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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
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a2 o . Doeket.Nos. 50-508/509 -
rt 5055(QC$fYD tmc Washington Public Power Supply System Box 1223 Elma, Washington 98541 (206) 482MTJy l l - g ll: 10 Docket Numbers 50-508 and 50-509 liEGD'iVi&2 February 8,1982 G03-82-123 cs N g,
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1 h *By U. S. Nuclear Regulatory Comission, Region V M_ 'D Qj4 Office of Inspection and Enforcement Au^
1450 Maria Lane, Suite 260 ;
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Walnut Creek, California 94596-5368
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Attention: Mr. B. H. Faulkenberry Chief, Reactor Construction Projects Branch
Subject:
PROJECT N05. 3 AND 5 FINAL REPORT OF POTENTIAL 10CFR50.55(e)
SHUTDOWN COOLING HEAT EXCHANGER DEFECTS (D/N #007)
Reference:
Letter, G03-80-1516, dated June 25, 1980, D. L. Renberger to G. S. Spencer, Reportable Deficiency,10CFR50.55(e).
In accordance with the provisions of 10CFR50.55(e), Region V was noti-fled of potential deficiencies associated with the Shutdown Cooling Heat Exchangers.
Attached is the Supply System approved finto report for the subject condition. The report provides a detailed description of the deft-ciencies and items of concern, corrective steps taken and an analysis of the safety implications.
The referenced letter addressed the subject 10CFR50.55(e) as " report-able;" however, based on the evaluation detailed in the attached re-port, it is considered that the defects associated with the Shutdown-Cooling Heat Exchangers would not adversely affect safe operations of the plant. Therefore, .the subject condition is not reportable in accordance with 10CFR50.55(e).
8202180332 820208 PDR ADOCK 05000500 S PDR lh 3 i
edhe ;
] Mr. .B. _ H.' Faulkenberry Page 2' . .
. February 8,1982 '
? G03-82-123 I
aimald you have any questions or desire further information, please contact me directly.
4
/ '
R. S. Leddick/1000 Program Director, WNP-3/5 DRC/tt' Attachment
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- J. Adams - NESCO-WO/A
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D. Smithpeter - BPA-WO/A
- Ebasco - New York-WO/A i
WNP-3/5 Files - Richland-WO/A i
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i
SHUTDOWN COOLING HEAT EXCHANGERS (D/N 0007)
ABSTRACT The Shutdown Cooling Heat Exchangers (SDHX's) supplied for WNP-3 and WNP-5 showed significant defects when the SDHX's were inspected at site prior to turnover to installation contractor. The defects were found on both weld overlay claddings and tubes. The tube defects were weld seam crevice and galled types, as well as contaminations with water and foreign substances containing high chloride. The weld overlay defects were cracks and below minimum thicknesses.
These units are safety related components manufactured for CE by Ametek, lo-cated at Bethayres, Pennsylvania under ASME Section III Class 2 for tube side and ASME Section III Class 3 for shell side.
Since extensive defects were found in these units, these units were returned to Ametek for indepth examinations and repairs.
Upon completion of indepth examinations, tubes for WNP-3 units supplied by Allegheny-Ludlum Tubing were rejected in their entirety and replaced with tubes supplied by Plymouth Tubing. Tubes for WNP-5 units supplied by Green-ville Tubing were accepted for use.
Existing cladding overlays for WNP-3 units were removed and reclad in most areas. For WNP-5 units only flange areas were reclad after removing orignal cladding. For other areas only thin areas were built up.
Following the repair, the Supply System reviewed and inspected the units at Ametek in July to August, 1981 and released the units for shipment for reinstallation at site.
Shop Numbers of these units and original and final installation locations are:
Shop No. Original Location Final Location N80-45600 WNP-3S WNP-55 N80-45601 WNP-3N WNP-5N N80-45602 WNP-55 WNP-35 N80-45603 WNP-5N WNP-3N The deficiencies identified above indicate a significant breakdown in Ametek's quality assurance program as defined by 10CFR50.55(e).
1.0 DESCRIPTION
OF THE DEFICIENCY AND ITEMS OF CONCERN The defects found in tube walls and in the weld overlay claddings are described below.
