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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation ML20203B9591997-09-18018 September 1997 Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn ML20210J1761997-07-31031 July 1997 Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept ML20138D1991997-04-0404 April 1997 Special Project97-928S, Sequoyah Nuclear Plant Assessments ML20138C5371997-03-24024 March 1997 Rev 0 to Pressurizer Level Event ML20217G2401997-03-0303 March 1997 Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow ML20117J3611996-08-0101 August 1996 SE of Safety Valve Setpoint Tolerance Relaxation ML20117K9461996-03-0505 March 1996 Reliability Study ML20117K9511996-02-29029 February 1996 Reliability Common Cause Assessment, for Feb 1996 ML20095J1891995-10-0505 October 1995 Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds ML20081D3831995-03-12012 March 1995 Simulator Four Yr Test Rept for 950312 ML20083N9521994-11-16016 November 1994 10CFR50.59 Rept to Nrc ML20024H8491993-07-19019 July 1993 Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles. ML20118D1941992-09-21021 September 1992 Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment ML20114A6641992-08-15015 August 1992 920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period ML20141M1341992-03-27027 March 1992 Spent Fuel Pool Mod for Increased Storage Capacity ML20029C2011991-03-12012 March 1991 Initial Simulator Certification. ML20028H8591990-09-0707 September 1990 Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues. ML20136J0431990-06-30030 June 1990 Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks ML20043B6061990-05-11011 May 1990 Diesel Generator Voltage Response Improvement Rept. ML20006E5771990-02-0505 February 1990 Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis. ML20246D5351989-02-28028 February 1989 Steam Generator Tubing Insp Results ML20247H1301988-11-30030 November 1988 Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns ML20236D1951988-11-18018 November 1988 HVAC Damping Values ML20134H6801988-09-0202 September 1988 Technical Evaluation of Procurement of Matls & Svcs ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151Q2691988-08-0101 August 1988 Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping ML20155J5721988-07-31031 July 1988 Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway ML20207F6231988-07-0505 July 1988 Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2 ML20207B6301988-06-27027 June 1988 Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program ML20147G9961988-03-31031 March 1988 Review of Operational Readiness Corrective Actions. Related Documentation Encl ML20147H6331988-02-29029 February 1988 Plant,Diesel Generator Evaluation Rept ML20147G7861988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input ML20147G8041988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs ML20234F2111988-01-0505 January 1988 Rept of Sequoyah Readiness Review ML20147F0581987-12-0202 December 1987 Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept ML20236B3481987-10-15015 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation ML20236B3511987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness ML20236B3541987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top ML20236B3441987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints ML20236B3581987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector ML20236Q2011987-10-0101 October 1987 Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses 1999-08-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
Text
C Attachment 3
~' Temperature Measurement Report for the Long Term Current Test on Littlefuse, FLAS-5, 5 Amp Fuses" l
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- L'NITED STATES GOVERNMS.YT
. Mc7nord7t d um TENNESSEE VALLEY AUTHORITY TO : 'i W.W8 S.C126 Raughley, C-K' Branch Chief; Electrical En61neering Branch, DNE,- 'j '
FROM :
Richard L.,,Morley, Chief Central Laboratories Services Branch, LA PSC 1-C l
DATE : October 1, 1987
SUBJECT:
SPECIAL TESTS ON LITTELFUSE FLAS-5 FUSES N hallab}e Co&
l Pursuant to your request, i.ttached 15 the final report containing the results of the special' tests that Central Laboratories Services Branch '!
(CLSB) performed on Littelfuse type FLAS-5 fuses for Sequoyah Nuclear Plant. This report replaces the. copy that was telecopied.'
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We hope that the report will assist you and.look forward to. continuing to support your future needs. 'Should you have any questions or additional needs, please feel' free to. contact CLSB.
