ML20236V517
ML20236V517 | |
Person / Time | |
---|---|
Site: | Sequoyah ![]() |
Issue date: | 11/19/1987 |
From: | Hight G, Faith Johnson, Walter R WYLE LABORATORIES |
To: | |
Shared Package | |
ML20236V477 | List: |
References | |
NUDOCS 8712040348 | |
Download: ML20236V517 (255) | |
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L QUALIFICATION TEST PROGRAM FOR SILICONE RUBBER CABLES WITH REDUCED INSULATION THICKNESSES FOR USE IN . TENNESSEE VALLEY AUTHORITY'S SEQUOYAH NUCLEAR PLANT, UNIT 2 For Tennessee Valley Authority 400 West Summit Hill Drive Knoxville, Tennessee 37902 8712040348 871124 PDR ADOCK 05000329 P PDR
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x v - Test Report - e b\ x REPORT NO. 17905-1 -
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[ T I" [ .w - 1 WYli JOB NO. CUSTOMER TV-56071 A _ P.O.NO. ($- e, S. PAGEi OF 246 PAGE REPORT
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See References in Paragraph 5.0 of this ( ,VY '- 'Y' Qr
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Y Summary Section L $.'. w ' . . - - 1.0 CUSTOMER Tennessee Valley Authority (TVA) ADDRESS 400 West Summit Hill Drive, Knoxville, Tennessee 37902 Sili 2.0 TEST SPECIMEN ne Rubber Insulated Cables With Reduced Insulation P/N SE-725 GE Compound, P/N KS 500 and P/N CC-2193 Nuclesil 3.0 MANUFACTURER American Insulated Wire. Rockbestos Wire and Cable. and Anaconda / Continental, respectively 4.0
SUMMARY
Silicone rubber insulated cables with reduced insulation, as described in Paragraph 6.0, were subjected to a Qualification Program to verify their ability to maintain loads during an accident simulation as specified by TVA. The Qualification Program described herein represents Unit 2. installations at the Tennessee Valley Authority's Sequoyah Nuclear Plant (SQN) The Qualification Test Program was performed to satisfy the intent of IEEE Standards 3231974, " Standard Stations", and for Qualifying Class IE Equipment for Nuclear Power Generating 3331974, " Standard for Type Test of Class IE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations." STATE OF ALAB AMA Alabama Professional Eng. ** COUNTY OF MADISON
- Reg. No. 7948 '**'*"'"*""*',***'**Q'L'"y,",*"
Frederick M. Sittason PREPARED BY i t-r1 -67
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eno caresuuy conouci is one is so e e e, or nos i.o true ano correci en APPROVEDB /-a - - // _ h suB i enis M osy W g 19 F WYLE Q. A. G. W. Hight / T!P7 pioiary/vbhc in e' on ' tor ine state of Aiaoem
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Peg 2 Ns.11 . . . Test Report No. 17905 - 4.0
SUMMARY
(Continued) - The Qualification Program was performed on three independent manufacturer's types of silicone rubber insulated cables. A description of the test specimens is . presented in Paragraph 6.0 of this Section. This report contains the following sections: , o Section I - Specimen Identification, Visual Inspection, Specimen-Preparation and Baseline Functional Tests o Section II - Radiation Exposure (Normal Plus Accident) and Post-Radiation Functional Tests o Section III - Accident Simulation (LOCA) o Section IV - Voltage Withstand / Breakdown Tests and Post Test Inspection - - o- Section V - TVA Analysis of Thermal Aging Exemption Justification, Post DBE Aging Specimen Test Load Requirements, Insulation Thickness Measurement Techniques, and Specimen Preparation (Shaved and - Impacted) o Section VI - Wyle Laboratories' Qualification Plan No. 17460 59 Revision C The test program was conducted in the sequence indicated by Section I through IV above and in accordance with Wyle Laboratories' Qualification Plan 17460 59, Revision C, which is contained in Section VL The test specimens were subjected to radiation exposure and demonstrated the capability to maintain specified voltage and current during the specified Design Basis Event (LOCA Simulation). It is therefore judged that the silicone rubber cables, described in Paragraph 6.0 of this section, met the acceptance criteria requirements of Wyle Laboratories' Qualification Plan (WLQP) 17460-59, Revision C.
5.0 REFERENCES
5.1 IEEE Standard 323-1974,"IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating St tions." 5.2 IEEE Standard 383-1974, 'IEEE Standard for Type Test of Class IE Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations.'
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WYLE LABORATORIES Huntsnue FacHrty _ . _ _ _ _ . _ . _ _ . _ _ _ _ . _ _ . . _ _ _ . _ _ _ _ _ _ _ _ __w
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1 - 1 Page Ns. til - r- ' Test Reptrt Nc. 17905 .s
5.0 REFERENCES
(Continued) , 5.3 10 CFR 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," U. S. Nuclear Regulatory Commission,1973. . 5.4 10 CFR 50.49, " Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants," U. S. Nuclear Regulatory Commission, January 21,1983. 't g 5.5 TVA Contract No. TV-56071A. IDibg, '- e. 5.6 Wyle Laboratories' (Eastern Operations) Quality Assurance Program Manual.
