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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20046B3981993-07-28028 July 1993 Special Rept 93-13:on 930715,fire Header in Auxiliary Bldg Removed from Svc as Result of Maint Activities in Process of Repairing & Replacing Leaking Lines.Fire Watches & Backup Fire Suppression Water Sys Established ML20046A6841993-07-23023 July 1993 Special Rept 93-10:on 930619,penetration Marks 20 & 1287 Were Breached to Route Electrical Sensor Cables Into Unit 1 Annulus Area & to Route Instrument Cables Into ABGTS Room. Roving Fire Watch Established ML20046A5341993-07-19019 July 1993 Special Rept 93-09 Provides Detail Re 19 Fire Protection Barriers,Detection Sys & Water Suppression Sys Being Impaired for Period Greater than TS Allowable Timeframe ML20045H9681993-07-16016 July 1993 Special Rept 93-12:on 930621,portion of Fire Header in Auxiliary Bldg Removed from Svc & Sys Not Restored to Operability within TS Required Time Period.Piping Repaired & Incident Investigation Initiated ML20045G6391993-07-0707 July 1993 Special Rept 93-11:on 930624,portion of Fire Header in Auxiliary Bldg Removed from Svc as Result of Maint Activities & Water Flooded Penetration Room.Fire Suppression Sys Declared Inoperable & LCO 3.7.11.1 Entered ML20045E6881993-06-25025 June 1993 Special Rept 93-07:on 930519,0521 & 0527,fire Doors A-146 & A-44 & A-196,respectively,were Breached Open.On 930525, Mechanical Sleeve C2/J Breached to Permit Cable Pulling. Detectors Verified Operable & Fire Watch Established ML20045C9211993-06-17017 June 1993 Special Rept 93-06:on 930511,HPFP Sys Operated W/Only One Operable HPFP Pump for Period,Exceeding TS 3.7.11.1 Allowable Timeframe Due to Maint.Dg 2A-A Returned to Svc on 930519 & EP Supply Reestablished to 2A-A HPFP Pump ML20044G5521993-05-27027 May 1993 Special Rept 93-05:on 930426,fire Barrier for Mechanical Sleeve Between 480-volt Shutdown Board Rooms 1B1 & 1B2 Breached.Caused by Unavailability of Fire Retardant Sealant.Roving Fire Watch Established ML20028H3751990-12-21021 December 1990 Special Rept 90-18:on 901213,four Fire Suppression Pumps Declared Inoperable Bybeing Placed in Manual in Accordance W/Work Request C010259.Caused by Bypass Leakage of Isolation Valve ML20043G4021990-06-13013 June 1990 Special Rept 90-11:on 900531,noncompliances W/License Conditions 2.C.13.a & 2.C.13.c Re Fire Protection Plan Identified.Caused by Design Deficiency in Original Wall Design.Roving Fire Watch Established ML20043D7131990-06-0505 June 1990 Special Rept 90-10:on 900522,noncompliance W/License Condition 2.C.13.c Re Section III.G.2 of 10CFR50,App R Noted.Initially Reported on 900523.Caused by Oversight During Previous Efforts to Ensure Compliance W/App R ML20043B6641990-05-29029 May 1990 Special Rept 90-09:on 900515,condenser Vacuum Exhaust Vent mid-range Noble Gas Monitor 2-RM-90-405 Inoperable for More than 7 Days.Caused by Damaged/Degraded Detector Cable.New Cable Expected to Be Installed by 900608 ML20043B8311990-05-23023 May 1990 Ro:On 900522,cables Re Indication of RCS Pressure Encl in 1-hr Fire Rated Barrier But Area Not Covered by Fire Detectors or Automatic Fire Suppression Sys.Corrective Actions Plan Will Be Provided in 14-day Followup Rept ML20043B2111990-05-22022 May 1990 Special Rept 90-08:on 900508,portion of Fire Suppression Water Sys in Auxiliary & Control Bldgs Removed from Svc & Declared Inoperable.Caused by Leak in Fire Header.Fire Watches & Backup Fire Suppression Sys Established ML20042E8581990-05-0101 May 1990 Special Rept 90-07:on 900411,inoperability of Fire Detection Instrumentation for Fire Zones 134,135,142,143,144 & 145 on Elevation 714 of Auxiliary Bldg.Continuous Fire Watch Established for Affected Zones ML20012A0111990-03-0101 March 1990 Special Rept 90-03:on 900121,trouble Alarm on Fire Protection Panel O-L-630 Observed.Caused by Malfunction of Fire Detector in Fire Zone 353 Located in Lower Compartment of Unit 2 Containment.Work Request Initiated ML20011E7961990-02-0909 February 1990 Special Rept 90-01:on 900126,Limiting Condition for Operation 3.7.11.1 Entered When Two Fire Suppression Water Strainers Removed from Svc During Planned Outage.Strainers Cleaned & Repaired & Pressure Control Valve Returned to Svc ML20006E3281990-02-0909 February 1990 Special Rept 90-02:on 900126,electrical Cables to Ensure RCS Letdown Path Exists Did Not Meet Separation Requirements in Two Plant Locations.Caused by Deficiencies in Development of App R Sketch Drawings.Roving Fire Watches Established ML20011E1351990-01-29029 