Addl Interim Report of Significant Const Deficiency 9, Noncompliance to Welding Requirements for HVAC Seismic Support Hanger to Embedded Plates. in Addition to Immediate Corrective Actions,Hanger to Plate Welds Are Being RepairedML19308A222 |
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Waterford |
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12/29/1978 |
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LOUISIANA POWER & LIGHT CO. |
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ML19308A221 |
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NUDOCS 7901040090 |
Download: ML19308A222 (17) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp ML20203J2521997-12-0101 December 1997 Deficiency Rept Re Failed Mdr Relays at Entergy Operations Inc,Waterford 3 Nuclear Generation Station.Caused by Contaminated Grease.Housekeeping Procedures Formalized & Added Enclosed Booth Isolating Mdr Final Assembly LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20117K9731996-09-10010 September 1996 Follow-up Part 21 Rept of Re Failures of Waterford 3 Dedication Testing Process of Seven Commercial Grade Barksdale Pressure Switches ML20116C7031996-07-29029 July 1996 Part 21 Rept Re Failures Identified by Waterford 3 Dedication Testing Process of 7 Commercial Grade Barksdale Pressure Switches ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept LD-94-019, Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info1994-03-16016 March 1994 Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info LD-93-177, Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested1993-12-23023 December 1993 Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested LD-93-003, Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared1993-01-13013 January 1993 Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127M5201992-11-24024 November 1992 Final Part 21 Rept Re Reject Lot Serial Numbers of Defective Fuel Nozzle Tips,Consisting of Corrected Page 6 of 921102 Rept Re Reject Lots for Fuel Injector Assembly ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20115D6331992-10-15015 October 1992 Part 21 Rept Re Nuclear Logistics Inc 10CFR21 Notification for Gnb Industrial Battery Co Batteries.Util Will Obtain Replacement Batteries from C&D Power Sys,Inc & Alarm Features to Be Tested by End of Refuel 5 ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20101Q9311992-07-0808 July 1992 Part 21 Rept Re Failure to Comply w/1 Minute Rating of NCX-17 Cells Mfg by Gnb Battery Co (Formally Gould).Addl Testing of Cell Sizes & End Voltages Scheduled to Begin on 920713 & Be Completed on 920815 L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl W3P85-1442, Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e)1985-08-0101 August 1985 Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e) ML20133G9741985-07-31031 July 1985 Part 21 Rept Re Anchor/Darling Valve Co Swing Check Valves W/Loose Set Screws &/Or Missing Lock Welds,Reported by Palo Verde Nuclear Generating Station.All Customers W/Similar Valves Notified.Ltr Re Waterford 3 Valves Encl W3P85-1420, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 8508011985-06-27027 June 1985 Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Submittal of Written Rept on Deficiency Rescheduled for 850801 W3P85-1400, Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 8507011985-05-29029 May 1985 Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time Needed to Evaluate Deficiency. Next Rept Will Be Submitted by 850701 ML20128G5101985-05-24024 May 1985 Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC W3P85-1240, Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 8505311985-04-29029 April 1985 Potentially Reportable Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals. Initially Reported on 840918.Written Rept Submittal Date Extended Until 850531 W3P85-0785, Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. Submittal of Written Rept Rescheduled for 8504301985-03-25025 March 1985 Interim Deficiency Rept 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Required. Submittal of Written Rept Rescheduled for 850430 W3P85-0551, Significant Const Deficiency Rept 93 Re Charging & Letdown Containment Isolation Valve.Potential Exists for Valve to Stick Open Due to Thermal Contraction.Testing Under Temp Conditions Being Performed1985-03-0606 March 1985 Significant Const Deficiency Rept 93 Re Charging & Letdown Containment Isolation Valve.Potential Exists for Valve to Stick Open Due to Thermal Contraction.Testing Under Temp Conditions Being Performed W3P85-0544, Supplemental Final Significant Const Deficiency 93 Re Failure of Containment Isolation Valve CVC-103 to Close After Plant Cooldown.Details Will Be Provided on Valve Failure When Info Obtained1985-02-27027 February 1985 Supplemental Final Significant Const