;_ lp 5.7 Wyle Laboratories' Qualification Plan No. 17460-59, Revision C.
6.0 TEST SPECIMEN DESCRIPTION ej . .'q Descriptions of the cable specimens are as follows:l-Originally Estimated Measured Minimum Insulation' Thickness Insulation Thickness"" Soeelmen Manufseturer P/N* (mili 's (mil) [' j.i ,. AIW-1-B-1.1 AIW SE-725 vw ' 8 .~~ 2 AIW 3-B-2.1 AIW SE-725 y%g.,'Qdl N15 4 p AIW-4 B-3.1 AIW SE-725j 'p3s$U 20 4 Ap,.jin? AIW 5-B-4.1 AIW SE-725 '%E 25 8 fE % AIW-6-B-5.1 AIW SE-7257 30 9 vg g .
+AIW-7-I 1.1 AIW , SE-725** ',
N/A N/A
, g; _ - +AIW 8-I-2.1 AIW SE-725*
- N/A N/A y &
( RWC-1 -B-1.1 RWC, , ' ._iKS-500 8 4
. 2' ..KS-500 15 4 RWC-3-B 2.1 RWC, ..
RWC KS-500 20 6 RWC-4-B-3.1 . RWC-5 B-4.1 RWC KS-500 25 9 RWC-7-1-1.1 RWC KS 500** N/A N/A RWC-8-I-2.1 RWC KS 500** N/A N/A AN CC-2193 8 2 AN-)-B 1.1 CC 2193 15 4 AN 2-B 2.1 AN , WYLE LABORATORIES Huntsyme Feeinty
i L Pcge No. Ir - Test Repart No. 17905-1 --- 6.0 TEST SPECIMEN DESCRIPTION (Continued) Originally Estimated Measured Minimum Insulation Thickness Insulation Thickness *" Snecimen Manufacturer P/N' (mil) (min , AN CC-2193 20 4
- AN-3-B-3.1 ?
AN-4-B-4.1 AN CC-2193 25 % 4 .. E-TAN-6-1-1.1 AN CC-2193** N/A DkgN/A ps, "-
~' + AN-7-I-2.1 AN CC-2193** N/A N/A
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.m.m ' 'All specimens with asbestos braid jacket removed except as noted) - ** Impacted specimens with jacket intact - remaining conductor.minsulation thickness not verifiable. V 2!* . ***As measured by TVA. / W ly $ + Specimens were not powered during the Accident'l Simulationsubjected ~ and to were not Voltage Withstand Tests, at TVA's direction. O~ cu ,.
s. 7.0 QUALITY ASSURANCE f~ g , Trdf /[ All work performed.on the ' test.programimas done in accordance with Wyle + Laboratories' Quality Assurance' Program,' which complies with the applicable requirements of 10 CFR 50,". Appendix B, ANSI N45.2, and the " daughter" standards. Defects are reporiable.in'accordance with the requirements of 10 CFR Part 21. ~ g%fMF
,sy m .L 8.0 TEST EQUIPMENT AND INSTRUMENTATION 2 jr All instrumentation,3hasuring, and test equipment used in the performance of this test program were calibrated in accordance with Wyle Laboratories' Quality Assurance Program ^which complies with the requirements of Military Specification MIL-STD-45662. Standards used in performing all calibrations are traceable to the National Bureau of Standards by report number and date.
When no national, standards exist, the standards are traceable to international standards or the basis for calibration is otherwise documented as auditable. k .f~$ j f. p ' N<
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WYLE LABORATORIES Huntsvibe Facility l I
1 . l l SPECIMEN RECEIPT INSPECTION, PREPARATION, AND' BASELINE FUNCTIONAL TEST l i i i 1
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! Page No.1-1 ' -A Test Report No. 17905-1 -~
l SECTION I .. SPECIhfEN RECEIPT INSPECTION, PREPARATION, AND BASELINE FUNCTIONAL TEST , 1.0 REQUIREhiENTS i . 1.1 Specimen Inspection / Identification n 6 ( l i The specimens shall be subjected to an inspectionif:or(the purpose of l identification and documentation as specified in Paragtnph 3.1 of;Section VL 1.2 Specimen Preparation and Baseline p
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Functional Test (p~s The test specimens, as provided by Tennessee Valley ' Authority (TVA), shall be mounted in open cable trays as specified in Paragraph 3.2, Section VI and shall be subjected to the Baseline Functional Tests described in Paragraph 3.3 of Section VL c Y. . A. x_w 2.0 PROCEDURES g'g % N 1... 2.1 Specimen Inspection / Identification ,8 N Q jf . A visual inspection of the test specimens was conducted upon receipt at Wyle Laboratories. This inspection, w1itssperformed in order to document manufacturer and model numberswof the specimens to be tested and any noticeable damage. In addition',4alh, specimens were tagged with Quality Assurance " Test Specimen
- ta'gs i slacilitate their identification during the test program. The results of[the / visual' inspections are recorded on the " Test Specimen Inspection" formsin Appendix ! of this Section.
