired & Returned to Svc.Fuel Oil Temp Problem Under Investigation ML20040C6731982-01-18018 January 1982 RO 219/82-01:on 820117,fire Diesels 1-1 & 1-2 Shut Down for Maint,Rendering Fire Suppression Water Sys Inoperable.Caused by Frozen Cooling Water Lines & Fuel Oil Due to Failure of Two Space Heaters.Heaters Replaced ML20040C6311981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-7-1:on 811207, Intake Temp Was 37.3 F & Discharge Temp 61.9 F Resulting in Temp Difference of 24.6 F Exceeding Permit Level of 23 F. Caused by Grass Clogging Intake & Reducing Flow ML20040C6261981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-6-2:on 811121, Dilution Pump 1-2 Tripped Leaving Only Dilution Pump 1-1 Operating for More than 15 Minutes & Ambient Water Temp Less than 60 F.Cause of Trip Not Determined ML20040C6151981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-4-2:on 811124, Dilution Pump 1-2 Tripped Leaving Only Dilution Pump 1-3 Operating for More than 15 Minutes & Ambient Water Temp Less than 60 F.Cause of Trip Not Determined ML20040C6201981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-5-2:on 811202, Dilution Pump 1-2 Tripped Leaving Only Dilution Pump 1-3 Operating for More than 15 Minutes & Ambient Water Temp Less than 60 F.Caused by High Oil Temps Due to Clogged Screen ML20040C6071981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-3-2:on 811128, Less than Two Dilution Pumps Were Operating for Greater than 15 Minutes & Ambient Water Temp Was Less than 60 F.Caused by Loose Pump Impeller on Pump 1-1 ML20039B2831981-12-10010 December 1981 RO 50-219/81-65-01P:on 811203 & 09,two Isolation Valves for Isolation Condenser Sys Found to Have Defects & Valve V-14-30 Found Inoperable.Damaged Threads in Lower Part of Stem Nut Repaired.Cause Under Investigation ML20038C7161981-12-0909 December 1981 RO 50-219/81-64/01P:on 811203,containment Spray High Drywell Pressure Switches IP-154A,IP-15B,IP-15C & IP-15D Tripped at Value Greater than Tech Specs.Caused by Instrument Repeatability.Switches Reset ML20010E7131981-08-28028 August 1981 RO 50-219/81-42/01P:on 810828,stack Gas Not Continuously Monitored as Required by Tech Spec Due to Trip of Stack Gas Sample Pump B.Probably Caused by Failure of Bearings &/Or Micarta Vanes in Pump ML20009E3471981-07-15015 July 1981 RO 81-030/01P-0:on 810714,during Required Surveillance at steady-state Power Standby Gas Treatment Sys 1 Failed to Start & Reactor Bldg Main Exhaust Valve V-28-22 Failed to Close.Caused by Faulty Tube Flow Sensor ML20004C8401981-06-0101 June 1981 Ro:On 800728 & 1219,data from 10-meter Wind Direction Monitoring Sys Was Lost.Caused by V76 Central Computer Disk Failure & Simultaneous Electronic Failure of Esterline Angus L1152S Recorder.Equipment Repaired ML19345H2541981-04-27027 April 1981 RO 81-001:on 810415 & 16,two Dilution Pumps Tripped & Reserve Pump Would Not Start.Caused by Component Failure. Flow Switch Jumpered After First Event,Lube Oil Cooler Switch Reset After Second ML19343B4331980-12-17017 December 1980 RO 50-219/80-13:on 801204,plant Intake Water Level Reached Critically Low Elevation,Affecting Supply of Cooling Water to Main Condenser,Reactor & Turbine Bldgs.Caused by Environ & Svc Conditions.Dilution Pumps 1-2 & 1-3 Restarted ML19347C7461980-12-17017 December 1980 RO:801121 Fire Diesel 1-2 Removed from Svc to Determine Cause of Failure to Start Automatically on Decrease in Sys Pressure.Caused by Failure of Corrosion Resistor Element in Cooling Water Line Resulting in Diesel Overheat ML19345C8111980-12-0202 December 1980 Nonroutine Environ Operating Rept 50-219/80-12:on 801122 During