Deficiency 93 Re Failure of Containment Isolation Valve CVC-103 to Close After Plant Cooldown.Details Will Be Provided on Valve Failure When Info Obtained W3P85-0509, Interim Rept of Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Needed.Next Rept Delayed Until 8503291985-02-26026 February 1985 Interim Rept of Potentially Reportable Deficiency 180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Addl Time to Evaluate Safety Significance Needed.Next Rept Delayed Until 850329 W3P85-0337, Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors1985-02-22022 February 1985 Final Significant Const Deficiency Rept SCD-80 Re Unsatisfactory Stroking of Emergency Feedwater Pump Turbine Steam Supply shut-off Valves.Pneumatic Operators for Valves 2MS-V611A & V612 Replaced w/D-C Motors W3P85-0339, Final Significant Const Deficiency Rept SCD-93 Re Charging & Letdown Containment Isolation Valve Deficiency.Vendor Repaired Valve W/New Seats Sized for Max Interference Fit1985-02-21021 February 1985 Final Significant Const Deficiency Rept SCD-93 Re Charging & Letdown Containment Isolation Valve Deficiency.Vendor Repaired Valve W/New Seats Sized for Max Interference Fit W3P85-0338, Final Part 21 & Const Deficiency Rept SCD-37 Re Unreliable Temp Signals from Resistance Temp Detectors (Rtd).Initially Reported on 810710.Safety-related RTDs Replaced or Environmentally Sealed.Design Change Notice Issued1985-02-21021 February 1985 Final Part 21 & Const Deficiency Rept SCD-37 Re Unreliable Temp Signals from Resistance Temp Detectors (Rtd).Initially Reported on 810710.Safety-related RTDs Replaced or Environmentally Sealed.Design Change Notice Issued W3P85-0083, Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Safety-related & Environmentally Qualified Equipment Manuals to Be Reviewed.Next Rept Anticipated by 8502281985-01-14014 January 1985 Deficiency Rept PRD-180 Re Failure to Maintain Adequate Document Control of Vendor Manuals.Initially Reported on 840918.Safety-related & Environmentally Qualified Equipment Manuals to Be Reviewed.Next Rept Anticipated by 850228 1999-03-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 05000382/LER-1999-014, :on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B1999-10-12012 October 1999
- on 990910,reactor Shutdown Due to Loss of Controlled bleed-off Flow,Occurred.Caused by Rotating Baffle failure.Two-piece Rotating Baffle of Original Design Was Located & Installed,In Order to Repair RCP 2B
ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with 05000382/LER-1999-013, :on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included1999-09-23023 September 1999
- on 990825,exceeding TS Limits for RCS Cooldown Rate Was Discovered.Caused by Inadequate Content & Inadequate Implementation of TS Requirements.Page 2 of 2 in Attachment 2 of Incoming Submittal Not Included
05000382/LER-1999-012-01, :on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With1999-09-13013 September 1999
- on 990812,potential Operation with Both Control Room Normal Outside Air Intakes Valves Inoperable Occurred.Cause for Event Was Indeterminate.Seat Leakage Requirements Calculated.With
ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With 05000382/LER-1999-011-01, :on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B1999-08-31031 August 1999
- on 990801,with Plant Operating 100% Power, Lowering RCP Seal Pressures,Along with Dropping Controlled bleed-off (Cbo) & Increasing Cbo Temp Discovered.Caused by fatigue-induced Failure of Rotating Baffle of RCP 2B
05000382/LER-1999-010-01, :on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity1999-08-26026 August 1999
- on 990726,discovered Inadequate Pumping Capacity in Dry Cooling Tower Area.Caused by Inadequate Design Control.Portable Pumps Were Installed in Each Dry Cooling Tower Areas to Ensure Sufficient Pumping Capacity
05000382/LER-1999-009-01, :on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established1999-08-26026 August 1999
- on 990727,discovered App R Noncompliance Condition Involving Inadequate Separation of Safe Shutdown Cables.Caused Design Analysis Deficiency.Compensatory Measures Were Established
ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With 05000382/LER-1999-008-01, :on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-021999-07-29029 July 1999
- on 990629,failure to Perform Testing of ESF Filtration Units Per TS Was Noted.Cause for Testing Charcoal Samples Contrary to TS Could Not Be Determined.All Future Analysis Will Be Performed IAW ASTM D3803-1989,per GL 99-02
05000382/LER-1999-007-01, :on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff1999-07-23023 July 1999
- on 990625,operation Outside Tornado Missile Protection Licensing Basis for turbine-driven EFW Pump & Steam Supply Piping,Was Discovered.Caused Indeterminent. Entergy Will Submit 10CFR50.90 to NRC Staff