2.2 Ah & Test Specimen Preparation F l %H The silicone rubber. cable. test specimens were subjected to n technique, by TVA personnel, that involved. shaving discrete thicknesses from the cable insulation. Each cable specimen 'was subjected to the shaving technique at three (3) individual places;along(the cable length. Based upon the thickness of the insulation that was shaved (removed) from the cable specimen, an assumption I was made as"to"thelemaining insulation on each cable specimen conductor. The I shaving procedure and results for the cable test specimen preparation are presented in Sectioh'V.
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Additionally, damage was incurred to certain specimens in the form of known j weights impacted on the surface of the cable specimen. Three (3) impact points werc mandated for each impact cable specimen as described in the TVA
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procedure outlined in Section V. I WYLE LABORATONES )
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l Psge Ns.1-2 j Test Report No. 17905-1 I 1 2.2 Test Specimen Preparation (Continued)
- l The test sper.imens were mounted in open cable trays 18 inches wide and 5 feet long. Amer.ean Insulated Wire (AIW) specimens were mounted in Cable Tray A, .
Rockbestos Wire and Cable (RWC) specimens were mounted in Cable Tray B, ] 1 and Anaconda / Continental (AN) specimens were mounted in Cable Tray C. The l test specimens were mounted as specified in Paragraph 3.2pf Section VI and when possible (without excessively twisting the cable), with the shaved sections - of the specimens making contact with the perforated steel, Photographs were taken of the mounted specimens and are presented in' Appendix II of this - N section. . 2.3 Baseline Functional Test Q.w_ "'D Insulation Resistance measurements were conducted by applying 500VDC for 1 mi tute prior to the reading of the resistance'between each conductor and ground (cable tray). The recorded measurements, for" informational purposes-only, are presented in Appendix III of this section.N.q. j:, '7 3.0 RESULTS ,' Vx -
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The test specimens were subjected to' the. receipt' inspection, preparation, and Baseline Functional Tests of Paragraphi2.0.4.and met the requirements of Paragraph 1.0. The data recorded'tiuring this phase of the test program is presented in Appendices I through'IV of'this'Section as noted below.
' Q_, y o Appendix I contains the Test Specimen Inspection Sheets. .' : 3 o...
o Appendix II contains T Phot 6gr[phs I-1 through I-4 which show the specimens mounted to the open cable tray. jgx v o Appendix III contains the Data Sheets generated during Baseline Functional Tests. -j o Appendix IV co ains Instrumentation Equipment Sheets required for the Baseline Functional Tests.
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PHOTOGRAPH I-I l AIW SPECIMENS MOUNTED IN CABLE TRAY A
- UPON COMPLETION OF SPECIMEN PREPARATION 1
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Test Report No. 17905-1 SECTION II . RADIATION EXPOSURE AND POST-RADIATION FUNCTIONAL TEST . . 1.0 REQUIREMENTS
- e 1.1 Radiation Exposure t;[c
%, V The test specimens shall be subjected to the radiationiexposure (normal plus accident dose) as specified in Paragraph 3.4 of Section.VI. Ne c3 1.2 Post-Radiation Functional Test /v 4 %y i
1 The test specimens shall be subjected to a functionai test, upon completion of radiation exposure, as specified in Paragraph.3.5 o,fgection VI. 1 j, % , i 2.0 PROCEDURES ,- y j e' 2.1. Radiation Exposure ..
+. Q3 y The test specimens were subjected ' to irradiation exposure in two groups.
Group I consisted of the AN specimens (Tray C) and Group II consisted of the AIW and RWC specimens (Trays A.and B respectively). The total dosage to the cable trays was as described below: % Qg N ND. Cumulative Specimen Cable V , Manufacturer f*Jr,gy,,, , Ns TTD (Rads) l' k;; f
- Q AIW NA, 9.15E7 gg vs RWC , B 9.15E7 t:: 9 AN t .C 7.65E7 y
A letter of certification for irradiation services performed is presented in Appendix I of this section.
.y 2.2 Post-Radiation Functional Test ~
Insulation Resistiance measurements, as specified in Paragraph 3.5 of 'Section
- VI, were conducted by applying 500VDC for 1 minute prior to the reading of the resistance between each conductor and ground (cable tray).