Reactor Shutdown W/Three Circulating Pumps in Svc, Water Temp in Discharge Canal Fell Below Lower Lethal Temp, Resulting in Fishkill.Blocking Devices Considered ML19350A0641980-11-25025 November 1980 Nonroutine Environ Operating Rept 80-219/80-11:on 801118, Fish Were Found Dead in Creek.Caused by Apparent Distraction from Fall Migration Due to Warm Water from Facility. Installation of Blocking Devices Under Review ML19345C3411980-11-21021 November 1980 Nonroutine Environ Operating Rept 50-219/80-10:on 801111,ETS Limiting Condition Exceeded When Less than Two Dilution Pumps Worked for 25 Minutes W/Ambient Intake Water Temp at Less than 60 F.Caused by Unusual Svc Condition ML19345B4361980-11-21021 November 1980 Nonroutine Environ Operating Rept 50-219/80-10:on 801111, Dilution Pump 1-2 Tripped.Caused by Debris in Barnegat Bay Clogging Pump Seal Water Strainers,Reducing Pressure.Lines cleared.Long-term Corrective Action Being Reviewed ML19340C1791980-11-0606 November 1980 RO 50-219/80-49/1P:on 801105,while Removing Isolation Condenser B from Svc to Repair Leak on Isolation Valve V-14-19,valves V-14-1 & V-14-19 Failed to Close.Cause Undetermined ML19340B5461980-11-0303 November 1980 RO 50-219/80-9:on 801026,intake Trash Racks,Ristroph Traveling Screens,Turbine Bldg Closed Cooling Water Heat Exchangers & Main Condensers Were Fouled W/Seaweed & Approx 10,000 Blue Crabs Due to Intense 801025 Northeast Storm ML19339C0881980-11-0303 November 1980 Nonroutine Environ Operating Rept 50-219/80-9:on 801026, Intake Trash Racks,Ristroph Traveling Screens,Turbine Bldg Closed Cooling Water Heat Exchangers & Main Condensers Were Fouled W/Seaweed & Blue Crabs.Caused by 801025 Storm ML19347A7461980-09-25025 September 1980 Nonroutine Environ Operating Rept 50-219/80-08:on 800910, Second Dilution Pump Placed Into Operation W/Bridge Water Temp Below ETS Requirements.Caused by Insufficient Pump Quota.Damaged Pump Removed & Repaired ML19338E6451980-09-25025 September 1980 Nonroutine Environ Operating Rept 50-219/80-8: on 800910, Second Dilution Pump Was Not Placed Into Operation W/Water Temp Exceeding 87 F for Period More Tht 2-h 15 Minutes. Caused by Damaged Inboard Motor Bearing ML19337A8341980-09-19019 September 1980 Nonroutine Environ Operating Rept 80-7:on 800901,02 & 04, Four Individual Dilution Pump Trips Occurred During Which Inoperative or Reserve Pump Could Not Be Started within Required 15 Minutes.Caused by Component Failure ML19344E6331980-08-26026 August 1980 RO 50-219/80-5:on 800808,09,11 & 12,during Steady State power,10 Dilution Pump Trips Occurred,Exceeding Limiting Condition Per Tech Spec.Caused by High Lubricating Oil Temp Due to Low Cooling Water Pressure ML19344E6451980-08-26026 August 1980 Nonroutine Environ Operating Rept 50-219/80-6:on 800811,at Steady State Power,Condenser Discharge Temp Exceeded 106 F. Caused by Shift in Meteorological Conditions.Load Reduction Initiated & Temp Stablilized ML19331E0541980-08-26026 August 1980 Nonroutine Environ Operating Rept 50-219/80-5.Total of Ten Dilution Pump Trips Occurred Between 800808 & 800812.Caused by High Lubricating Oil Temp.Evaluation Completed for Upgrading Cooling Water Sys ML19338C6631980-08-0707 August 1980 Nonroutine Environ Operating Rept 50-219/80-4:on 800727-29, Dilution Pump 1-1 Tripped & Could Not Be Restarted within 15 Minutes.Caused by High Lubricating Oil Temp Due to Low Cooling Water Pressure.Sys Mods Proposed ML19331B6551980-08-0606 August 1980 RO 50/219/80-32/1P:while Performing Tour of Reactor Bldg, Discovered Both Doors to Containment Spray Pump Compartments Open.Verification Surveillance to Check Doors