Ro:On 750613,during Pressure Transient,Porv Actuated & Failed to Close,Resulting in Rupture of Quench Tank Rupture Disc.Caused by Corrosion of Lever Pin,Lever Hinge & Solenoid Bracket.Valve RepairedML20024B436 |
Person / Time |
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Site: |
Oconee, Three Mile Island |
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Issue date: |
12/01/1976 |
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From: |
Burnley R, Creacy C, Klein S BABCOCK & WILCOX CO. |
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To: |
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Shared Package |
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ML20024B434 |
List: |
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References |
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TASK-03, TASK-3, TASK-GB GPU-2512, NUDOCS 8307080724 |
Download: ML20024B436 (5) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML20024E6601983-08-0404 August 1983 RO 83-18:on 830804,during Maint Insps on Hydraulic Snubbers, Two Small Bore Snubbers Identified as Being Installed on RCS Hot Leg Vent Piping Downstream of Valves RC-V15A & B.Caused by Personnel Error ML20024C1271983-07-0101 July 1983 Ro:On 830623,visual Insp Revealed Three Broken Holddown Springs.Investigation Incomplete.Ro 269/83-13 Will Be Submitted by 830721 ML20024C4181983-07-0101 July 1983 Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised ML20024C4141983-06-29029 June 1983 Ro:On 830509 & 12,fire Barrier Smoke Exhaust Penetrations 3-K-5-2,3-C-5-3 & 4 Found W/O Seal & 3-C-5-3 Did Not Have Fusible Damper,Respectively.Caused by Inadequate Info & Insufficient Guidance Provided by Design Engineering ML20023B6511983-04-29029 April 1983 ROs 269/83-10 & 287/83-04 Re 821212 & 830303 Loss of Containment Integrity.Mgt Audit in Progress.Summary List of Completed & Remaining Activities,W/Projected Completion Dates,Encl ML20027B8581982-09-21021 September 1982 Ro:Advising That 820820 Occurrence Involving Loss of Electric Power to Valve CCW-8 Determined Not Reportable. Operability of Valve Demonstrated.No Further Action Required ML20027B7691982-09-16016 September 1982 RO 269/82-14:investigation Re Reactor Bldg Penetrations That May Not Have Been Leak Rate Tested Incomplete.Rept to Be Submitted by 820930 ML20052A3291982-04-0909 April 1982 Informs That Review Per RO-269/82-07 Has Determined That Plant Design & Const Predate Std Re Westinghouse SAI-1 Type Relays Not Meeting Full Surge Requirements ML20052A4261982-04-0202 April 1982 RO 269/82-06:on 820306,steam Generator 1B Indicated Tube Leak of 0.08 Gpm.Incident Under Investigation.Next Rept Expected by 820416 ML20050A5431982-03-18018 March 1982 Ro:On 820318,water W/Ph of 3.5 Was Discharged from Secondary Waste Water Neutralizing Tank WT-T-1 Into Plant Discharge Effluent Stream.Caused by Accidental Overflow of Approx 2,500 Gallons of Water from Neutralizing Tank ML20050A9751982-03-12012 March 1982 RO 287/82-04:on 820226,3A2 HPI Normal Makeup Nozzle Found to Have Broken Thermal Sleeve Tack Welds.Investigation Revealed Cracks in Safe End & Upstream Piping.Next Rept Expected by 820409 ML20049J5541982-02-25025 February 1982 Ro:Advising of Delay Until 820311 to Provide Complete Rept of RO-281/82-03 Re Steam Generator Tube Leak ML20040F7611982-02-0505 February 1982 Ro:On 820122,during