|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20079B8591991-06-10010 June 1991 Interim Deviation/Noncompliance Rept 067 Re dry-type Insulator Cracking in Transformer Supplied by Westinghouse.Initially Reported on 910513.Util Notified Vendor on 910430 That Problem Affects Class 1E Transformer ML20245B8701989-04-21021 April 1989 Deficiency & Part 21 Rept Re Degradation of Nonmetallic Components & Sludge Formation in Lubricating Oil.Initially Reported on 890327.Degradation of Nonmetallic Parts & Fouled Bearings Evaluated ML20236P0061987-11-13013 November 1987 Final Part 21 & Deficiency Rept Re Failure of LPSI Pump When Energized.Initially Reported on 840523.Results of C-E Analytical & Test Program Showed That Excessive Shaft Deflection Eliminated by Use of Larger Diameter Motor Shaft ML20214M6471987-05-27027 May 1987 Final Deficiency Rept NY-QA-8 Re Atwood & Morrill Natural Frequency ASME III Active Valves,Identified During Ebasco Engineering Review.Initially Reported on 870515.Valves Will Be Reanalyzed & Modified.Not Reportable Per 10CFR50.55(e) ML20214E4681987-05-15015 May 1987 Deficiency Rept Re Natural Frequency of ASME III Active Valves.Initially Reported on 870413.Interim/final Rept Will Be Submitted by 870527 ML20207F1031986-12-18018 December 1986 Final Deficiency Rept Re Four Elgar Corp Static Uninterruptible Power Supply Units That Could Potentially Result in Failure of Class 1E 120-volt Vital Ac Bus. Condition Not Reportable Per 10CFR50.55(e) ML20214W7711986-11-26026 November 1986 Interim Deficiency Rept Re Uninterruptible Power Supply Assembly Deficiencies.Initially Reported on 860708. Final Rept Will Be Provided by 870116 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 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 ML20212N1371986-08-25025 August 1986 Part 21 Rept Re Potentially Defective Operation of Synchro-Start Products,Inc Synchronizing Speed Switches Used in Auxiliary Generating Equipment.Initally Reported on 860820.Next Rept Will Be Submitted by 860926 ML20205G0201986-08-0808 August 1986 Interim Deficiency Rept 64 Re Uninterruptible Power Supply Assembly Defects.Initially Reported on 860708.Cracked or Stressed Fuse Blocks Will Be Replaced by Nov 1986.Final Rept Anticipated by 861201 ML20202H2271986-03-26026 March 1986 Part 21 & Final Deficiency Rept D/N 62 Re Potential Overspeed Trip in Diesel Generators Mfg by Colt Industries. Initially Reported on 860224.Vendor Forwarded Proposed Mods Whereby Air Will Be Positively Vented After Engine Started 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 ML20137J4601985-12-27027 December 1985 Interim Deficiency Rept Re Rejectable Suction Nozzle Weld Defect on Ingersoll-Rand HPSI Pump.Initially Reported on 851127.C-E Performing Technical Review of Defect.Final Rept Will Be Submitted Upon Receipt of C-E Review Results ML20133E1111985-09-27027 September 1985 Final Part 21 & Deficiency Rept D/N 59 Re Possible Fractured or Cracked Welds on Louis Allis Emergency Standby Generators.Initially Reported on 850624.Item Not Reportable Per 10CFR50.55(e) ML20209H8381985-09-0404 September 1985 Final Part 21 & Deficiency Rept 58 Re Titus Products Tension Wires.Initially Reported on 850311.Tension Wires Replaced & Air push-on Locknuts Installed to Secure Wires to Shafts of Air Deflection Blades ML20133P1611985-07-24024 July 1985 Interim Part 21 & Deficiency Rept D/N 59 Re Cracked Welds on Diesel Generator Air Deflectors Supplied by Louis-Allis Co. Initially Reported on 850624.Corrective Actions Not Received from Vendor.Next Rept Expected by 850927 ML20128K1911985-07-0101 July 1985 Deficiency Rept D/N 52 Re LPSI Pump Failures.Pump Evaluation Necessary for Final Rept Not Yet Received.Final Rept to Be Provided as Soon as Info Received ML20115J9201985-04-0101 April 1985 Final Deficiency Rept Re Brown Boveri Voltage Balance Relays W/Excessive Operating Time.Initially Reported