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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20132C0751996-12-13013 December 1996 Part 21 Rept Re Testing of Six HFD3045 & HFD3060 Molded Case Circuit Breakers w/125 Volt DC Shunt Trip Devices.Identified Incorrectly Installed DC Shunt Trip Units & Are in Process of Being Returned to Vendor 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 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 ML20070A6861991-01-17017 January 1991 Part 21 Rept Re Failure of 4.16 Kv vertical-lift Switchgear Cell Mounted,Auxiliary Contacts to Operate on Demand During Testing of Auxiliary Standby Switchgear at Facility. Initially Reported on 901101.New Test Link Sent to Facility ML20062D9351990-11-0101 November 1990 Part 21 Rept Re Failure of 4.16 Kv Vertical Lift Switchgear, cell-mounted Auxiliary Contacts to Operate on Command During Testing of Standby Switchgear at Plant.Caused When Maladjusted Test Link Inserted Between Breaker & Switch 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 ML20246N7911989-05-10010 May 1989 Part 21 Rept Re Room Cooler Vents & Drains Mfg by Carrier Corp Per Bechtel Specs,W/Galvanic Corrosion at Interface w/90-10 copper-nickel Room Cooler Supply & Return Headers. Vents & Drains Will Be Modified During Current Outage 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 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 ML20151Y8141986-02-0404 February 1986 Part 21 Rept Re Colt-Pielstick Engine Tripping Out on High Speed When Started for Test Purposes at Seabrook.Caused by Source of Air Pressure Staying On.Engines Will Be Modified to Positively Vent Air from Rack Boost Cylinder ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek 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 ML20135G0651985-08-28028 August 1985 Supplemental Part 21 & Deficiency Rept U-70 Re Failures of Crane-Deming Keepwarm Lube Oil Pumps.Initially Reported on 840328.Permanent ASME Section III Equivalent Pumps Will Be Installed on Engine Skid by First Refueling ML20135D4481985-08-15015 August 1985 Part 21 Rept Re Raychem auto-trace 20PTV1 self-regulating Electric Heat Tracers & Associated Derivatives.Licensees Advised of Problem & Procedures to Determine Any Effect on Operation ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20129J7381985-06-24024 June 1985 Part 21 Rept Re Auto-Trace 20PTV1,self-regulating Electric Heat Trace,W/Lower than Specified Power Output.Deficiency Could Result in Lower Maint Temp in Electric Pipe Heating Sys.Affected Licensees Identified ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20116D3201985-04-22022 April 1985 Part 21 Rept Re Ruskin Mfg Co Welds Used to Join Damper to Damper & Damper Section to Mullion Plates.Welds Not in Accordance W/Approved Design Drawings.Drawing 5415 Revised to Indicate Weld Spacing.Drawing of Weld Spacing Encl ML20115J1361985-04-15015 April 1985 Forwards Insp Procedure for Investigating Emergency Diesel Generators for Fractured or Cracked Welds to Determine If Part 21 Problem Exists,Per Jg Borman ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed NRC-85-3024, Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware1985-03-22022 March 1985 Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware ML20113A4291985-01-11011 January 1985 Part 21 Rept Re Incorrect Insulating Tape.Instructions Governing Handling of Incoming Matls Fully Adequate & If Followed,Would Have Prevented Error ML20133N9311984-09-28028 September 1984 Final Deficiency Rept SDR 83-08 Re Seismic Chatter of Ntc Card Relay Used in Westinghouse 7300 Process Protection Sys. Initially Reported on 840124.Bypass Mod Will Be Installed. Westinghouse Continues to Pursue Solution Re Ntc Card ST-HL-AE-1141, Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors1984-09-14014 September 1984 Part 21 Rept Re Capacitor Terminations Used in GE ferro- Resonant Transformers Utilized in Westinghouse Vital 7.5 Kva Inverters.Initially Reported on 840913.Technical Bulletin Issued W/Instructions for Proper Connection of Capacitors ML20098D9941984-09-12012 September 1984 Supplemental Deficiency & Part 21 Rept U-70 Re Failures of Crane-Deming Model 1549 Positive Displacement Gear Pumps Used as Keepwarm Lube Oil