ML20028E227
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| ML20028E227 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/11/1983 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20028E221 | List: |
| References | |
| NUDOCS 8301210092 | |
| Download: ML20028E227 (1) | |
Similar Documents at Hatch | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045B0641993-06-10010 June 1993
[Table view]Special Rept 93-004:on 930512,fire Rated Assemblies Were Inoperable for More than 14 Days Due to Inadequate Design. LCO 1-93-2010 Initiated,Appropriate Fire Detectors Were Verified Operable & Fire Watch established.W/930610 Ltr ML20044F6101993-05-21021 May 1993 Special Rept 2-93-002:on 930430,licensed Plant Operations Declared Fire Door Inoperable.Caused by Fire Door 2L48-2R53 Blocked Open.Fire Door 2L48-2R53 Restored to Operable Status & LCO 2-93-238 Terminated ML20044D0831993-05-0303 May 1993 Special Rept 1-93-003:on 930322 & 0405,discovered That Fire Wrap Matl Not Installed on Several safety-related Cable Trays & Trays Not Installed Properly Following Breach on 930301.Maint Work Order Issued to Make Repairs ML20043A9861990-05-21021 May 1990 Special Rept 90-002:on 900328,portions of Recirculation Pump Motor Generator Set Room Wall Declared Inoperable.On 900327,electrical Raceways Declared Inoperable Due to Damaged Fire Wrapping.Hourly Fire Watch Initiated ML20042F9531990-05-0707 May 1990 Special Rept 90-003:on 900329,20 Smoke Detectors on Working Floor of Control Bldg Inoperable.Caused by Damaged Power & Control Cables to Detectors Preventing Common Input Signal from Traveling to Computer.Fire Watch Patrol Established ML20012E4681990-03-26026 March 1990 Special Rept 2-90-002:on 900321,seismic Monitoring Instrument Inoperable for Longer than 30 Days.Cause Not Determined.Seismic Instrument Declared Inoperable & Tracking of Limiting Condition for Operation Established ML20005H0971990-01-16016 January 1990 Special Rept 90-001:on 900109,drywell high-range post-accident Radiation Monitor Inoperable for More than 7 Days.Caused by Monitor Spiking Due to Component Damage. Connector Repaired & Monitor Returned to Svc ML19327A8051989-10-10010 October 1989 Special Rept 89-005:on 890919,25,28 & 1002,fire Rated Assemblies Inoperable for Longer than 14 Days.Caused by Fire Rated Assemblies & Sealing Devices Breached to Support Refueling Outage Work Activities.Fire Watches Established ML20024E7601983-07-27027 July 1983 Ro:On 830722,HPCI Auto Initiated & Injected Into Reactor to Restore & Maintain Level Following Loss of Feedwater Transient.Transient Initiated When RFPT 2B Tripped for Unknown Reasons.Rfpt 2A Out of Svc Due to Fire ML20023C3051983-05-0202 May 1983 Supplemental Narrative Summary to Rev 5 to RO 50-321/1979-021.Updated Data on Tritium Levels in Groundwater Samples During First Quarter 1983 Encl.No Radionuclides Above Background Identified ML20028E2271983-01-11011 January 1983 RO 50-321/1982-04:on 821231,cooling Tower 1A Fire Protection Deluge Sys Tripped,Decreasing Fire Water Storage Tank Vol Below Acceptable Limits.Caused by Failure of Trip Alarm in Cooling Tower.Design Change Requested ML20052G4571982-04-30030 April 1982 RO 50-321/1979-021:on 820423,tritium Levels Exceeded 3.0 E4 pCi/1 Allowance for Tritium in Environ Water Samples Per Table 3.2-3 of Ets.Cause Might Be Attributed to Slight Shifts in Main Body of Tritiated Groundwater ML20052A4331982-04-0606 April 1982 Ro:On 820217,electrician Found a 125/250-volt Dc Station Svc Batteries W/Low Specific Gravity.When Batteries Placed on Charge,Voltage Went from 130 to 142-volts Dc Causing Topaz Inverter to Trip on High Voltage ML20052A3501982-02-26026 February 1982 RO Discussing Substandard Smoke Detection Installation.Mods to Affected Areas & App R Smoke Detection Additions Will Coincide W/App R Schedule to Allow for More Complete Design Review & Consolidated Smoke Detection Plan