on 850227. Relays Removed from Control Panels & Returned to Vendor for Replacements.Item Not Reportable Per 10CFR50.55(e) ML20115D0491985-03-29029 March 1985 Interim Deficiency Rept (D/N 58) Re Titus Model 272 Grille Tension Wire Failing to Remain in Place.Initially Reported on 850311.Existing Tension Wires Will Be Replaced ML20112E6631985-03-0707 March 1985 Interim Deficiency Rept Re Failure of Borg-Warner 2-inch HPSI Header Isolation Valves.Initially Reported on 850204. Opening Torque Switch Light Bypassed & Valve Yoke Tack Welded to Valve Body ML20113A5381984-12-27027 December 1984 Final Part 21 & Deficiency Rept Re Damaged Wires on Westinghouse Ds/Dsl Circuit Breakers.Initially Reported on 841012.Damaged Wires Will Be Replaced & Addl Wire Ties Installed ML20101B1571984-12-0303 December 1984 Corrected Final Deficiency Rept (D/N 55) Re Foxboro N-2AC Module Fuse Pin Damage.Fabrication Dates for Defective Modules Should Be May 1981 - Jul 1982 ML20100F9111984-11-21021 November 1984 Final Deficiency Rept (D/N 55) Re Foxboro N-2AC Module Fuse Pin Damage.Initially Reported on 841026.Defective Modules Will Be Replaced Prior to Startup ML20100H5991984-11-16016 November 1984 Deficiency Rept (D/N 54) Re Defective Westinghouse Ds/Dsl Circuit Breakers.Field Insp of All Applicable Class 1E Circuit Breakers in Progress to Determine Extent of Problem. Next Rept Will Be Submitted by 841228 ML20099H1961984-11-13013 November 1984 Part 21 & Final Deficiency Rept (D/N 53) Re Rockbestos Cable Insulation Damage.Initially Reported on 841012.Four Installed Cables Having Reworked Areas Will Be Identified & Either Removed or Abandoned ML20099F4911984-11-0606 November 1984 Interim Deficiency Rept D/N 51 Re Potential Defect in Reactor Coolant Pump.Initially Reported on 830927.Final Rept Will Be Submitted Upon Receipt of C-E Specific Repair Program ML20094Q8041984-08-0707 August 1984 Part 21 Rept Re Tension Wires on Titus Grille,Model 272, Not Remaining in Place When Deflection Blades Closed. Affected Job Sites Identified in Encl.Products Being Tested Provide Acceptable Fix for Retention ML20094Q8281984-08-0707 August 1984 Part 21 Rept Re Failure of Tension Wires Used for Adjustment of Blades on Grille Model 272.Testing to Identify Rework Methods to Be Utilized in Progress ML20092M7991984-06-22022 June 1984 Interim Deficiency Rept D/N 52 Re LPSI Pump Failures. Initially Reported on 840523.Corrective Action Will Be Proposed Upon Completion of Investigation.Final Rept Will Be Provided by 850630 ML17325B6701984-06-20020 June 1984 Final Deficiency Rept (D/N#49) Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Initially Reported on 830624.Total of 1,442 Beam Assemblies Examined,Including 3,318 Coped Corners.All Physical Repair Activities Completed ML20197H1741984-06-0404 June 1984 Interim Deficiency Rept Re C-E Sys 80 Reactor Coolant Pump Hydraulic Defect.Initially Reported on 830927.Design Problems Identified & Corrected.Next Rept Will Be Submitted by 841101 ML20080G5361984-01-31031 January 1984 Interim Deficiency Rept D/N 49 Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Cb&I Will Complete Investigation & Forwards Results to Ebasco by Apr 1984.Final Rept Expected by 840615 ML20083B6811983-12-0606 December 1983 Final Deficiency Rept Re Main Steam & Feedwater Penetration Anchors.Initially Reported on 830426.No Addl Deficiencies Found.Ebasco Procedures Revised ML20082E6451983-11-0808 November 1983 Interim Deficiency Rept D/N 49 Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Initially Reported on 830722.Similar Deficiencies May Have Occurred in Jet Impingement Barrier Matls.Final Rept Will Be Submitted by 840215 ML20082E3611983-10-31031 October 1983 Interim Deficiency Rept 51 Re Reactor Coolant Pump Defect. Initially Reported on 830927.Cause Under Investigation. Existing Design Will Be Retested W/Addl Instrumentation. Final Rept Will Be Provided by 