January 1990 Ro:On 900126,fire Suppression Sys Declared Inoperable Due to Extended Fire Header Outage.Alternate Flow Path Established by Installing Hose Around Strainers.Repair Work Completed & Limiting Condition for Operation Exited ML19332C0561989-11-17017 November 1989 Special Rept 89-14:on 891021,four Fire Barriers Nonfunctional for Interval Greater than 7 Days.Caused by Centrifugal Charging Pump Room Coolers Leaking ERCW from Cooling Coils.Roving Fire Watch Remains in Effect ML19325F2721989-11-13013 November 1989 Special Rept 89-13:on 891028,upper & Lower containment,high- range,post-accident Radiation Monitors Declared Inoperable. Caused by Channel Calibr Surveillance Interval Being Exceeded.Alternative Method to Monitor Bldg Provided ML19327B1381989-10-23023 October 1989 Special Rept 89-12:on 890907,smoke Detectors in Fire Detection Zone 352,lower Compartment Coolers Inoperable Per Trouble Light on Panel O-L-629.Cause Will Not Be Determined Until Entry Into Fire Zone.Air Temp Monitored Hourly ML19325D4621989-10-17017 October 1989 Special Rept 89-11 Re Noncompliance W/Requirements of License Condition Section 2.C.13.c Re 10CFR50,App R.Caused by Inadequate Design Review in Area of Power Supplies to Main Control Room Recorders.Roving Fire Watches Established ML20028G6431983-02-0909 February 1983 RO-83-01:on 821214,diesel Generator 2B-B Tripped on Differential Overcurrent.On 821216,diesel Generator 2B-B Started But Failed to Exceed 2,000-volt Output.On 821219, Diesel Generator 1B-B Leaked Oil from Tee Fitting ML20028F4551983-01-27027 January 1983 RO 83-02:during Functional Test,Discovered Ruskin Mfg Co Vertical Fire Dampers Will Not Completely Close in Ductwork W/High Velocity Air Flow.Installation of Negator Spring & Positive Blade Latch Recommended ML20052H5281982-04-0808 April 1982 RO 82-1:on 820112,19 & 21,unit Experienced Safety Injection Actuation.Caused by Inadvertent Opening of Turbine Throttle Valves,Low Pressurizer Pressure Following Reactor Trip & High Steam Flow Signal Coincident w/Lo-Lo Tavg Signal ML20040G7811982-02-0909 February 1982 Ro:On 820128,sample Collected on Svc Bldg Sump Discharge Exceeded Limitations of NPDES Permit TN0026450.Caused by Failure to Clean Sump Routinely Due to Plant Workload.Sump Cleaned ML20040E9421982-01-25025 January 1982 RO 81-7:on 811104,during Surveillance Instruction 90.12, Safety Injection Actuation Occurred.Caused by Shorted Connector Wire Between Low Pressure Logic Board Pins in Train B Solid State Protection Sys ML20039C4071981-12-22022 December 1981 Telecopy of RO 50-328/81152:on 811222,while Increasing Reactor Parameters for Power Ascension,Control Rod Withdrawal Limits Were Violated.Operating Limits Not in Startup Procedures.Boron Concentration Diluted ML20011A7261981-10-16016 October 1981 RO 50-327/81120:on 811016,while re-evaluating Max post- Accident Water Level Inside Containment,Class IE Electrical Components 1-PT-68-68,1 & 2-TE-68-1/24/60/83 & Four Lower Containment Hydrogen Igniters Were Found Potentially Unsafe ML20009H5061981-07-29029 July 1981 RO 50-327/81085:on 810719,during Linkage Interlock Test on Lower Containment Personnel Access Lock,Inner Door Slammed & Bounced Back While Outer Door Was Opened.Caused by Excessive Slack in Door Operating Linkage ML20009F8631981-06-26026 June 1981 Ro:On 810531,w/unit at 98% Power,Inadvertent Safety Injection Occurred.Caused by Use of Radio in Vicinity of Pressurizer Pressure Transmitters in Unit 1 Incore Instrument Room.Use of 2-way Radios Prohibited ML20009F6161981-06-26026 June 1981 Ro:On 810626,equipment Insp Revealed Steam Generator Level Transmitters 1-LT-3-148,156,164,172,174 & 175 Could Fail During Loca.Caused by Degraded Teflon Insulation.Defective Amplifiers Replaced ML20009G0971981-06-19019 June 1981 Ro:Fire Door A62,located in Auxiliary Bldg Was Determined Nonfunctional in Excess of 7 Days.Caused by Damaged Door Frame,Preventing Door from Completely Closing & Latching. Fire Watch Coverage Ordered,Pending Repair ML20004D4561981-06-0505 June 1981 RO 81-2:on 810423 & 0501,during Performance of Main Turbine Overspeed Test & Recovery from Generator Trip Test, Respectively,Inadvertent Safety Injections Occurred.Safety Injection Signal Was Actuated & RCS Restored to Normal ML19347E6011981-05-11011 May 1981 Ro:On 810504,chlorine Residual Exceeded Max Permit Limit. Caused by Insufficient Water Being Added to Sodium Hypochlorite Reservoir to Achieve Proper Chlorine Dilution. Solution Diluted by Adding More Water ML20003J2971981-05-0404 May 1981 Ro:During First Quarter of 