I 3.0 RESULTS The test specimens were subjected to the radiation and post-radiation functional tests of Paragraph 2.0 and met the requirements of Paragraph 1.0. , l There was no evidence of degradation of the specimens due to radiation exposure. The data recorded during this phase of the test program is presented in Appendices I through III, of this Section, as noted below: I WYLE LABORATORIES f Humsvm. r.enny l
l l n Pege No. II-2
~
Test Report No. 17905-1 3.0 .RESULTS (Continued)
~ 'o Appendix I contains a Letter of Certification indicating dose -rates, exposure time and cumulative total dose on the test specimens. '
o Appendix II contains Data Sheets showing the data recorded during the e Post-Radiation Functional Tests. j
$'n o Appendix III contains Instrumentation Equipment' Sheets generated fer 'he Post-Radiation Functional Tests.
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~ ~ ~ ,; , b. . ::g.. /y..,,'c, ;_nGeorgia Instittite ofTechnology O M 'i ~ NEELY NUCLEAR AESEAACH CENTE A '
1, N / [ 900 ATLANTC CAfVE e# 4 . ,m * * / ATLANTA. GEC AGIA 3C332-0425 (404)894-3600 November 10, 1987 i Wyle Laboratories 7800 Governors Drive West C:$ _ P. O. Box 1008 Buntsville, Alabama s 35807-4411 [$
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Attention: Mr. Todd Walter
Reference:
4-7929-S
. ;;m,. 731064 ,9.t Gentlemen: '
sv The items covered by the above' ntimber have been irradiated in accordance with quality assurance requirements using Cobalt 60 (gamma energies 1.173 Mev, 1.331.Mev) to the total dose requested. nod g'
- . %:pp We certify the specifics of the irradiation as follows:
2
- m. g%
Irradiation Period: Intervalibetween October 6, 1987 through October 17541987 as shown on the enclosed
~
Gamma ~ Irradiation Log Sheets.
<y ~ ~ yy Dese Rate: (NTE) 1.00 E6 Rads /hr (Air Equivalent) %:;, .. ~
Total Dose: _,.,7 . 6 51 & 9.15 E7 Rads (Air Equivalent) Dosimetry: l Victoreen Model 500B-1 Integrating / Rate V ' Electrometer System with ionization _ chamber probe. Calibration by Victoreen traceable to NBS Cobalt-60. Calculations, a sketch, or photographs of the arrangement . are enclosed. Please let us know if any additional information - is needed. J l Yours truly, Dr. R. A. Karam Director RAK:dwa Enclosures i A Umt of t** Uwersny Sysiem of Georg.a An Ecwas Ecucanon and F~ma**' Oa""a'"' '"""""*
Page Ns. II-6 ~~ " Tsst Rep:rt No .17905-1
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OOSE RATE DETER:C::t.TIO:: 4 E x-P x D x T x :4 x' M x R = Octo Rate, Reas/hr (Air Egiuivislent) .
. E = Electrometer liigh Level- Conversion P = Probe Efficiency / .t+
0 : Dose. Conversion, Roentgen to Rad . 'g. l T = Temperature Correctica tv 0 Degree Celsius f.w!A M = Pressure Correction to 760 Millimeters Merc'IJrf4T(*gCs H = Time Conversion, Minutt.s to Hours R = Electrometer Reading g,,',' Jig-N".y,o}tAQ4r . E 'P D T ri il :.., R Oose Rate, Rads /hr
~v..- % +
100 0.939 =0.869 1.one 1.029- 50 dCI:50.03.' u.73 E5 100 0.939 0.869 1.0nu 1.029 60gt u.75 E5 100 0.939 0.869. 1.Onu 1.016 f.~:n 50 kj,j, 129.92 90.35 6.7u E5 100 0.939 0.369 . 1.oun 1.031 4 . 60 w 130.32 0.36 ES yy%la m, m i V. 4r
'.lYLE L' LABORATORIES: u-792'i-S GEORGIW7ECll AUMBER: 731068' A%h.. N 5? v e"Dh, %n ?mebkw ,s .' Nkw ,~
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..a '- ~ - ' GEORGIA INSTITUTE OF TZCHNOLOGY i Nuclear Research Center 900 Atlantic Drive. N.W. -
Atlanta. Georgia 30332 4 04)894 3608 GAMMA IRRADIATION LOG . Client: Wule Laboratories NRC
Reference:
731064
Reference:
4-7979-S Total Dose: 9.15 E7 ttem: cable trav/ Wires
- Asa _ Dose Rate: '(NTE) l'.D E6
& n9'% - %,y .