ML20210D8951999-07-23023 July 1999 Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020 05000382/LER-1999-006-01, :on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With1999-07-14014 July 1999
- on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With
ML20209H3781999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Waterford 3 Ses. with 05000382/LER-1999-005-01, :on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested1999-06-24024 June 1999
- on 980702,determined That Four Contacts in Control Circuits of EFW Control Valves Were Untested.Caused by Personnel Error.Untested Contacts Have Been Tested
ML20195J8951999-06-17017 June 1999 Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) ML20195J9741999-06-16016 June 1999 Safety Evaluation Supporting Amend 152 to License NPF-38 ML20207E8631999-06-0303 June 1999 Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 ML20195D5491999-06-0303 June 1999 Safety Evaluation Supporting Amend 151 to License NPF-38 ML20195K3391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Waterford 3 Ses.With ML20195C3041999-05-28028 May 1999 Annual Rept on ABB CE ECCS Performance Evaluation Models 05000382/LER-1999-004-02, :on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing1999-05-14014 May 1999
- on 990415,discovered That Complete Response Time for ESFAS Containment Cooling Function Had Not Been Performed.Caused by Response Time Testing Deficiency. Procedures Will Be Revised to Include Subject Testing
ML20206S7401999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Waterford 3.With ML20205T2621999-04-22022 April 1999 LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with ML20206A9641999-04-21021 April 1999 Safety Evaluation Supporting Amend 150 to License NPF-38 05000382/LER-1999-003-02, :on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With1999-04-0909 April 1999
- on 990311,determined That Four Containment Vacuum Relief valves,CVR-101,CVR-201,CVR-102 & CVR-202,were Not Tested.Caused by Contractor Supply of Misinformation. Details of Event Discussed with Contractor.With
ML20205N9671999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With ML20205E8531999-03-30030 March 1999 Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr ML20205A6331999-03-25025 March 1999 SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 05000382/LER-1999-002-03, :on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired1999-03-25025 March 1999
- on 990225,discovered RCS Pressure Boundary Leakage on Two Inconel 600 Instrument Nozzles.Caused by Axial Cracks Near HAZ of Nozzle Partial Penetration Welds Resulting from Pwscc.Leaking Nozzles Have Been Repaired
ML20204H1401999-03-23023 March 1999 Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3 ML20204H1231999-03-22022 March 1999 Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping ML20204H2451999-03-22022 March 1999 Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3 ML20204F0791999-03-17017 March 1999 Rev 1 to Waterford 3 COLR for Cycle 10 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207F3491999-03-0505 March 1999 LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With ML20204B5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Waterford 3.With ML20203H8151999-02-17017 February 1999 Safety Evaluation Supporting Amend 149 to License NPF-38 ML20203H8591999-02-17017 February 1999 Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 05000382/LER-1999-001, :on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With1999-02-0404 February 1999
- on 990105,TS 3.0.3 Was Entered.Caused by Less than Adequate Chiller Thermostat Control.Placed Tamper Seal on Chiller Thermostat.With
ML20202H9161999-02-0202 February 1999 Safety Evaluation Supporting Amend 148 to License NPF-38 ML20199H6261999-01-21021 January 1999 Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change 05000382/LER-1998-020, :on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With1998-12-31031 December 1998
- on 981204,determined That Certain Core Power Distribution SRs Had Been Incorrectly Scheduled.Caused by TS Change Implementation Error.Will Perform Final Review of TS SRs with 4.0.4 Exemption.With
ML20199C9101998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Waterford 3.With ML20198F4691998-12-21021 December 1998 Safety Evaluation Supporting Amend 147 to License NPF-38 ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20206N4131998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Waterford 3.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 1999-09-30
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- n. WATERFORD SES - UNIT NO 3 ADDITIONAL INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO 9 KONCOMPLIANCE TO WELDING REQUIREMENTS FOR llVAC SEISMIC SUPPORT IIANGER TO EMEEDDED PLATES DECEMBER 27, 1978 790104co9o 4
s I .
