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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20249C0011997-11-30030 November 1997 Reactor Vessel Fluence Analysis Methodology ML20148E7091997-05-31031 May 1997 Vols 1 & 2 to Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Ors,Usi A-46, Per GL 87-02 ML18151A7101996-09-30030 September 1996 Supplemental Info for VA Power Nomad Code & Model. ML20249C4051996-05-16016 May 1996 Rev 0 to CE-0082, Review of Augmented ISI Frequency for Pressurizer Spray Lines ML20249C4031996-04-23023 April 1996 Rev 0 to CE-0081, Review of Augmented ISI Frequency for Reactor Coolant Bypass Lines ML20092A2611995-08-31031 August 1995 EDG Preventive Maint Insp Outage Probabilistic Safety Assessment for August 1995 ML20078P9261994-09-26026 September 1994 Service Water System Operational Performance Assessment 940711-29 ML18153B4221993-07-31031 July 1993 Rev 11 to Engineering Evaluation 25, Evaluation of Existing Fire Enclosure Around Ventilation Duct,North Anna Power Station. ML18153B4211993-07-31031 July 1993 Rev 11 to Engineering Evaluation 24, Evaluation of Radiant Energy Shields,North Anna Power Station. ML20046D1581993-02-28028 February 1993 Virginia Power Sys Transient Analysis Using Version 1 of North Anna Retran Model. ML18152A0711993-02-0101 February 1993 NFPA Heat & Flame Evaluation of MSA Custom 4500 SCBA Using Enriched O2 Breathing Air for VA Power,Final Rept. ML20116A2901992-09-23023 September 1992 Conceptual Engineering Final Rept NP-2653, RG 1.97 Isolation Devices Type 2,North Anna Power Station. W/One Oversize Encl ML20101B0331992-04-30030 April 1992 Suppl to Update of Settlement Monitoring Points & Graphs NAPS - Supplement to Technical Rept CE-0019,North Anna Settlement Data Oct 1989 - Apr 1992 ML20077A6601991-05-0707 May 1991 Summary Rept on Exam of Steam Generator Tube R11-C14,North Anna Power Station,Unit 1 ML18153C3111990-07-26026 July 1990 Decommisioning Financial Assurance Certification Rept for Surry Power Station & North Anna Power Station. ML20011F6221990-02-26026 February 1990 Analysis of Small Steamline Break Performance W/O Low Pressurizer Pressure Safety Injection North Anna Units 1 & 2. ML20248E8641989-09-19019 September 1989 Rev 0 to Evaluation of Settlement Monitoring Program for Main Plant Structures in Support of Proposed Changes to Tech Spec 3/4.7.12. W/One Oversize Figure ML20246J1391989-08-17017 August 1989 Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding EP-2 ML20246J1581989-08-0909 August 1989 Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding MC-1 ML20246J1261989-07-20020 July 1989 Rev 0 to Coordination of Load Ctr Circuit Breakers,EP-1 ML20246J1191989-07-20020 July 1989 Rev 0 to Response to SSOMI Item IC-8 of NRC ML20246J0991989-07-18018 July 1989 Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-2 ML20246J1071989-07-18018 July 1989 Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-7 ML20246J1481989-06-30030 June 1989 RCS Leakage Detection Sys ML20246K3461989-05-0505 May 1989 Technical Evaluation & Safety Analysis:Solid State Protection Sys Slave Relay Testing REA-88-51 ML20245K7311989-04-26026 April 1989 Rev 0 to 890225 Steam Generator Leak Event Rept ML20056A0341989-04-18018 April 1989 Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement ML18151A9661989-04-18018 April 1989 Nuclear Decommissioning Trust Agreement. ML20245A5311988-09-13013 September 1988 Simulator Certification Submittal ML20148J6311988-03-16016 March 1988 Generator Tube Fatigue Evaluation & Remedial Actions Rept ML20147F5621988-03-0202 March 1988 Safety Evaluation in Support of Containment Temp Increase for North Anna Power Station ML20196J2901988-02-24024 February 1988 Rev 1 to Civil Engineering Technical Rept 0005, Differential Settlement Between Svc Bldg & Unit 2 Main Steam Valve House ML20148J6401988-02-12012 February 1988 Rev 2 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept ML20091L7041987-10-19019 October 1987 Generator Row 9 Column 51 Tube Failure Analysis ML20235G2441987-09-25025 September 1987 Steam Generator Downcomer Mods Safety Evaluation for North Anna Units 1 & 2 ML20238F6161987-09-15015 September 1987 Rev 1 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML20235U6701987-08-0707 August 1987 Loss of Inventory Event 870617-21 ML20235Q0661987-08-0505 August 1987 Metallurgical Svcs Rept FAL-00050 ML20237G9791987-07-29029 July 1987 Rev 0 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept. W/Pages from Facility Updated FSAR ML20235U3431987-07-20020 July 1987 Rev 0 to Chronology Steam Generator Tube Rupture Event North Anna Power Station Unit 1 870715. Related Info Encl ML20238E1611987-07-15015 July 1987 Rept of Emergency Preparedness Events Re Unit 1 Steam Generator Tube Rupture ML20215G5471987-06-17017 