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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML20132D8091996-12-18018 December 1996 Part 21 Rept Re Defect of Welds on Weld Nut Holding Filter Assembly Panel.Failure of Weld or Weld Nut Could Allow Filter Assembly Panel to Break Loose Under Seismic Stress & Cause Damage to Other Components in Charger ML20082D9011995-01-27027 January 1995 Final Part 21 Rept Re Valves Installed W/Shim Between Yoke & Adapter Plate Involved in Jan 1994 Incident.Caused by Operational Problems Involving Maint Procedures.Ltr Sent to Affected Utils.Item Not Reportable Under 10CFR21 ML20080D5921994-12-28028 December 1994 Submits Followup to 940418 Part 21 Re Investigation W/ Respect to Jan 1994 Incident at Prairie Island Generating Plant Involving Crane Design Gate Valves ML20072S9581994-08-30030 August 1994 Part 21 Rept Re Crane Design Gate Valves Involved in Jan 1994 Incident at Praire Island Nuclear Generating Plant. Historical Records Do Not Contain Info Addressing Total Number of Configuration Mfg by Crane ML20065G4671994-04-0101 April 1994 Part 21 Rept Re Failure of Support Studs on Discharge Piping Bracket to Turbocharger That Provide Support for Air Inlet Housing ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20028H3531990-12-13013 December 1990 Part 21 Rept Re Cable Assemblies Failing to Meet IEEE-383 Section 3 Flammability Tests.Results of Tests Conducted on 901206 Encl.Corrective Actions Include Applying Flame Retardant Covering to Cable or Cable Replacement NRC-90-3528, Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 9007231990-07-16016 July 1990 Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 900723 ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20132F3521985-09-26026 September 1985 Preliminary Part 21 Rept Re 3.5-inch Crack on Snubber Ball Bearing.Vendor Attempting to Have Bearing Returned for Exam & Evaluation by Skf Industries.Next Rept Will Be Submitted When Significant Info Available ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML20135D4481985-08-15015 August 1985 Part 21 Rept Re Raychem auto-trace 20PTV1 self-regulating Electric Heat Tracers & Associated Derivatives.Licensees Advised of Problem & Procedures to Determine Any Effect on Operation ML20129J7381985-06-24024 June 1985 Part 21 Rept Re Auto-Trace 20PTV1,self-regulating Electric Heat Trace,W/Lower than Specified Power Output.Deficiency Could Result in Lower Maint Temp in Electric Pipe Heating Sys.Affected Licensees Identified ML20094S4971984-08-16016 August 1984 Part 21 Rept Re Separation of Rod Eye Connected to Piston Rod from Threaded Portion of Piston Rod at Approx 750,000 Lb Stress Load.Caused by Insufficient Matl Thickness to Withstand Faulted Load.Matl Certification Encl ML20092L1421984-06-21021 June 1984 Part 21 Rept Re Static Load Rating on Anker-Holth,Baxter Hydraulic Suppressor.Caused by Failure of Torrington self-aligning Ball Bushing.Recommends Replacement W/ Paul-Monroe Hydraulics Part PA-89492 & PA-89493 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30
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- 1 Phone: 312 -- 830-7400 ER OCORPORATION 411 North Avenue . Streamwood, lllinois 60103 August 16, 1984
$(p - 2 b'd 3 h b Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Notification of Test Failure Gen tlemen :
Tb the extent that a component was manufactured to a purchase order stipulating part 10CFR21, we as seller and manufacturer of the component are not clear if it is our responsibility in reporting such failure, but feel obligated, due to the stipulation of part 10 CFR21 to do so, that we may be advised if it was necessary at this stage to have reported such failure.
Purchaser: ITT Grinnell of Providence R. I. , P.O. P-12211 Seller & Manufacturer of component: Chicago Fluid Power Corporation Streamwood, Illinois Component : Snubber cylinders believed to be used for pipe support.
(4 units)
Nuclear Station to be delivered to: Northern State-s Power, Prairie Island 1 or 2 Nature of Defect: Rod eye connected to piston rod separated from threaded portion of piston rod at approximately 750,000 lbs stress load. Load requirement is 1,000,000 lbs.