ML20041A5991982-02-0404 February 1982 RO 50-321/1979-021,Revision 5.Provides Updated Data on Tritium Levels in Groundwater Samples Taken from Locations Where Average Value Over Fourth Quarter of 1981 Exceeded Samples According to Table 3.2-3 of ETS ML20010H8311981-09-22022 September 1981 RO 50-321/1981-090:on 810921,while Performing Surveillance Procedure HNP-1-3414,switches E51-NO12A-D Found to Be Actuating Outside Tech Spec Acceptance Criteria.Caused by Setpoint Drift.Switches Recalibr Per HNP-1-5279 ML20010H8491981-09-15015 September 1981 Ro:On 810909,HPCI Injection Valve Would Not Open Automatically During Reactor Level Decrease.Caused by Valve Motor Failure.Valve Opened Manually ML20010A3101981-07-30030 July 1981 RO 50-321/1979-021,Revision 5:provides Updated Data on Tritium Levels in Groundwater Samples.Quarterly Average Tritium Levels at Affected Locations Encl ML20010A0021981-07-30030 July 1981 RO 50-321/1981-081:on 810729,while Performing Review in Response to IE Bulletin 79-14,Bechtel Engineer Discovered RHR-SW Piping in Vicinity of RHR-SW Strainers Was Inadequately Supported.Caused by Inadequate Design ML20008F5081981-04-13013 April 1981 Ro:On 810411,following Reactor Scram on Low Reactor Water Level,Hpci Auto Initiated on Low Reactor Water Level & Injected Into Reactor Vessel.Caused by Loss of Feedwater. Reactor Water Level Was Restored to Normal ML20008E6711981-02-26026 February 1981 Special Rept:On 810221,following Reactor Scram on Low Reactor Water Level Due to Loss of Condensate Booster Pump, HPCI Was Manually Initiated & Injected Into Reactor Vessel. HPCI Was Secured After Water Level Was Restored to Normal ML19351G2981981-02-12012 February 1981 Ro:On 810113,spray/sprinkler Sys Providing Protection to Hcpi Room Discovered to Be Inoperable for 14 Days.Mod Work & Functional Test Expected to Be Complete Before End of Refueling Outage ML19340E1481980-12-31031 December 1980 Special Rept 1-sp-80-3:on 801206,during Routine Survey of Waste Oil Drums,Several Areas on Ground Were Found to Be Contaminated.Caused by Storage of Previous Waste Oil Drums. Addl Controls Re Release of Contaminated Oil Under Review ML19340D8251980-12-19019 December 1980 Ro:On 801213,sprinkler Sys Providing Protection for Reactor Bldg Heating,Ventilation & Air Conditioning Had Been Inoperative for 14 Days.Caused by Implementation of Design Mods to Bring Sys Into NFPA Code Compliance ML19347C7251980-12-19019 December 1980 Ro:On 801213,sprinkler Sys Providing Protection for Reactor Bldg Heating,Ventilation & Air Conditioning Room Had Been Inoperable for 14 Days.Sys Isolated to Implement Mods for Corrective Action to Open Item in IE Rept 50-321/80-02 ML19340D1681980-12-0404 December 1980 Ro:On 801031,at 1400-h It Was Determined That Smoke Detectors Were Not Installed Per NFPA Code 72D.Cause Not Stated.Analysis Being Made of All Detection Sys & Design Work for Affected Sys Initiated ML19338F9851980-10-21021 October 1980 Ro:On 801009,following Reactor Scram on Low Reactor Water Level Due to Loss of Feedwater,Hpci Tripped on High Reactor Water Level.Caused by HPCI Auto Initiating on Low Reactor Water Level & Injecting Into Reactor ML19338D4821980-09-15015 September 1980 Ro:On 800908,following Reactor Scram,Hpci Auto Initiated & Injected Due to Low Reactor Water Level.Caused by MSIV Closure,Which Caused Reactor Scram,Loss of RFPT & Increased Reactor Pressure.Hpci Returned Water Level to Normal ML19330B5471980-07-29029 July 1980 Ro:On 800521 & 0711,following Reactor Scram HPCI Auto Initiated & Injected.Hpci Allowed to Return Reactor Level to 58 Inches.Msiv Closed Rendering Reactor Feed Pump Turbine Unavailable for Injection.Hpci Started Manually & Injected ML19320D4541980-07-14014 July 1980 Ro:On 800711,Unit 1 LPCI Inverter Tripped & Unit 2 4-kV Bus 2F Supply Breaker & HPCI Tripped.Supply Breaker Trip Caused by Jumper Missing from Neutral Leg.Motor Valve on HPCI