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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] Category:TEST REPORT
MONTHYEARML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20064M0881994-03-0707 March 1994 Reactor Containment Bldg Integrated Leak Rate Test Sequoyah Nuclear Plant Unit 1 Conducted 931217-20 ML20099B8841992-07-0909 July 1992 Reactor Containment Bldg Intergrated Leak Rate Test Sequoyah Nuclear Plant Unit 2, Conducted on 920427-29 ML20029A3091991-01-31031 January 1991 Nonproprietary Sequoyah Nuclear Plant Unit 2 Cycle 5 Restart Physics Test Summary. ML20059H1881990-08-31031 August 1990 Nonproprietary Sequoyah Nuclear Plant Unit 1,Cycle 5 Restart Physics Test Summary ML20056A5321990-08-0606 August 1990 Reactor Bldg Containment Integrated Leak Rate Test, Sequoyah Nuclear Plant Unit 1 Conducted on 900504-06 ML20044B2191990-07-13013 July 1990 Eagle 21 Start-Up Rept for 900522- 0616. W/900713 Ltr ML20245B3631989-03-18018 March 1989 Reactor Bldg Containment Integrated Leak Rate Test ML20195J8251987-11-23023 November 1987 Insulation Wall Thickness Measurement of Silicone-Rubber Cables at Identified Failure Points ML20236V5171987-11-19019 November 1987 Qualification Test Program for Silicone Rubber Cables W/ Reduced Insulation Thicknesses for Use in TVA Sequoyah Nuclear Plant,Unit 2 ML20236T5381987-11-13013 November 1987 Rev 1 to DC High Voltage Cable Test Rept ML20236Q1871987-10-13013 October 1987 Elevated Temp Test Rept & Mechanical Pull Test Rept for Littelfuse Flas 5,5 AMP Fuses Lot 2,3,4 & 6 ML20236T9461987-09-0303 September 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1730B, Incorporating Instruction Change Icf 87-1616 ML20236T6421987-09-0101 September 1987 Rev 0 to Special Test Instruction STI-34, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit Mc 1497B, Incorporating Temporary Change 87-1520 ML20195J8031987-08-31031 August 1987 Impact Testing of Rockbestos & Anaconda Cables ML20236T9891987-08-31031 August 1987 Rev 0 to Special Test Instruction STI-29, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1606A, Incorporating Temporary Change TCF 87-1623 ML20236T8481987-08-25025 August 1987 Rev 2 to Special Test Instruction STI-17, DC High Voltage Test for Selected Unit 2 1E Cables in Vertical Drop Configuration ML20236T6141987-08-17017 August 1987 Rev 0 to Special Test Instruction STI-33, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T9781987-08-0303 August 1987 Rev 1 to Special Test Instruction STI-28, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1605A ML20236T8641987-07-29029 July 1987 Rev 1 to Special Test Instruction STI-19, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Jamming, Incorporating Change 87-1251 ML20236T9101987-07-29029 July 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1748A, Incorporating Change 87-1176 ML20195J7721987-07-22022 July 1987 Impact Testing of Aiw Cable ML20236S0511987-07-22022 July 1987 Rev 0 to Special Test Instruction STI-31, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1732B ML20236T8971987-07-21021 July 1987 Rev 0 to Special Test Instrustion STI-22, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1728B, Incorporating Instruction Change Icf 87-1619 ML20236T9641987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-27, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Change ICF-87-1283 ML20236T9261987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-25, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1754A, Incorporating Change 87-1252 ML20236T9181987-07-21021 July 1987 Rev 1 to Special Test Instruction STI-24, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Instruction Change ICF-87-1253 ML20236T8801987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-21, Cables ML20236T6521987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-35, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T5931987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-32, Cables ML20236T5691987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-30, Functional ML20195J7581987-07-20020 July 1987 Tests on Silicone Rubber Insulated Control Cables ML20236A2541987-06-10010 June 1987 Rev 1 to Lab Tests of Air Entrapment in Slightly Sloped Sensing Lines & Consequent Pressure Transmission Error ML20215C5691986-05-30030 May 1986 Cable Sidewall Bearing Pressure Tests ML20154K7711986-02-14014 February 1986 Reactor Bldg Containment Integrated Leak Rate Test,Sequoyah Nuclear Plant Unit 1,Conducted 851203-05 ML20107F6541985-02-19019 February 1985 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 841120-21 ML20071B3981983-02-17017 February 1983 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 821208-09 ML18025B8521982-03-18018 March 1982 Revision a to Qualification Test Rept for Model 1801104-05 PSA 1/4 Shock. ML20039A7801981-12-10010 December 1981 Summary Auxiliary Feedwater Pump Endurance Test,Sequoyah Nuclear Plant Unit 2. ML20010H7341981-08-31031 August 1981 Catalytic Combustion Hydrogen in Presence of Methyl Iodide, Final Rept ML20004A9741981-05-19019 May 1981 Reactor Bldg Containment Integrated Leak Rate Test, Conducted 810214-15 ML20050D0091981-04-16016 April 1981 Main Steam Line Break Qualification Test on Okozel Insulation, Final Rept ML20008F8721981-04-13013 April 1981 Table 14.1-2a to Revised Startup Test Program ML20003F0931981-04-13013 April 1981 Startup Test Revisions. ML20050D0111981-04-0808 April 1981 Qualification Tests of Electric Cables Under Simulated Steam Line Break (Slb) by Sequential Environ Exposure to Environs of Thermal Aging,Radiation,Steam & Chemical Spray. ML20008E5551981-02-27027 February 1981 Insp Device in Lieu of Insp Ports. Photographs Encl 1999-03-21