ADDITIONAI. INTL: RIM RI: PORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO 9 NONCO.'tPl.TANCE TO WELD 1NG RP.QU1REMENTS 1OR llVAC SI:ISMIC SUPPORT llANGER TO EMBEDDED Pl.ATES BACKCR0_liND_
As a result of a review of the American Welding Society - Structural Welding Code, it has beeil determined that 425 IIVAC seismic suppor' hangers at the Waterf ord 3 Steam Electric Station have been welded to embedded plates with-out applying the required preheat to the plates. The velding was performed by The Waldinger Corporation at various elevations in the Reactor Auxiliary and Fuel llandling linildings utilizing E-6011 series electrodes. As identi-fled in the Structural Welding Code - AWS Dl .1-75, metal:. with a thickness over 3/4" to 1-1/2" must be preheated to 150 degrees F when an E-60XX series electrode is used.
RESUI.TS OF INVESTIGATIO_NS
- 1. The single 1-1/2 inch thick embedded plate involved in this deficiency was selected as the apparent " worst case" for hydrogen embrittlement cracking. The hanger to embedded plate attachment welds were Investi-gated by magnetic particle tosting and liquid penetrant t.e s t in g . This testing was repeated as the weld was incrementally removed by grinding, including the heat affected zone. No indication os cracking was found.
- 2. A detailed weld evaluation was clso undertaken. This evaluation, des-cribed fully in the attached report utilized samples from plates avail-abic at Waterford 3 in addition to one specially procured plate repre-senting a range of carbon equivalencies.
This investigation concluded that the acceptability of the welds could not be demonstrated.
CORRECTIVE ACTION In addition to the immediate corrective action taken and reported in the Interim Report deted September 29, 1978, all of the hanger to embedded plate welds are now being repaired by:
a) Providing additional structural or mechanical attachments to carry the design loads of the af fected welds.
b) Removal of the unacceptable weld and replacement using low hydrogen elec-trodes.
This in described nore fully in the attached report.
A final report is now scheduled for December 1, 1979 at which time most, if not all, of this work will be completed.
4 MATERIALS APPL.ICATIO'J REPORT EVALUATION OF NONCOMPLI ANCE TO UP.I. DING REQUIREMENTS FOR llVAC SEISMIC SUPPORT llN;GER TO EMBEDDED PLATE UELD's i s.
APPROVED BY:
PREPARED BY:
Original signed by Original signed by J Brodsky L A Gunther J lirodsky L A Gunther
/
Materials Applica'tions Report
Subject:
LOUISIANA l'0WF.R AND LICllT COMPANY WATERIORD UNIT 3 EVALUATION OF NONCOMPLIANCE TO WELDISC REOUIREMESTS 10R llVAC SE1SMIC SUPPORT IIANGER TO EMBEDDED PLATE WELDS
_C_ONCI USIONS_
lt is the opinion of the Ebasco Materials Applications Department, an investi-based upon evaluation of information received from the site, gation of the literature and metallurgical testing performed on test weld-ments, that:
- 1. The velds made by the Waldinger Corporation to attach seismic support hangers to ASTM A-36 embedded plates 1 inch to lh inch in thickness using E 60 11 electrodes without a minimum 150 F preheat are i;naccept-able because of the possibility of cracks existing in ihe embedded steel under the fillet velds.