Replaced Making It Operable.Events Submitted Per Ieb 80-17 ML19329F9241980-07-0202 July 1980 RO 50-321/80-076:while Reviewing as-builts Submitted Per IE Bulletin 79-14,util Discovered Hangers 1E11-RHRH-196 & 1E11-RHRH-313 Would Not Adequately Support Loads During Dbe. Caused by Faulty Design in Incorrect Valve Weights ML19329F9221980-07-0202 July 1980 RO 50-366/1980-100:on 800702,while Performing Surveillance Procedures HNP-2-3002 & HNP-2-3172M,high Drywell Pressure Switches 2C71-N002A Through D & 2E11-N011A Through D Found Out of Tolerance.Caused by Setpoint Drift.Switches Recalibr ML19329F8841980-06-27027 June 1980 RO 50-321/1980-069:on 800626,following Auto Initiation Signal,Hpci Failed to Inject to Reactor Pressure Vessel Due to Isolating on Steam Line High Dp Isolation Signal.Cause Under Investigation.Reset Isolation & Opened Inboard Valve ML19326D7421980-06-25025 June 1980 Ro:On 800522,licensee Reviewed Kinemetrics,Inc 800513 Calibr Rept Re Seismic Instrumentation.Triaxial Time-History Accelerograph 2L51-NO21 Calibr Indicates Excessive Change in Longitudinal Channel Characteristics ML19329F8731980-06-23023 June 1980 RO-50-321/1980-61:on 800622,while Preparing to Run RHR Sys, B RHR Loop Min Flow Manual Valves Were Discovered Closed. Caused by Failure to Return to Open Position After Loop Was Taken Out of Shutdown Cooling Mode.Valves Locked Open ML19318A6511980-06-12012 June 1980 RO 50-321/1980-062:on 800612,w/facility in Cold Shutdown, Investigation Began to Determine Cause of Pavement Deflection Which Occurred Beneath Crane Outrigger Pad at Intake Structure.Cause of Fill Separation from Pipe Unknown ML19318A6321980-06-0202 June 1980 RO 50-321/1980-055:on 800531,snubber 36 on X32-1F7,1-inch Instrument Line from Recirculation a Loop,Appeared Locked Up During Visual Insp.Caused by Snubber Corrosion.Snubbers Failing Surveillance Test Will Be Replaced Prior to Startup ML19318A6491980-05-30030 May 1980 RO 50-321/1980-054:on 800530,nondivisional Cables H21-P173-C010 & H21-P173-C013 Found Routed W/Div I & II Type Cables/Raceways.Caused by Design & Installation Error.Design Change Request 80-166 Submitted for Cable Rerouting ML19318A6431980-05-27027 May 1980 RO 50-321/1980-053:on 800524,discovered That Loss of Essential Motor Control Ctr 1B(R24-S011) or Loss of Diesel Generator 1A During Loss of Offsite Power Will Cause RHR & Core Spray a Loops to Be Inoperable.Caused by Faulty Valve ML19323E3101980-04-30030 April 1980 Supplemental Narrative Summary to RO 50-321/79-021,Revision 5:updates Tritium Levels in Ground Water Samples.Any Releases to Unrestricted Areas Are Miniscule & Result in Insignificant Doses to Public ML19309G0441980-04-24024 April 1980 Ro:On 800206,HPCI Was Manually Started & Injected Into Reactor Vessel to Maintain Reactor Vessel Water Inventory Following Trip of Reactor Feed Pump.Caused by Loss of Reactor Feed Pump Loop Seal.Hpci Was Shut Down ML19309F1351980-04-0707 April 1980 RO 50-366/1980-045:on 800405,during Cold Shutdown,Leak Rate Test on Automatic Depressurization Sys Valve Air Supply Accumulator Check Valves Indicated Unacceptable Leakage Rates.Cause Under Investigation.No Immediate Action Taken ML19290E6311980-03-0303 March 1980 Suppl to RO 50-321/1979-021,Revision 5 Providing Data on Tritium Levels in Ground Water ML19296D1711980-02-18018 February 1980 Supplemental Narrative Summary to RO 50-321/1979-021, Revision 5:on 791202,tritium Levels in Groundwater Samples Exceeded Limits.Caused by Leakage from Blown Seal on Condensate Transfer Pump.Pumps Temporarily Confined ML19210F0301979-11-0606 November 1979 RO-79-089:on 791106,while Evaluating as-built Seismic Piping & Supports,Head Vent Line Portion of RHR Head Spray Piping & Bypass to Condenser Valve Chest Found Unsupported.Caused by Omission of Supports from Design ML19209C6511979-10-11011 October 1979 RO 50-366/79-112:on 791011,during Shutdown for Maint,Found That