Was Not Performed.Pump Room Doors Closed & Dogged Shut ML19327A2551980-07-30030 July 1980 Nonroutine Environ Operating Rept 50-219/80-3:on 800720,w/ Us Route 9 Discharge Bridge Temp Above 87.0F,second Dilution Pump Was Not Placed Into Operation,Which Exceeded ETS Limiting Conditions.Caused by Insufficient Pump Quota ML19330C2821980-07-29029 July 1980 RO 50-219/80-2:on 791125-26,during Routine Startup,Less than Two Dilution Pumps Were Operating for 9-h & 47 Minutes While Ambient Water Temp Was Less than 60.0 F.Caused by Error in Plant Procedures.Plant Procedures Were Revised ML19321A5401980-07-17017 July 1980 RO 50-219/80-27-1P:on 800716,reactor Bldg to Suppression Chamber Vacuum Breaker Sys Inlet Pipe Was Found Blocked by Plastic Bag.Caused by Personnel Error.Plastic Bag Was Removed from Vacuum Breaker Inlet Opening ML19323J2221980-06-16016 June 1980 Ro:On 800502,during Routine Surveillance Testing of Isolation Condenser Initiation Pressure Switches,False High Pressure Signal Caused Reactor Scram.Caused by Opening of Gauge Valve.Mod Performed on Instrument Line ML19323H2661980-06-0606 June 1980 RO 50-219/80-20-1P:on 800605,following Insp of Fire Barrier, Several Penetrations Found in Degraded Condition.Caused by Delay in Performing Further Fire Watches Attributed to Personnel Error.Fire Watch Being Conducted ML19323E4191980-05-16016 May 1980 RO 50-219/80-17-1P:on 800516,while Performing Control Rod Interference Checks, green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Bypass Jumpers Removed & Control Rod Panels Inspected ML19323C8831980-05-13013 May 1980 RO-50/219/80-16-1P:on 800420,during Surveillance of Generator Load Rejection Sensors,Pressure Switch Psl D Found Defective.Caused by Mislocated Operating Lever in Switch Housing.Switch Removed & Will Be Replaced ML19290E9281980-03-0707 March 1980 RO 50/219/80-13/1P:on 800309,fire Suppression Water Sys Will Be Removed from Svc to Replace Cracked Valve V-9-4.Fire Truck Pumper & Power Supply for Both Core Spray Sys Will Be Available During Repair ML19305A7651980-02-21021 February 1980 RO-50/219/80/10-1P:on 800220,during Insp Per IE Bulletin 79-14,three Pipe Hangers in Liquid Poison Sys Found Improperly Installed.Hangers Reset.Restraint in Cleanup Sys Under Design Review to Correct Deficiency ML19290D7621980-02-19019 February 1980 RO 50/219/80/8-1P:on 800215,during Insp Required by IE Bulletin 79-14,nine Improperly Installed Pipe Clamps Found on Piping to Isolation Condensers.Caused by Installation Error.Corrective Action Will Be Determined 1991-02-12 Category:LER) MONTHYEARML20029A5461991-02-12012 February 1991
[Table view]Special Rept 91-01:on 910113,inoperable Condenser Bay Sprinkler Sys 2 Not Restored within 14 Days.Caused by Steam Leak in Vicinity of Sprinkler Head.Sprinkler Will Be Replaced During Refueling Outage 13R 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 ML20028D6511983-01-0707 January 1983 RO 82-9:on 821208,temp Sensor Instrumentation Located Upstream of Us Route 9 Bridge Did Not Meet Overall Sys Accuracy Limits.Caused by Downdrift of Temp Transmitter Zero & Span Adjustments.Temp Transmitter Recalibr ML20028D6631983-01-0707 January 1983 RO 82-10:on 821210,during shutdown,364 Dead or Severely Stressed Fish Collected.Caused by Temp in Discharge Canal Below Lethal Temp for Affected Species ML20050D9991982-04-0202 April 1982 RO 50-219/82-20/01P:on 820401,abnormal Degradation of Primary Containment Identified,Based on MSIV Leak Rates Outside of Acceptable Limits.Cause Under Investigation.Msivs Adjusted & Repaired ML20050D5471982-04-0101 April 1982 RO 50-219/82-19/01P:on 820331,results of