1981,calculated Dose to Bone for Hypothetical Individual Exceeded Tech Spec Limits.Caused by Personnel Error.All Releases Terminated Until Demineralizer Was Installed ML19350C1871981-03-24024 March 1981 Special Rept 80-8:during Third & Fourth Quarters of 1980, Tech Spec 3.11.1.2 Found Exceeded.Caused by Effluent Releases of P-32 from Facility.Investigation of P-32 in Secondary Cycle Will Continue Following Plant Startup ML19345G2601981-03-0909 March 1981 RO 80-008:exceeded Tech Spec 3.11.1.2 During Third & Fourth Quarters of 1980,failing to Notify Commission When Dose Requirements Limit Was Broken.Apparently Caused by Breakdown in Inter/Intradivisional Communications Sys ML19341A0221981-01-0909 January 1981 RO 80-6 on 801201 & 02:Na-24 Was Inadvertently Injected Into Turbine Bldg Sump.Caused by Inadequate Test Instructions & Poor Communications Between Test Directors & Radiochemical Lab Personnel ML19340B2791980-10-0606 October 1980 RO 80-069:inadvertent Initiation of Safety Injection Signal Occurred But Did Not Result in Water Injection Into Rcs. Caused by Sys Lineups Utilized for Overpressure Protection ML19338D5931980-09-17017 September 1980 Special Rept 80-4:on 800623,unit Received Safety Injection Signal from High Steam Flow & lo-lo Tave Signal or Lo Steam Generator Pressure.Approx 540 Gallons Borated Water Injected Into RCS at 190 F.Originally Reported as 5,400 Gallons ML19331D6201980-08-27027 August 1980 RO 80-3:with Reactor on Mode 4,both Centrifugal Charging Pumps Automatically Started Injecting 535 Gallons of 20,000 Ppm Borated Water at 193 F Into Rcs.Caused by Incorrect Switch Manipulation During Test Performance ML19344E0371980-08-18018 August 1980 Special Rept 80-2,Revision 1:on 800706,moderator Temp Coefficient Found Not to Meet Tech Specs Criteria.Control Rod Withdrawal Limits Determined.Conservatism Included in Limits to Ensure Proper Reactor Operation ML19331B5551980-08-0606 August 1980 Notifies That on 800723,samples Taken of Const Sewage Treatment Plant Effluents Contained Suspended Solids in Excess of Tech Spec Limits.Caused by Change in Aeration Cycle & Failed Air Lift Pump.Aeration Cycle Readjusted ML19330A8401980-07-15015 July 1980 RO 80-2:on 800706,during Low Power Physics Testing at all- Control Rods Out Configuration,Moderator Temp Coefficient Found Out of Spec.Control Rod Withdrawal Limits Determined ML19326E0521980-07-15015 July 1980 Special Rept 80-02:on 800706,moderator Temp Coefficient Measured Less Positive than Limit Established in Tech Specs During Low Power Physics Testing.Control Rod Withdrawal Limit Determined as Shown in Encl Graph ML19320A9761980-07-0101 July 1980 Special Rept 80-01:on 800605,firestop Penetration MK121 Support Clearance Reported Excessive During Piping Configuration insp.Seven-day Time Requirement Exceeded Prior to Penetration Remeasurement & Closing on 800606 ML19316B1061980-05-15015 May 1980 RO SQRC-50-327/80049:on 800514,insufficient Clearance Found Between Support Guide 1-SIH-316 & 4-inch Safety Injection Pipe.Apparently Caused by Incorrect Installation Due to Misinterpretation of Specs.Guide Support Repaired ML19323H0611980-05-0202 May 1980 Ro:On 800427,2-inch Containment Spray Test Lines Analyzed Using Incorrect Outside Diameter for Pipe Resulting in Analytical Model Being More Rigid than Actual Pipe.Caused by Error in Input Not Found During Checking 1993-07-07
[Table view] Category:LER)
MONTHYEARML20046B3981993-07-28028 July 1993 Special Rept 93-13:on 930715,fire Header in Auxiliary Bldg Removed from Svc as Result of Maint Activities in Process of Repairing & Replacing Leaking Lines.Fire Watches & Backup Fire Suppression Water Sys Established ML20046A6841993-07-23023 July 1993 Special Rept 93-10:on 930619,penetration Marks 20 & 1287 Were Breached to Route Electrical Sensor Cables Into Unit 1 Annulus Area & to Route Instrument Cables Into ABGTS Room. Roving Fire Watch Established ML20046A5341993-07-19019 July 1993 Special Rept 93-09 Provides Detail Re 19 Fire Protection Barriers,Detection Sys & Water Suppression Sys Being Impaired for Period Greater than TS Allowable Timeframe ML20045H9681993-07-16016 July 1993 Special Rept 93-12:on 930621,portion of Fire Header in Auxiliary Bldg Removed from Svc & Sys Not Restored to Operability within TS Required Time Period.Piping Repaired & Incident Investigation Initiated ML20045G6391993-07-0707 July 1993 Special Rept 93-11:on 930624,portion of Fire Header in Auxiliary Bldg Removed from Svc as Result of Maint Activities & Water Flooded Penetration Room.Fire Suppression Sys Declared