Stop Lapsed Dose Rate Total Dose Cumulative Start I Hours Rads / hour A Rads Dose Rads 10/12/87 10/17/87 l$ 1354 0318 133.40 6.86 ES : $9.lS.E7 9.15 E7
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900 Atlantic Dnve. N.W. , Atlanta. Georgia 30332 (404 894-3608 GAMMA IRRADIATION LOG . Client: Wule Mcratories NRC
Reference:
731064
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Reference:
4-7979-S Total Dose: 7.65 r7 i item: cable trau/ wire oc Dose Rate: (NTE) 1.0 Eh ,_
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r~ n a Lapsed Dose Rate Total Dose Cumulative Stad Stop Hours Rads / hour RadsC^t Dose Rads
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10/06/87 10/07/87 ' 1640 1551 23.18 4.73 ES 1.09 E7 % 1.09 E7 s % . . . . . . . _
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1636 1242 44.10 4.75 ES 2.09 E7 3.18 E7 i. 10/09/87 10/12/87
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Test Rapsrt No. 179051f * ' - ' ~~55 A::. ,u,.,.. .....?-..-. TRACEABILITY DATA Victoreen Electrometer b Model Number 500s-1 ys Serial Number 340 Z2p~2b qq* e November i7, 1986 fe%t: Calibrated: M By: Neely Nuclear Research Center k N )r;E g' i Georgia Institute of Tecnnology Ng .4 900 Atlantic Drive, N.W.
- Atlanta, Georgia 30332 gy,,
pg,Qp ,, Hext Calibration Due: November 17, 1937 %-o
/W Yi Instrument'lsUsed, & Y y R<:,
vu Keithley Picosmoere Source f Model Number 261 q[ntp/? jr Serial Number 71987 jg Kg f Ks 't Calibration: October 9, 1986,, ,3 Sy: General Electric Company,, N %~ Integrated Communicationdervices Operation 2825 Pacific Drike',tsuite'A Norcross, Georgia. 3007L Next Calibration Due: /OctoN r 9,"1987 9.f4 # General Electric Traceability SLN-7031 Number.0004802 (Dated July 17, 1986 and due January 17, 1987) KEI-515 Number 23666 (Dated December 6,1935 and due December 6,1936 Dw F Hewlett Packard DigitalLYoltmeter Model Numoer .3460B Serial Number 709-00133
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Calibration:,' September 10, 1936 By: s 'Hewlett Packard
.,~, Product Support Division N 2000 South Park Place Atlanta, Georgia 30339 Next Calibration Due: March 10, 1937 Hewlett Packard Traceability N.B.S. Number 23hu94 (Dated April 30, 1936 and due October .40, 1936)
Pcge No. II-10 u. - Tsst Rspsrt No. 17905-1 - --v + 6-. .
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p Traceability Data Continued Victoreen Probe Model Number 550-6A Serial Number 502 L Calibration: June 30, 1987 "4-By: Victoreen, Inc. 10101 Woodland Avenue g g @, p. Cleveland, Ohio nul0a j
- n. ,s+. n Next Calibration Due: June 30, 1983 j.g,y 9~ m .-
pg., ,, - Victoreen Traceability s Test Number DG8118/83 Calibration: September 29, 1983 e. _QV : - PTW Chamber Model 30-3u3 .
- , , f -' \J Serial Number N23361-142 g.C .
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DATA SHEET 7 r Tennessee valley A thoritY WYLE LABORATORIES Specimen Silicone Wire Cable Part No Variou8 Amb. Temp. 7g-# Job No,17905 g hTLQP J7460-59 Photo VO Report No. 17905-1 P a 3.5 Test Med. M# See BelW
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- Test Report No. 17905-1
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INSTRUMENTATION EQUIPMENT SHEET , '~^-
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DATE: 10/16/87 J03 NUMBER: 17905-00 TEST AREA: c'r' LAB 1 TECHNICIAN: C. ARBUCKLE CUSTOMER: . T.V. A. TYPE TEST: POST RADIAT!DN FIDC* CNra ; NO. INSTR 1 MENT NAMFACTURER - MODElf SERIAL # WYLE 4 RANGE 1 ACCURACY ! - CALDATE CA;AE 1 MEB NTR GENERAL RADID 1664 657113180 O!!898 $0K-50TDhN / 10/06/67 04/06/88 h;.M% RANGE 4 .. we f2h 5h% %W .. q% .1.. h&M*:r Q: ff
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d) .h , h n uu THIS IS TO ERTIFY THAT THE AN' INST:tLSTS WERI CALIBRATD USING STATE-OF-THE-ART TEGNIQUES i;ITH STACAR TRA2fdlLE TO TE NATIONAL BUREAU Or STANDARDS.
,k M l 0 -/4 8 7 l INSTRUMENTATION ,x CHECKD 8 SECEIVED Py 0"S *bh a A. 1 o M'N wf,i.