Intermediate Range Monitor Had Been Removed & Was Not in Control Rod Driveline Cavity of Drywell.Caused by Removal for Clean Up Operation ML19249E1021979-09-11011 September 1979 RO 50-321/1979-OB1:on 790910,LOCA Conditions Discovered Capable of Causing Several Primary Containment & Inserting Valves to Overtravel During Closure.Caused by Differential Pressure Across Valves & Loss of Seating Ability ML19249C8911979-09-10010 September 1979 Ro:On 790908,Unit 1 Was in Run Position & Unit 2 Was in Hot shutdown,E11-C001A,B & D Pumps Failed to Meet Operability Procedure HNP-1-3167 Due to Formula Errors in Pump Discharge Pressure Calculations.Units Shut Down & Formulas Reviewed ML19249C8791979-09-0404 September 1979 RO-50-366/79-98:on 790902,NSSS Supplier Contacted Plant Mgt About Possible Cable Separation Irregularities within HPCI Sys.Caused by Design Error.Proposed Design Change in Process ML19249C9061979-08-29029 August 1979 Ro:On 790812,RHR Pump Suction Torus Isolation Valve E11-F004B Leaked Back Toward Containment.Local Leak Rate Test Performed.Leakage Less than Acceptance Criteria. LER Not Required.Valve Tightened & Tested Satisfactorily 1993-06-10 Category:LER) MONTHYEARML20045B0641993-06-10010 June 1993
[Table view]Special Rept 93-004:on 930512,fire Rated Assemblies Were Inoperable for More than 14 Days Due to Inadequate Design. LCO 1-93-2010 Initiated,Appropriate Fire Detectors Were Verified Operable & Fire Watch established.W/930610 Ltr ML20044F6101993-05-21021 May 1993 Special Rept 2-93-002:on 930430,licensed Plant Operations Declared Fire Door Inoperable.Caused by Fire Door 2L48-2R53 Blocked Open.Fire Door 2L48-2R53 Restored to Operable Status & LCO 2-93-238 Terminated ML20044D0831993-05-0303 May 1993 Special Rept 1-93-003:on 930322 & 0405,discovered That Fire Wrap Matl Not Installed on Several safety-related Cable Trays & Trays Not Installed Properly Following Breach on 930301.Maint Work Order Issued to Make Repairs ML20043A9861990-05-21021 May 1990 Special Rept 90-002:on 900328,portions of Recirculation Pump Motor Generator Set Room Wall Declared Inoperable.On 900327,electrical Raceways Declared Inoperable Due to Damaged Fire Wrapping.Hourly Fire Watch Initiated ML20042F9531990-05-0707 May 1990 Special Rept 90-003:on 900329,20 Smoke Detectors on Working Floor of Control Bldg Inoperable.Caused by Damaged Power & Control Cables to Detectors Preventing Common Input Signal from Traveling to Computer.Fire Watch Patrol Established ML20012E4681990-03-26026 March 1990 Special Rept 2-90-002:on 900321,seismic Monitoring Instrument Inoperable for Longer than 30 Days.Cause Not Determined.Seismic Instrument Declared Inoperable & Tracking of Limiting Condition for Operation Established ML20005H0971990-01-16016 January 1990 Special Rept 90-001:on 900109,drywell high-range post-accident Radiation Monitor Inoperable for More than 7 Days.Caused by Monitor Spiking Due to Component Damage. Connector Repaired & Monitor Returned to Svc ML19327A8051989-10-10010 October 1989 Special Rept 89-005:on 890919,25,28 & 1002,fire Rated Assemblies Inoperable for Longer than 14 Days.Caused by Fire Rated Assemblies & Sealing Devices Breached to Support Refueling Outage Work Activities.Fire Watches Established ML20024E7601983-07-27027 July 1983 Ro:On 830722,HPCI Auto Initiated & Injected Into Reactor to Restore & Maintain Level Following Loss of Feedwater Transient.Transient Initiated When RFPT 2B Tripped for Unknown Reasons.Rfpt 2A Out of Svc Due to Fire ML20023C3051983-05-0202 May 1983 Supplemental Narrative Summary to Rev 5 to RO 50-321/1979-021.Updated Data on Tritium Levels in Groundwater Samples During First Quarter 1983 Encl.No Radionuclides Above Background Identified ML20028E2271983-01-11011 January 1983 RO 50-321/1982-04:on 821231,cooling Tower 1A Fire Protection Deluge Sys Tripped,Decreasing Fire Water Storage Tank Vol Below Acceptable Limits.Caused by