June 1987 Safety Evaluation for Change in Methodology & Supporting Analyses ML20235Q0551987-05-21021 May 1987 Investigation Rept FAL-00024, Emergency Diesel Generator Floating Busing Failure ML20206D6721987-03-31031 March 1987 Engineering Analysis Svc & Maint North Anna Power Station Fairbanks-Morse 38 TD8-1/8 Diesel Engines Phase II ML20207B5231986-11-30030 November 1986 Reactor Vessel Fluence & Rt/Pts Evaluations Suppl to WCAP 11016 ML20213D7771986-10-31031 October 1986 RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices ML20213D7601986-10-31031 October 1986 RCS Loads & Component Support Margins Evaluation for Elimination of Rcs,Main Loop Pipe Break Protective Devices ML20210F6821986-10-17017 October 1986 Reactor Protection Sys Trip Setpoint Drift Characterization 1999-10-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
[Table view] |
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ATTACIMENT 1 POW 18 PERFORMANCE SERVICES FAILURE ANALYSIS LABORATORY
- 1. REPORT TITLE: Emergency Diesel Generator Floating Bushing Failure
- 2. REPORT NUMBER: FAL-00024
- 3. DATE: May 21, 1987 ,
- 4. WORK AREA / STATION AND UNIT: North Anna Unit 1
- 5. WORK REQUESTED BY: M. R. Kansler, 5. M.-Kotowski
- 6. WORK PERFORMED BY: M. B. Shelton, E. M. Focht
- 7. COMPONENT /OR SYSTEM AND LOCATION: Number 12 Floating Bushing from the lH Emergency Diesel Generator. The Number 9 Floating Bushing (undamaged) was supplied for comparison.
- 8. STATEMENT OF PROBLEM: The Number 12 floating bushing showed two distinct but related damage mechanisms: wear of the bushing interior and exterior surfaces and plastic extrusion of the worn regions.
- 9. CONCLUSIONS REACHED BY FAILURE ANALYSIS LABORATORY:
The results of this investigation indicate that the bushing wear damage is due to insufficient lubrication, which in turn can occur from use of an inadequate lubricat-ing oil, excessive engine loads, or a combination of both.
The plastic extrusion is likely the result of increased stresses imparted on the bushing rather than a degradation in mechanical flow strength of the bushing material. A determination of the source of these stresses, whether from increased contact stresses from insufficient lubrication or 8710070477 870930 PDR ADOCK 05000338 G PDR
,y,
POW 18 from excessive engine loading, was beyond the scope of this 4
investigation.
- 10. . ANALYSIS'RESULTS:
Macroscopy
. Figure 1 is an exterior surface view of bushing #12 as received.. The lead flashing was wiped from the exterior and interior surfaces of the bushing over a.circumferential arc of slightly less than 180*, however, lead was still visible within the oil grooves. In areas where the lead flashing was removed, the surface had a burnished appearance with discoloration due to a heat tint film. Some visible removal of the lead flashing and a similar heat tint were present over portions of the remaining interior and exterior sur-faces of the bushing, however, the damage was not as severe.
In addition to the removal of the lead' flashing and the heat tint film, some base metal had been smeared into. the oil grooves as shown in Figure 2. Figure 3 is a macrophoto-graph of the less severely damaged interior surface of the bushing with the lead flashing still intact and only limited wear evident.
Dimensional Measurements:
Dimensional measurements were performed by station NDE services, and so were not repeated in detail in this analy-sis. Random measurements were made, however, to verify that plastic deformation had occurred on the damaged portion of the bushing. The bushing had been extruded, effectively reducing the bushing thickness and increasing the axial
POW 18 length in the damaged region by roughly 0.015" and 0.07",
respectively.
Electron Microscopy The damaged surfaces of the bushing were examined by scanning electron microscopy in order to determine the !
damage mechanism. Figure 4 is an electron micrograph of the interior surface of a damaged area of the bushing which shows a large amount of adhesive wear (galling) with some evidence of abrasive wear (score marks).
Chemical Analysis Chemical analyses were performed on samples from undamaged and damaged regions of the Number 12 bushing and on a sample from the Number 9 bushing. Results are shown in Table 1.
The chemical analysis results indicate that the materi-al of both bushings meets the specified composition require-ments of SAE64 cast bronze.
Microscopy Several metallographic specimens were prepared of damaged and undamaged cross sections of the Number 12 bushing and of undamaged bushing Number 9. Variances in grain size were observed in bushing Number 12, apparently a result of the casting process (Figures 5 and 6). The variation did not ' appear to be a contributing factor to, or a result of, bushing damage.