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i l l 1 h e ACCIDENT SIMULATION AND FUNCTIONAL TESTS [
- _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i
Pcge Nr. III-I . i
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Test Report No. 17905-1 i
.1 i
SECTION III ACCIDENT SIMULATION AND FUNCTIONAL TESTS 1.0 REQUIREMENTS 1.1 ' Accident Simulation 4 The test specimens shall be subjected to the accident simulation as specified in Paragraph 3.6 of Section VI. '~w
~
1.2 Functional Tests . _
;- ,n-The test specimens shall be subjected to Insulation Resistance tests and visual inspections as specified in Paragraphs 3.6.6 and 3.7 of Section VI. ~
2.0 PROCEDURES -
~
2.1 Test Setup 2.1.1 Chamber Calibration A " trial run" accident simulation was performed in the test chamber, which encompassed the first four hours 'of _the required profile, in order to verify the actual temperature and pressure capabilities of the test chamber. Dummy loads we're placed in the chamber in order to approximately simulate actual i volume and mass of the specimens:4' Plots of the "trir,1 run" are presented in Appendix II of this section.f~~') c-q, / %. 2.1.2 Test Snecimen Preparation"
- a. a The cable ' specimens that were originally estimated to possess 8 mil of remaining conductor ' insulation (i.e., AN-1, RWC-1, and AIW-1) were subjected to a measurement of each specimen's insulation outer diameter. The specimens were measured ' in a non-shaved area, using a micrometer, in both the horizontal and vertical planes (with respect to the cable tray) and as specified in Paragraph 3.6.3 of Section VI.
The cable specimens were spliced to the TVA supplied test leads using uninsulated butt splices and Raychem WCSF-N heatsbrink tubing. The splices between the cable specimens and the test leads were prepared by TVA technician personnel prior to mounting the cable trays in the test chamber. The cable trays were mounted in the test chamber and the test lead chamber penetrations were sealed as specified in Paragraph 3.6.3 of Section VI. Photographs of the cable trays mounted in the test chamber, the test leads exiting the test chamber, and the test leads terminated to terminal blocks are presented in Appendix I of this section. 0 0 WYLE LABORATORIES Muritsville Facility
Page Ne. III-2 Test Rep:rt Ne. 17905-1 i l
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l 2.1 Accident Simulation (Continued) 2.1.3 Electrical Powerine l Each test specimen in the program was connected to an individual circuit with the powering setup typical of the circuit shown in Figure 3 of Section VI. The test specimens were powered as listed below:
,q Applied T Test Soeelmen No. Voltace (V ACT - ' Curr'ent ( Amos)
AIW-5-B-4.1 305 ~3 H 25 AIW-6-B-5.1 305 n 25 I
. RWC-5-B 4.1 305 Q ,7l/ N ' 25 AN-4-B-4.1 305 25 AIW-7-I-1.1 0 .. % 0 AIW-8-I-2.1 0 ~,'"Sr 0
AN-6-I-1.1 0 %7~ 0 AN-7-I 2.1 0 i 0
^
All other specimens 305 ; y 15
.y ..
Allowable tolerances were as followsr > ! M .. g j o Voltage +10, -0 VAC N]f . ..) o Current +10%, -0% of the specified value m y :3
-% -r y The loading assigned to the_ test specimens was determined by TVA personnel and documentation for the required v'oltage and current loads is presented in Section V. - .s. . r CN r w 2.1.4 Monitorine .,
The test specimen circuits were monitored and recorded as specified in Paragraph 3.6.5 of Section VI. The monitored channels on the Data Acquisition System (DAS) are as presented below:
# l Channel No. Units Description ,s s ~
1
*F . Thermocouple No. I mounted to Cable Tray "A" 3,f'* _
2 . s*F Thermocouple No. 2 mounted to Cable Tray "C"
.,. . . q r 3 2 'F Thermocouple No. 3 mounted to Cable Tray "B" 4 , 'F Average Temperature of Thermocouple Nos.1, 2, and 3 5 PSIG Chamber Pressure 6 GPM Chemical Spray Flow 7 mA --- Circuit 1 Leakage ( AIW 1-B-1.1) !... -. g agge , _ . . - , , - . .4 Humnme Facwty ; 39- u 4.'~ - ~ ~
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', -.- j Pcge No. III-3 '-- j .- Test Report No. 17905-1 1 2.1.4 Monitorine (Continued)
Channel No. 17,g111 Description . 8 mA Circuit 2 Leakage (AIW-3-B-2.1) 9 mA Circuit 3 Leakage (AIW-4-B-3.1) y mA 5 10 Circuit 6 Leakage (RWC-1-B i$i)4%.., -. 11 mA Circuit 7 Leakage (RWC$N-2.1) [L L:<Q: l 12 mA Circuit 8 Leakage (RWC-4-B-3.1) ' 13 mA Circuit 9 Leakage (RWC- -1.1) 14 mA Circuit 10 Leakage (RWC-8-I 2.1) y ~. V 15 mA Circuit 11 Leakage (AN-1-B-1.1) 16 mA Circuit 12' Leakage (IN-2 B-2.1)
, y 17 mA CircuitJ3. Leakage (AN-3-B-3.1) 4, '%g#~
18 mA Circultu6 Leakage (AIW-5-B-4.1) m %%
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19 mA /Clicult J7 Leakage (AIW-6-B-5.1) km / S i' Circuit 18 Leakage (RWC 5-B 4.1) 20 mA C; ~4 21 mA ,
' Circuit 19 Leakage (AN-4-B-4.1)
N .j ; Chemical spray PH was' monitored hourly during the 24-hour period in which the chemical spray was present. A Fluke Datalogger (Model 2240C) was utilized to monitor and record the circuit current and applied voltage for each of the powered. specimens. The Datalogger also transmitted the monitored data to a high-speed line printer for collection of hard copy data. The Data Acquisition System (DAS) was utilized to monitor all of the environmental channels and leakages on the .;pecimen circuits as listed above. The DAS displayed requested information on a color monitor, fed a high-speed line printer and fed a Hewlett Packard (HP) Model 1000 minicomputer. The HP 1000 stored data on hard disk and was used to generate the plots of various parameters versus time. Both the Datalogger and DAS line printers operated during the test program at the print rates listed below: WYLE LABORATORIES MuntsvlHe FECihty