Failure of Trip Alarm in Cooling Tower.Design Change Requested ML20052G4571982-04-30030 April 1982 RO 50-321/1979-021:on 820423,tritium Levels Exceeded 3.0 E4 pCi/1 Allowance for Tritium in Environ Water Samples Per Table 3.2-3 of Ets.Cause Might Be Attributed to Slight Shifts in Main Body of Tritiated Groundwater ML20052A4331982-04-0606 April 1982 Ro:On 820217,electrician Found a 125/250-volt Dc Station Svc Batteries W/Low Specific Gravity.When Batteries Placed on Charge,Voltage Went from 130 to 142-volts Dc Causing Topaz Inverter to Trip on High Voltage ML20052A3501982-02-26026 February 1982 RO Discussing Substandard Smoke Detection Installation.Mods to Affected Areas & App R Smoke Detection Additions Will Coincide W/App R Schedule to Allow for More Complete Design Review & Consolidated Smoke Detection Plan ML20041A5991982-02-0404 February 1982 RO 50-321/1979-021,Revision 5.Provides Updated Data on Tritium Levels in Groundwater Samples Taken from Locations Where Average Value Over Fourth Quarter of 1981 Exceeded Samples According to Table 3.2-3 of ETS ML20010H8311981-09-22022 September 1981 RO 50-321/1981-090:on 810921,while Performing Surveillance Procedure HNP-1-3414,switches E51-NO12A-D Found to Be Actuating Outside Tech Spec Acceptance Criteria.Caused by Setpoint Drift.Switches Recalibr Per HNP-1-5279 ML20010H8491981-09-15015 September 1981 Ro:On 810909,HPCI Injection Valve Would Not Open Automatically During Reactor Level Decrease.Caused by Valve Motor Failure.Valve Opened Manually ML20010A3101981-07-30030 July 1981 RO 50-321/1979-021,Revision 5:provides Updated Data on Tritium Levels in Groundwater Samples.Quarterly Average Tritium Levels at Affected Locations Encl ML20010A0021981-07-30030 July 1981 RO 50-321/1981-081:on 810729,while Performing Review in Response to IE Bulletin 79-14,Bechtel Engineer Discovered RHR-SW Piping in Vicinity of RHR-SW Strainers Was Inadequately Supported.Caused by Inadequate Design ML20008F5081981-04-13013 April 1981 Ro:On 810411,following Reactor Scram on Low Reactor Water Level,Hpci Auto Initiated on Low Reactor Water Level & Injected Into Reactor Vessel.Caused by Loss of Feedwater. Reactor Water Level Was Restored to Normal ML20008E6711981-02-26026 February 1981 Special Rept:On 810221,following Reactor Scram on Low Reactor Water Level Due to Loss of Condensate Booster Pump, HPCI Was Manually Initiated & Injected Into Reactor Vessel. HPCI Was Secured After Water Level Was Restored to Normal ML19351G2981981-02-12012 February 1981 Ro:On 810113,spray/sprinkler Sys Providing Protection to Hcpi Room Discovered to Be Inoperable for 14 Days.Mod Work & Functional Test Expected to Be Complete Before End of Refueling Outage ML19340E1481980-12-31031 December 1980 Special Rept 1-sp-80-3:on 801206,during Routine Survey of Waste Oil Drums,Several Areas on Ground Were Found to Be Contaminated.Caused by Storage of Previous Waste Oil Drums. Addl Controls Re Release of Contaminated Oil Under Review ML19340D8251980-12-19019 December 1980 Ro:On 801213,sprinkler Sys Providing Protection for Reactor Bldg Heating,Ventilation & Air Conditioning Had Been Inoperative for 14 Days.Caused by Implementation of Design Mods to Bring Sys Into NFPA Code Compliance ML19347C7251980-12-19019 December 1980 Ro:On 801213,sprinkler Sys Providing Protection for Reactor Bldg Heating,Ventilation & Air Conditioning Room Had Been Inoperable for 14 Days.Sys Isolated to Implement Mods for Corrective Action to Open Item in IE Rept 50-321/80-02 ML19340D1681980-12-0404 December 1980 Ro:On 801031,at 1400-h It Was Determined That Smoke Detectors Were Not Installed Per NFPA Code 72D.Cause Not Stated.Analysis Being Made of All Detection Sys & Design Work for Affected Sys Initiated ML19338F9851980-10-21021 October 1980 Ro:On 801009,following Reactor Scram on Low Reactor Water Level Due to Loss of Feedwater,Hpci Tripped on High Reactor Water Level.Caused