Inoperable & LCO 3.7.11.1 Entered ML20045E6881993-06-25025 June 1993 Special Rept 93-07:on 930519,0521 & 0527,fire Doors A-146 & A-44 & A-196,respectively,were Breached Open.On 930525, Mechanical Sleeve C2/J Breached to Permit Cable Pulling. Detectors Verified Operable & Fire Watch Established ML20045C9211993-06-17017 June 1993 Special Rept 93-06:on 930511,HPFP Sys Operated W/Only One Operable HPFP Pump for Period,Exceeding TS 3.7.11.1 Allowable Timeframe Due to Maint.Dg 2A-A Returned to Svc on 930519 & EP Supply Reestablished to 2A-A HPFP Pump ML20044G5521993-05-27027 May 1993 Special Rept 93-05:on 930426,fire Barrier for Mechanical Sleeve Between 480-volt Shutdown Board Rooms 1B1 & 1B2 Breached.Caused by Unavailability of Fire Retardant Sealant.Roving Fire Watch Established ML20028H3751990-12-21021 December 1990 Special Rept 90-18:on 901213,four Fire Suppression Pumps Declared Inoperable Bybeing Placed in Manual in Accordance W/Work Request C010259.Caused by Bypass Leakage of Isolation Valve ML20043G4021990-06-13013 June 1990 Special Rept 90-11:on 900531,noncompliances W/License Conditions 2.C.13.a & 2.C.13.c Re Fire Protection Plan Identified.Caused by Design Deficiency in Original Wall Design.Roving Fire Watch Established ML20043D7131990-06-0505 June 1990 Special Rept 90-10:on 900522,noncompliance W/License Condition 2.C.13.c Re Section III.G.2 of 10CFR50,App R Noted.Initially Reported on 900523.Caused by Oversight During Previous Efforts to Ensure Compliance W/App R ML20043B6641990-05-29029 May 1990 Special Rept 90-09:on 900515,condenser Vacuum Exhaust Vent mid-range Noble Gas Monitor 2-RM-90-405 Inoperable for More than 7 Days.Caused by Damaged/Degraded Detector Cable.New Cable Expected to Be Installed by 900608 ML20043B8311990-05-23023 May 1990 Ro:On 900522,cables Re Indication of RCS Pressure Encl in 1-hr Fire Rated Barrier But Area Not Covered by Fire Detectors or Automatic Fire Suppression Sys.Corrective Actions Plan Will Be Provided in 14-day Followup Rept ML20043B2111990-05-22022 May 1990 Special Rept 90-08:on 900508,portion of Fire Suppression Water Sys in Auxiliary & Control Bldgs Removed from Svc & Declared Inoperable.Caused by Leak in Fire Header.Fire Watches & Backup Fire Suppression Sys Established ML20042E8581990-05-0101 May 1990 Special Rept 90-07:on 900411,inoperability of Fire Detection Instrumentation for Fire Zones 134,135,142,143,144 & 145 on Elevation 714 of Auxiliary Bldg.Continuous Fire Watch Established for Affected Zones ML20012A0111990-03-0101 March 1990 Special Rept 90-03:on 900121,trouble Alarm on Fire Protection Panel O-L-630 Observed.Caused by Malfunction of Fire Detector in Fire Zone 353 Located in Lower Compartment of Unit 2 Containment.Work Request Initiated ML20011E7961990-02-0909 February 1990 Special Rept 90-01:on 900126,Limiting Condition for Operation 3.7.11.1 Entered When Two Fire Suppression Water Strainers Removed from Svc During Planned Outage.Strainers Cleaned & Repaired & Pressure Control Valve Returned to Svc ML20006E3281990-02-0909 February 1990 Special Rept 90-02:on 900126,electrical Cables to Ensure RCS Letdown Path Exists Did Not Meet Separation Requirements in Two Plant Locations.Caused by Deficiencies in Development of App R Sketch Drawings.Roving Fire Watches Established ML20011E1351990-01-29029 January 1990 Ro:On 900126,fire Suppression Sys Declared Inoperable Due to Extended Fire Header Outage.Alternate Flow Path Established by Installing Hose Around Strainers.Repair Work Completed & Limiting Condition for Operation Exited ML19332C0561989-11-17017 November 1989 Special Rept 89-14:on 891021,four Fire Barriers Nonfunctional for Interval Greater than 7 Days.Caused by Centrifugal Charging Pump Room Coolers Leaking ERCW from Cooling Coils.Roving Fire Watch Remains in Effect ML19325F2721989-11-13013 November 1989 Special Rept 89-13:on 891028,upper & Lower containment,high- range,post-accident Radiation Monitors Declared Inoperable. Caused by Channel Calibr Surveillance Interval Being Exceeded.Alternative Method to Monitor Bldg Provided ML19327B1381989-10-23023 October 1989 Special Rept 89-12:on 890907,smoke Detectors in Fire Detection Zone 352,lower Compartment Coolers Inoperable Per Trouble Light on Panel O-L-629.Cause Will Not Be Determined Until Entry Into Fire Zone.Air Temp Monitored Hourly ML19325D4621989-10-17017 October 1989 Special Rept 89-11 Re Noncompliance W/Requirements of License Condition Section 2.C.13.c Re 10CFR50,App R.Caused by Inadequate Design Review in Area of Power Supplies to Main Control Room Recorders.Roving