840601 ML20076L5951983-09-0202 September 1983 Final Deficiency Rept 50 Re Cracked Weld & Loose Parts in C-E Steam Generators.Initially Reported on 830801.Documented Missing,Damaged or Defective Parts & Loose Parts Tightened ML20080D3261983-08-17017 August 1983 Interim Deficiency Rept NY-QA-5 Re Main Steam & Feedwater Penetration Anchors.Addl Time Required to Complete Comprehensive Evaluation.Final Rept Submittal Anticipated by 831205 ML20077Q5131983-08-0101 August 1983 Interim Deficiency Rept NY-QA-5 Re Main Steam & Feedwater Penetration Anchors.Initially Reported on 830609.Pipe Rupture Analysis & Seismic Analyses Conducted.Final Rept Expected by 830915 ML20024D1711983-07-22022 July 1983 Interim Deficiency Rept Re Nonconforming Weld Repair of Beam Cope Burn Cuts.Initially Reported on 830624.Cause & Extent of Burn Cuts & Nonconforming Weld Problem Investigated.Final Rept Scheduled for 840215 ML20024A4381983-06-0909 June 1983 Interim Deficiency Rept NY-QA-5 Re Main Steam & Feedwater Penetration Anchor Stress Analyses.Initially Reported on 830426.Engineering Procedure Revised & Analyses Performed. Final Rept Expected by 830729 ML20069M4371983-04-20020 April 1983 Final Deficiency Rept Re Rockbestos Insulated Cable Type D60-1.Initially Reported on 821203.Dented Cable to Be Reworked to Restore Cable to Original Specified Thickness. Deficiency Determined Not Reportable Under 10CFR50.55(e) ML20074A7571983-04-0606 April 1983 Supplemental Final Deficiency Rept Re Safety Injection Tank safe-end Indications (D/N 23).Safe-end-to-nozzle-welds for Injection Tanks Reradiographed,Approved & Accepted Per Spec & ASME Code Requirements ML20072R0151983-03-25025 March 1983 Part 21 Rept Re Deviation in Quality of Shielded Instrumentation Cables.Initially Reported on 820412.Problem Determined Not to Be Reportable Per Part 21 ML20069E6951983-03-14014 March 1983 Final Deficiency Rept Re Failure of Structural Welds to Meet Aws Min Weld Size Requirements.Initially Reported on 821124. Condition Not Reportable Per 10CFR50.55(e) Based on Satisfactory Completion of Qualification Testing ML20071D3671983-03-0202 March 1983 Final Deficiency Rept Re Safety Injection Tank safe-end Indications (D/N 23).All Linear Indications Found in safe-end-to-nozzle Welds of Safety Injection Tanks 3 & 4 Removed & Rewelded Per ASME Section XI Plan ML20071D7141983-03-0202 March 1983 Final Deficiency Rept Re Safety Injection Tanks - safe-end Indications.All Linear Indications in safe-end-to-nozzle- Welds in Safety Injection Tanks 3 & 4 Removed & Rewelded Per ASME Section XI Plan.Final Radiographs Verified Repairs ML20065B5841983-02-11011 February 1983 Final Deficiency Rept D/N 44 Re Compressible Matl - Embedded Containment Penetrations.Initially Reported on 820921.Load Case Test Results Confirm Subj Deficiency Not Reportable Per 10CFR50.55(e) ML20065B5071983-02-0808 February 1983 Final Deficiency Rept D/N 46 Re Diffuser Retaining Cap Screws on Reactor Coolant Pumps.Initially Reported on 821105.Cap Screw Matl Heat Treatment Changed So Matl Not Susceptible to Hydrogen Corrosion Cracking ML20070V9801983-02-0808 February 1983 Final Deficiency Rept Re Failed Diffuser Retaining Cap Screws to Sys 80 Reactor Coolant Pumps.Cap Screw Matl Heat Treatment Will Be Changed to Prevent Hydrogen Embrittlement/ Stress Corrosion Cracking.Not Reportable Per 10CFR50.55(e) 1991-06-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20202C8081999-01-22022 January 1999 Safety Evaluation Supporting Order Terminating Construction Permit CPPR-154 ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B2121997-12-31031 December 1997 Washington Public Power Supply Sys Annual Rept for 1997. W/980108 Ltr ML17292A6361996-12-31031 December 1996 Washington Public Power Supply Sys Annual Rept for 1996. W/961212 Ltr ML17291B1501995-12-31031 December 1995 Washington Public Power Supply Sys Annual Rept 1995. W/ 951201 Ltr