Page Nr. III-4 Test Rep:rt No. 17905-1
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1 l 2.1.4 Monitorine (Continued) f I Test Time j Print Rate (Aceroximate) Comments j l 5 seconds 7 minutes ' 20 seconds 17 minutes 1 minute I hour 8 minutes 10 seconds I hour 33 minutes Initiate chemical spray 1 minute 15 hours 50 minutes
~~ %" "%'
10 minutes (or less) 25 hours 40 minutes + 1 hour (or less) 242 hours To end of test 2.2 Pre-Accident Functional Test
- L, o g. ' '
m The test specimens were subjected to Insulation,~ Resista'nce measurements, as specified in Paragraph 3.3.2 of Section VI, by applying 500VDC for 1 minute prior to the reading of the Resistance between,each conductor (specime.n, splice, and test lead out of the chamber);and chamber ground. The chamber was then flooded with tap water and the In.;ulation Resistance measurements repeated. _/^ %
~
2.3 Accident Exposure f3A h The test specimens were powered with the' required voltage and current and were subjected to steam in order to st'abilize at 104*F for a minimum of 30 minutes. Upon stabilization, the tist . specimens were subjected to the accident profile as specified in Figure 2.of Section VI. The peak conditions of 342*F at 15 PSIG were achieved within130. seconds and the chamber temperature and pressure were varied as'necessary-in order to envelope the required profile. The specimens were subjected to chemical spray at approximately 77 minutes into the Accident Simulation. The chemical spray injected into the chamber resulted in.a chamber temperature drop and the spray was discontinued until the chamber temperatu're could be stabilized. The chemical spray was restarted at approximately 88 minutes into the Accident Simulation and remained on for 24 hours from that point in the Accident Simulation. The Post-DBE accelerated aging period of 216 hours, at a chamber temperature of 190*F, was completed without incident. 2.4 ( E,.s Post-Accident Funitional Test i
, N The test specimens were subjected to Insulation Resistance measurements, as l
specified'in Paragraph 3.3.2 of Section VI, with the specimens at ambient conditions inside the test chamber. The test chamber was then flooded with tap water,and the Insulation Resistance measurements were repeated. Upon completion of the submerged functional test, the test chamber was drained, opened, and the specimens were removed after an Insulation Resistance measurement was repeated for Specimen AN-1. The cable specimens were visually inspected and the outer diameters of the cable types were measured, as l described in Paragraph 2.1.2 of this Section, as close to the original { measurement point as possible. Photographs are presented in Appendix I of l this Section. j m e g g
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Test Report No. 17905-1
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L 3.0 RESULTS - i The test specimens were subjected to the functional tests and Accident i Simulation of Paragraph 2.0 with results as follows: 3.1 Pre-Accident Functional Test i i Data Sheets generated during the Insu4 tion Resistance measurements, with the I specimens at ambient temperature and again with the specimens submerged in tap water, are presented in Appendix III of this Section%2Q 3.2 Accident Simulation /N l; }%% All test specimens successfully. maintained the applied voltage and current throughout the Acident Test. Leakage currents on all specimens except : AIW-5-B-4.1, AIW-6-B 5.1, RWC-5-B 4.1, andJAN-4-B-4.1 remained at 0 amp throughout the Accident Test. Some leakage'on these;four test specimens was
~
indicated during the first 90 hours of, the seeident profile; however, all returned to 0 and remained there throughout the femainder of the test. A plot of these indicated leakage currents is shown in ' Appendix II, Figure III-10. -l Close examination of the data revealed _that all four indicated leakage I currents, although different in magnitude, exactly shadowed each other over the indicated time. In addition, all ' indicated leakage currents were less than 100 milliamps. The leakage circuits were setup and calibrated to measure from 0 to 1000 milliamps with an accuracy.of.&20 milliamps. The leakage circuits for all of the test specimensNere checked by Wyle technicians, at several points in the test program, and it'was determined that the leakage circuits and their associated DAS chann'els were calibrated and operating correctly. Based upon the above information,KitJwas judged by Wyle personnel that the indicated leakages were a: result 'of interference impressed on the DAS channels although it could not be reproduced for verification. Data Sheets indicating cthe chemical spray solution PH and flow were generated during the 24-hour period of chemical spray and are presented in Appendix III of this' Section.