Visual Insp of Core Barrel Assembly, Thermal Shield & Shock Pad Bolts Found Broken & Shock Pad Was Skewed.Thermal Shock Bolts to Be Replaced.Loosened Shock Pad Evaluation Underway ML20040E6871982-01-28028 January 1982 RO 269/81-50:on 811229,reactor Bldg Cooling Unit C Declared Inoperable Due to Inability to Open Discharge Valve 1LPSW-24.Investigation & Rept Expected to Be Completed by 820211 ML20040C8421982-01-0808 January 1982 Suppl 3 to RO 269/81-11:re Broken Lower Thermal Shield Bolts.Caused by Intergranular Stress Corrosion Cracking in Region of Pronounced Microstructure Transition at head-to-shank Fillet.Bolts Replaced.Drawings Encl ML20039C6331981-12-23023 December 1981 RO 81-14:nine Pipe Support & Structural Interfacing Areas Identified Requiring Further Evaluation & Potential Corrective Action.Failure of Pipe Supports Could Damage safety-related Components.Followup Rept Expected in 14 Days ML20011A7231981-10-21021 October 1981 Ro:On 811019,four Liquid Waste Releases Were Made W/O Adequate Sampling.Caused by Failure to Make Change to Sample Point.Procedure Revised to Specify Correct Sampling Point for Sys Configuration ML20010F6791981-09-0404 September 1981 RO 270/81-14:on 810821,2A1 Reactor Coolant Pump Electrical Penetration Was Discovered Depressurized & Could Not Be Repressurized w/SF6 Gas.Cause Not Stated.Investigation & Complete Rept Will Be Sent by 810918 ML20038C8171981-08-25025 August 1981 Ro:On 810814,tritium Concentrations in Downstream Water Samples Exceeded Tech Spec Control Level for Second Quarter of 1981.Analysis of Max Dose Estimates Concluded That Concentrations Will Not Adversely Affect Public Health ML20010A8721981-08-0505 August 1981 RO 269/81-11,Suppl 1:on 810715,core Barrel Assembly Thermal Shield Bolts Found Broken.Cause Not Stated.Search for Loose Parts Turned Up All Missing Thermal Shield Parts Except for One Thermal Shield Bolt Head.Investigation Continuing ML20009E7351981-07-28028 July 1981 Ro:On 810717,fire Suppression Water Sys Found Inoperable. Caused by Open Main Control Source Breakers.Breakers Closed & Sys Successfully Tested ML20038C8031981-07-0606 July 1981 Ro:On 810210,radioactivity Levels of Aquatic Vegetation Samples Exceeded Control Level by Greater than 50 Times.Info Supersedes 810225 Submittal ML20009F4311981-07-0101 July 1981 Ro:On 810630,during Performance of Normal Power Procedure, Backup Function of Units Isolating & Transfer Diodes on 125 Volt Dc Instrumentation & Control Sys Was Observed. Proposed Tech Spec Change Will Be Submitted ML20009H2701981-04-0101 April 1981 RO:810319 Determination Declaring Portions of Low Power Injection Sys Seismically Inoperable Was Premature.Hanger Noncomformance Repaired within 48-h Per IE Bulletin 79-14. Item Not Reportable Per Tech Spec 6.6.2.1a(9) ML20005A8771981-02-25025 February 1981 Ro:On 810219 Analytical Results of Aquatic Vegetation Samples Collected on 810210 Indicated That Radioactivity Levels Exceeded Tech Specs.Cause Not Stated ML19345A9741980-11-17017 November 1980 RO 80-013/03L-0 Committed to Forwarding Final Valve Testing Evaluation by 801101.Investigation Requires More Time than Anticipated.Requests Extension Until 801219 ML19337A8631980-09-23023 September 1980 RO 80-17:determined Insufficient Documentation to Demonstrate That Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C Environmentally Qualified.Redundant