ML17291A6761994-12-31031 December 1994 Washington Public Power Supply Sys 1994 Annual Rept. W/ 950302 Ltr ML17290A9581993-12-31031 December 1993 Washington Public Power Supply Sys Annual Rept,1993. W/940209 Ltr ML17289B1231992-12-31031 December 1992 Washington Public Power Supply Sys 1992 Annual Rept. W/930119 Ltr ML17289A2761991-12-31031 December 1991 Washington Public Power Supply Sys 1991 Annual Rept. W/ 920128 Ltr ML17286B2761991-07-31031 July 1991 Rev 0 to Washington Nuclear Plant 3 Seismic Design Basis Model Validation,Soil Variation Studies. ML20079B8591991-06-10010 June 1991 Interim Deviation/Noncompliance Rept 067 Re dry-type Insulator Cracking in Transformer Supplied by Westinghouse.Initially Reported on 910513.Util Notified Vendor on 910430 That Problem Affects Class 1E Transformer ML17286B2681991-05-0707 May 1991 Justification for Revised Tornado Design Criteria. ML17286A5541990-12-31031 December 1990 WPPSS,1990 Annual Financial Rept. W/910115 Ltr ML17285A9891989-12-31031 December 1989 WPPSS,1989 Annual Rept. W/900129 Ltr ML20245B8701989-04-21021 April 1989 Deficiency & Part 21 Rept Re Degradation of Nonmetallic Components & Sludge Formation in Lubricating Oil.Initially Reported on 890327.Degradation of Nonmetallic Parts & Fouled Bearings Evaluated ML20154D3231988-05-16016 May 1988 Safety Evaluation Supporting Util 841102 & 860310 Requests for Extension of Plant Const Completion Date from 850101 to 990701 ML20147D3921988-02-29029 February 1988 Seismic Hazards Assessment for Washington Nuclear Plant-3, Satsop,Wa Contract C-20453, Final Rept ML17279A7641987-12-31031 December 1987 WPPSS,1987 Annual Rept. W/880108 Ltr ML20236P0061987-11-13013 November 1987 Final Part 21 & Deficiency Rept Re Failure of LPSI Pump When Energized.Initially Reported on 840523.Results of C-E Analytical & Test Program Showed That Excessive Shaft Deflection Eliminated by Use of Larger Diameter Motor Shaft ML20215C3061987-06-11011 June 1987 Safety Evaluation Supporting Application of Modified Itt/ Grinnell Stiff Clamps for Use in safety-related Piping Sys ML20214M6471987-05-27027 May 1987 Final Deficiency Rept NY-QA-8 Re Atwood & Morrill Natural Frequency ASME III Active Valves,Identified During Ebasco Engineering Review.Initially Reported on 870515.Valves Will Be Reanalyzed & Modified.Not Reportable Per 10CFR50.55(e) ML20214E4681987-05-15015 May 1987 Deficiency Rept Re Natural Frequency of ASME III Active Valves.Initially Reported on 870413.Interim/final Rept Will Be Submitted by 870527 ML17278B1731986-12-31031 December 1986 Wppss Annual Rept 1986. ML20207F1031986-12-18018 December 1986 Final Deficiency Rept Re Four Elgar Corp Static Uninterruptible Power Supply Units That Could Potentially Result in Failure of Class 1E 120-volt Vital Ac Bus. Condition Not Reportable Per 10CFR50.55(e) ML20214W7711986-11-26026 November 1986 Interim Deficiency Rept Re Uninterruptible Power Supply Assembly Deficiencies.Initially Reported on 860708. Final Rept Will Be Provided by 870116 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 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 ML20211A8421986-09-0808 September 1986 Final Rept of Earthwork Module C3-01 of Facility Const Assurance Program of Facility Readiness Review Program ML20212N1371986-08-25025 August 1986 Part 21 Rept Re Potentially Defective Operation of Synchro-Start Products,Inc Synchronizing Speed Switches Used in Auxiliary Generating Equipment.Initally Reported on 860820.Next Rept Will Be Submitted by 860926 ML20205G0201986-08-0808 August 1986 Interim Deficiency Rept 64 Re Uninterruptible Power Supply Assembly Defects.Initially Reported on 860708.Cracked or Stressed Fuse Blocks Will Be Replaced by Nov 1986.Final Rept Anticipated by 861201 ML20203E6321986-06-30030 June 1986 Validation of Ebasco Foundation Spring Modeling for Elastic Half-Space Seismic Model ML20198N5431986-05-31031 May 1986 Addendum