[Table view] |
Text
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- f EIS 871013 001' 1
ELEVATED TEMPERATURE TEST REPORT AND MECHANICAL PULL TEST REPORT FOR j LITTELFUSE PLAS 5, 5 AMP FUSES l
LOT NOS. 002, 003, 004, and 006 l
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This intermediate report is being lesued at the request of the Division of Nuclear Engineering (DNE) for documentation 'of tests performed on Littelfuse fuses Lot Nos. 002, 003. 00a. and 006.
continuing.along with tests on later manufacturer'sTests on lots.
tot Nos. 00s and 006 are this report will also pertain to tests on these other lots. Several sections of PURPOSE Fuses rate at manuf actured Sequoyah by Littelfuse Nuclear plant. as Let 'No. 003 have exhibited a high failure These tests were conducted to determine . if.
the replacements manufactured as Lot No. 006 are of better quality, and if possible, to determine when the fuses in tot No. 006 will begin to fall. Lot No. 004 and future production lots may also be tested.
SCOPE Fuse samples were received from the plant for testing'in several conditions; used and still intact, used and f ailed, or as a test sample from a'new production lot.
Initial work consisted of preliminary examination of two failed fuses from Let No. 003, all other work was performed on fuses that. wore intact when received. Tests to destruction by r.iechanical loading, application of current for long periods of time, and elevated temperature were used to evaluate the fuses.
TECTS Scanning electron microscope photos of failed and intact fuses provided a preliminary method of failure and possibly some clue' as to how to test the remainder of the fuses. Sectioned samples were made to attempt to examine the internal porosity and bending of the~ soldered joint. Tests were set up to pass a nominal current of two amperes through approximately one half of the sample and four amperes through the other half. The time ~ until the first f ailure was asasured for each half of the sample. The current was reapplied to the sample, the time until the next f ailure recorded, and the resulting total number of days service for each sample lot wee reported weekly. Several of each lot were reserved for tests regarding mechanical load. bearing capabilities strength andand it" possible failure rate. to determine the relation between mechanical g y gest AVSu* .,
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TEST SPECIMEN IDENTIFICATION I
Specimens were identified by Lot No. and individual fuse according to the type test to be performed. !
Fuses that were to be mechanically loaded to f ailure were designated " Lot No. 00K 5". The individual fuse number (example: Lot -
No.001, D.)
destruction. indicates the third fuse in Lot No. 6 that was pulled to The letter in the fuse which the individual fuse was subjected as described below. identifier refers to th
- P" = pull tests "M" elevated temperature "L" = two Ampere current !
"H" . four Ampere current PP00EDUPE 1 I
Scanning electron microscope photos of the fuses and mechanical tests of the strengths of the solder joints and the indicator pin actuating spring were used tests. to provide a preliminary cause of f ailure and to identify other needed Fuso holders arrangement forwere obtained long-term currentand tests.the fuses fitted into them in a series power supplies and loads were configured to obtain the nomine' test currents of' two and four' amperes.for }
sach test. A shunt of approxi. i in series with each group. A out aly the same resistance as a fuse was placed i monitored the current by sampling the voltage drop across theThe shunt.
data acquis lessor b'e low 0.8provided a printout every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a printout if the current dropped amperes (indicating a blown fuse), a printout if the current went above 5 amperes (fuse current limit), and a printout on demand. In the event of a power failure the time will be printed in red until the correct time is resst. i These records show interruptions to the test and allow proper accumulation of the total test time.
REPORTS Daily reports preliminary t%sts.to the plant on an informal basis- were.made during the the plant. Weekly progress reports on long-term tests will be sent to Intermediate reports will be provided as report issued at the conclusion of the long-term current tests. requested and a final 3
TEST EDUIPMENT. y , a y
V .