by HPCI Auto Initiating on Low Reactor Water Level & Injecting Into Reactor ML19338D4821980-09-15015 September 1980 Ro:On 800908,following Reactor Scram,Hpci Auto Initiated & Injected Due to Low Reactor Water Level.Caused by MSIV Closure,Which Caused Reactor Scram,Loss of RFPT & Increased Reactor Pressure.Hpci Returned Water Level to Normal ML19330B5471980-07-29029 July 1980 Ro:On 800521 & 0711,following Reactor Scram HPCI Auto Initiated & Injected.Hpci Allowed to Return Reactor Level to 58 Inches.Msiv Closed Rendering Reactor Feed Pump Turbine Unavailable for Injection.Hpci Started Manually & Injected ML19320D4541980-07-14014 July 1980 Ro:On 800711,Unit 1 LPCI Inverter Tripped & Unit 2 4-kV Bus 2F Supply Breaker & HPCI Tripped.Supply Breaker Trip Caused by Jumper Missing from Neutral Leg.Motor Valve on HPCI Replaced Making It Operable.Events Submitted Per Ieb 80-17 ML19329F9241980-07-0202 July 1980 RO 50-321/80-076:while Reviewing as-builts Submitted Per IE Bulletin 79-14,util Discovered Hangers 1E11-RHRH-196 & 1E11-RHRH-313 Would Not Adequately Support Loads During Dbe. Caused by Faulty Design in Incorrect Valve Weights ML19329F9221980-07-0202 July 1980 RO 50-366/1980-100:on 800702,while Performing Surveillance Procedures HNP-2-3002 & HNP-2-3172M,high Drywell Pressure Switches 2C71-N002A Through D & 2E11-N011A Through D Found Out of Tolerance.Caused by Setpoint Drift.Switches Recalibr ML19329F8841980-06-27027 June 1980 RO 50-321/1980-069:on 800626,following Auto Initiation Signal,Hpci Failed to Inject to Reactor Pressure Vessel Due to Isolating on Steam Line High Dp Isolation Signal.Cause Under Investigation.Reset Isolation & Opened Inboard Valve ML19326D7421980-06-25025 June 1980 Ro:On 800522,licensee Reviewed Kinemetrics,Inc 800513 Calibr Rept Re Seismic Instrumentation.Triaxial Time-History Accelerograph 2L51-NO21 Calibr Indicates Excessive Change in Longitudinal Channel Characteristics ML19329F8731980-06-23023 June 1980 RO-50-321/1980-61:on 800622,while Preparing to Run RHR Sys, B RHR Loop Min Flow Manual Valves Were Discovered Closed. Caused by Failure to Return to Open Position After Loop Was Taken Out of Shutdown Cooling Mode.Valves Locked Open ML19318A6511980-06-12012 June 1980 RO 50-321/1980-062:on 800612,w/facility in Cold Shutdown, Investigation Began to Determine Cause of Pavement Deflection Which Occurred Beneath Crane Outrigger Pad at Intake Structure.Cause of Fill Separation from Pipe Unknown ML19318A6321980-06-0202 June 1980 RO 50-321/1980-055:on 800531,snubber 36 on X32-1F7,1-inch Instrument Line from Recirculation a Loop,Appeared Locked Up During Visual Insp.Caused by Snubber Corrosion.Snubbers Failing Surveillance Test Will Be Replaced Prior to Startup ML19318A6491980-05-30030 May 1980 RO 50-321/1980-054:on 800530,nondivisional Cables H21-P173-C010 & H21-P173-C013 Found Routed W/Div I & II Type Cables/Raceways.Caused by Design & Installation Error.Design Change Request 80-166 Submitted for Cable Rerouting ML19318A6431980-05-27027 May 1980 RO 50-321/1980-053:on 800524,discovered That Loss of Essential Motor Control Ctr 1B(R24-S011) or Loss of Diesel Generator 1A During Loss of Offsite Power Will Cause RHR & Core Spray a Loops to Be Inoperable.Caused by Faulty Valve ML19323E3101980-04-30030 April 1980 Supplemental Narrative Summary to RO 50-321/79-021,Revision 5:updates Tritium Levels in Ground Water Samples.Any Releases to Unrestricted Areas Are Miniscule & Result in Insignificant Doses to Public ML19309G0441980-04-24024 April 1980 Ro:On 800206,HPCI Was Manually Started & Injected Into Reactor Vessel to Maintain Reactor Vessel Water Inventory Following Trip of Reactor Feed Pump.Caused by Loss of Reactor Feed Pump Loop Seal.Hpci Was Shut Down ML19309F1351980-04-0707 April 1980 RO 50-366/1980-045:on 800405,during Cold Shutdown,Leak Rate Test on Automatic Depressurization Sys Valve Air Supply Accumulator Check Valves