1 RLM:EC l Attachment '
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RIMS, MR AN 72A-C Ken Greene, W8 C144 C-K ,
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1 TEMPERATURE MEASUREMENT REPORT FOR THE LONG TERE CURRENT TEST ON LITTELFUSE, FLAS 5, 5 AMP PUSES Best Available Copy i
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o INTRODUCTION b# ^
During Long Term Current Tests on fuses for Sequoyah Nuclear Plant at the CLSB, some temperature measurements were made and reported to the plant and to the Division of Nuclear Engineering (DNE). Ken Greene of DNE verbally requested that more data be obtained. A formal report was requested on September 18, 1987 and this document summarizes the data collected, in Table I.
TEST REQUIREMEN]S The test requirements were to select various fuses, already under test in the Long Term Current Test at the Central Laboratories Services Branch (CLSB), and make temperature measurements at four different locations on each selected fuse. Figure I identifies these locations.. The fuses that were examined are l Littelfuse, 010, and 011. indicating type PLAS 5, 5 amp fuses from lot numbers 004, 006, The temperature measurements were recorded after the fuses were placed in the circuit and had reached thermal equilibrium.
At least 10 fuses from each lot were sampled. A breakdown of the sampling is !
detailed in the test setup section of this report.
TEST EQUIPMENT t
Digital Thermometer Fluks Model 2165A US TVA No. 462383, with type K thermocouple, US TVA No. 903320.
Digital Volt Meter, Fluke Model 8400A US TVA No. 305628. -
Precision Resistors, US TVA No. 903309, US TVA No. 903310, US TVA No. 903311 US TVA 903312, US T7A 903319.
4 TEST SETUP The ongoing Long Term Current Test was used as the test setup. Figure II provides a simplified wiring diagram for each fuse lot tested. Figure III provides a physical layout of the test setup for each lot of fuses. This consisted of at least 5 high current and 5 low current samples, 4 amps and 2 amps respectively. Each fuse bears the vendor's label which has the lot number visible.
Additionally, fuses were individually labeled for easy identification by labeling them with either an H or an L, high current or low current and sequentially numbering them within each test loop. A test loop tested at. of a particular lot number of fuses and the current #level they were consisted 3 L V There DNE. were two special test loops of 1 amp and .25 amp that were requested by One fuse each from lot 010 and 011 were installed in the 1 amp loop.
Temperature readings were not made until sufficient time had passed for the fuse temperature to stabilize. After the temperature measurements at this current level were recorded, the current was adjusted to .25 amp and the process repeated.
The test setup and measurements taken on the special test loops were the same as the other test loops.
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- In Figure II th:ro is notatica of a precision resistor that is used to measure the current flow in each test loop. Table II provides a breakdown of each !
test loop and the precision resistor number installed in it. i MEASUREMENT PROCESS '
Best Available Copy All of the fuses. tested had been installed, and carried their specified current longmeasurements temperature enough for temperature being made. stabilization to take place prior to any conducted was approximately 760F and stable.The room temperature where this was 1 A Fluke 2165A digital thermometer with a type K thermocouple (TC) was used to make all of the temperature measurements.
Measurements made at locations 1 2, and 3 were made by placing the TC against the fuse surface at each location l until the reading stabilized, then the measurement was recorded. To make the measurement solder junction. at location a, a small hole was drilled in the fuse case at the The TC was then inserted into the hole and held against the 1 solder joint until the reading stabilized, then the measurement was recorded.
A Flute Model 8400A DVM and precision resistors, as shown in Table II, were used to monitor the current in each test loop during temperature measurements.
CONCLUSION Table I contains all of the data recorded during this test. It is grouped by fuse lot number and by test loop current level.
It should be noted that the i measurements =ade at location 4 were the most difficult measurements to m{
The reason for this was in making sure the solder joint was not damaged when drilling the access hole and in making good physical contact between the IC '
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and the joint on each fuse examined for, consistency from fuse to fuse. (
4 Since the fuses are a part of the Long Term Current Test, we will leave them in that test for future reference. Notations regarding the drilling of holes j were made in the daily test log.