Digital Thermometer, thermocouple, US TVA No.Flute 903320.Model 216SA, US TVA No. 462383, with type K Liquid in Glass Thermometer, US TVA 903322. * '
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, 10/13/1997 142 ;6 Ot2M/ ENGINEERING'DBPCO-O 613 E37 C64 P.06 Digita2 Volt Noter, fluke Model 8400A, US TVA No. 305678. i Data Acquisition System. US TVA No. 903250. ;
Precision Resistors, US TVA No. 903309, US TVA No. 903310. US 7VA No. 90 US TVA 903312. US 77A 903319.
TEST DESCRIPTION Long No. 006 term on July current tests, as described in the procedure, were started for Lo* ,
August 11, 1987. 10, 1987, for Let No. 003 on July 21, 1987, and tot No. 004 or .
Scannin5 electron microscope photos and a meterials analysis of the selder in the fuse were reviewed by Ken Greene of DNE at the Central Laboratories Services Branch (CLSB).
These examinations and information provided by the manufacturer indicated that the element Bismuth was included in the used in Lot No. 003. Fuses from Lot No. 006 did not indicate a presence of Bismuth.
under no Fourelectrical fusesloadfrom each of Lot No. 003 and 006 were placed in an oven, at 200 degrees Parenheit on July 29, 1987 to ;
point, was a cause of the failure of003Lot No. determine if the pres fuses.
l programmed to print the time when each fuse failed due to this temperature.The dat l
{
PESULTS The photographs taken at the CLSB indicated partial moltir.g was present in a of the failed porosity in the fuses; solder,however, there was also present a larse amount of by the solder inside thea great variability in the wettin$ of ths cemponents '
These fusos, and even one fuse with almost no solder.
! These problems also influenced to some extentproblems were v4wed The pull tests were made on tot No. the pull tests that were made.
' the solder joint was stronger than 002, 003, and 004 fuses and indicated that attached. the resistor body to which it was pounds lessThe thanLot Lot No.
No. 002 004 and 003 fuses pulled apart at approximately 10
- 1. The pull test results are attached as Appendix i
h covits of tne elevated temperature tests provided a more pronounced difference.
The first fuse from tot No. 003 failed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The second failed priorand failed on September to 80 third hours fuses failed into the test.between 24 and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and the The first fuse _ from Lot No. 006' second fuse failed *on day AS, the third on day $1,oneand . .
fuse there re from Lot No. 006 that has not failed at present (71 days).
Additional tests on tot No. 00s, 006 and later manufactured. lots to measure the effects October 1, of temperature rise with various currents were reported to DNE 1987 (alms No. E13 871001 167 ), n o
results for Lot No. 003. but these results did not include
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. . . _ , . . ~ . - . - -
a m eruu4:En it& %P5C3-C EIS 697 4364 P.37 The Isng-tera curr;nt tests on Lot No.
The fuses in the higher. current loop 003 were discontinued af ter 40. days.
(which produced higher solder - joint temperatures in all Lot Nos.) f ailed at a much higher rate than Let Nos 004 and 006. Eleven of the fuses in the four ampere circuit f ailed within 33 days.
two ampere The first fuse in this circuit failed on day five of the test. In the days. circult only one fuse failed (at day 26) during a total of 40 than those No fuse in Lothas, at this time, failed in the long-term current tests other No. 003.
The duringphotographs, the tests are 'being data held logger records, and failed fuses that were not de at the current as appropriate. tests on all other fuse lots and will be included in the final r jaw:Oc5 01800 Best MadMC M i
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APPENDIX I
]
FUSE IDENTIFIER SPRING TENSION PAILURE LOAD REMA RKS (1bs) (1bs)
LOT 002 P1 1.15 29.25 _ resistor body failed P2 1.12 5.25(pin) .
' spring unwound at 15.25 lbs P3 1.13 5.25(pin) spring unwound at 15.25 lbs
-)
i LOT 003 P1 1.23 5.25(pin) spring' unwound at 15.2$_Ibs P2 1.13 23.25 resistor body fallec.
P3 1.12 18.25 resistor body failed PA 1.14 22.25 resistor body failed PS 1.13 19.25 resistor body failed j P6 1.12 5.25(pin) spritig unwound at 11.25 lbs J P7 1.10 19.25 resistor body failed p8 1.12 22.25 reslutor-body failed i P9 1.15 22.25 resistor body failed !