Valves Fully Qualified ML19338F5461980-09-23023 September 1980 RO 80-17:on 800923,determined That There Is Insufficient Documentation to Demonstrate Environ Qualification of Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C. Cause Not Stated.Corrective Action Will Be Submitted ML19330C3041980-08-0404 August 1980 Ro:On 800716,during Radiation Emergency Exercise,Use of Emergency Notification Sys Phone Line Became Uncertain, Making Accurate Info Transfers Questionable.Recommends That Microphone Headset Be Made Available to Allow Mobility ML19326E2061980-07-22022 July 1980 RO 80-15/4P:confirming 800722 Telcon,On 800721,river Water Discharge Temp Was More than 3 F Below Inlet River Water Temp for Approx 6-h.Incident Will Be Reviewed to Determine Corrective Action.Review to Be Included in Followup Rept ML19326E0841980-06-27027 June 1980 RO 80-12/IP:during Review of Equipment Required by IE Bulletin 79-01B,found That post-accident Pressure & Temp Would Be Higher than Postulated in NSC 730705 Rept.Short & long-term Action to Be Discussed in Followup Rept ML19323H3421980-06-0606 June 1980 RO-80-10/1P:on 800603,B&W Ltr Informed Util of Potential Reportability of Steam Generator Tube Rupture Safety Analysis.Caused by Nonconservative Error in Fsar.Corrective Action Will Be Addressed in Followup Rept ML19323D5151980-04-23023 April 1980 RO 80-07/TP:on 800423 Results of Radiographic Exams of Piping Welds Associated W/Reactor Bldg Penetrations 415-16 for Leak Rate Test Sys Showed Several Welds Not within Tech Specs.Unit Is Shut Down ML19309A7831980-03-26026 March 1980 RO 80-06/1P:on 800325,during Refueling Frequency Reactor Bldg Local Leak Rate Test of Valve RB-V7,updated Total Leakage Exceeded Tech Specs.Testing Is Continuing W/Approx 1/4 of Test Program Complete ML19322B5081979-11-0808 November 1979 RO 79-17/1P:on 791108 Support Boltings for Rigid Anchor DHH-127A Found to Be Inadequate in Design & Installation. Details & Corrective Action Will Be Addressed in Followup Rept ML19282D0291979-01-15015 January 1979 RO 269/7827 on 781214:on 781213,reactor Coolant Temp Became Erratic.Feedwater Problem Resulted from Operation of One or More Feedwater Valves.Power Cords Have Been Fitted ML19263C9841978-11-30030 November 1978 RO 270/78-12 on 781105:stop Check Valve from 2AHPI Pump to 2A12C Pump Closed During Flow Test.Valve Was Opened & Check Valve Functional Test Completed ML19316A3701978-06-0505 June 1978 RO 269/78-13:on 780427,primary-to-secondary Leak in 1B Steam Generator Occurred.Caused by Tube Leaks.Tube 69-1 Had Weld Crack.Tube 74-2 Had Circumferential Crack.Cracked & Suspect Tubes explosive-plugged.Investigation Continuing ML19312C2361978-04-21021 April 1978 RO-269/78-07 & 09:on 780314 & 22,field Flashing Breaker Found Inoperable.Cause for Repeated Inoperability Has Not Been Determined.Faulty Relays Replaced Before 780322 Failure.Recorder Will Be Installed to Monitor Trip Circuits ML19316A3811978-04-11011 April 1978 RO 269/78-08:on 780315,valve FDW-108 Failed to Close.Failure Has Occurred Previously.Caused by Apparent Unsuitability of Valves for long-term Operation in Sys Environ.Valve Stem Lubricated.Valves Will Be Replaced ML19316A4041978-04-0707 April 1978 RO 269/78-06:on 780310,field Flashing Breaker Failed to Close During Startup of Keowee Hydro Unit 2.Breakers & Associated Relays Checked.Circuits Checked.Cause