to CEN-315 Summary of Diversity Between Reactor Trip Sys & Auxiliary Feedwater Actuation Sys for C-E Plants ML20202H2271986-03-26026 March 1986 Part 21 & Final Deficiency Rept D/N 62 Re Potential Overspeed Trip in Diesel Generators Mfg by Colt Industries. Initially Reported on 860224.Vendor Forwarded Proposed Mods Whereby Air Will Be Positively Vented After Engine Started ML20140A7621986-02-28028 February 1986 Informs of Plans for Implementing Severe Accident Policy Statement & Regulatory Use of New source-term Info 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 ML17278A6141985-12-31031 December 1985 Wppss 1985 Annual Rept. W/860225 Ltr ML20137J4601985-12-27027 December 1985 Interim Deficiency Rept Re Rejectable Suction Nozzle Weld Defect on Ingersoll-Rand HPSI Pump.Initially Reported on 851127.C-E Performing Technical Review of Defect.Final Rept Will Be Submitted Upon Receipt of C-E Review Results ML20138D7281985-11-30030 November 1985 Draft SER Re Status of Staff Review of FSAR & Associated Submittals Until Const Delay Announced in 1983 ML20133E1111985-09-27027 September 1985 Final Part 21 & Deficiency Rept D/N 59 Re Possible Fractured or Cracked Welds on Louis Allis Emergency Standby Generators.Initially Reported on 850624.Item Not Reportable Per 10CFR50.55(e) ML20209H8381985-09-0404 September 1985 Final Part 21 & Deficiency Rept 58 Re Titus Products Tension Wires.Initially Reported on 850311.Tension Wires Replaced & Air push-on Locknuts Installed to Secure Wires to Shafts of Air Deflection Blades ML20132H0331985-07-31031 July 1985 Rev 1 to Evaluation of Itt/Grinnel Figure 215 Stiff Clamp Application on Safety-Related Piping Sys ML20133P1611985-07-24024 July 1985 Interim Part 21 & Deficiency Rept D/N 59 Re Cracked Welds on Diesel Generator Air Deflectors Supplied by Louis-Allis Co. Initially Reported on 850624.Corrective Actions Not Received from Vendor.Next Rept Expected by 850927 ML20128K1911985-07-0101 July 1985 Deficiency Rept D/N 52 Re LPSI Pump Failures.Pump Evaluation Necessary for Final Rept Not Yet Received.Final Rept to Be Provided as Soon as Info Received ML20115J9201985-04-0101 April 1985 Final Deficiency Rept Re Brown Boveri Voltage Balance Relays W/Excessive Operating Time.Initially Reported on 850227. Relays Removed from Control Panels & Returned to Vendor for Replacements.Item Not Reportable Per 10CFR50.55(e) ML20115D0491985-03-29029 March 1985 Interim Deficiency Rept (D/N 58) Re Titus Model 272 Grille Tension Wire Failing to Remain in Place.Initially Reported on 850311.Existing Tension Wires Will Be Replaced ML20112E6631985-03-0707 March 1985 Interim Deficiency Rept Re Failure of Borg-Warner 2-inch HPSI Header Isolation Valves.Initially Reported on 850204. Opening Torque Switch Light Bypassed & Valve Yoke Tack Welded to Valve Body ML20129A0631985-02-20020 February 1985 Rev 2 to Preservation of Assets Preventative Program ML17277B6301984-12-31031 December 1984 1984 Annual Rept. W/850222 Ltr ML20113A5381984-12-27027 December 1984 Final Part 21 & Deficiency Rept Re Damaged Wires on Westinghouse Ds/Dsl Circuit Breakers.Initially Reported on 841012.Damaged Wires Will Be Replaced & Addl Wire Ties Installed ML20101B1571984-12-0303 December 1984 Corrected Final Deficiency Rept (D/N 55) Re Foxboro N-2AC Module Fuse Pin Damage.Fabrication Dates for Defective Modules Should Be May 1981 - Jul 1982 1999-01-22
[Table view] |
Text
Docket.Nos. 50-508/509
. ?c,
- (
50 55(e) Report Washington Public Power Supply System g Box 1223 Elma, Washington 98541 (206)482-4428 '-'
- 4" ,
Docket Numbers 50-508 and 50-509 @ ._. y April 16, 1982 k 1 G03-82-391 p g C co g' U. S. Nuclear Regulatory Commission, Region V e ,
Office of Inspection and Enforcement s Q 1450 Maria Lane, Suite 260 -
Walnut Creek, California 94596-5368 9
~ M Attention: Mr. T. W. Bishop E ' O EN ---
Chief, Reactor Construction Projects Branc d "$E.5]l[fy $ y 3 /)
M .