P10 1.13 24.25 resistor body failed-P11 1.18 i 5.25(pin) spring unwound at 13.25 lbs P12 1.13 F13 17.25 resistor body failed 1.13 10.25(pin) spring unwound at 11.25 lbs P14 1.03 5.25(pin) spring unvound at 11'.25 lbs P15 1.08 13.25(pin) spring unwound at 16.25 lbs P16 1.20 20.25 resistor body failed P17 1.20 {
5.25(pin) spring unwound at 13.25 lbs PIB 1.13 l 5.25(pin) spring unwound at 12.25 lbs l P19 1.09 13.25 resistor body failed P20 1.24 25.25 joint Iailed 1.
l l
LOT 004 P1 1.02 31.25 resistor body falled P2 1.06 I 29.25 resistor body failed '
P 3. 0.91 33.25 resistor body failed P4 0.80 34.25 spring-resistor joint failed P 5 .. 1.02 28.25 resistor body failed P6 1.07 35.25 resistor body failed P7 1.18 20.25(pin) spring unwound et 18.25 lba ^
P8 1.15 30.25 resistor body failed P9 ~
1.13 20.25(fatigue) weight applied overnight >
P10 1.15 P11 30.25 resistor body failed '
5 1.12 ~
33.2[ _ resistor body fa}1ed yayab\c CDW . :-
I. ( ,
I [ 32/;2/1997 14:49 C&EfVEN3]NEERING/DBS503-C 6:5 697 4:54 5.09
, APPENDU ((
est Available Copy FUSE IDENTIFIER STARI DAT8 STOP DATE TOTAL TIME Lot No.003 L1 7-21-87 6-31-87*
L2 7-21-87 40 days L3 6 31-87* 40 days 7-21-87 8-31-87*
LA 7-21-87 40 days LS 6-16-87 26 days !
7-21-87 6-31-87*
i L6 7-21-87 40 days L7 6-31-875 40 days 7-21-87 6-31-875 LB 7-21-87 40 days L9 8-31-87* 40 days !
7-71-87 6-31-87* i L10 7-21-87 40 days L12 .8-31-87* 40 days 7-21-87 6-31-87*
L12 7-21-87 40 days L13 8-31-875 40 days 7-21-87 6-31 87*
L14 7-21-87 40 days LIS 6-31 87* 40 days !
7-21-87 6-31-87* i L16 7 21-87 40 days L17 6-31 87* 40 days
' 7-21-87 6-31-87*
L18 7-21-87 40 days L19 B-31-875 40 days 7-21-87 8-31-87*
L20 40. days 7-21,87 6-31-E7' 40 days FilSE IDENTIFI!_R START DATE STOP DATE TOTAL TIME kot No.003 H1 7-21-87 8-5-87 H2 7-21-87 15 days H3 7-30-87 9 days 7-21-87 8-31-875 H4 7-21-87 40 days ;
HS 7-28-87 7 days '
7-21-87 7-28-87 N6 7-21-87 7 days '
. H7 6-31-87* 40 days 7-21-87 B-31-87*
HB 7-21-87 40 days H9 7-26-87 5 days 7-21-87 8-13-87 H10 7-21-87 23 days H11 6-31-875 40 days 7-21-87 8-31-875 E12 7-21-87 40 days HIS 8-11-87 21 days
_ 7-21-87 8-31-87*
H14 7-21-87 40 days 3 H1$ % 8-7-87 "17 days V 7-21-87 6-3$-87* ~
H16 7-21-87 40 days Hi? 8-6-87 16 days '
- 7-21-87 8-31-87*
H18 7-21-87 40 days H19 B-19-87 29 days 7-21-87 6-31-875 H2O 7-21-87 40 days 1 8-4-87 14 days
- Lot No. 003 removed from test by instruction from DNE on 8-31-87.
'N
i Attachment 2 l 1
"Sequoyah Nuclear Plant j Littlefuse Type FLAS-05 Fuses Predicted Service Life SME-MET-87-901" ;
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- DNITt:D BTATES GOVERNMENT c4y B43 77 C 92 8 001-
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Memorandum TENNESSEE VALLEY AUTHORITY To :
I W. S. Raughley, Chief Electrical Engineer, W8 0126 C-K ynom :
D. W. Wilsort, Chief Nuclear Engineer, W10 C126 C-K Hest Available Lopy utTE , ,SEP 281987 l st:10ECT:
SEQUOYAH LIFE NUCLEAR PLANT - LITTLETUSE TYPE FLAS-05 FUSES -
We are transmitting the Singleton Materials Engine.ering Laboratory report SHE-MET-87-901 as requested by Ken Green on August 18, 1987. Please refer i i
to a preliminary report on FLAS-05 fuses given as QIE NEB 87281 (B46 870919 003). I OU Und y D. W. Wilson (p,PVG:MHD p Attaohnents N.
oo (Attachments): \
...EINS._SL26 C-K t
s ,
W. H. Childres, SME-K j l
This was prepared principally by Paul V. Outhrie Jr., extension 2771. .
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4 A27149 7 . O t
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