- 2. Since no method of nondestructive testing is available to examine the heat affected zone of the embedded plate base material under the fil-let welds for the presence of underhead cracks each of the seismic support han>;cr at tachments should be repaired.
- 3. The seismic support hanger attachments may be repaired by providing additional structural or mechanical attachments which will be designed or to carry the loads which the ouspect welds were designed to carry by removal of the suspect weld, verification of the integrity of the excavated base material, and rewelding using low hydrogen electrodes.
INTRODUCTION It was determined on June 16, 1978, that 425 llVAC duct seismic support hangers at the Katerford 1 Steam Elcetric Station Site had been welded to t
- -7 embedded plates without applying preheat to the plates as required by the American Welding Society DI.1-75 Structural Welding Code for the base nate-rials and weld filler metals involved. The 425 seismic support s and approxi-mately 1300 embedded plates involved are located at various elevations in the Reactor Auxiliary Building and the Fuel llandling Building.
The seismic supports and embedded plctes are fabricated from ASTM A36 material. The enbedded plate r'aterial is 1 inch to 1!$ Inch thick. The weld-t.he llVAC Contractor, using ing was performed by the Waldinger Corporation, E-6011 Class electrodes as identified in their Welding Procedure Specifica-tion No PQW-1. In accordance with the AUS Dl.1-75 Code, welds made to AST.i A36 metal with a base material thickness of over 3/4 inch to 115 inch using the shielded metal arc process and other than low hydrogen electrodes must be preheated to a minimum of 150 F prior to welding. This requirement applies to welds made using E6011 electrodes which have a cellulose type The fail-coating and are desigred to contain between 2% and 4% moisture.
ure to preheat the embedded plates was a violation of both the AUS D1.1-75 Structural Welding Code and the Waldinger Corporation's Weld Procedure Spe-cification No PQW-1.
The welding deficiency was originally reported in Nonconformance Re-port No W3-957.
The deficiency was classified as reportable because of the extensive.
engineering evaluation required to determine the significance of the de-ficiency under 10CFR50.55(e). The deficiency was reported to the U S 9 Nuclear Regulatory Commission as Interim Significant Deficiency Report No
- 9. Further welding using the deficient welding method was stopped and the use of 7018 low hydrogen electrodes in accordance with a revised welding procedure was implemented on hanger to enhedded plate weldments.
SURVEY OF hTTI:RATtfRE Hl: LATED TO !!ONCONFOR:!ANCE The existence of the underbead cracking problem in carbon manganese steels and the causes for the occurrence of the problem are well documented in the metallurgical and welding literature. The three elements required to cause underbead cracking are hydrogen, restraint-induced st.resses and the presence of mhrtensite in the heat-affected zone of the base material under the weld deposit. The primary cause of underbead cracking Is moisture.
Moisture causes atomic hydrogen to form in the welding arc and this hydrogen is absorbed by the weld and base metals during welding. The moisture con-tent for which E6011 electrodes are designed to operate, i.e., 2% to 4%, can produce sufficient hydrogen to cause a cracking problen. The restraint-induced stresses are present on the HVAC h:inger to embedded plat e welds due to the fillet weld. The third rclevant factor, the presence of martensite in the heat affected zone, can occur because of the cheuical composi. tion of the embedded plate material, and the material thicknesses which are suf fi-cient to induce high enough cooling rates to promote the formation of martensi. .
The hardness of a weld heat affected zone is usually considered as a good indication of the presence of martensite and thus potential cracking.
An extensive program of research on the weldability of carbon manganese steels was conducted by the Battelle Memorial Institute. This study in-cluded an investigation of underbead hardness as a method of evaluating the weldability of these steels. The generally accept.ed industry criteria for underbead hardness which evolved from this work and earlier work was "350 Vickers maximum to insure absence of cracking, and 250 Vickers maximum for satisfactory performance of the heat-affected zone under service loading, particularly instructures which are to serve in the as-welded condition".
A Vickers hardnest, number of 350 corresponds to a Rockwell hardness number of 35.5 on the C Scale.
. -4 Another aspect of the P,attelle research program was an evaluation of the effect of preheat on underbead crack sensitivity using bead on plate upecimens which were sectioned and examined for underbead cracking.