Leak Rate Testing on Main Steam Isolation Drain Valves Identified Abnormal Degradation of Primary Containment.Cause Unknown.Valve V-1-106 Repaired & Valve V-1-111 Will Be Replaced ML20049H4711982-02-19019 February 1982 RO 82-10/01P:on 820218,determined Apparent Deficiency in Safety Evaluation 218.77-81 Re safety-related Sys.Electrical Fire on 820109 Caused Deluge Sys to Actuate.Ac & Dc Ground Faults Occurred Due to Water Damage ML20041A9821982-02-11011 February 1982 RO 82-06/01P:on 811203,control Power Fuses 16F301A,16F302A, 16F303A & 16F304A Removed from Svc for Maint on Electromatic Relief Valve Pressure Switch,Rendering Valve a & Automatic Depressurization Sys Inoperable.Switch Replaced ML20040F4981982-02-0101 February 1982 RO 82-01:on 820117,fire Suppression Water Sys Declared Inoperable.Caused by Inoperability of Fire Diesels Due to Extremely Low Temps.Space Heaters Repaired & Returned to Svc.Fuel Oil Temp Problem Under Investigation ML20040C6731982-01-18018 January 1982 RO 219/82-01:on 820117,fire Diesels 1-1 & 1-2 Shut Down for Maint,Rendering Fire Suppression Water Sys Inoperable.Caused by Frozen Cooling Water Lines & Fuel Oil Due to Failure of Two Space Heaters.Heaters Replaced ML20040C6311981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-7-1:on 811207, Intake Temp Was 37.3 F & Discharge Temp 61.9 F Resulting in Temp Difference of 24.6 F Exceeding Permit Level of 23 F. Caused by Grass Clogging Intake & Reducing Flow ML20040C6261981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-6-2:on 811121, Dilution Pump 1-2 Tripped Leaving Only Dilution Pump 1-1 Operating for More than 15 Minutes & Ambient Water Temp Less than 60 F.Cause of Trip Not Determined ML20040C6151981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-4-2:on 811124, Dilution Pump 1-2 Tripped Leaving Only Dilution Pump 1-3 Operating for More than 15 Minutes & Ambient Water Temp Less than 60 F.Cause of Trip Not Determined ML20040C6201981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-5-2:on 811202, Dilution Pump 1-2 Tripped Leaving Only Dilution Pump 1-3 Operating for More than 15 Minutes & Ambient Water Temp Less than 60 F.Caused by High Oil Temps Due to Clogged Screen ML20040C6071981-12-22022 December 1981 Nonroutine Environ Operating Rept 50-219/81-3-2:on 811128, Less than Two Dilution Pumps Were Operating for Greater than 15 Minutes & Ambient Water Temp Was Less than 60 F.Caused by Loose Pump Impeller on Pump 1-1 ML20039B2831981-12-10010 December 1981 RO 50-219/81-65-01P:on 811203 & 09,two Isolation Valves for Isolation Condenser Sys Found to Have Defects & Valve V-14-30 Found Inoperable.Damaged Threads in Lower Part of Stem Nut Repaired.Cause Under Investigation ML20038C7161981-12-0909 December 1981 RO 50-219/81-64/01P:on 811203,containment Spray High Drywell Pressure Switches IP-154A,IP-15B,IP-15C & IP-15D Tripped at Value Greater than Tech Specs.Caused by Instrument Repeatability.Switches Reset ML20010E7131981-08-28028 August 1981 RO 50-219/81-42/01P:on 810828,stack Gas Not Continuously Monitored as Required by Tech Spec Due to Trip of Stack Gas Sample Pump B.Probably Caused by Failure of Bearings &/Or Micarta Vanes in Pump ML20009E3471981-07-15015 July 1981 RO 81-030/01P-0:on 810714,during Required Surveillance at steady-state Power Standby Gas Treatment Sys 1 Failed to Start & Reactor Bldg Main Exhaust Valve V-28-22 Failed to Close.Caused by Faulty Tube Flow Sensor ML20004C8401981-06-0101 June 1981 Ro:On 800728 & 1219,data from 10-meter Wind Direction Monitoring Sys Was Lost.Caused by V76 Central Computer Disk Failure & Simultaneous Electronic Failure of Esterline Angus