Subject:
PROJECT N05. 3 AND 5 10CFR50.55(e) REPORTABLE CONDITION
% g , f , .,i \ J' WELDING DEFICIENCIES IN RP PLATES (D/N #25)
In accordance with the provisions of 10CFRSO.55(e), Region V was noti-fied that the subject condition was potentially reportable. Subsequent investigation has determined that the deficiency is significant and were it to have remained uncorrected could have adversely affected the safety of operations of the facility.
Attached is the Supply System approved final report for the subject con-dition detailing a description of the deficiency, safety analysis and corrective / preventive actions taken.
Should you have any questions or desire further informatian, please con-tact me directly. ,
c' R. S. Leddick, 760 Program Director, WNP-3 DRC/tt Attachment cc: J. Adams - NESCO D. Smithpeter - BPA Ebasco - New York WNP-3/5 Files - Richland 7677J
//
8204270Ahd . _ _ _ .-
32,~a 9
e -
ATTACHMENT 1 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NUMBERS 50-508 AND 50-509 FINAL 10CFR50.55(e) REPORT WELDING DEFICIENCIES IN RP PLATES (D/N #25)
INTRODUCTION Fought Steel, Portland, Oregon,'-fabricated the type RP enbed plates under Contract 3240-95 for WNP-3/5. The embed plates are designed for installation in concrete on the interior and exterior shear walls of the Reactor Auxiliary Buildings (RAB) to support the pipe rupture restraints and seismic interface restraints for main steam and feedwater piping.
RP is a designation given to identify these embed plates for the main steam and feedwater piping and is subdivided into a number of RP types. These embed plates are fabr.icated from ASTM A-36 steel to Quality Class I and the thickness of the plates varies from 1 inches to 3 inches. Most of the RP pl,ates have shear lugs welde8 on the back. In addition to these shear' lugs, some of the RP plates have shear bars welded on the face of the pla,tes . The thickness of these shear bars and shear lugs also varies from 1 inch to 3 inches.
Cracks were found in the welds placed at the corner joints where transverse and longitudinal shear lugs meet. These cracks were discovered during the course of the fabrication of the embed plates. The design does not require these two plates to be we'.ded together, but Fought Steel welded across the corner with a thin pass seld.
During the course of the Engineer $ng investigation of the cracks identified above, it was also found that the fabrication of these plates did not provide full penetration welds nor was post veld heat treatment performed as required by the design drawings and contract specifications. Failure to meet these requirements constitutes a significant breakdown in the Quality Assurance Program.
I
e c.
DESCRIPTION OF DEFICIENCY The deficiencies can be categorized as follows:
Weld Crack: Welds were applied across the ends of the shear lugs and in corners formed at the intersection of the shear lugs. These welds were not shown on design drawings and cracks were found in these welds.
Partial Penetration Welds Instead of Full Penetration Welds: Shear lugs and bars were welded to the plate by partial penetration groove welds whereas design drawings required full penetration welds.
Lack of Post Weld Heat Treatment: The Project Specification required a post weld heat treatment of welds thicker than 1 1/2 inches; however this was not performed.