Reason for Failure: Material and material thickness not sufficient to withstand faulted load.
Background:
Purchaser hired seller to design and manufacture cylinder snubber to replace existing snubbers in current service. The cylir, der snubbers were to withstand 10,000 PSI hydraulic pressure representing 1,000,000 lbs loading. c/linder snubbers were designed with 5-1/2" thick rod eye and eye me.ating. Purchaser then informs seller that the ma~.imum thickness of eye mount and rod eye can .only be 2-7/8" thick to match existing mounting space with maximum center to center dimensions established. There were no dimension restrictions on the cylinder itself, but rather only on the eye mount and rod eye. The purchaser was to specify the rod bearing and seal materials and configuration, all other design was to be done by seller. After noti.
fication of the requirement of 2-7/8" maximum thickness of the rod h
I
i OCORPORATION ER USNRC August 16, 1984 eye and eye mounting, there was considerable verbal communication between purchaser and sellers engineering departments as to whether the eyes would handle the load, it was determined that if appropriate material and testing of the material were supplied that the faulted load could be obtained mathematically, however, the final determin-ation would be made during testing.
The cylinder snubbers were hydrotested to 10,000 PSI, witnessed, certified, and shipped to purchaser. In order to meet their speci-fications the purchaser was to sandblast and paint the cylinder snubbers. In doing so, sand particles lodged in some of the fastener holes also did some damage to the rod bearings. Purchaser then sent back the snubbers to have the sand flushed out and sent new rod bearings to replace the possibly damaged ones. This was accomplished and the snubber cylinders were re-assembled, hydro tested again and returned to purchaser to complete actual load testing.
Notification: On 8-14-84, purchaser notifies seller by phone that during load testing a rod eye had separated and could a representative from seller be in purchasers Warren Ohio plant the following morning for eve.luation. On 8-15-84, the writer of this report arrived at purchasers facilities to evaluate failure. An additional load test was performed on a third unit after two previous units had separated during this test the third unit separated. It was concluded that seller would return separated pieces to home facilities for further evaluation and that both purchaser and seller would calculate a stress analysis to see if any material with the limited dimensions could withstand the 1,000,000 faulted load, or if by re-designing the rod eye engagement to the threaded portion and adding additional metal would afford the additional strength required. This is the current status ot the project.
Conclusion:
There are no cylinder snubbers of this manufacturer in service at any nuclear facility. Further, we would like to obtain an invitation to the Northern States Power Prairie Island f acility to examine the material specifications and design of the existing cylir. der snubters to see if they could experierce this possible failure, considering the high grade materials and testing done on the materials by Chicago Fluid Power Corporation (copies enclosed ), or if the existing units have been exposed to actual fault load testing on equipment similar to that owned by ITT Grinnell. As it has become apparent that mathematical calculations do not always agree with actual testing. It is not clear at this time how long the redesign and evalu-ation and manufacturing will take, an estimate would be 8 to 10 weeks.
Respectf FM[ ______
C. . Mills, President CRM/eb Enclosures cc: Q/A Dept
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CsCETO. IL.
CLINTON WI.
SPRI G GROVE, IL 60081 9
CHICAGO FLUID POWER CORP MATERIAL CERTIFICATION 411 NORTH AVE STREAMWOOD, IL 60103 DATE$ HIPPED ITEM OF CUSTOMER JOB NUMBER CUSTOMER ORDER NUMBER 1 1 SERIAL #204-1,204-2,204-3,204-4 10/14/83 C-3814-N WA DATE PREP ARED E'P NUMSER PART NUMBER D-1 TURK'S 10/17/03 DESCRIPTION OF MATERIAL AND SPECIFICATIONS ._ - - - - - - - - - - - - _ _ _ -----------
88 FORGINGS PERTB/P D-1 STEEL TO MEET ASTMjA-668 CLASS L (AISI,.414.0.)A.G.)
, ' i .lMM '
NORMALIZE.