of Breaker Malfunction Unknown.Search for Possible Causes Continues ML19316A3891978-04-0707 April 1978 RO 269/78-10:on 780323,Unit 2 Not Verified Operable within Time Limit.Caused by Personnel Error.Station Procedure, Removal & Restoration of Equipment, Not Properly Used. Personnel Instructed by Operating Engineer ML19308A7531978-03-23023 March 1978 RO 269/78-03:on 780222,Unit 2 Field Flashing Breaker Failed to Close.Cause of Breaker Malfunction Not Determined.Relays in Breaker Control Circuit Were Replaced.Investigation to Control Breaker Sys Faults Continues ML19316A4641978-03-15015 March 1978 RO 269/78-04:on 780301,two Reactor Bldg Cooling Units Found Inoperable Simultaneously.Caused by Insufficient Installation Procedures Allowing Trip Point to Be Set Too Low.Breaker Reset & Trip Setpoint Increased ML19316A4171978-02-0303 February 1978 RO 269/78-01:on 780203,field Flashing Breaker Failed to Close.Controls Checked & Found in Proper Condition.Breaker Checked & Cleaned.Cause of Failure Not Determined ML19317F3461978-02-0202 February 1978 RO 270/78-04:on 780202,nuclear Instruments Found Out of Calibr in Less Conservative Direction & Could Have Prevented Fulfillment of Functional Requirements of Reactor Protective Sys.Cause Not Stated.Administrative Measures Taken ML19308A5241978-02-0202 February 1978 RO 78-08/1P:on 780202,util Informed by NSSS of Deviation Discovered Between FSAR Steam Line Break Analysis & Actual Operating Parameters.Procedure Mod Will Limit Secondary Site Water Volume ML19308A7971978-01-31031 January 1978 RO 269/78-02:on 780105,Keowee Hydro Unit 1 Not Verified Operable within 1-h of Taking Keowee Unit 2 Out of Svc. Caused by Failure to Follow Established Procedures by Personnel.Operators Instructed in Tech Specs ML19317E0451978-01-26026 January 1978 RO 269/77-31:on 771229,leakage of Less than 1 Gallon Per Minute Noted.Caused by Failure of Switch 1PS-364 Diaphragm. Switch 1PS-364 to Be Replaced During Future outage.1PT-21P Switch Recalibr & Returned to Svc 1990-04-30
[Table view] Category:LER)
MONTHYEARML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML20024E6601983-08-0404 August 1983 RO 83-18:on 830804,during Maint Insps on Hydraulic Snubbers, Two Small Bore Snubbers Identified as Being Installed on RCS Hot Leg Vent Piping Downstream of Valves RC-V15A & B.Caused by Personnel Error ML20024C1271983-07-0101 July 1983 Ro:On 830623,visual Insp Revealed Three Broken Holddown Springs.Investigation Incomplete.Ro 269/83-13 Will Be Submitted by 830721 ML20024C4181983-07-0101 July 1983 Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised ML20024C4141983-06-29029 June 1983 Ro:On 830509 & 12,fire Barrier Smoke Exhaust Penetrations 3-K-5-2,3-C-5-3 & 4 Found W/O Seal & 3-C-5-3 Did Not Have Fusible Damper,Respectively.Caused by Inadequate Info & Insufficient Guidance Provided by Design Engineering ML20023B6511983-04-29029 April 1983 ROs 269/83-10 & 287/83-04 Re 821212 & 830303 Loss of Containment Integrity.Mgt Audit in Progress.Summary List of Completed & Remaining Activities,W/Projected Completion Dates,Encl ML20027B8581982-09-21021 September 1982 Ro:Advising That 820820 Occurrence Involving Loss of Electric Power to Valve CCW-8 Determined Not Reportable. Operability of Valve Demonstrated.No Further Action Required ML20027B7691982-09-16016 September 1982 RO 269/82-14:investigation Re Reactor