Breakdown in Quality Assurance Program: Failure to detect the material and fabrication deficiencies described above represents a breakdown in the Quality Assurance Program. This is evidenced by the following:
- 1. Vendor failure to adequately implement special process controls;
- 2. Vendor and Engineer failure to perform work in accordance with in-structions, procedures or drawings;
- 3. Vendor fa'ilure to perform inspections to verify conformance to draw-ings.
4
SAFETY ANALYSIS The type RP plates are provided to attach pipe rupture and seismic interface restraints for main steam and feedwater piping to building structure and are installed in the Reactor Auxiliary Building exterior and interior shear walls and on the roof. Rupture restraints are provided to support this piping during postulated pipe break.
All the questionable RP plates are on the outside face of the exterior shear wall. The piping restraints and embeds in this area will be exposed to the outside atmosphere.
Six RP-18 plates are provided to support the rupture restraints, three each on the north and south exterior shear walls. These restraints are located on the outside of exterior sh~ar e wall, immediately after the main steam and feedwater pipes exit the Reactor Auxiliary Building.
the Administrative Building on the north side, transformer and
, refueling tank area on the south side, and the RAB exterior walls could be exposed to the resulting jet i=pingement and impact loads due to the pipe rupture if the plates fail and allow the support to fail.
Damage to these structures could result with attendant danger to plant personnel and equipment.
Because of the deficiencies previously identified, the structural integrity of the RP plates could not be assured during the postulated pipe breaks without implementing the corrective actions which were taken. Hence, the above deficiency is considered significant and reportable per 10CFR50.55(e).
CORRECTIVE ACTIONS Weld Cracks All plates were reinspected by Magnetic Particle testing method except those plates which were already installed. Based on the inspection results, corrective actions were taken as follows:
- 1) Where no defects were found, the filler veld metal at corner joints was removed back 1/4" to 3/4" from the corners until faying surfaces between intersecting lugs were visible down to the surface of the base plates.
- 2) When defects were found, the repairs were made as follows:
a) When the defects were found entirely in the weld metal, the indications were co=pletely removed. Weld metal at the corner was re=oved to the surface of the base metal. The reworked areas were reinspected using MT or PT techniques.
b) When the defects were found to extend into the base plate, the defects were removed by excavating into the base plate.
Defect removal was confirned by PT or HT. The plate was repaired and the thickness of the plate was restored to its original thickness. The repaired area was UT examined to ascertain the soundness.
- 3) The four RP-29 plates which were installed in the concrete were UT examined. No cracks were found in these plates.
Weld cracks were found only in Types RP-33 and RP-28. Two RP-33 and eight RP-28 plates were involved.
Fought Steel used cold bending procedures to remove a slight warpage in the plates after veldup. Cold bending is a standard mill practice employed-by steel mills to straighten rolled plates to comply with the shape and dimensional tolerances. Fabricators also use the same techniques. ASME Section NC and NF also allow cold bending in the case of steel plates.
i Partial Penetration Welds The plates which had partial penetration velds instead of full penetration welds were UT examined. On the basis of the UT results the plates were reanalyzed for the individual support design loads. All but Type RP-18 were found to be acceptable. Type RP-18 plates were redesigned to acco=modate the load transfer to the supporting wall. A Design Change Notice was issued to rework the plates. The required rework has been completed.
l l
l l
l l
CORRECTIVE ACTIONS (C0hT'D)
Lack of Post Weld Heat Treatment A comparative study was made of two Type RP plateI samples (RP-16 and RP-38) as welded without post veld heat treatment and new welded sections with post weld heat treatment. The results and analysis are discussed in the following paragraphs:
Fabrication Conditions -
The embedments of concern were fabricated by Fought, employing the flux cored are welding process and a weld energy input of 72 kilojoules/ inch.
Preheats are reported to have ranged from 175 F-250 F for sections up to 2b" thick and 275 F-325 F for thickness over 2 ", the preheat maintained until completion of welding. The preheats used by Fought were in excess of those required by AWS Dl.1, which are, 150 F for up to 2h" thickness, 225 F for greater than 2 ". The weld energy input used by Fought to fabricate the embeds, combined with the preheat and interpass temperatures used, b developed a more favorable, slower cooling rate and a sof ter veld zone.