Pumps on Emergency Diesel Generators.Design Change to Keepwarm Pumps Initiated ML20093N4721984-07-20020 July 1984 Supplemental Final Deficiency Rept Re Generic Defects in Gould/Rundel 4-position & 2-position Selector Switches Failure.Initially Reported on 840209.Failed Units to Be Replaced from Alternate Supplier ML20094A4701984-07-20020 July 1984 Interim Significant Deficiency Rept SDR 84-04 Re Limitorque Operator Motor Pinion/Worm Shaft Clutch Gear Failure. Limitorque Will Conduct Cycle Testing & Westinghouse Will Conduct Metallurgical Tests.Next Rept Expected by 840930 ML20093F8271984-07-0202 July 1984 Amend to Final Deficiency Rept U-72 Re Silicone Foam Penetration Seals.Actions Meet Intent of Fire Protection Program & Do Not Diminish Effectiveness of Seals ML20092H6641984-06-14014 June 1984 Supplemental Part 21 Rept Re Possible Exhaust Valve Cage Holddown Undertorquing.Torque Values Adequate.Unit Free of Reported Defects ML20091L6451984-06-0101 June 1984 Interim Significant Deficiency Rept SDR 84-04 Re Limitorque SB-2-80 Actuators Susceptability to Gear Damage.Initially Reported on 840419.Actuators to Be Replaced W/Fully Qualified SB-1-60 Actuators ML20091H9061984-05-26026 May 1984 Supplemental Final Deficiency & Part 21 Rept U-70 Re Failure of Crane-Deming Emergency Diesel Generator Keepwarm Lube Oil Pump PKJ03B.Initially Reported on 840118.Pump Failures Due to Insufficient Operating Clearances ML20091A6411984-05-22022 May 1984 Final Deficiency & Part 21 Rept U-82 Re Use of Terminal Blocks of Indeterminate Qualification Status in Limitorque Actuators.Initially Reported on 840521.Questionable Terminal Blocks Replaced ML20091J3591984-05-17017 May 1984 Final Deficiency & Part 21 Repts U-64 Re Limitorque Operator Motor Pinion/Worm Shaft Clutch Gear Failure.Initially Reported on 831017.Caused by Improperly Installed Motor Pinion Gears.Gear Failures May Also Impact Wolf Creek ML20084P4661984-05-11011 May 1984 Final Deficiency Rept U-75 Re Potential Essential Svc Water Pump Degradation.Item Not Reportable as Significant Deficiency Under 10CFR50.55(e).Rept Withdrawn ML20084P5321984-05-11011 May 1984 Final Deficiency Rept U-78 Re Failure of Chemetron Check Valve Spring Seat During Halon Fire Protection Sys Discharge Testing.Reworked Check Valves,W/Upgraded Spring Seat, Installed in All Halon Sys ML20084Q0921984-05-10010 May 1984 Supplemental Part 21 & Deficiency Rept SDR 84-02 Re Improperly Rated Field Run Cables Connecting Valcor Solenoid Valves.Followup Investigation Identified Similar Deficiencies in Target Rock & Asco Solenoids ML20084Q3911984-05-0909 May 1984 Final Significant Deficiency Rept SDR 84-05 Re Potential for Valve Operator Motor Pinion Gear Key Failure Due to Improper Matls in Certain Limitorque Motor Operators.Initially Reported on 840418.All Affected Gear Keys Replaced ML20084L1151984-05-0808 May 1984 Suppl 1 to Part 21 Rept Re United Electric Controls Fuel Oil Filter Differential Pressure Switches at Shoreham Plant. Switch Also Provided to Listed Plants.Corrective Actions Defined in 840328 Rept Will Be Applied ML20084M0631984-05-0707 May 1984 Interim Significant Deficiency Rept U-71 Re Induction of Exhaust Gases Into Control Room.Util Accepts Bechtel Conclusion That Issue Not Reportable Per 10CFR50.55(e).Addl Monitors Will Be Installed to Add Level of Conservatism ML20084K1571984-05-0101 May 1984 Final Deficiency Rept SDR 83-08 Re Seismic Chatter of Ntc Card Relay in Westinghouse 7,300 Process Protection Sys. Util Will Have Option to Install Replacement Relay Once Relay Developed ML20084M0301984-05-0101 May 1984 Supplemental Deficiency Rept SDR 83-13 Re Limitorque Valve Operator Limit Switch Rotor Matl.Util Will Install Fibrite Rotors in Class IE Valve Before Declaring Valve Operational for Particular Mode ML20084A5971984-04-20020 April 1984 Supplemental Final Part 21 & Final Deficiency Rept U-80 Re Failure of Containment Cooling Fans to Remain in Safeguards Position Following Safety Injection Signal Reset.Initially Reported on 840403.Circuit Modified ML20084C3011984-04-18018 April 1984 Amended Final Deficiency Rept U-72 Re Silicone Foam Penetration Seal Installation & Insp.All Seals Will Not Be Completed by 840422.Fire Watch Will Be Established at Time of