GUENCH 8, TEM.'ER TO 125,000LTENSILE 105,000 YIEtD 16% ELOG 7.50%7 RED #
9IN AREA (255/321 BHN)
- HEAT TREATMENT TOjBESDONEfBY CUSTOMER /S SOURCE -
LINDBERGH HEATpTREATING CD., MELROSE PARK
- PHYSICAU4 TEST / REQUIRED-
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CHARPY V-NOTCH TEST REGUIREDit<38, DEGREES F..(+-2 DEGREES) TO MEET 15 FT/LBS AVERAGE WITH NOT,0NE4 SPECIMEN LESS THAN 12 FT/LBS
- DESTRUCTIVE TESTINO TO.BE'DONE?BY CUSTOMER'S SOURCE -
CHICAGO SPECTRO SERVICE LABS,. CHICAGO
- ROUGH MACHINE WITH~ ALLOWANCE TO FINISH TO SIZES SHOWNj0N(B/P - 250.RMS
' ' " ' ULTRASONIC TEST:REGUIRED~PER'.SS-N-437 PARAGRAPHSmi, 2, 3, &.19 ..r ,m. ,
HAGWETIC PARTICLE' TEST REQUIRED /PER3SS-M-437. PARAGRAPHS-1,2,3r-& ^
LIC.VID PENETRANT INSPECTION t REQUIRED' PER SS-N-437. PARAGRAPHS .1,2,3, &7
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MAONAFLUX GUALITY SERVICES, ELK GROVE VILLAGE *
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NO. OF PIECES .
SU SI NI CR MO CU AL OTHER GRAIN CARBON MN PHOS 7
.430 .830 .015 .021 .290 .150 .960 . 180 110
- 7 9 10 11 12 13 14 15 16 18 20 24 28 32 1 2 3 4 5 6 8 39 56 55 54 54 53 52 52 51 49 48 45 42 41 40 59 58 58 57 57
==-
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SCOT FOR THISIS TO CERTIFY THAT THE REPORTED LADLE AN ALYSIS(AND/OR TESTS) SHOWN ON THIS REPORT ARE CORRECT AS CONTAINED IN THE RECORDS OF THE COMPANY.
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cuMTON.wt BOX 8 SPRING GROVE,IL 60081 CHICAGO FLUID POWER CORP MATERIAL CERTIFICATION 411 NORTH AVE STREAMWOOD, IL 60103 OF CUSTOMER JOS NUM8ER DATE SHIPPED CUSTOMER ORDER NUMBER ITE M C-3814-N 1 1 SERIAL #204-1,204-2,204-3,204-4 10/14/03 B/P NUM8ER VIA DATE PREPARED P ART NUMBER D-1 TURK'S 10/17/83 PHYSICAL PROPERTIES
TENSILE YIELD PSI ELONGATION REDUCTION PCS PSI (.2% OFFSET) 4 % '
OF AREA % COMMENTS 1 144,600 115,900 -
j 76.7 tL MPACT2RE LTS TEMP 1st .
3rd A ' COMMENTS (CHARPY) 38 20. FT/LBS ((19
.LBS
- 18.S OAFT/LBS HARDNESS'RESULTS //
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/W' BRINELL PCS s;. I u ,.'e, 'l30'00 KG LOAD 1 />M g IJ ':
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MAGNETIC PAR TICLE,.'4 TESTED bdACCEP. TABLE =,;PER SS-N-437-PARAGRAPHS 1?' 2,3,$ & 4111,, ' .
LIQUID PENETRANT ' INSPECTED. &kACCEPTABLEiPER SS-N-437 PARAGRAP_NS ifk/3,'..di7GG & -
@jy'Ql ,'y.., c, - y ; n
, FREQUENCY (=f.100 L SEVERIT,Y/= .'00 -
MACROETCH INSPECTEDs RESULTS1* ACCEPTABLE a
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- fE l THIS IS TO CERTIFY TH AT THE REPORTED LADLE AN ALYSIS(AND/OR TESTS) SHOWN ON THIS REPORT ARE CORRECT AS CONTAINED IN BY: , o THE AECORDS OF THE COMPANY.
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