The total length of the cracks in any one specimen was expressed as a per-centage of weld bead length, preheat temperaturer. of room temperature, 150 F and 225 F vpre used on several heats of carbon-manganese steels having varying chemical compositions. Comparisons were made of the aver-age underhead crack sensitivity, expressed in percent, with the chemical composition as defined by the carbon equivalent expresulon C + h + 7h .
The results showed in all cases, that there was a definiu relation be-For commercially tween carbon equivalent and underbead cracking sensitivity.
room ten-rolled 1 inch thick steel plate welded with E6010 electrode at perature cracks were found for carbon equivalent values as low as 0.38 and values crack sensitivity increased dramatically for carbon equivalent above 0.42. When preheat was increased to 150"F cracking did not appear in material of carbon equivalents below 0.44. The average amount of crack-ing in carbon equivalents above 0.44 was also decreased. At 225 F the crack-Ing tendency was further decreased and cracking did not appaar in material below carbon equivalents of 0.57. The preheat requirements specified for A36 steel in the AWS Dl.1-75 Structural Welding Code may have been estab-lished based upon the results of the work performed by Battelle.
EBASCO TESTING pROGR/d!S The recommended disposition initially proposed by Ebasco Engineering Site Support personnel for Nonconformance Report W3-957 called for magnetic Because particle examination of a sample selected from the suspect welds.
of the underbead nature of the potential cracking problem the Materiale, Applications Departuent did not belleve that this nondestructive test
method would be sufficiently searching to warrant acceptance of the results by the U S Nucicar Regulatory Commission. For this reason a program was initiated to conduct crack sensitivity tests which would examine the poten-tial cracking problem for materials with chemistries and thicknesses simi-lar to the steel used for the embedded plates.
An evaluation of the certified chemical reports for the embedded plates involved in the nonconformance indicated that the compositions varied from carbon equivalents of 0.37 to approximately 0.57 and the plate thicknesses varied f rom 1 inch to l's irch. A piece of A36 plate material 1-15/16 inch thick was procured from the Lukens Steel Corporation for the initial test work. The composition of this heat of material is given in Table 1. The Carbon Equivalent of this material based on the C + f" + SI expression is 0.607. This material was selected for testing since it conservatively re-presented the upper levels of the chemistry and material thickness range of the embedded plates. The plate material was flame cut to yield 2" x 3" test pieces as shown in Figure 1. The 3 inch dimension of the plate was oriented along the rolling dir ection of the plate. This Loagitudinal-Bead-Weld Underbead-Cracking Test Samole was deveJ oped by Battelle Memorial In-stitute and is a widely accepted method for testing the sensitivity of steels to underbead cracking. The E6011 c1cetrode was provided by the Waterford 3 Site from material used for site installation. The welding parameters duplicated those used by the Waldinger Corporation at the site and are presented in Table 2. The tests were run on 1-15/16 inch thick material at 78 F and 50 F initial temperature and on material reduced to 3/4 inch thickness at 78 F. The reduction in thickness was proposed to evaluate the effect of thickness on the veld cooling rate and the crack sensitivity of the weld heat affected zone. Only 1/8 inch diameter elec-trodes were used on these tests. The resultu are presented in Table 3.
Followingthecompletionoftheakiovetest it was decided that material whose chemistry was representative of lower carbon equivalents should be tested. It was thought that these chemistries would provide a more complete the site. A representation of the range of embedded plate material used at search was made at the <:ite to find material corresponding to 0.40, 0.45, 0.50 and 0.55 carbon equivalent chemistries. The site provided 1 inch thick t i.
material from three (3) heats covering the chemistry range of 0.414 to 0.475 carbon equivalent as presented in Table 1. In order to nake the test more the <;1te on embedded representative of the restraint conditions experienced at run on plates, the longitudinal bead weld underhead cracking tests were larger sampics. Samples 4" x 5" x 1" were flame cut by the site from each heat of material. The 6 inch dimension of the plate was oriented along the rolling direction of the plate as shown in rigure'2. The tests were run at 65 F initial temperature.