L1152S Recorder.Equipment Repaired ML19345H2541981-04-27027 April 1981 RO 81-001:on 810415 & 16,two Dilution Pumps Tripped & Reserve Pump Would Not Start.Caused by Component Failure. Flow Switch Jumpered After First Event,Lube Oil Cooler Switch Reset After Second ML19343B4331980-12-17017 December 1980 RO 50-219/80-13:on 801204,plant Intake Water Level Reached Critically Low Elevation,Affecting Supply of Cooling Water to Main Condenser,Reactor & Turbine Bldgs.Caused by Environ & Svc Conditions.Dilution Pumps 1-2 & 1-3 Restarted ML19347C7461980-12-17017 December 1980 RO:801121 Fire Diesel 1-2 Removed from Svc to Determine Cause of Failure to Start Automatically on Decrease in Sys Pressure.Caused by Failure of Corrosion Resistor Element in Cooling Water Line Resulting in Diesel Overheat ML19345C8111980-12-0202 December 1980 Nonroutine Environ Operating Rept 50-219/80-12:on 801122 During Reactor Shutdown W/Three Circulating Pumps in Svc, Water Temp in Discharge Canal Fell Below Lower Lethal Temp, Resulting in Fishkill.Blocking Devices Considered ML19350A0641980-11-25025 November 1980 Nonroutine Environ Operating Rept 80-219/80-11:on 801118, Fish Were Found Dead in Creek.Caused by Apparent Distraction from Fall Migration Due to Warm Water from Facility. Installation of Blocking Devices Under Review ML19345C3411980-11-21021 November 1980 Nonroutine Environ Operating Rept 50-219/80-10:on 801111,ETS Limiting Condition Exceeded When Less than Two Dilution Pumps Worked for 25 Minutes W/Ambient Intake Water Temp at Less than 60 F.Caused by Unusual Svc Condition ML19345B4361980-11-21021 November 1980 Nonroutine Environ Operating Rept 50-219/80-10:on 801111, Dilution Pump 1-2 Tripped.Caused by Debris in Barnegat Bay Clogging Pump Seal Water Strainers,Reducing Pressure.Lines cleared.Long-term Corrective Action Being Reviewed ML19340C1791980-11-0606 November 1980 RO 50-219/80-49/1P:on 801105,while Removing Isolation Condenser B from Svc to Repair Leak on Isolation Valve V-14-19,valves V-14-1 & V-14-19 Failed to Close.Cause Undetermined ML19340B5461980-11-0303 November 1980 RO 50-219/80-9:on 801026,intake Trash Racks,Ristroph Traveling Screens,Turbine Bldg Closed Cooling Water Heat Exchangers & Main Condensers Were Fouled W/Seaweed & Approx 10,000 Blue Crabs Due to Intense 801025 Northeast Storm ML19339C0881980-11-0303 November 1980 Nonroutine Environ Operating Rept 50-219/80-9:on 801026, Intake Trash Racks,Ristroph Traveling Screens,Turbine Bldg Closed Cooling Water Heat Exchangers & Main Condensers Were Fouled W/Seaweed & Blue Crabs.Caused by 801025 Storm ML19347A7461980-09-25025 September 1980 Nonroutine Environ Operating Rept 50-219/80-08:on 800910, Second Dilution Pump Placed Into Operation W/Bridge Water Temp Below ETS Requirements.Caused by Insufficient Pump Quota.Damaged Pump Removed & Repaired ML19338E6451980-09-25025 September 1980 Nonroutine Environ Operating Rept 50-219/80-8: on 800910, Second Dilution Pump Was Not Placed Into Operation W/Water Temp Exceeding 87 F for Period More Tht 2-h 15 Minutes. Caused by Damaged Inboard Motor Bearing ML19337A8341980-09-19019 September 1980 Nonroutine Environ Operating Rept 80-7:on 800901,02 & 04, Four Individual Dilution Pump Trips Occurred During Which Inoperative or Reserve Pump Could Not Be Started within Required 15 Minutes.Caused by Component Failure ML19344E6331980-08-26026 August 1980 RO 50-219/80-5:on 800808,09,11 & 12,during Steady State power,10 Dilution Pump Trips Occurred,Exceeding Limiting Condition Per Tech Spec.Caused by High Lubricating Oil Temp Due to Low Cooling Water Pressure ML19344E6451980-08-26026 August 1980 