Fuel Load ML20084C2371984-04-13013 April 1984 Final Part 21 & Deficiency Rept U-66 Re Gould Containment Cooling Fan Starter Coil Failure.Initially Reported on 831123.Caused by Overvoltage of 130-volt Diode Incorporated in Coils.Diodes Replaced w/150-volt Diode ML20084B0221984-04-13013 April 1984 Final Deficiency Rept SDR 84-02 Re Field Run Cables for Solenoid Valves.Initially Reported on 840315.Design Changes Implemented to Replace Field Wiring W/Qualified High Temp Wiring w/392 F Rated Insulation.Also Reported Per Part 21 NRC-84-0064, Significant Deficiency Rept 84-03 Re Failures in Control Devices in RCS Porvs.Initially Reported on 840302.Design Change Package Issued to Incorporate 15 Amp Fuses Into PORV Control Circuit & to Add Dc Contactor1984-04-13013 April 1984 Significant Deficiency Rept 84-03 Re Failures in Control Devices in RCS Porvs.Initially Reported on 840302.Design Change Package Issued to Incorporate 15 Amp Fuses Into PORV Control Circuit & to Add Dc Contactor NRC-84-0067, Supplemental Deficiency Rept 84-01 Re Gould/Rundel Selector Switch Failures.Initially Reported on 840316.Failed Switches Returned to Gould.Caution Flyers & QC Sheets Will Be Supplied W/Future Shipments1984-04-13013 April 1984 Supplemental Deficiency Rept 84-01 Re Gould/Rundel Selector Switch Failures.Initially Reported on 840316.Failed Switches Returned to Gould.Caution Flyers & QC Sheets Will Be Supplied W/Future Shipments ML20083P5671984-04-13013 April 1984 Final Significant Deficiency Rept 84-03 Re Failures in Control Devices in RCS Porvs.Initially Reported on 840302. Design Mods Developed to Correct Problem & Design Drawings Revised to Reflect Mods ML20084B4631984-04-13013 April 1984 Final Deficiency Rept Re Field Run Cables for Valcor Solenoid Valves.Initially Reported on 840315.Design Changes Implemented to Replace Field Wiring W/Qualified High Temp Wiring.Also Reported by Bechtel Per Part 21 1996-12-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E2691999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Callaway Plant,Unit 1.With ML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20212A3361999-09-14014 September 1999 1999 Biennial RERP Exercise, for Callaway Plant. Pages 7,8 & 9 (of 9) in Mini Scenario 1 Section of Incoming Submittal Not Included ML20211N0451999-09-0202 September 1999 Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding ML20212A0201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Callaway Plant,Unit 1.With ML20210P0441999-08-10010 August 1999 Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1 ML20210Q8331999-08-0505 August 1999 Rev 4 to Callaway Cycle 10 Colr ML20210T9481999-08-0303 August 1999 Informs Commission Re Status of Issues Related to Risk Informed Decision Making That Were Raised During Staff Review of License Amend Approving Electrosleeve SG Tube Repair Method for Ue Callaway Plant,Unit 1 ML20216D8791999-07-31031 July 1999 Rev 3 to Callaway Cycle 10 Colr ML20210T4451999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Callaway Plant,Unit 1.With ML20210H6531999-07-30030 July 1999 SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 ML20209H0881999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Callaway Plant,Unit 1.With ML20195H4831999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Callaway Plant,Unit 1.With ML20206R7111999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Callaway Plant Unit 1.With ML20205Q5561999-04-19019 April 1999 Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp ML20205S5791999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Callaway Plant Unit 1.With ML20207A7401999-03-30030 March 1999 Draft, Evaluation of Risk of Induced Steam Generator Tube Rupture, for Callaway Plant ML20205G4071999-03-25025 March 1999 Security Event Rept:On 990304,failure to Properly Compensate for Loss of Safeguards Equipment That Could Have Resulted in Undetected Intrusion Into Protected or Vital Area,Was Discovered.Caused by Msk 325 Failure.Replaced Msk 325 ML20204B6741999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Callaway Plant,Unit 1.With ML20199E7011998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Callaway Plant.With ULNRC-03990, 1998 Annual Rept for Ameren Corp/Union Electric Co. with1998-12-31031 