In order to provide data for the tuo E6011 electrode diameters and parameters used by the Waldinger Corporat ion on the fillet velds, tests were run on 1/8 inch and 5/32 inch diameter electrodes.
The parameters are presented in Table 2. The samples were sectioned longi-The rr ' ' ; are presented in tudinally and examined for underbead cracking.
Table 4.
In order to provide additional information on the condition of the base material heat af f ected zone under the weld deposit , transverse cross sec-The samples tions were removed for hardness testing as shown in Figure 3.
were run using 1/8 inch and 5/32 inch diameter E6011 electrodes and a 65 F initial welding temperature.
The cross sections were prepared metallographi- .
cally and microhardness survey was performed on the weld, heat affected zone and base metal using a Knoop llardness Indentor and a 500 gram load. Since the maximum underbead hardness of the heat affceted none is the data of con-cern to t his evaluat ion these results are presented in Table 5. The results are listed as Knoop liardness Numbers and their equivalent Re liardness Values.
Magnetic particle and liquid penetrant tests were run at the site on a fillet veld on a #P-53 embedded plate which is 1 inches thick. The paint was removed from the weld and adjacent areas and the wald surface was examined by magnetic particle (!Tf) and liquid penetrant (LP) test methods.
Additional MT and LP examinations were performed after the weld had been ground 1/3 and 2/3 of its original size and flush with the base material.
il An attempt was made to examine the weld heat affected zone by grinding 1/16 The re-inch into the base material and performing MT and LP examinations.
sults of these tests are reported on Peabody Test.ing Certifled Reports of Only minor Nondestructive Examination Numbers PBT-MT-285 and PBT-PT-633.
undercut and rounded indications were reported.
Discussion of Test Program Results The Longi t udinal-Bead-Weld Underbead-Cracking Test results exhibited unc'erhead cracking in samples of t.he 1-15/16 inch thick 0.607 carbon equi-valent material, liowever, no cracking was observed in camples of this material at 3/4 inch thickness or in the other sample .taterials of lower carbon equivalent. chemistry tested at 1 inch thichness. The results show less cracking sensitivity for steels havine lower carbon equivalents, but do not agree with the results of the more extensive testing program con-In addition the test is limited, as ducted by Battelle Memorial Institute.
are all available underbead cracking tests, in their ability to duplicate all conditisas experienced at the site. For example, the Longitudinal-Bead-Weld Underbead-Cracking Test does not provide any information on the effects of restraints other than that developed in a bead-on-plate on the*
cracking tendency. Therefore, the results of these tests are not considered as conclusive evidence that underbead cracking is not present in the em-hedded plate materials.
g_
The underhead crack: observed and those der,cribed in the literature are nornally concentrated in the hardest region of the heat affected zone adjacent to the weld fusion line. This ret; ion may be less than 1/32 inch wide depending upon the welding energy input and the cooling rate experi-enced by the material. There is a high probability that attempts to iso-late this area by grinding through the fillet weld into the base material f l.
prior to magnetic particle or liquid penetrant testing would miss the most critical area. Therefore, the resul ts of the exploratory grinding and non-destructive testing are not considered as conclusive proof that underhead cracks do not exist in the embedded plates.
The results of the underbead hardness tests indicate that weld heads deposited using 1/8" and 5/32" diameter electrodes on 1 inch thick material even at the lever carbon equivalent chemistry level are capabic of producing hardness levels above the Rockwell C 35.5 value in the heat affected zone adjacent to the weld fusion line. The values observed on the test ;amples indicate that a hardened area containing martensite in formed. The high hardness values observed are considered unacceptable for the restrained fil-let welds nade using E6011 electrodes which can provide adequate hydrogen to cause underbead cracking. These hardness values would be very unfavorabic for any structure welded using these electrodes and left in service in the as-welded condition.
