ML19263C962
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| ML19263C962 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/05/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 7903200163 | |
| Download: ML19263C962 (1) | |
Similar Documents at Sequoyah | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20046B3981993-07-28028 July 1993
[Table view]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 Category:LER) MONTHYEARML20046B3981993-07-28028 July 1993
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20212J6311999-10-0101 October 1999
[Table view]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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- TELEPHONE REPORT 6 '. .-
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'50-327 FACG ITY: Sequoyah 1 and 2 DOCKET f: 50-328 DATI: February 5, 1979
- TDiE: 1:20 pm MC. OL h SU3 JECT: Error in Design of Small Line Supports
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f.SCIIFIIO.'i 0F OrtTTitnF' ICE: TV5 notified RII that the movement of the steel
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. cap ain,one vessel'11nes van overlooked in the design of the smal'1 line sunoorts. The small lines are being re-analyzed and supports will be re-designed per the anlaysis. TVA is evaluating for generic implications. #
Written report due 3/7/79.
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