Indicated Unacceptable Leakage Rates.Cause Under Investigation.No Immediate Action Taken ML19290E6311980-03-0303 March 1980 Suppl to RO 50-321/1979-021,Revision 5 Providing Data on Tritium Levels in Ground Water ML19296D1711980-02-18018 February 1980 Supplemental Narrative Summary to RO 50-321/1979-021, Revision 5:on 791202,tritium Levels in Groundwater Samples Exceeded Limits.Caused by Leakage from Blown Seal on Condensate Transfer Pump.Pumps Temporarily Confined ML19210F0301979-11-0606 November 1979 RO-79-089:on 791106,while Evaluating as-built Seismic Piping & Supports,Head Vent Line Portion of RHR Head Spray Piping & Bypass to Condenser Valve Chest Found Unsupported.Caused by Omission of Supports from Design ML19209C6511979-10-11011 October 1979 RO 50-366/79-112:on 791011,during Shutdown for Maint,Found That Intermediate Range Monitor Had Been Removed & Was Not in Control Rod Driveline Cavity of Drywell.Caused by Removal for Clean Up Operation ML19249E1021979-09-11011 September 1979 RO 50-321/1979-OB1:on 790910,LOCA Conditions Discovered Capable of Causing Several Primary Containment & Inserting Valves to Overtravel During Closure.Caused by Differential Pressure Across Valves & Loss of Seating Ability ML19249C8911979-09-10010 September 1979 Ro:On 790908,Unit 1 Was in Run Position & Unit 2 Was in Hot shutdown,E11-C001A,B & D Pumps Failed to Meet Operability Procedure HNP-1-3167 Due to Formula Errors in Pump Discharge Pressure Calculations.Units Shut Down & Formulas Reviewed ML19249C8791979-09-0404 September 1979 RO-50-366/79-98:on 790902,NSSS Supplier Contacted Plant Mgt About Possible Cable Separation Irregularities within HPCI Sys.Caused by Design Error.Proposed Design Change in Process ML19249C9061979-08-29029 August 1979 Ro:On 790812,RHR Pump Suction Torus Isolation Valve E11-F004B Leaked Back Toward Containment.Local Leak Rate Test Performed.Leakage Less than Acceptance Criteria. LER Not Required.Valve Tightened & Tested Satisfactorily 1993-06-10 Category:TEXT-SAFETY REPORT MONTHYEARML20217D3061999-10-13013 October 1999
[Table view]SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207E7631999-06-0303 June 1999 Safety Evaluation Concluding That Licensee Proposed Alternative to Use Code Case N-509 Contained in RR-4 Provides Acceptable Level of Quality & Safety.Considers Rev 2 to RR-4 & RR-6 Acceptable HL-5795, Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with ML20206G1691999-05-0404 May 1999 SER Approving Requirements of Istb 4.6.2(b) Pursuant to 10CFR50.55a(a)(3)(ii) HL-5784, Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5766, Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207M1891999-03-11011 March 1999 SER Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Weld HL-5755, Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20206P6981999-01-0707 January 1999 Ehnp Intake Structure Licensing Rept HL-5726, Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20196J4931998-12-0707 December 1998 Safety Evaluation Accepting Proposed Alternatives in Relief Requests RR-V-12,RR-V-15,RR-P-15,RR-V-7,RR-V-12,RR-V-14 & RR-V-15 HL-5714, Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5706, Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With ML20155B6121998-10-28028 October 1998 Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Topical Rept. Rept Acceptable HL-5691, Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20153G2481998-09-24024 September 1998 SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request ML20239A2531998-09-0303 September 1998 SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl HL-5675, Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20238F7131998-08-31031 August 1998 9,change 2 to QAP 1.0, Organization HL-5667, Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998 Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures ML20236W3441998-07-30030 July 1998 Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2 ML20236V5191998-07-28028 July 1998 Safety Evaluation Accepting Proposed License Amend Power Uprate Review ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L1821998-07-0707 July 1998 Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3) HL-5653, Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5640, Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20248B8651998-05-15015 May 1998 Quadrennial Simulator Certification Rept HL-5628, Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant1998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant HL-5604, Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20216B2711998-02-28028 February 1998 Extended Power Uprate Safety Analysis Rept for Ei Hatch Plant,Units 1 & 2 HL-5585, Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5571, Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 11998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 1 HL-5551, Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20199B0561997-12-31031 December 1997 Rev 0 GE-NE-B13-01869-122, Jet Pump Riser Weld Flaw Evaluation Handbook for Hatch Unit 1 HL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 21997-12-31031 December 1997 Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2 HL-5533, Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5514, Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 21997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20212A1981997-10-16016 October 1997 Safety Evaluation Denying Licensee Request for Relief from Implementation of 10CFR50.55a Requirements Re Use of 1992 Edition of ASME Code Section XI for ISI of Containments ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H5311997-10-0101 October 1997 Rev 2 to Unit 1,Cycle 17 Colr ML20211H5251997-10-0101 October 1997 Rev 3 to Unit 1,Cycle 17 Colr 1999-09-30 |
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',. N Narrative for Special Report 50-321/1982-04 This special report is submitted to report the reduction of fire water minimum acceptable limits as tank storage inventory below the
, specified in Unit 1 Tech. Specs. 3.13.2.b and Unit 2 Tech. Specs.
3.7.6.1.b and the failure to meet reporting requirements per Unit 2 Tech. Specs. 3.7.6.1, ACTION b.2.a. Information regarding this event is given below:
On 12-31-82, at 0038 CST with Unit 1 in a refueling outage and Unit 2 in steady state operation at 2413 MWt, the lA cooling tower fire protection deluge system tripped. This trip caused both diesel fire pumps to start on low fire protection system heeder pressure which began decreasing the fire water storage tank volume. Also at the same time, the cooling tower trip alarm failed to activate on the control room fire alarm panel. As a result, the locating of the syste:a trip was hindered, this resulted in reduction of the storage tank levels below the minimum acceptable limits. Unit 1 Tech. Specs. 3.13.2.b and Unit 2 Tech. Specs. 3.7.6.1.b require a minimum level of 270,000 gals per storage tank. The event dropped the level in both the fire water storage tanks to a useable volume of approximately 245,000 gals per tank or a total of 490,000 gals. During this event, the two diesel fire pumps remained operable.
The 1A cooling tower deluge system was isolated and the fire protection system returned to normal per Tech. Specs. sections 3.13.2.b and 3.7.6.1.b. Due to personnel error the telephone contact within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was not met, as required per Tech. Specs. section 3.7.6.1 ACTION b.2.a. Personnel have been counseled as to the importance of meeting Tech. Specs. reporting requirements.
To prevent recurrence of the fire water storage tank low level problem, modifications are to be made under a Design Changu Request to provide a more adequate warning of fire tan': water levels.
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