Bldg Penetrations That May Not Have Been Leak Rate Tested Incomplete.Rept to Be Submitted by 820930 ML20052A3291982-04-0909 April 1982 Informs That Review Per RO-269/82-07 Has Determined That Plant Design & Const Predate Std Re Westinghouse SAI-1 Type Relays Not Meeting Full Surge Requirements ML20052A4261982-04-0202 April 1982 RO 269/82-06:on 820306,steam Generator 1B Indicated Tube Leak of 0.08 Gpm.Incident Under Investigation.Next Rept Expected by 820416 ML20050A5431982-03-18018 March 1982 Ro:On 820318,water W/Ph of 3.5 Was Discharged from Secondary Waste Water Neutralizing Tank WT-T-1 Into Plant Discharge Effluent Stream.Caused by Accidental Overflow of Approx 2,500 Gallons of Water from Neutralizing Tank ML20050A9751982-03-12012 March 1982 RO 287/82-04:on 820226,3A2 HPI Normal Makeup Nozzle Found to Have Broken Thermal Sleeve Tack Welds.Investigation Revealed Cracks in Safe End & Upstream Piping.Next Rept Expected by 820409 ML20049J5541982-02-25025 February 1982 Ro:Advising of Delay Until 820311 to Provide Complete Rept of RO-281/82-03 Re Steam Generator Tube Leak ML20040F7611982-02-0505 February 1982 Ro:On 820122,during Visual Insp of Core Barrel Assembly, Thermal Shield & Shock Pad Bolts Found Broken & Shock Pad Was Skewed.Thermal Shock Bolts to Be Replaced.Loosened Shock Pad Evaluation Underway ML20040E6871982-01-28028 January 1982 RO 269/81-50:on 811229,reactor Bldg Cooling Unit C Declared Inoperable Due to Inability to Open Discharge Valve 1LPSW-24.Investigation & Rept Expected to Be Completed by 820211 ML20040C8421982-01-0808 January 1982 Suppl 3 to RO 269/81-11:re Broken Lower Thermal Shield Bolts.Caused by Intergranular Stress Corrosion Cracking in Region of Pronounced Microstructure Transition at head-to-shank Fillet.Bolts Replaced.Drawings Encl ML20039C6331981-12-23023 December 1981 RO 81-14:nine Pipe Support & Structural Interfacing Areas Identified Requiring Further Evaluation & Potential Corrective Action.Failure of Pipe Supports Could Damage safety-related Components.Followup Rept Expected in 14 Days ML20011A7231981-10-21021 October 1981 Ro:On 811019,four Liquid Waste Releases Were Made W/O Adequate Sampling.Caused by Failure to Make Change to Sample Point.Procedure Revised to Specify Correct Sampling Point for Sys Configuration ML20010F6791981-09-0404 September 1981 RO 270/81-14:on 810821,2A1 Reactor Coolant Pump Electrical Penetration Was Discovered Depressurized & Could Not Be Repressurized w/SF6 Gas.Cause Not Stated.Investigation & Complete Rept Will Be Sent by 810918 ML20038C8171981-08-25025 August 1981 Ro:On 810814,tritium Concentrations in Downstream Water Samples Exceeded Tech Spec Control Level for Second Quarter of 1981.Analysis of Max Dose Estimates Concluded That Concentrations Will Not Adversely Affect Public Health ML20010A8721981-08-0505 August 1981 RO 269/81-11,Suppl 1:on 810715,core Barrel Assembly Thermal Shield Bolts Found Broken.Cause Not Stated.Search for Loose Parts Turned Up All Missing Thermal Shield Parts Except for One Thermal Shield Bolt Head.Investigation Continuing ML20009E7351981-07-28028 July 1981 Ro:On 810717,fire Suppression Water Sys Found Inoperable. Caused by Open Main Control Source Breakers.Breakers Closed & Sys Successfully Tested ML20038C8031981-07-0606 July 1981 Ro:On 810210,radioactivity Levels of Aquatic Vegetation Samples Exceeded Control Level