Fire Watches Established ML20028G6431983-02-0909 February 1983 RO-83-01:on 821214,diesel Generator 2B-B Tripped on Differential Overcurrent.On 821216,diesel Generator 2B-B Started But Failed to Exceed 2,000-volt Output.On 821219, Diesel Generator 1B-B Leaked Oil from Tee Fitting ML20028F4551983-01-27027 January 1983 RO 83-02:during Functional Test,Discovered Ruskin Mfg Co Vertical Fire Dampers Will Not Completely Close in Ductwork W/High Velocity Air Flow.Installation of Negator Spring & Positive Blade Latch Recommended ML20052H5281982-04-0808 April 1982 RO 82-1:on 820112,19 & 21,unit Experienced Safety Injection Actuation.Caused by Inadvertent Opening of Turbine Throttle Valves,Low Pressurizer Pressure Following Reactor Trip & High Steam Flow Signal Coincident w/Lo-Lo Tavg Signal ML20040G7811982-02-0909 February 1982 Ro:On 820128,sample Collected on Svc Bldg Sump Discharge Exceeded Limitations of NPDES Permit TN0026450.Caused by Failure to Clean Sump Routinely Due to Plant Workload.Sump Cleaned ML20040E9421982-01-25025 January 1982 RO 81-7:on 811104,during Surveillance Instruction 90.12, Safety Injection Actuation Occurred.Caused by Shorted Connector Wire Between Low Pressure Logic Board Pins in Train B Solid State Protection Sys ML20039C4071981-12-22022 December 1981 Telecopy of RO 50-328/81152:on 811222,while Increasing Reactor Parameters for Power Ascension,Control Rod Withdrawal Limits Were Violated.Operating Limits Not in Startup Procedures.Boron Concentration Diluted ML20011A7261981-10-16016 October 1981 RO 50-327/81120:on 811016,while re-evaluating Max post- Accident Water Level Inside Containment,Class IE Electrical Components 1-PT-68-68,1 & 2-TE-68-1/24/60/83 & Four Lower Containment Hydrogen Igniters Were Found Potentially Unsafe ML20009H5061981-07-29029 July 1981 RO 50-327/81085:on 810719,during Linkage Interlock Test on Lower Containment Personnel Access Lock,Inner Door Slammed & Bounced Back While Outer Door Was Opened.Caused by Excessive Slack in Door Operating Linkage ML20009F8631981-06-26026 June 1981 Ro:On 810531,w/unit at 98% Power,Inadvertent Safety Injection Occurred.Caused by Use of Radio in Vicinity of Pressurizer Pressure Transmitters in Unit 1 Incore Instrument Room.Use of 2-way Radios Prohibited ML20009F6161981-06-26026 June 1981 Ro:On 810626,equipment Insp Revealed Steam Generator Level Transmitters 1-LT-3-148,156,164,172,174 & 175 Could Fail During Loca.Caused by Degraded Teflon Insulation.Defective Amplifiers Replaced ML20009G0971981-06-19019 June 1981 Ro:Fire Door A62,located in Auxiliary Bldg Was Determined Nonfunctional in Excess of 7 Days.Caused by Damaged Door Frame,Preventing Door from Completely Closing & Latching. Fire Watch Coverage Ordered,Pending Repair ML20004D4561981-06-0505 June 1981 RO 81-2:on 810423 & 0501,during Performance of Main Turbine Overspeed Test & Recovery from Generator Trip Test, Respectively,Inadvertent Safety Injections Occurred.Safety Injection Signal Was Actuated & RCS Restored to Normal ML19347E6011981-05-11011 May 1981 Ro:On 810504,chlorine Residual Exceeded Max Permit Limit. Caused by Insufficient Water Being Added to Sodium Hypochlorite Reservoir to Achieve Proper Chlorine Dilution. Solution Diluted by Adding More Water ML20003J2971981-05-0404 May 1981 Ro:During First Quarter of 1981,calculated Dose to Bone for Hypothetical Individual Exceeded Tech Spec Limits.Caused by Personnel Error.All Releases Terminated Until Demineralizer Was Installed ML19350C1871981-03-24024 March 1981 Special Rept 80-8:during Third & Fourth Quarters of 1980, Tech Spec 3.11.1.2 Found Exceeded.Caused by Effluent Releases of P-32 from Facility.Investigation of P-32 in Secondary Cycle Will Continue Following Plant Startup ML19345G2601981-03-0909 March 1981 RO 80-008:exceeded Tech Spec 3.11.1.2 During Third & Fourth Quarters of 1980,failing to Notify Commission When Dose Requirements Limit Was Broken.Apparently Caused by Breakdown in Inter/Intradivisional Communications Sys ML19341A0221981-01-0909 January 1981 RO 80-6 on 801201 & 02:Na-24 Was Inadvertently Injected Into Turbine Bldg Sump.Caused by Inadequate Test Instructions & Poor Communications Between Test Directors & Radiochemical Lab Personnel ML19340B2791980-10-0606 October 1980 RO 80-069:inadvertent Initiation of Safety Injection Signal Occurred But Did Not Result in Water Injection Into Rcs. Caused by Sys Lineups Utilized for Overpressure Protection ML19338D5931980-09-17017 September 1980 Special Rept 80-4:on 800623,unit Received Safety Injection Signal from High Steam Flow & lo-lo