Tubes for the WNP-3 SDHX's were manufactured by Allegheny Ludlum Steel Corporation and the tubes for the WNP-5 SDHX's were manufactured by Greenville Tube Corporation.
The Ametek purchase orders required the tubes (1" 00, .049" wall thickness) to meet the requirements of ASME Section III, 1974 Edition.
Winter '75 Addenda and ASME Section II SA-249 Type 304.
A. Defects in Tube wall
- 1) Finding of Contaminants Water contaimination of WNP-3 SDHX's was not discovered until August, 1979 after the first SDHX was received at site on June 30, 1978 because the SDHX was nitrogen purged and the existing procedure in effect did not require opening of the equipment for inspection of internals until the time of turn-over to the installing contractor.
Stagnant water with a high concentration of chloride (50 ppm for unit 45600 and 32 ppm for unit 45601) was found submerg-ing the lower 4-6 rows of tubes on ooth units of WNP-3.
l l Also, unidentified black and yellow " crud" and a scale-like l
' substance containing up to 7.58% chloride and heavy metal was collected from I.D. tube surfacesoof both WNP-3 and WNP-5 units.
- 2) Eddy Current Test Results of the Supply System As a result of the potential impact due to contamination, the Supply System performed Eddy Current (ECT) examination on two SDHX's of WNP-3 units.
They observed indications of.the tube pitting, and 0.D.
imperfections, tube dents and distorted tube support signals.
ECT on WNP-5 was attempted but was discontinued after crud and scale like substances were picked up on the ECT probe.
- 3) Metallurgical and Nondestructive Examination by CE As a result of ECT, two tubes from SDHX #45600 and three tubes from SDHX #45603 were removed to observe directly the tube defect.
. __ . _ _ _ _ _ _ . A
a) Visual Examination After Tube Slitting
- 45600 Tube 0.D. showed severely galled indications around the-entire circumference and along the entire length. Tube I.D. showed clearly evident weld seam.
- 45603 No lack of side wall fusion (LOF) condition was evi-dent. Shallow, longitudinal. scratches were found on I.D. Several tuigsten inclusions were observed in the weld with maximum depth of 0.012". No weld seam was evident on I.D.
b) -Metallographic Observations - #45600 Two types of defects were observed; first type is a de-fect involving 0.D. and I.D. weld centerline surface imperfections. (ie., shrinkage cavities, inclusions)
The second type is characterized by intermittent LOF at the I.D. of the tube.
c) Bend Test Results - #45600 A bend test was made. The sample was bent such that the I.D. of the weld was strained in tension. The weld readily tore open from the I.D. and exposed a portion of tube wall, clearly indicating LOF over approxi-mately one-third of the tube wall. The test results confirmed that these tubes furnished to SA-249 Specifi-cation did not meet the applicable requirements of SA-450.
- 8. Defects in Overlay Weld Cladding
- 1) Finding of Defects Rust, crack-like indications and pitted areas in certain small areas of the flange I.D. were discovered after two WNP-3 SDHX's were cleaned.
This network of cracks was found to exist only in the stain-less overlay, most extended down to the interface of overlay and base metal. In no case did the cracks extend into the carbon steel base uetal.
- 2) Results of NDE Examination by the Supply System Following the discovery of overlay cladding defects during the attempted repair in the field, liquid penetrant (LP) and ultrasonic (UT) examinations were conducted.
b _ _ _ _
a) Liquid Penetrant (LP) Examination Unacceptable linear indications, beyond code allowable, were found on vessel's channel in 45600, on closure head and flange face in 45601, and on ves;el flange in 45602-and 45603.
b) Cladding Thickness The CE SD:1X Specification calls for a minimum stainless steel overlay of 1/8 inch on all channel sections except for the tube sheet which is required to have a minimum 3/16 inch overlay. UT examin~ation of overlays shows the following thicknesses which are much less than the mini-mum thicknesses specified in the SDHX Specification on certain spots.
45600 - Vessel - 0.03" - 0.07" 45601 - Vessel - 0.06" - 0.08" 45602 - Head - 0.1", Tube Sheet - 0.04", Shell - 0.07" 45603 - Vessel Flange - 0.012", Vessel Head - 0.05", Tube Sheet - 0.06", Vessel - 0.04" - 0.08".