by Greater than 50 Times.Info Supersedes 810225 Submittal ML20009F4311981-07-0101 July 1981 Ro:On 810630,during Performance of Normal Power Procedure, Backup Function of Units Isolating & Transfer Diodes on 125 Volt Dc Instrumentation & Control Sys Was Observed. Proposed Tech Spec Change Will Be Submitted ML20009H2701981-04-0101 April 1981 RO:810319 Determination Declaring Portions of Low Power Injection Sys Seismically Inoperable Was Premature.Hanger Noncomformance Repaired within 48-h Per IE Bulletin 79-14. Item Not Reportable Per Tech Spec 6.6.2.1a(9) ML20005A8771981-02-25025 February 1981 Ro:On 810219 Analytical Results of Aquatic Vegetation Samples Collected on 810210 Indicated That Radioactivity Levels Exceeded Tech Specs.Cause Not Stated ML19345A9741980-11-17017 November 1980 RO 80-013/03L-0 Committed to Forwarding Final Valve Testing Evaluation by 801101.Investigation Requires More Time than Anticipated.Requests Extension Until 801219 ML19337A8631980-09-23023 September 1980 RO 80-17:determined Insufficient Documentation to Demonstrate That Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C Environmentally Qualified.Redundant Valves Fully Qualified ML19338F5461980-09-23023 September 1980 RO 80-17:on 800923,determined That There Is Insufficient Documentation to Demonstrate Environ Qualification of Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C. Cause Not Stated.Corrective Action Will Be Submitted ML19330C3041980-08-0404 August 1980 Ro:On 800716,during Radiation Emergency Exercise,Use of Emergency Notification Sys Phone Line Became Uncertain, Making Accurate Info Transfers Questionable.Recommends That Microphone Headset Be Made Available to Allow Mobility ML19326E2061980-07-22022 July 1980 RO 80-15/4P:confirming 800722 Telcon,On 800721,river Water Discharge Temp Was More than 3 F Below Inlet River Water Temp for Approx 6-h.Incident Will Be Reviewed to Determine Corrective Action.Review to Be Included in Followup Rept ML19326E0841980-06-27027 June 1980 RO 80-12/IP:during Review of Equipment Required by IE Bulletin 79-01B,found That post-accident Pressure & Temp Would Be Higher than Postulated in NSC 730705 Rept.Short & long-term Action to Be Discussed in Followup Rept ML19323H3421980-06-0606 June 1980 RO-80-10/1P:on 800603,B&W Ltr Informed Util of Potential Reportability of Steam Generator Tube Rupture Safety Analysis.Caused by Nonconservative Error in Fsar.Corrective Action Will Be Addressed in Followup Rept ML19323D5151980-04-23023 April 1980 RO 80-07/TP:on 800423 Results of Radiographic Exams of Piping Welds Associated W/Reactor Bldg Penetrations 415-16 for Leak Rate Test Sys Showed Several Welds Not within Tech Specs.Unit Is Shut Down ML19309A7831980-03-26026 March 1980 RO 80-06/1P:on 800325,during Refueling Frequency Reactor Bldg Local Leak Rate Test of Valve RB-V7,updated Total Leakage Exceeded Tech Specs.Testing Is Continuing W/Approx 1/4 of Test Program Complete ML19322B5081979-11-0808 November 1979 RO 79-17/1P:on 791108 Support Boltings for Rigid Anchor DHH-127A Found to Be Inadequate in Design & Installation. Details & Corrective Action Will Be Addressed in Followup Rept ML19282D0291979-01-15015 January 1979 RO 269/7827 on 781214:on 781213,reactor Coolant Temp Became Erratic.Feedwater Problem Resulted from Operation of One or More Feedwater Valves.Power Cords Have Been Fitted