Tave Signal or Lo Steam Generator Pressure.Approx 540 Gallons Borated Water Injected Into RCS at 190 F.Originally Reported as 5,400 Gallons ML19331D6201980-08-27027 August 1980 RO 80-3:with Reactor on Mode 4,both Centrifugal Charging Pumps Automatically Started Injecting 535 Gallons of 20,000 Ppm Borated Water at 193 F Into Rcs.Caused by Incorrect Switch Manipulation During Test Performance ML19344E0371980-08-18018 August 1980 Special Rept 80-2,Revision 1:on 800706,moderator Temp Coefficient Found Not to Meet Tech Specs Criteria.Control Rod Withdrawal Limits Determined.Conservatism Included in Limits to Ensure Proper Reactor Operation ML19331B5551980-08-0606 August 1980 Notifies That on 800723,samples Taken of Const Sewage Treatment Plant Effluents Contained Suspended Solids in Excess of Tech Spec Limits.Caused by Change in Aeration Cycle & Failed Air Lift Pump.Aeration Cycle Readjusted ML19330A8401980-07-15015 July 1980 RO 80-2:on 800706,during Low Power Physics Testing at all- Control Rods Out Configuration,Moderator Temp Coefficient Found Out of Spec.Control Rod Withdrawal Limits Determined ML19326E0521980-07-15015 July 1980 Special Rept 80-02:on 800706,moderator Temp Coefficient Measured Less Positive than Limit Established in Tech Specs During Low Power Physics Testing.Control Rod Withdrawal Limit Determined as Shown in Encl Graph ML19320A9761980-07-0101 July 1980 Special Rept 80-01:on 800605,firestop Penetration MK121 Support Clearance Reported Excessive During Piping Configuration insp.Seven-day Time Requirement Exceeded Prior to Penetration Remeasurement & Closing on 800606 ML19316B1061980-05-15015 May 1980 RO SQRC-50-327/80049:on 800514,insufficient Clearance Found Between Support Guide 1-SIH-316 & 4-inch Safety Injection Pipe.Apparently Caused by Incorrect Installation Due to Misinterpretation of Specs.Guide Support Repaired ML19323H0611980-05-0202 May 1980 Ro:On 800427,2-inch Containment Spray Test Lines Analyzed Using Incorrect Outside Diameter for Pipe Resulting in Analytical Model Being More Rigid than Actual Pipe.Caused by Error in Input Not Found During Checking 1993-07-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
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. -: s ~~ - :t 1 1750 Cheetant street Tower II January 9, 1981 tir. J.*ess P. O'Emilly, Director U.S. iiuelear 2ngulatory Co-f amion Office of Inepection and Enforcement l 2egion II 101 Marietta Street, Suite 3100 i
Atlanta, Georgia 30303
Dear Mr. O'Reilly:
TAMESSEE VALLET AllIbORITY - SEQU0YAH WCLEAR PIET UNIT 1 - D0CIIT NO. 50-327 - FACILITY OPEAATING LICCSE DPR SPECIAL 2EPORT do-6 The enclosed special report provides information concerning an inaavertant injectics of Sodim-24 into the Sequoyah turbineo' uilding sump. Ihis report is suseitted in accordance with 10 CF2 20.405.
Very truly yours, TEXWESSEE VALLZY AUTHORITY H. J. Green Director of Maalaar Power l
Eaclaeure ca (Easleemst):
Director (3)
Office of Management Information and Program Control U.S. Muelaar Assulatory Camelmaios
'Jashington, D.C. 20555 Director (40)
Offias of Inspectism and Inforcement U.S. keelear Regulatory Commissism Wash 4 -* . n.c. 20553 _/i I
Mr. Bill Lavallee ihnelaar Safety Analysis Cantar ag Pale Alto, Califeraia 94303 NaC Inspector, Sequoyah 820moqn .- .. . , .
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l I REPORT ON DISCHARGE OF SODIUM-24 ,
9 FROM SEQUOYAH NUCLEAR PLANT -
ll DECEMBER 1-2, 1980 i e i
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Report Prepared by - Douglas A. Fraser, Chemical Engineer l
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Date December 31, 1980 ,
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Summiary This report discusses events which led up to the inadvertent, uncontrolled discharge of a quantity of the radioactive tracer, sodium-24, during n test on December 1 and 2, 1980, and the action taken to mitigate the effects of the discharge. The release was caused by inadequate test instructions and poor communications between the radiochemical laboratory personnel ar.d the test directors. No personnel received a measurable dose due to the release, and no detectable radioactivity was released to the Tennesaae River.
Introductfen
- This report discusses the circumstances including the inadvert ent ar.d un-planned release of a quantity of radioactive sodium-24 from Sequoyah Juclear .
Plant during a plant steam generator carryover test conducted on Decembir 1 and 2, 1980. The efforts made to mitigate the environmental effects of the release are also presented.