- 3) Evaluation of Manufacturing Processes at Ametek Because of the severity of defects confirmed by the Supply System following their LP and UT examinations, the Supply System reviewed the manufacturing processes at Ametek. The review revealed the following:
a) Unit 3 Exchangers: The weld overlay applied to the tubesheet, flange, and channel cover was produced by the submerged arc welding (SAW) process using a single bare wire plus a supplementary powder filler material to in-crease deposition rates. The overlay was oroduced in one layer only and had a 308L chemistry. This process was found to be unacceptable.
b) Unit 5 Exchangers: The overlay was performed using the SAW strip cladding process. Dimensions of the strip filler metal are 60 mm wide by 0.5 mm thick. The over-lay was produced in two layers - the first with a 309L chemistry and the second with a 308L chemistry. This process was found to be acceptable, c) In general, none of the weld overlay procedures'were properly qualified to the requirements of ASME Code Sec-tion IX because the selection of the location for the weld chemistry sample was not documented.
2.3 CE Submittal of Repair Plan and Procedures On July 11, 1980,. CE formally requested from the Supply System X permission to remove four SDHX's from site to Ametek's facility for repair and inspecticn.
On September 3, 1980, the Supply System directed CE to remove all four SDHX's installed at site for the' purpose of inspection and rework as necessary to bring these SDHX's in full compliance with the contract requirements. This direction was contingent upon CE furnishing detailed plans, methods, procedures and schedules for accomplishing the repairs.
In early October, 1980, CE drafted preliminary repair plans and procedures. CE, then submitted the plans and procedures, to the Supply System for its review and insertion of witness and holri points. On October 28, 1980, CE submitted approved Ametek rtpair plans and procedures incorporating the Supply System's comments and witness and hold points.
By mid-October 1980, CE removed all four units from the site.
2.4 Tube Repair A) 45600 and 45601 The lack of fusion (LOF) on I.D. of the longitudinal weld seam discovered during the destructive examination of the tubes pu'iled from 45600 resulted in CE's rejecting the WNP-3 tube bundles (Alleghey-Ludlum tubes) in their entirety.
The tubes to replace the scraped tubes bundles were ordered from Plymouth Tubing, Inc. of West Monroe, Louisiana.
Prior to acceptance of Plymouth Tubes, a review of their manufacturing procedures was made and 100% of the Plymouth tubes were ECT'd utilizing a CE developed procedure.
B) 45602 and 45603 Since the Greenville tubes in these units had exhibited high chloride contaminants in the inside, these tubes were cleaned with a mechanical rotary stainle'ss steel wire brush combined with a continuous flushing with a warm detergent solution followed by a flush with demineralized water. In addition, U-bend specimens cut from a cleaned tube were run for 90 days in an autoclave under operating environmental conditions with no signs of cracking.
After the satisfactory cleaning operation, all the tubes in these units were subsequently ECT'd utilizing a C-E developed
' procedure. A review of the ECT data revealed some signals in the Greenville tubes that could be interpreted as a LOF con-dition. Subsequently three tubes exhibiting these signals were removed from 45603 for destructive examination.
The examination of three tubes, showed only minor scratches.
The rest of the tubes for these-two units were accepted based on this examination.
2.5 Cladding Overlay Repair Upon arrival of four (4) SDHX's to the Ametek facility from the site, each SDHX was inspected for any shipping damage and the channel cover was removed. The front suoport was removed from the tube sheet and the channel was parted from the tube sheet at their circumferential weld. Dye penetrant examination of all weld over-lay cladding was done. Metallurigical boat samples of the clad-ding including some base metal where practical were taken. Boat semples location were selected by CE based on the results of the dye penetrant examinations.
Among the boat samples taken, the samples taken out of the area clad with the submerged arc (SAW) strip cladding process in two layers were deemed acceptable and the samples taken out of the areas clad with the SAW process in one~ layer, which used E-308L electrode with a supplementary metal powder, were deemed unaccep-table by C-E.
Unacceptable areas include the channel cover, the flange face, the flange ID and the tubesheet face on SDHX's 45600 and 45601. These same areas on SDHX's 45602 and 45603 were clad with an acceptable two layer strip clad technique by the'SAW process. However, the cladding on the flange faces of these'latter two heat exchangers were removed because of incorrect weld. wire issuance slips.