Figure 7 is a photomicrograph of the Number 12 bushing j cross section at the damaged interior surface. The 1
L_____---------
if ,' :t POW 18 y microstructure is indicative of centrifugally
/, [4x cast high jf '
o lead-tin-bronze. The ' lead flashing is completely removed ;
, from the bushing surface. No significant grain deformation was observed in the damaged region. A cross section of the undamaged portion 1'of bushing Number the 12 shows lead flashing still intact and a similar microstructure to that of the damaged area. The lead flashing is still visible on the bushing surface (Figure 8). Bushing Number 9 revealed a microstructure similar to bushing Number 12 (Figure 9).
Hardness Testing -
Macrohardness measurements were made of damaged and undamaged regions of the bushing. The results of these i
measurements show an increase in hardness in the damaged "
area. of the bushing versus the undamaged area. Hardness averages ranged from 50.1 Rb -(~89 Brinell) in the undamaged area to 64.7 Rb (~ 109 Brinell) in the damaged area. No significant variations in hardness were observed from the exterior to interior surface of the bushing. '
- 11. DISCUSSION:
Bushing damage appears to be the result of lubrication i film failure which results in adhesive and abrasive wear of the bushing and subsequent plastic extrusion. The visual appearance of the damage is similar to that which has been observed in some Navy diesel engine bushing i
failures. )
.l Research performed on the Navy bushing failures attributed '
the damage to the use of zine bearing lubricating oils l
1
__ ___ - _ . _ _ .]
?
POW 18 i
similar to types used nthe past in the North Anna diesel engines.
Smearing of the bushing metal into the axial oil grooves will result in further degradation of lubrication
, effectiveness. Inadequate lubrication will result in increased bushing metal temperatures due to friction heat.
-The increase in bushing hardness is indicative of strain hardening due to cold working. The presence of a temper film and apparent strain ha'rdening suggest that the bushing metal temperature was in the 400*F - 700'F tempera-ture range during operation with inadequate lubrication.
Only limited reduction in flow strength will occur in this temperature range versus normal lubricated temperatures of approximately 350*F (Figure 10). This indicates that the plastic extrusion of the bushing is likely the result of j increased stress rather than decreased flow strength.
{
Increased contact stresses will occur with insufficient lubrication. Insufficient lubrication may result from either an inadequate lubricating oil or excessive engine j loading, or a combination of both.
l f
//'/ , , LJ !
M. B. Shelton investigating Engineer MBS/035: cit
3, POW 18 TABE 1 OEMICAL ANALYSIS OF FURTING BUSHING #9 and #12 Cu,% Sn,I Pb,% Ni,! Zn,I Number 12 Bushing 78.67 9.73 8.77 0.44 0.75
-(undamaged)-
Nubmer 12 Bushing 78.70 9.02 8.66 0.43 0.76 (damaged)
Nteber 9 Bushing 78.66 9.12 8.95 0.43 0.72
POW 18 r -- -
m -
e um . 4 FIGURE 1 EXTERIOR SURFAG VIEW OF BUSHING #12 AS-REGIVED, A TEMPER OXIDE FIIM IS VISIBLE ON THE BUSHIIC SURFAG.
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FIGURE 2 INTERIOR SURFAG VIEW OF BUSHING #12 SHORING BASE METAL SMEARED INIO OIL GROOVES, J
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FIGURE 3 L \ 2B .
INIERIOR SURFACE OF RELATIVELY UNDAMAGED SECTION OF BUSHING #12. THE LEAD FLASHING IS STIII INIACI.
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FIGURE 4 SCANNING ELECTRON MICR0 GRAPH SH0 JING ADHESIVE AND I ABRASIVE WEAR ON INITRIOR SURFACE OF BUSHING #12.
MAGNIFICATION - 68.8X.
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FIGURE 5 PHOIW ICROGRAPH OF BUSHING #12 CROSS SECTION SHOW-ING 1ARGE GRAIN SIRUCIURE. MAGNIFICATION - 12X.
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FIGURE 6 PHOIW ICROGRAPH OF BUSHING #12 CROSS SECTION SHORING FINE GRAIN STRUCIURE. MAGNIFICATION - 12X.
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FIGURE 7 PHOITMICROGRAPH OF BUSHING #12 CROSS SECTION AT MRGED WIERIOR SURFACE. MAGNIFICATION - 400X.
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Lead Flashing FIGURE 8 PHDIIMICROGRAPH OF B'JstING #12 CROSS SECTION AT UNDAMAGED INTERIOR SURTACE. MAGNIFICATION - 400X.
EIGANT - FeCl3 '
POW 18
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ead Flashing l
FIGURE 9: PHOIN ICROGRAPH OF BUSHING #9 CROSS SECTION AT INIERIOR SURFACE. MAGNIFICATION - 400X. EIGANT
- FeCl3*
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Yield strength A . i 1 20 N O 5'4 e:t under load 15
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Q 'w + =
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-00 O +100 200 300 400 500 600 700 800 Testmg temperature, F
{ Data extrapolated above 450 F based on discussions with Mr. Carl Caffoglio of the Copper Development Association )
{
k FIGURE 10- YIELD STRENGTH VS. TEMPERATURE FOR SAE 64 i
_ _ - - - - - - - - - - - - - - - - - )