Discussion Sodium-24 is used as a radioactive tracer during steam generator moisture carryover tests performed at various power icvels. A known concentration of the element is injected into the steam generator feedwater, and the con-densate is monitored .'or the pre ence of sodium-24. By measuring the concen-tration of sodium-24 present in the condensate, the rate of moisture carryover in the steam is calculated. It was during preparations for the carryover tect at 75% power that the sodium-24 was released from the plant.
Figure 1 is a simplified flow diagram of the system used for injection of sodium-24 into the steam generator feedwater. A feed tank is connected bc3 ween the sample line from feedwater heater IC-1 and the sample line from the fled-water header downstream of the feedwater isolation valve. The motive force far injecting the sodium-24 into the feedwater header is derived from the pressure drop across the feedwater faniscion valve.
During the injection process, valves VS-2, VS-3, VS-4, VS-6, and VC-2 are closed. Valves VC-1, VS-1, and VS-5 are opened. The sodium-24 is deposited in the feed tank and valve VS-5 is closed. By opening valves VS-2 and VS-3, the pressure differential across the system causes the sodium-24 solution to ficw into the feedwater header. The injection is verified by monitoring the radiation field around the feed tank.
Once the sodium-24 has been injected, valves VS-1, VS-2, and VS-3 are closed, and VS-6 is opened to drain the feed tank. Valvt VC-2 is then opened to allow l the sample line from feedwater heater IC-1 to fl..sh. Val *es VA-1, VA-2, VB-1, l and VB-2 are also opened to flush the sample lines from feedwater heaters 1A-1 l and 1B-1, respectively. Samples are then taken periodically from the feedwater heaters 1A-1, IB-1, and IC-1 and analyzed to monitor levels of sodium-24 in the water which has completed the thermal cycle.
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At approximately 2:30 p.m. , chemical laboratory personnel opened valves VA-1, VA-2, VB-1, VB-2, VC-1, and VC-2 to flush sample lines to obtain representa-tive samples in preparation for the test. The laboratory personnel were briefed by the Nuclear Results Section personnel a't 4:30 p.m. to inform them of the sampling and analyses for which the laboratory would be responsible.
This briefing did not include information on system design and flow paths to be used during the test.
At approximately 5:30 p.m., the sodium-24 was received onsite (activity at 4:30 p.m. was 0.96 Ci). The Nuclear Results Section personnel proceeded to setup the system for injection of the sodium-24 solution. Personnel were unaware that valve VC-2 was open (having been opened during the sample line flushing operation) during the injection process. Valve VC-2 positioning did not appear in the step by step instructions but in a prerequisite state-
- ment. This resulted in the oversight of re-checking VC-2 position prior to the eedium injection as the prerequisite was performed before laboratory personnel re-opened VC-2. The lack of a rpecific check-off for VC-2 and proper instructions to the laboratory personnel was the cause of the incident.
When designated valves were opened at approxicately 8:15 p.m. (activity at 8:15 p.m. was 0.798 Ci) to inject the sodium-24 frem the feed tank to the feedwater header, the pressure from the header forced the sodium-24 solution back through valves VS-2, 75-1, and VC-2 to the saeple sink, which drained to the turbine building sump. The station sump pumps actuated on high water level at approximately 10:55 p.m. , and the sodium-24 present caused the effluent radiation monitor (0-RE-90-212) to alarm. The discharge lasted approximately ten minutes and was routed to the yard drainage pond. The yard drainage pond contents eventually reae.h the Tennessee River through .
the plant diffuser pond.
At 11:10 p.m., the discharge from the turbine buildit a surp was rerouted to the unlined chemical cleaning pond for retention. All further sump discharges were routed to the unlined chemical cleaning pond.
Table 1 lists the calculated amount of sodium-24 discharged to the yard drainage pond and unlined chemical cleaning pond during the incident. Table II lists the concentration of sodium-24 observed following the release. Attachment 1 provides a discussion of doses incurred as a result of this incident. Figure 2 shows the relationship between the turbine building sump, yard drainage pond, unlined pend, plant diffuser pond and the Tennessee River.
Conclusion This incident resulted directly f rom inadequate test instructions and improper communications between the test directors arm laboratory personnel. No personnel received measurable exposure as a result of this incident, and no detectable radioactivity was released to the Tennessee River. The test instructions have been clarified to avoid any similar misunderstanding of the instructions on future carryover tests.