Hardness Testing Sections from weldments produced by Fought were obtained from embedment RP16 (2" thick) and embedment RP38 (3" thick). Both are identical to the embedments of concern and were welded according to the same procedures. The carbon equivalent of both the RPl6 and RP38 esbedments steel material was found to be .47%.
The test cross-sections, supplied in the saw-cut condition, were prepared for as-welded hardness measurement by polishing and etching.
( Knoop hardness surveys were made at two locations in the weld, one at the toe, where higher hardnesses were expected because this region was not tempered by a subsequent weld bead, and in the throat approximately halfway through the weld. All Knoop readings were converted to Rockwell.
The maximum hardness values obtained in the weld zone of the 2" embed-ment (RP16) was 24 HRC for the weld toe; maximum hardness of the 3" embedment (RP38) weld toe was found to be 25 RRC. All other hardnesses in the RP16 and RP38 embedments were in the 90-95 HRB eange.
l l
l l
1
CORRECTIVE ACTIONS (CONT'D)
Lack of Post Weld Heat Treatment (Cont'd)
Post Weld Heat Treatment And Metallographic Evaluation Tb2 Fought embedments test material weld zone maximum hardness of ? ' and 7.5 HRC, was found to be .in excess of the industry-accepted upper is el which is considered suitable for installation without post weld heat treatment.
Recent concerns for notch toughness of pipe rupture restraint materials by the industry prompted furnace treatment testing so as to dispel concerns over the 25 HRC hardness and its notch toughness. Accordingly, a section of Fought embedment, sa=ple RP38, was furnace heat treated for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 1150 F. A hardness traverse, si=ilar to that conducted on the as-welded RP38 test sample, was performed on the heat treated material. Maximum hardness of the material was found to have decreased from 24 HRC to 93 HRB.
The apparent need for an explanation regarding the suitability of material at no=inal 25 HRC for service prompted a microstructural evaluation. The 25 HRC hardness of the as-welded material suggested that a minimal a=ount of martensite, a brittle constituent causing the weld zone hardness, may be present in the hard zone, on the order of 5%. Microscopy was conducted to provide credence for the 5% martensite estimate; this level known to have negligible effect of ductility.
Examination of the structures at 1000X and lesser magnifications did not reveal any martensite. A minor amount of material, considered to be martensite at 300X magnification, was found to be a fine dense pearlite upon examination at higher magnification.
Summary This evaluation has established that embedments composed of carbon steel materials and containing a moderate level of constituents affecting hardenability do not, when fabricated according to suitable conditions, experience significant hardening in the weld zone. This was confirmed by the relatively low hardness values obtained, 25 HRC maximum in the weld zones of duplicates of the welded embedment co=ponents.
P l
I l
l l
l l
i
~
CORRECTIVE ACTIONS (CONT'D) 4 Lack of Post Weld Heat Treatment (Cont'd)
Summary (Cont'd)
The results, as supported by the as-welded hardness values, also confirmed that the use of a relatively high heat input, in combi-nation with the preheat /interpass temperature ranges applied, re-sulted in a cooling rate sufficiently slow to inhibit the forma-tion of an undesirable transformation structure in the weld heat-affected zone. The reduction in hardness determined for the post weld heat treated material was found to have resulted from soften-ing of dense early transformation products in the weld zone. This material is known to be more ductile in the as-welded condition than is the undesirable and more brittle structure, martensite, and does not require thermal treatment for achieving adequate ser-vice performance. The possibility for presence of the martensite phase in the weld zone, owing to the lack of weld process selection controls on fabricators, mandated the inclusion of a post weld heat treatment requirement in the component specification.
Based on the above analysis all plates covered by this report have been accepted without post weld heat treatment.
Breakdown in Quality Assurance Program The contract for the supply of these components is being closed out.
With no components being supplied in the future, no corrective action has been imposed on Fought. The supplier has been informed of these deficiencies.
The responsible Ebasco VQAR assigned to the Vendor's facility was re-moved from the WNP-3/5 Project activities. On site training sessions l have been held for the Vendor Quality Assurance Representatives (VQARs).
The training consisted of visual welding inspection requirements.
Additionally, vendor inspection plans have been reviewed to assure the .
, inclusion of post weld heat treatment verification, as required. The VQARs have been informed of these requirements.
l l
l l l i
- ~