The unacceptable cladding noted above was machined off to the car-bon steel base metal. Prior to recladding some surfaces were built up with carbon steel weld metal. The cladding was then re-done using the two layer strip clad technique. Areas that were determined to be under minimum clad thickness by EMT were built up. Clad thicknesses were remeasured.using an UT method on all four SDHX's. All unacceptable dye penetrant (PT) indications were repaired and PT'd again; this process continued until an accep-table PT result was achieved.
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- 4) Metallurgical Investigation by CE CE reviewed.the welding procedures used by Ametek as well as undertook metallurgical investigation of boat samples from selected locations of overlay weld cladding.
Examination of boat samples showed the cladding in two layers using SAW method gave satisfactory results, i.e., austenitic microstructure, low hardness and no cracks. '
However, the cladding ootained using SAW method with one layer of ER-308L filler metal gave martensitic microstruc-ture, high hardness and many cracks.
The average chemical composition of the martensitic SAW clad-ding was 13.2% Cr and 6.4 % Ni representing an average dilu-tion factor of 36.5% which is very high. The hardness of the martensitic SAW cladding was found to vary from 365 to 460 DPH.-
The overall effect of cooling and change of the microstruc-ture of cladding from aust.aite to martensite is found to cause a 2.06% linear contraction of cladding during cooling.
This contraction of the very thin cladding on the thick base metal results in tension stress within the cladding, with peak stresses occuring just above the interface cladding / base metal causing the cracking observed.
In conclusion, CE rejected the cladding carried out using SAW method in one layer with supplementary metal powder on the channel cover, tube sheet and the' flange of WNP-3 SDHX's.
2.0 CORRECTIVE STEPS TAKEN 2.1 Defects in Receiving Inspection and Maintenance Procedures To prevent recurrence of a delay in discovery of nonconforming conditions of Class I equipment, revised source inspection and/or receiving inspection procedures now require internal examination prior to acceptance.
2.2 Rejection of SDHX's Based on the unacceptable condition of the SDHX's as confirmed by NDE performed by the Supply System and evaluation of unsatisfac-tory manufacturing processes and QA program implementation at Ametek's facility, the Supply System formally notified CE in June, 1980 that the current Certificate of Equipment on all of the SDHX's manufactured by the Ametek for WNP-3/5 projects was not acceptable.
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Following the completion of the above, the SDHX's were reassem-bled. The channels were rewelded to the tubesheets; the front supports were welded back on; as noted previously, the clad thick-ness was measured by UT; the channels were cleaned; the covers were put back on. 45600 and 45601 were hydrostatically tested on the tube and shell sides; 45602 and 45603 were hydrostatically tested on the tube side. All four units were re N-stamped and the N-I data forms corrected.
2.6 Vendor Surveillance by the Supply System The Supply System monitored the progress and quality of inspec-tion / repair activities of CE and Ametek to verify that proper corrective steps are taken by CE and Ametek in the repair of SDHX's meeting the requirement of the repair plan.
In addition, the Supply System conducted vendor surveillance to witness inspection and review documentation at Ametek prior to ac-ceptance of repaired units for shipment to site. The surveillance and release of 45602 and 45603 were done during July 2-15, 1981 and of 45600 and 45601 were done during August 17-25, 1981.
During the surveillance, the Supply System reviewed and inspected shop travelers, cladding, accessible welds, cleanliness, coating, radiographs, and QA records to assure the repairs are completed meeting both specifications and QA requirements of the purchase order.
3.0 ANALYSIS OF THE SAFETY IMPLICATION The SOHX'S are used to remove decay heat and pump heat during reactor cool down and cold shutdown. There are two SDHX's in each unit of WNP-3 and WNP-5. Failure of one of the SDHX's during residual heat re-moval will not result in a loss of core cooling capability. The reactor coolant system can be brought to refueling temperature using one of the low pressure safety injection pumps and one SDHX. Simulta-neous failure of both SDHX would be possible but very unlikely since the nature of the defects would not result in an instantaneous failure of the heat exchanger. If a tube to shell leak develops in the SDHX, the water level in the component cooling water surge tank would in-crease resulting in a high level alarm and the leaking SDHX can be isolated. Therefore, there is no safety implication from failure of ,
one of two SDHX's.