Sensitivity and Table 1 - Corposi t ion of A16 Plat e Material lised for Crat i liardnes . Tes ts MATEl!I Al, PROVIDED liY WATERl'ORD 'l SITE
!! EAT DESIGNATIO'l PLATE Pl!OCl!nED FROM 1.UK!;S STEEh
_ 45204 491W1221 56927 11.
0.18 0.19 0.22 O.26 C
0.90 0.97 0.98 Mn 1.15 0.011 0.005 0.013 P 0.009 0.027 0.071 0.029 S 0.028 0.036 0.010 0.041 S1 0.24
"" 0.414 0.4 35 0.475 C+ -+ 0.607 4 4 Table 2 - Teyt Welding Parameters Emp, loved With E6011 Electrodes Measured Approxinate Measiired Ayy_,roximig Voltnyjn Travel Speed Enerqv_ inytg Dianeter Current Volts Inches / Minute Kilo .loules/ Inch Ann 25-27 4.5-5.3 27-40 1/8"95-110 25-27 4.5-5.3 31-50 5/32" 110-140
T on Table 3 -_ Resul t s of I,ongittvlinal-Cead-Weld Underbead CrackinLyst:.
pgterial Procured From I,ul: ens Steel Preheat Temperature Results No. of Sanples Teste_d Sample Size All samples 2"x3"xl 15/16" 78 F 5
exhibited underhead cracks.
50 F 3 of 5 5 2"x3"xl 15/16" sampics exhibited underbead cracking.
78"F No cracks 5 2"x3"x3/4" (*)
observed.
testing.
(*) Plate material was reduced to 3/4 inch thicknens before Table 4 - Results of 4x6"xl" Lonr;itudinal-Bead-Weld Underbead Cracking Teuts on } tat erlal Obtained f rom Waterford 3 Site No. of Samples Results_
lle a t_ Carbon Electrodes Equivalent Deameter Tested No.
No Cracks 45204 0.414 1/8" 1 45204 0.414 5/32" 1 491W1221 0.435 1/8" 1 491W1221 0.435 5/32" 1 56927 0.475 1/8" 1 56927 0.475 5/32" 1
- Initial Welding Temperature 65 F
Table 5 - Maxtruim lleat Af fected Zone (IIAZ) liardrn";s Electrode Saraple Maximum llAZ liardness Diarac te r Size Kiln KC llent No. Carbon Equivalent 2"x 3"x l" 378 38 45204* 0.414 1/8" 31 2"x 3"x 1" 321
" " 5/32" 2"x3" x l" 395 39 491W1221* 0.435 1/8" 42.5
" n. " 5/32" 2"x3"xl" 432 2"x3"xt" 382 42 56927* 0.475 1/8" 42 2"x3"x1" 423
" 5/32" Lukens 15" 46 2"x3"x1g 490 Material *** 0.607 1/8" 2"x3" x 3 / 4" 510 48 1/ 8"
- Initial. welding temperature 65"r 0
- Initial welding temperature 78 p
t REFERENCES
- 1. Metals llandbook Volume 6, " Welding and Brazing", American Society for Metals, Metals Park, Ohio, 1971, page 7.
p l.
Voldrich, C.B. and liarder, 0.E. : " Review on the Weldabillty of Carbon-2.
Manganese Steels", The Welding Journal, Vol. 28 No. 7, Research Supplement, July 1949, page 326s-336s.
and Voldrich, C.B. : "The
- 3. Williams, R.D., Roach, D.B., Martin, D.C.,
7, Weldability of Carbon-Managnese Steels", The Welding Journal, Vol, 28, No.
Research Supplemert, July 1949, pages 311s-325s.
- 4. Stout, R.D., Daty,W.D., Weldability of Steels, ed. Epstein, Sand Somers, R.E., 2nd Edition, New York: Welding Research Council, 1971, pages 253-254.
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- 2. Age for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at room temperature to allow sufficient time for cracking to occur.
- 3. Saw cut specimen to the right of weld center line and grind to wcld center line.
- 4. Examine using 20x magnification for cracking.
Figure 1 - Longitudinal llead - Weld Cracking Specimen Developed at liat te lle steraorial Institute.
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