~
A typical printout of the data monitored, by the Fluke Datalogger, during the Accident Simulation Test is provided with a data printout legend in Appendix j III of this Section?' ! 1 Plots of the Accident Simulation profiles (required and actual), including the Post DBE Aging period, are presented in Appendix II and are listed below: Figure III-1 is a plot of the " trial run" accident simulation (Thermocouple 1,2, 3 and average temperature plotted). Figure III' 2 is a plot of temperature and pressure for the " trial run" accident simulation. l Figure III-3 is a plot of temperature and pressure for the test specimen accident simulation (with the required profiles included for reference). WYLE LABORATORIES ! Muntsvine Facahty I _ _________________-__-_-__l
Page No. III-6 Test Report No. 17905-1 3.2 Accident Simulation (Continued) . Figure III-4 is a plot of chamber temperatures and pressure for the first 19 minutes of the Accident Simulation. Figure III-5 is a plot 7f chamber temperatures and pressure for the first 160 minutes of the Accident Simulation. ;g Figure III-6 is a plot of chamber temperatures and pressu\re for the first 15 h hours of the Accident Simulation. 4622D% m a-Figure III-7 is a plot of chamber average temperature with the required profile included for reference. 4 ; Q7 cc. Figure III 8 is a plot of chamber pressure for the Accident Simulation with the required profile included for reference. g '
.a}Q fr Figure III-9 is a plot of chamber average temperature and chamber pressure with the required profiles included for JeferenceS$,
MA 7 Figure III-10 is a plot of the recorded'lenkage for Specimen Circuits 16,17,18, I and 19 during the Accident Simulatio~n. "'E f&x Figure III-11 is a plot of the recorded) leakage for specimen circuits 16, 17, 18, and 19 for the entire Accident:and Post-DBE Aging period.
%g '%/
Figure III-12 is a plot of the-recordgflow rate of the chemical spray during the 24 hours of operation.ff*"h N ,i D 3.3 Post-Accident Functional Test! Q k Data Sheets generated during the Insulation Resistance measurements, with the specimens at ambient' temperature and again with the specimens submerged in tap water, are presented in.. Appendix III of this Section.
._N 1
Cable Specimen AN-1-B-1.1 did not indicate an Insulation Resistance reading of greater than 0.5E6 ohms (equipment minimum limitation) when submerged in tap water. 'The-voltage was decreased until an Insulation Resistance of 1.0E5 ohms?at 1.3VDC was measured using a Fluke hand held digital multimeter. ThE' water was drained from the test chamber and the Insulation Resistance N wis missured to be 6.6 Ell ohms at 500VDC. Upon inspection of the specimen % cable, a hole in the shaved area insulation was found. The insulatio'n thickness in this shaved area was tested, by TVA personnel, and determined to be 2 mil or less thick. It is probable that the attempt to measure Insulation Resistance at.500VDC caused the cable insulation to breakdown in the submerged test. At TVA's direction, the damaged section of the cable specimen was removed in order to allow further testing of the remaining shaved sections of the specimen. l l N ,_YLEW LABORATORIES . . _ . . '
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. Test Report No. 17905-1 3.3 Post-Accident Functional Test (Continued)
The measurement of the outer diameter of each cable type (not in a shaved area) was compared to the pre Accident recorded values and it was determined - that the Accident conditions had no apparent effect on the diameter of the cable specimens insulation. The recorded measurements of the cable types outer diameters are presented in Appendix III of this Section. (.. g, 3.4 Appendices n The data recorded from this portion of the test program is ' presented in the Ddh Appendices as noted below: c g?g ~Y2h,, o Appendix I contains Photographs III-I through III-22 which show " trial run" tests, test specimen configuration, test equipment, and the AN-1 -B-1.1 specimen breakdown point;(as . a result of Insulation Resistance measurements). N_';. - 1,. 4: o Appendix II contains Accident Simulation plots (Figures III-l through. III 9) which indicate temperatures:and pressure for both " trial run" and actual profiles. Specimen Leakage Plots (Figures III 10 and 111-11), as discussed previously in this Section, are included along with a plot of chemical spray flow ratef (Figure III-12) for the 24-hour period of ff chemical spray operation. iu Ap%.6g o Appendix III contains the.-Data Sheets / Data Printouts generated during functional tests, cable _ thickness measurement and the Accident Simulation. /M N o k l??f Appendix IV contains ^ Instrumentation Equipment Sheets required for the conducted tests., N.A-3 f.- fw,
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/? u%9 ACCIDENT SIMULATION PLOTS OF'". TRIAL' RUN" AND ACTUAL PROFILES. LEAKAGE PLOTS.:AND A TYPICAL CIRCULAR CHART OF THE'3CCIDENT' RAMP AND INITIATION OF CHEMICAL. SPRAY Q.,,fd ./@
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