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 RepairedML19316B106 |
Person / Time |
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Site: |
Sequoyah |
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Issue date: |
05/15/1980 |
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From: |
Ballentine J TENNESSEE VALLEY AUTHORITY |
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To: |
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References |
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SQRC-50-327-800, NUDOCS 8006110318 |
Download: ML19316B106 (1) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20046A6841993-07-23023 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 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 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 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 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 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 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 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 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 ML19254E9331979-09-10010 September 1979 Ro:On 790906,Westinghouse Review Concluded That Conditions Associated W/High Energy Line Breaks Inside/Outside Containment & Impact on Nonsafety Control Sys May Constitute Unreviewed Safety Question ML19263C9621979-02-0505 February 1979 Telcon Rept:Tva Notified Region II That Movement of Steel Containment Vessel Lines Was Overlooked in Design of Small Line Supports.Small Lines Are Being Reanalyzed & Supports Will Be Redesigned Per Analysis ML19276E6681979-01-30030 January 1979 Telcon Rept:Dynalco Type Rt 2429 Relay Tachometers Purchased About 1971 Have Failed on One Unit 1 & Two Unit 2 Diesel Generators.Zener Diodes in Power Supply Have Shown Evidence of Overheating Prior to Failure 1993-07-07
[Table view] Category:LER)
MONTHYEARML20046A6841993-07-23023 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 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 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 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 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 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 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 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 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 ML19254E9331979-09-10010 September 1979 Ro:On 790906,Westinghouse Review Concluded That Conditions Associated W/High Energy Line Breaks Inside/Outside Containment & Impact on Nonsafety Control Sys May Constitute Unreviewed Safety Question ML19263C9621979-02-0505 February 1979 Telcon Rept:Tva Notified Region II That Movement of Steel Containment Vessel Lines Was Overlooked in Design of Small Line Supports.Small Lines Are Being Reanalyzed & Supports Will Be Redesigned Per Analysis ML19276E6681979-01-30030 January 1979 Telcon Rept:Dynalco Type Rt 2429 Relay Tachometers Purchased About 1971 Have Failed on One Unit 1 & Two Unit 2 Diesel Generators.Zener Diodes in Power Supply Have Shown Evidence of Overheating Prior to Failure 1993-07-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
ML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 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 ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively 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 ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20212A1841999-08-25025 August 1999 Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program 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 ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With 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 05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively 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 ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively 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 05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
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 ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively 05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
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 05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
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 ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively 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 05000327/LER-1998-002-03, :on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance1998-08-14014 August 1998
- on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance
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 1999-09-30
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