December 1998 1998 Annual Rept for Ameren Corp/Union Electric Co. with ML20198D9811998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Callaway Plant,Unit 1.With ML20195C8341998-11-10010 November 1998 Rev 20 to Operating QA Manual ML20195C8181998-11-0909 November 1998 Rev 19 marked-up Changes to Operating QA Manual ML20195D6931998-10-31031 October 1998 Non-proprietary Rev 3 to Electrosleeving Qualification for PWR Recirculating SG Tube Repair ML20195D3581998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Callaway Plant,Unit 1.With ML20154L4931998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Callaway Plant Unit 1.With ML20151Y5151998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Callaway Plant,Unit 1.With ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20237B8421998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Callaway Plant,Unit 1 ML20155H7381998-06-30030 June 1998 10CFR50.59 Summary Rept for Jan-June 1998. with ML20236Q9991998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Callaway Plant,Unit 1 ML20249C5851998-06-30030 June 1998 Rev 1 to Callaway Cycle 10,COLR ML20248M0501998-06-0808 June 1998 Special Rept 98-02:on 980502,Channel 3 of loose-part Detection Sys Was Declared to Be Inoperable.Caused by Failure of Component Inaccessible at Power.Addl Troubleshooting Will Be Performed ML20249A7681998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Callaway Plant,Unit 1 ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247G0811998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Callaway Plant Unit 1 ML20217R2031998-04-27027 April 1998 Cycle 10 Colr ML20216H0651998-04-15015 April 1998 SER Approving Licensee Proposed Alternative to Use Code Case N-508-1 for Rotation of Serviced Snubbers & Prvs for Purpose of Testing in Lieu of ASME B&PV Code,Section Xi,Article IWA-7000 Requirements ML20216K0531998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Callaway Plant,Unit 1 ML20217F3181998-03-24024 March 1998 SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp Program ML20216G3551998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Callaway Plant, Unit 1 ML20203M0101998-02-25025 February 1998 Rev 11 to Callaway Cycle 9 Colr ML20203A7951998-02-0909 February 1998 Rev 10 to Callaway Cycle 9 Colr ML20202D4821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Callaway Plant ML20198S6361998-01-22022 January 1998 Ro:On 980121,determined That Plant Shutdown Would Be Required IAW TS 3.8.1.1,Action D.Caused by 'B' Train EES Charcoal Absorber Being Determined Inoperable.Requested 24 Hour Extension to Allow Restoration of EDG & ESW Train ULNRC-03775, 1997 Annual Rept for Union Electric1997-12-31031 December 1997 1997 Annual Rept for Union Electric ML20198Q0631997-12-31031 December 1997 Rev 9 to Callaway Cycle 9 Colr ML20198J6791997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Callaway Plant,Unit 1 1999-09-30
[Table view] |
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_
UNION El ECTRIC' COMPANY seos onArsor armeer ST. Louis.- MissoU RI November 28, 1980 , , , , , , , , , , , , ,
-. JOHN M. IIRYAN P. O. R O u .4.
. . . . . .v. 6avi.. w..ouR. .....
Mr. James G. Keppler U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 ULNRC- 400
Dear Mr. Keppler:
FINAL 10CFR50.55(e) REPORT IMPROPER PREHEAT OF HEAVY STRUCTURAL MEMBERS PRIOR TO WELDING CALLAWAY PLANT UNIT 1 On April 18,'1980 we-provided the NRC Resident Inspector-at Callaway verbal notification of a potential 10CFR50.55(e) report regarding use of improper preheat when welding pipe supports to heavy structural. steel. members. The above notification was made after discrepancies-in weld control records were identified by the Resident Inspector. The discrepancies identified by the Resident Inspector are covered by NRC Inspection Report No.
50-483/80-12. Further investigation indicated that these same discrepancies existed for some welds on HVAC ductwork supports and on some -Upairs to structural steel.
Our final report, which shows that the welds in question are acceptable as is, is enclosed.
Since evaluation of this deficiency included a physical test program on sample welds of representative material trickness an-earlier submittal of this final report was not. practicable.