ML19263C9841978-11-30030 November 1978 RO 270/78-12 on 781105:stop Check Valve from 2AHPI Pump to 2A12C Pump Closed During Flow Test.Valve Was Opened & Check Valve Functional Test Completed ML19316A3701978-06-0505 June 1978 RO 269/78-13:on 780427,primary-to-secondary Leak in 1B Steam Generator Occurred.Caused by Tube Leaks.Tube 69-1 Had Weld Crack.Tube 74-2 Had Circumferential Crack.Cracked & Suspect Tubes explosive-plugged.Investigation Continuing ML19312C2361978-04-21021 April 1978 RO-269/78-07 & 09:on 780314 & 22,field Flashing Breaker Found Inoperable.Cause for Repeated Inoperability Has Not Been Determined.Faulty Relays Replaced Before 780322 Failure.Recorder Will Be Installed to Monitor Trip Circuits ML19316A3811978-04-11011 April 1978 RO 269/78-08:on 780315,valve FDW-108 Failed to Close.Failure Has Occurred Previously.Caused by Apparent Unsuitability of Valves for long-term Operation in Sys Environ.Valve Stem Lubricated.Valves Will Be Replaced ML19316A4041978-04-0707 April 1978 RO 269/78-06:on 780310,field Flashing Breaker Failed to Close During Startup of Keowee Hydro Unit 2.Breakers & Associated Relays Checked.Circuits Checked.Cause of Breaker Malfunction Unknown.Search for Possible Causes Continues ML19316A3891978-04-0707 April 1978 RO 269/78-10:on 780323,Unit 2 Not Verified Operable within Time Limit.Caused by Personnel Error.Station Procedure, Removal & Restoration of Equipment, Not Properly Used. Personnel Instructed by Operating Engineer ML19308A7531978-03-23023 March 1978 RO 269/78-03:on 780222,Unit 2 Field Flashing Breaker Failed to Close.Cause of Breaker Malfunction Not Determined.Relays in Breaker Control Circuit Were Replaced.Investigation to Control Breaker Sys Faults Continues ML19316A4641978-03-15015 March 1978 RO 269/78-04:on 780301,two Reactor Bldg Cooling Units Found Inoperable Simultaneously.Caused by Insufficient Installation Procedures Allowing Trip Point to Be Set Too Low.Breaker Reset & Trip Setpoint Increased ML19316A4171978-02-0303 February 1978 RO 269/78-01:on 780203,field Flashing Breaker Failed to Close.Controls Checked & Found in Proper Condition.Breaker Checked & Cleaned.Cause of Failure Not Determined ML19317F3461978-02-0202 February 1978 RO 270/78-04:on 780202,nuclear Instruments Found Out of Calibr in Less Conservative Direction & Could Have Prevented Fulfillment of Functional Requirements of Reactor Protective Sys.Cause Not Stated.Administrative Measures Taken ML19308A5241978-02-0202 February 1978 RO 78-08/1P:on 780202,util Informed by NSSS of Deviation Discovered Between FSAR Steam Line Break Analysis & Actual Operating Parameters.Procedure Mod Will Limit Secondary Site Water Volume ML19308A7971978-01-31031 January 1978 RO 269/78-02:on 780105,Keowee Hydro Unit 1 Not Verified Operable within 1-h of Taking Keowee Unit 2 Out of Svc. Caused by Failure to Follow Established Procedures by Personnel.Operators Instructed in Tech Specs ML19317E0451978-01-26026 January 1978 RO 269/77-31:on 771229,leakage of Less than 1 Gallon Per Minute Noted.Caused by Failure of Switch 1PS-364 Diaphragm. Switch 1PS-364 to Be Replaced During Future outage.1PT-21P Switch Recalibr & Returned to Svc 1990-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident 1999-09-30
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w SITE PROBLEM REPORT BABCOCK L IlLCDI_ [
CONTRACT NO. Nss-c9 $PR NO.107 REY.NO.