1 W. G. Jones at extension 4219-C.If you have any questions regarding this rep that we can. We will be glad to assist you in any way l
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Let No. 004 Fuse # 1
~MEASUR8 MENT LOCATION' 2
JUNCTION / AMBIENT-3_ 4 aT H2 1218F 1080F -1040F' H3 129D7 $307 1170F 104aF 1000F 123*F H5 470F -
1240F 1010F 1040F 1360F
.H 7 1210F 40 P' 1050F- 1020F 132*F 560F' H10 1190F 1040F 1050F 1360F 60 F
-H14 121oF 1030F 1040F 1350F. 590Fc HIS 1190F 1000F. 101*F 1270F 510F H18 1170F 1010F 1010F 1260F 500F H19 HI *F, 93*F 970F 1200F 440F Average Temp. lisoF 1020F 102of 129aF 530F '
L5 870F 82 P 820F 880F-L7 66'F 820F 120F-820F 900F 140F L10 860F 820F 82*F L14 890F -130F 880F 830F 830F 890F L15 87aF 130F l 830F 83*F 890F L18 880F 130F-860F 870F 880F Avera6e Temp. 120F-l 87'F 83ar- 830F 890F -130F Lot No. 006 'N 5 1250F 1050F 111 F 1330F 570F E10 1250F '1070F 105DF 1300F 540F H15 1230F 1060F 1090F 1310F 550F H2O 1250F 1070F 1020F 1420F- 660F H25 H9'F 10&oF Average Temp. 1190F 1470F- 71oF 1230F 106of 1090F 1360F 61*F- .
L5 88'F 850F 860F L10 900F 14*F 88cF $40F 860F 890F L15 900F 130F-850F 860F 90oF L20 890F 140F 850F -87*F 910F L25 ,,8,7 'F 150F Average Temp. 880F 850F_
.8SoF 850F 860F E 140F 900F 140F Lot No. 010 H5 1090F 950F 960F 1160F H7 114cF 1030F 400F -l l -940F 111 F 350F H10 1120F 950F
( HIS 940F 1190F 430F 1120F 970F 940F E18 1220F 460F 1100F 960F_ 960F Average Temp. lilof M00F_ 440F_
970F 950F 118SF 420F L5 .
86*F 830F 830F- 86*F L7 '860F 830F 100F 1 L105 .820F 870F lioF 860F' 820F 410F .
L15 880F 120F 860F 82*F 820F L18 860F 100F 878F 82cP 820F Average Temp. _860F 100F 860F 82*F 82 F. 870F 'llof SPECIAL CURRENT TESI 1A 76*F 770F 770F 78*F
.25A 750F 750F 758F 750F
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TABLE I (cont.)
MEASUREMENT LOCATION Lot No. 011 Fuse /t JUNCTION / AMBIENT-
__1__ __[__ 3 4 aT H7 1130F 990F 97 F 1180F-H14 1120F 42of 970F- 96*F 1230F 470F-H21 1100F 96eF 950F 1150F 3?oF
.H28 1100F 980F 950F H35
- 119 0F. 430F-J120P- _91og 940F 1190F 430F Average Temp. 1110F 970F 950F 1190F 430F L7 850F- 820F 820F 870F L14 11oF.
860F B20F 820F 87"F L21 11oF '
870F 830F . 820F 890F-
- L28 130F 86*F 820F 830F 880F L35 _860F 12 F
_820[ 810F- _860F- '100F 2v'erage Temp. 860F 82 F .620F 87 F 11oF SPECIAL CURRENT TEST 11 780F 770F 770F 790F
.25A 75*r 750F 750F 760F' Note:
The temperature data for fuses in Lot 004, No. H2, HS, H10, HIS, and H19 was collected on September.3, 1987.
September 11, 1987. The remainder was collected on 9
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[> cst Available Copy 1 TABLE II l
Fuse Lot __ Resistor I.D. In Test Loop Number 2_ amp loop A_ amp loop s 004 US TVA No. 903312 US TVA No.- 903312 .;
l 006 US TVA No. 903309 US ITA No.- 903309 010 US TVA No. 903311 i
US TVA No. 903311 I 011 US TVA No. 903310 US TVA No. .903310 Special 1 amp and .25 amp test loop used US ITA No. 903319. R2.
I Precision Resister Installation Guide '
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1 indicates the exposed end of <he indica:ing pin.
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4 indicates :he solda: junc:Lon inside che fuse.
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