Very truly yours,
-J W N'f h
_ J n K. Bryan ,
RPW/sla Enclosure cc: H. M. Wescott, Region III w/ enc. ON B. H. Grier,' Region I w/ enc.
g Victor Stello, Jr., Director I&E w/ enc./
W. A. Hansen, NRC Resident Inspection w/ enc.
Mo. Public Service Commission, W. enc. //
80120307h .s I
10CFR50.55(e) FINAL REPORT IMPROPER PREHEAT OF HEAVY STRUCTURAL MEMBERS PRIOR TO WELDING CALLAWAY PLANT UNIT 1 INTRODUCTION This final report, submitted in accordance with 10CFR50.55(e),
describes the disposition of welds made on heavy (1 " thickness and greater) carbon steel structural members without preheat treatment. prescribed by the AWS and ASME' Codes. This deficiency
-was initially reported on April 18, 1980 after discrepancies in weld control records-were identified by the NRC Resident Inspector and is covered in NRC Inspection Report No. 50-483/80-12, and UnionLElectric. response ULNRC-358, dated June 6, 1980.
DESCRIPTION OF DEFICIENCY The' applicable AWS and ASME Codes require preheating of material 1 " thick and greater to 1500F or higher. Review of all Weld Control Records for welding on heavy members indicated that proper preheat temperatures had not been designated and used for welds on some pipe hangers, HVAC duct hangers and structural steel repairs. Table 1 provides a summary of the welds involved.
ANALYSIS OF SAFETY IMPLICATIONS Carbon st- snd to harden when they aire heated to a high temperature an. .en rapidly cooled. The extent of hardening and the hardness achieved is dependent on the composition of the steel, particularly its carbon content. When these steels are welded, the area adjacent to the weld, called the heat-affected-zone
-(HAZ), undergoes a heating and rapid cooling cycle for each weld pass that is made. However, hardening in this area is of secondary concern. The primary concern is the possibility of embrittlement which can result from the hardening. The embrittlement, in combin-ation with other adverse conditions, such as restraint due to geometrical conditions surrounding the weld, thickness, and the presence of hydrogen, can give rise to a type of cracking called.
"underbead cracking".
Such cracking could possibly propagate and result'in failure of members'or supports with potential safety implications.
Hardening in the heat-affected-zone, and its associated embrittlement, can be reduced by slowing down the cooling rate from the high temperature'Inr applying a preheat to the weld. area.
One of the principal' reasons for preheating the weld area during.
welding operations is to effectively ~ slow down the cooling rate
-from the high temperature of the weld, thereby reducing the hardening in the heat-affected-zone, andLits associated embrittlement.-
. - - ~ . . -
The amount of preheat required depends primarily on the composition of the steel, its thickness, the amount of restraint, and type of welding material. For plain, low-carbon steels, the need for preheat is minimal, unless there is a high level of restraint in the weld area. Steels with a carbon content of less than 0.3%,
such as ASTM A-36 used for the. members in question, fall into this category. Application of preheat for ASTM A-36 steel is standard practice for thicknesses in excess of about 1 inch, without regard to joint design or_ restraint conditions, or even welding material type. The use of preheat is a conservative measure which is not absolutely necessary to control underbead cracking for the applica-tions in question, i.e., fillet welding of unrestrained attachments using low-hydrogen welding electrodes. To support the above conclusion that preheating was not necessary to control underbead cracking for the welds in question, a test program was conducted by Bechtel Power' Corporation on sample welds of representative material thickness which were not preheated.
The' test program consisted of field welding three attach-ments to a 3-inch thick carbon steel plate in accordance with the Preheat Test Procedure and Preheat Test Coupon shown on Figures 1 and 2. The attachments and the weld sizes were selected to be-representative of types of attachments and sizes of the actual welds involved in the reported nonconformances. The carbon content of the 3-inch thick plate equaled .25%, the highest carbon content available, and representative of the upper limit for structural steel. The 3-inch thick plate was selected to maximize the quench effect by acting as a large heat sink. Both of these parameters were selected to-increase the potential of underbead cracking in the test samples. Overhead welding was specified to minimize heat input. The test was conducted at the Callaway site on July 21, 1980.
l No indications of underbead cracking were noted on the unprepared
- cut sections.
The unprepared cut sections were shipped to the Bechtel Power Corporation Gaithersburg office and from there were sent to Artech Corporation, Falls Church, Virginia for grinding, etching,
- and photographing. _ The ground and etched cross sections of all the welds were examined visually for the presence of cracks in the entire weld areas. No cracking, or any other form of defect, was found which could be attributed to lack of preheat. Photomicro-
_graph s of the test welds sections are on file with the complete Bechtel Power Corporation Report.