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TABLE I ACTIVITY DISCHARGED TO PONDS
- Time Ended Volume Curios _ Pond
- Puspout Time Began, 1 2255 2305 16000 gal 0.297 Ci . YDP 2 2345 0005 30000 gal 0.37 Ci UCP 3 0110 0120 11000 gal 0.068 Ci UCP -
4 0215 0247 22400 gal 6.93x10-3Ci UCP
- YDP - Yard Drainage Pond UCP - Unlined Chemical Cleaning Pond
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i TABLE II SODIUM-24 CONCENTRATIONS FOLLOWING RELEASE DATE TIME LOCATION SODIUM-24, uCi/ml 12/1/80 2320 TBS 3.27x10-3 2400 YPI 1.44x10-6
- 2400 YPO ND 12/2/80 0215 YPI 8.71x10-7 0215 YPO ND 0315 YPI ND -
0315 YPO 1.71x10-5 0415 YPI ND 0415 YPO 3.07x10-5 0515 YPI ND 0515 YPO 4.36x10-5 0515 DF0 ND 0615 YPO 3.62x10-5 0615 YPO (West Bank) ND 0615 DP0 ND 0720 TBS 2.70x10-0 0745 YPO 3.20x10-5 0745 YPO (West Bank) ND 0745 DP0 ND 5
0845 YPO 3.52x10 1.10x10-6 0845 YPO (West Bank 0845 DP0 ND 0945 YPO ND 0945 YPO (West Bank) 3.21x10-5 0945 DP0 ND 1045 YPO (West Bank) ND 1045 DP0 ND 1145 YPO 1.75x10-5 1145 YPO (West Bank) 1.30x10-5 1145 DP0 ND 12/3/80 0600 TBS ND 0600 YPO ND 0600 DP0 ND 0600 DP0 (West of YPO) ND 1000 UCP (East) 2.18x10-6 1000 UCP (South west) 2.66x10-6 1100 UCP (West) 2.63x10-6 12/4/80 0835 UCP ND Key - TBS-Turbine Building Sucp YPI-Yard Drainage Pond Inlet YPO-Yard Drainage Fond Outlet l DPO-Diffuser Pond Outlet UCP-Unlined Chemical Cleaning Pond ND-None Detected I
I ATTACHMENT 1 l I
HP DATA DURING 24Na INJECTION AND FOLLOWUP l i
At approximately 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on 12-1-80 a zone was erected on the north end of El 685 TB (TB = Turbine Building) to contain the 24Na source prior to injec-tion. This zone was posted as high radiation and contamination area.
Entry to the El 662.5 TB, U1 main steam valve rooms and the steam generator blowdown tank / monitor area was prohibited by barricades. .
All source handling was performed behind a lead brick wall by personnel using remote handling tools and extremity TLDs. All personnel involved wore the normal TLD badge and self-reading dosimeter. .
Readings at the time of the injection were: 9R/hr y @l8", 4R/hry @3', no centact reading was made.
The injection pathway was conitored with no increase in levels indicated.
During the inicial steam generator blowdcwn, continuous coverage was provided by HP with no radiaticn increase indicated.
At 2255 hrs, operations notified HP of an alarm on T.B. sump effluent radiation monitor (0-RE-90-212). Investigation found 1 mrem /hr y G.A. around the sump and -
monitor. At 2310 hrs. HP escorted a chem lab analyst to sample the T.B. sump water. The one aiter sample read 0.5 mrem /hr y @ contact. A dose rate measure-mentwasmadeatthesumpwateryevel, indicating 10 mrem /hry. Chemistry's analysis showed 3.27E-3 pCi/ml Na, .
At 2340 hrs operations notified HP that the sump water was being pumped into the unlined pond. HP supervision was notified.
roximately 0015 hrs, 12-2-80, HP initiated a survey tracing the path of AtapgNafromtheinjectionpointtotheT.B.
the Z sump. A 20' section of drai-trough below the chemiccl station El 685 up to the 24 Na injection zone indicated readings of 1.0 to 1.C nten/hr y on the grating = 1' above water level. 3.0 mrem /hr y was indicated at water level. The trough was zoned at this time. Water was flowing continuously in this area, going directly into the T.B. sump.
The path from the sump :o the pond was traced with the following results:
Pipe at sump 2.0 mrem /hr y Pipe on El 685 2.0 mrem /hr y Pipe leaving UII to ponds 1.0 mrem /hr y Storm drain at UII wall 3.0 mrem /hr y Pipe at unlined pond during pumping 0.2 mrem /hr y Water in unlined pond = 60' from inlet pipe showed indications of low level radiation with an RM 14 survey meter.
The storm drain was immediately zoned as a regulated area.
) At 0130 hrs the El 662.5 T.B. was cleared except for the sump area itself. The l steam generator blowdown area El 685 was cleared.
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At approximately 0700 hrs a followup survey from the sump was performed.
Pipe at sump 0.1 mrem /hr y Pipe on El 685 < 0.1 mrem /hr y Pipe leaving UII wall to ponds < 0.1 mram/hr y Storm drain to ponds 0.2 mrem /hr y Pipe at unlined pond 0.15 mrem /hr y .
Water in unlined pond showed no detectable activity with an RM 14.
The storm drain was cleared at this time.
Per Title 10 Code of Federal Regulations - Part 20.405 a written report is required when radiation levels in a restricted area exceed any applicable limit or when radiation levels in an unrestricted area exceed by ten times any' applicable limit set forth. These levels were not exceeded.
Per 10CFR20.105 (B) the radiation level limits for an unrestricted area were met or exceeded on the UII pipe, the storm drain and the pipe outside UII going to the ponds. The UII piping read 2.0 mrem /hr at contact but is located near the ceiling off El 685 and is not rer 'ily accessible. Readings 3 foot above floor level were 0.3 mrem /hr y.
The storm drain read 3.0 mrem /hr y at contact with the water level in the bottom. This drain was posted immediately.
The piping outside UII going to the ponds read 2.0 mrem /hr y at contact.
These areas existed for a total period of less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (2255 hrs., 12-1-80/
0700 hrs. ,12-2-80) . During this time there were no personnel present and no individual received exposure. Public safety personnel were stationed at the holdup pond to prevent unauthorized entry of personnel in the area until the Na 24 had decayed to non detectable limits.
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