Nonroutine Environ Operating Rept 50-219/80-6:on 800811,at Steady State Power,Condenser Discharge Temp Exceeded 106 F. Caused by Shift in Meteorological Conditions.Load Reduction Initiated & Temp Stablilized ML19331E0541980-08-26026 August 1980 Nonroutine Environ Operating Rept 50-219/80-5.Total of Ten Dilution Pump Trips Occurred Between 800808 & 800812.Caused by High Lubricating Oil Temp.Evaluation Completed for Upgrading Cooling Water Sys ML19338C6631980-08-0707 August 1980 Nonroutine Environ Operating Rept 50-219/80-4:on 800727-29, Dilution Pump 1-1 Tripped & Could Not Be Restarted within 15 Minutes.Caused by High Lubricating Oil Temp Due to Low Cooling Water Pressure.Sys Mods Proposed ML19331B6551980-08-0606 August 1980 RO 50/219/80-32/1P:while Performing Tour of Reactor Bldg, Discovered Both Doors to Containment Spray Pump Compartments Open.Verification Surveillance to Check Doors Was Not Performed.Pump Room Doors Closed & Dogged Shut ML19327A2551980-07-30030 July 1980 Nonroutine Environ Operating Rept 50-219/80-3:on 800720,w/ Us Route 9 Discharge Bridge Temp Above 87.0F,second Dilution Pump Was Not Placed Into Operation,Which Exceeded ETS Limiting Conditions.Caused by Insufficient Pump Quota ML19330C2821980-07-29029 July 1980 RO 50-219/80-2:on 791125-26,during Routine Startup,Less than Two Dilution Pumps Were Operating for 9-h & 47 Minutes While Ambient Water Temp Was Less than 60.0 F.Caused by Error in Plant Procedures.Plant Procedures Were Revised ML19321A5401980-07-17017 July 1980 RO 50-219/80-27-1P:on 800716,reactor Bldg to Suppression Chamber Vacuum Breaker Sys Inlet Pipe Was Found Blocked by Plastic Bag.Caused by Personnel Error.Plastic Bag Was Removed from Vacuum Breaker Inlet Opening ML19323J2221980-06-16016 June 1980 Ro:On 800502,during Routine Surveillance Testing of Isolation Condenser Initiation Pressure Switches,False High Pressure Signal Caused Reactor Scram.Caused by Opening of Gauge Valve.Mod Performed on Instrument Line ML19323H2661980-06-0606 June 1980 RO 50-219/80-20-1P:on 800605,following Insp of Fire Barrier, Several Penetrations Found in Degraded Condition.Caused by Delay in Performing Further Fire Watches Attributed to Personnel Error.Fire Watch Being Conducted ML19323E4191980-05-16016 May 1980 RO 50-219/80-17-1P:on 800516,while Performing Control Rod Interference Checks, green-green Rod Position Indication Remained Illuminated While Withdrawing Rod 10-23.Bypass Jumpers Removed & Control Rod Panels Inspected ML19323C8831980-05-13013 May 1980 RO-50/219/80-16-1P:on 800420,during Surveillance of Generator Load Rejection Sensors,Pressure Switch Psl D Found Defective.Caused by Mislocated Operating Lever in Switch Housing.Switch Removed & Will Be Replaced ML19290E9281980-03-0707 March 1980 RO 50/219/80-13/1P:on 800309,fire Suppression Water Sys Will Be Removed from Svc to Replace Cracked Valve V-9-4.Fire Truck Pumper & Power Supply for Both Core Spray Sys Will Be Available During Repair ML19305A7651980-02-21021 February 1980 RO-50/219/80/10-1P:on 800220,during Insp Per IE Bulletin 79-14,three Pipe Hangers in Liquid Poison Sys Found Improperly Installed.Hangers Reset.Restraint in Cleanup Sys Under Design Review to Correct Deficiency ML19290D7621980-02-19019 February 1980 RO 50/219/80/8-1P:on 800215,during Insp Required by IE Bulletin 79-14,nine Improperly Installed Pipe Clamps Found on Piping to Isolation Condensers.Caused by Installation Error.Corrective Action Will Be Determined 1991-02-12 Category:TEXT-SAFETY REPORT MONTHYEARML20217K4451999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With 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 ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.