Although a preheat of 150 F to 200 F minimum would normally be' applied during the fillet welding of attachments to lh" and thicker carbon steel material,fthe tests performed have indicated.
that the absence of such. preheat has not caused detrimental effects
~
to the weldments or to the. base metal. This can be attributed to the low carbon content of the base material, the lack of restraint at-the joints and to.the use of low hydrogen welding electrodes.
L
CORRECTIVE ACTION TAKEN Corrective Action Report No. 2-G-0006 was issued by Daniel International to implement review of all welds to heavy structural members and to prevent recurrence of improper designa-tion of preheat requirements on Wold Control Records. Noncon-formance Reports were issued for welds made with improper preheat as summarized in Table 1. Based on the results of the Bechtel Power Corporation Test program all Nonconformance Reports, except the one covering pipe hanger welds within the jurisdictional boundary of ASME Section III, will be dispositioned "USE AS IS".
Because of administrative requirements involved with the hanger welds within the jurisdictional boundary of ASME Section III, the Nonconformance Report covering these welds will be dispositioned
" REPAIR" as an expediency to construction.
RPW t
11/?:/80 l
l
I.
TABT.E 1 - Surnmary of NCRs NCR No. Description Cat. Bechtel Spec. Material i Required Actual NCR Govern. Code Thickness Preheat Preheat Disposition 2SN HVAC Duct Hangers M-618.2 4 1\" 500F USE AS IS 1893 R-1216 (Aux.) Q AWS Op 1h" 1500F None DIC to C R-3091 (Control) D1.1-75 )P 25" 225 F revise weld, procedures 2SN Non-Q Pipe M-205 USE 1918 s Hangers attached Q ANSI ?> ik" 1750F . 600F AS
. P to Q Steel B31.1 IS (22) ,
~2SN Q Pipe Hangers M-204 1919 (21) Q ASME )>1%" 2000F 60 F REPAIR P Sec t . - III 2SN Q Steel Repairs C-121 Varies 1500F 60 F USE 2010 Aux. Bldg. Columns , Q C-122 See 2250F 150/600F AS
~
C (13 cases) AWS NCR IS i
D1.1-75
a g I f '
Table 1, continued NCR No., Description Cat. Iechtal S Pec. Material Required Actual NCR
> Covern. Code Thickness Preheat Preheat Disposition 2NN II/I Pipe llanger Non M-205 USE 1223 (1) Q ANSI > 1\" 175 F 60 F AS P B31.1 IS
[
2NN HVAC Duct llangers M-635.2 /1" 50 F USE AS IS 1193 H-4001 Non AWS 71" 150*F
M H-4027 Q D1.1-75 7 '25" 225 F procedures (Turbine Bldg.) to be revised.
. 2NN llVAC Dact llangers M-635.2 4 li" 500F USE AS IS t
1194 R-3218 Non -
> 1\" 150 F None DIC weld M R-3298 Q AWS 7 2)" 2250F procedures (Control Bldg.) D1.1-75 to be revised
.T 2NN Non-Q' Steel C-121 Varies Varies Varies USE 1314 Repairs Non C-122 See See See AS C . Turbine Bldg. Cols. Q AWS NCR NCR NCR IS i
(18 cases) D1.1-75
1 k
PROCEDURE FOR PREHEAT TEST i
The following details shall be followed for the preparation of a simulated test plate to assess the effects of insufficient preheat.
- 1. The tes t plate (ASD'. A516, Gr. 70, 4' x l' x. 3") shall be cleaned on one side of all scale, loose rust, Erease, etc.
2 The th: ee attachment pieces shall be located approximately as shown in the sketch, and tack-weAded in place. .
- 3. The attachments shall be welded to the test plate with fillet velds of the size shown, using a preheat trzperature of 707 naxin.nn, and an interpass temperature of 100F maxiz:um for each separate attachment.
4 The welding electrode used shall be E7018.
l 5. All" welding shall be performed in the overhead position.
- 6. The welding procedure used shall be the one nor= ally used by DIC for making similar production welds (understood to be N-1-1).
- 7. A Bechtel welding engineer shall witness the welding activities.
- 8. On completion of the welding the test plate shall be sawcut at the locations shown on the sketch, and one side of each cut chall be prepared for macroexamination of the exposed weld cactions. Further sawing for ease of handling shall be perfor=ed if deemed necessary.
- 9. The exposed welds shcIl be etched and examined for the presence of underbead cracking by Bechtel.
- 10. At the direction of the Bechtel enginee'r, photographs of the welded assembly before, during and after co=pletion of welding shall be taken. Photomacrographs of the etched specimens shall also be taken. ,
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