CUSTCutR oconee III P.O. NO. 20158Ls TASR NQ. 28 CROUP NO. 41 SEO.NO.003 VENDOR Dresser M50L DAIE am GmP. 0 AIE y SITE ENGINEER T.C.Crisbaus For info ontv Ilb EI.ECTRCMATIC RELEIT VALVE MALT 1.3CTION CESCRIPi!QN OF PROBLEg on Friday, June iJth Duke reduced power to 12: FP in pre-paration to cold shutdown for RCP seal replacement. During the transition from e turW to turbine bypass the primary system experienced a pressure transient to ~
226l psia.. The power relief valve actuated at 2257 psig and f ailed to close. This causeithe Quench Tank rupture disc to rupture. Failure to promptly close the L power relief isolation valve caused violations of the fuel compression curve, ;
cooldown rates and RC ptmps hPSP. curve. Inspection of the power relief vs1ve afte r '.
shutdown indicated that the pilot valve lever had remained in the ported position I MMN8.}hgagive,f fg,,resyting.13estrainho{the lever was caused by e
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$lAluS . ACilCN 10 QAIE ]NCLU0 LNG PERSGNS CCNIACIED JT J.nis.NSD, Lynchburg, KA Ellison, NSD, Lynchburg, advised of problem. Valve [r has been repaired (6/20/75) and reinstalled. Repair was effected by increasing the ng clear
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sites be advised to conduct periodic inspection / operation of valve to insure i operability. When plant shuts devn, perform manual / visual checks for freedom I
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INSTRUCTIONS FOR PDS-21091 - SITE PKOBLCi RIPORT t,
Initiated by EW Construction or NPCD Nuclear Service .j
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(1) Originator - Fill in: Customet;, Contract Number; Vendor; Purchase Order
- I Nu=ber; Task Nu=Eer;" Croup Number; Sequence Number; Name; Title; Description oIProblem; Status; Furtheir Action Recornended by Site Personnel; Originator Signature and Date; Vendor Claim (NPCD only - if applicable) 3 (2) Senior BW Construction - Fill in: SPR Nu=ber; Revision Nu=ber; Reg'd. Resol.
Co. Site Representative Date; Req'd. Coep. Date; Approval Signature; or Site Operations Date.
Manager ,
(3) Nuclear Service Support Engineer - Fill in: Cost Category; Authorized Charge
- (4) Nuclear Service t' nit Manager - Fill in: Resolution; FC Req. and FC Number; and/or Task Engineer Signature and Date.
(5) Plant Start-up Section - Approve Resolution; Signature; Date.
Manager or Service and Maintenance Unit Manager (6) Project Manager or - Verify Charge Nu=ber; Approve Resolution; Signature and i
Contract Engineer Date.
~ ~ (7) Senior B&W Construction - Implement resolution; upon completion, fill in:
Co. Site Representative Completion Report: Date Completed and Signature.
or Field Engineer (8) Site Operations Manager - Approve completion; sign.
or Senior 3&*J Construction Co. Site Representative
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This SPR has been reviewed by Task Ingineering Croup: at.d is applicable to
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f is the status ard/or resolution of this SPR on other contra' cts, d^
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.. TILZ: 12M2 q To For Infor:sation CCNT1 TACT No 620-do 4 %
Central Enrineering Files SFR \D ,
C. C. Flunket t - Contract Admin.
TITLE % b d k
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- ' S. H. Klein - Quality As s uran c e '
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The attached. . cleared SPA is s af tted for your information. ..
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. 'TO: E. L. Lo5an: - TLORIDA rJ.
. L. C. Rogers - ET.D.
L J. Baker - TCLEDO 3 '.'
B. L. Day - Intl. Suppare ,
.F. E. Perrone - CTI ' - ,
el f Attached is one copy of Site Prrblem Report No. N1 which *was processed '
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on Contract 620-00 @ . Future contracts h' ave been. re' vie.wed for. the ._
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potential of a similar problem. This problem Mis not considered applicable l to other contracts
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C. M. Jacks - Plant Integration
- C88 NUCLEAR SERVICE SL;PPORT E.NGI'iEER s This SPR has bee.n reviewed I.W NPC-1707-01 -
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