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 ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.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 ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.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 ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R 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 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 ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20237B0131998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Oyster Creek Nuclear Generating Station ML20236R0511998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Oyster Creek Nuclear Generating Station ML20249B2981998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Oyster Creek Nuclear Station ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247F1891998-05-0505 May 1998 Risk Evaluation of Post-LOCA Containment Overpressure Request ML20247G0581998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Oyster Creek Nuclear Generating Station ML20216K0341998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Oyster Creek Nuclear Generating Station ML20151Y4651998-03-31031 March 1998 Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216J0841998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Oyster Creek Nuclear Generating Station ML20203B2781998-02-16016 February 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Systems & Procedures ML20203A3801998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Oyster Creek Nuclear Generation Station ML20198P1791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Oyster Creek Nuclear Station ML20217C7591997-12-31031 December 1997 1997 Annual Environmental Operating Rept for Oyster Creek Nuclear Generating Station ML20197E9131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Oyster Creek Nuclear Station ML20199E4561997-11-13013 November 1997 Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant ML20199D4381997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Oyster Creek Nuclear Station ML20202E8511997-10-21021 October 1997 Rev 0 to Scenario 47, Gpu Nuclear Oyster Creek Nuclear Generating Station Emergency Preparedness (Nrc/Fema Evaluated) 1997 Biennial Exercise. Pages 49 & 59 of Incoming Submittal Were Not Included ML20211M9481997-10-0303 October 1997 Supplemental Part 21 Rept Re Condition Effected Emergency Svc Water Pumps Supplied by Bw/Ip Intl Inc to Gpu Nuclear, Oyster Creek Nuclear Generation Station.No Other Nuclear Generating Stations Effected by Notification ML20198J7361997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Oyster Creek Nuclear Generating Station ML20211B7461997-09-24024 September 1997 Part 21 Rept Re Failure of Emergency Service Water Pump Due to Threaded Flange Attaching Column to Top Series Case Failure.Caused by Dissimilar Metals.Pumps in High Ion Svc Will Be Upgraded to 316 Stainless Steel Matl ML20210V0181997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Oyster Creek Nuclear Generating Station ML20210L2961997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Oyster Creek Nuclear Station ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20196H0111997-07-11011 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 ML20210L3081997-06-30030 June 1997 Corrected Page to MOR for June 1997 for Oyster Creek Nuclear Generating Station ML20141H2051997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Oyster Creek Nuclear Station 1999-09-30 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML19247A067&oldid=1895044"