ML20064B840
| ML20064B840 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/31/1975 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20064B837 | List: |
| References | |
| NUDOCS 7810110147 | |
| Download: ML20064B840 (52) | |
Text
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Report c . TESTS OF RAYCllEM Ti!ERMOFIT* INSULATION SYSTEMS UNDER SIMULTANEOUS EXPOSURE b. TO llEAT, GAMMA RADIATION, STEAM AND CilEMICAL SPRAY WillLE ELECTRICALLY ENERGIZED Prepared for ( RaychcIn Corporation Menlo Park, California January 1975 LPOR.
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000 Tile FRANKLIN INSTITUTE RESEARCll LADORATORIES
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-
- CONTENTS Sectinn Title Page 1
1 INTRODUCTION TEST SPECIMENS 2 2 3 TEST PROGRAh! 4 3.1 Pretest inspection and Preparations 4 3.2 Envi onmental Test Facility 4 3.3 Electrical Energizing 5 3.4 Instrumentailon 6 3.5 Combined Radiation and Thermal Aging Exposure 6 3.6 Loss-of-Coolant Accident UDCA) Environment 6 Exposure ( 3.7 51andrei Wrap and High-Potential Withstand Tests 6 4 TEST RESULTS 7 4.1 Prctest Electrient Measurements 7 4.:: Combined Radiation and Thermal Aging 7 4.3 LOCA Environment Exposure 7 4.4 Final inspection and Electrical Tests 7 5 CONCLUSIONS 11 G CERTIFICATION 12 AITENDICES f I a O ill
~
FIGURES Number Title Page 1 Coaxial cable splice with Raychem Thermofit 8 3 heat-sbrinkabic tubing splice cover (Raychem photo 206-82E11) 2 View of typical metal grounding mesh over 3 splice arca (FIRL photo 11 2848-2) 3 Pretest view of specimens on mandrels with 4
, head nttuched (FIRL photo H 2848-4) 4 View of test vessel with specimens installed 5 (FIRL photo H 2848-5) 5 Diagram of test vessel showtng sa!!ent features 5 und location of thermocouples 6 Electrical loading circuit for energizing specimens 5 7 during environmental exposure 7 View of cicetrical energizing cabinets 5 (FIRL photo H 2847-7) 8 Temtersture/ pressure profile for simulation of 6 lowof-coolunt accident environment 9 Mandrcl being wrapped with a specimen fo!!owing 9 .
removal from test (Raychem photo 206-82Z28) 10 View of high potential withstand testing 9 . (Ituychem photo 206-82AC1) 11 Post test view of specimens on vessel man'drcl 10 (FiltL photo II 28G3-4) 12 Close-up view of specimens on test mandrcl 10 (Raychem photo 206-82W14) 13 View of one splice in specimen 13 being flexed by 10 fingers (Raychem photo 206-82AG23), 14 View of one splies in specimen 13 being flexed 10 around mandrcl (Raychem photo 206-82AG25) 15 View of method of high voltage testing of splices 11 in specimens 13 and 15 (Roychem photo 206-82AE36) ORegletcreu Trademark Raychem Corporation iv ,
_ _ _ _ _ . _ _ . . _ . _ _ . -_ ._m .. _ . _ . . .__ - . _ _ _ . . . . _ _ _ _ . . - _ . . - - .m .
.i ,, s TADLES i
Number Title Page O 1 Test Specimens 2 2 Summary of Insulation Resistance Measurements 4 Electrical Loading Results 8 3 4 Results of Mandrel Wrap and High-Potential 9 Withstand Tests 5 Results of Additional Testing 11 i t i l, f
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'1. INTRODUCTION During the S/C/R portion of the program, the specimens were exposed to un additional gamma radiation dose of 1.5 x 10' rods. The specimens, were also electrically Six specimen loops containing in total two Thermofit # cnergized during the S/C/R exposure. This exposure in cimtninment transition field splices und 25 Therm- simuluted the in-contrinment environmental conditions O ofit in-line field splices submitted by Raychem resulting from a postula.ed Loss-Of-Coolant Accident were subjected to nn environmental scal program (II)CA) in a generating plant inving a boiling watcr based on the guidelines of IEEE Standarum 323-19743 or pressurized water reactor, and those occurring und 383-1974 8 to determine their suitability for during the cooldown after the postulated II)CA.
serviec within the containment of a nuclear power The electrical integrity of the specimens was evalu-generating station. ated by:
' The test progrum commenced with u seven-day 1. Insulation resistance measurements combined thermal and radiation aging period at 150*C 130 *F) and 5 x 16 rads gamma radiation 2. The ability to maintain electrical dose while the specimens were electrically energized, loading during the test cycle The thermal and radintion period was followed by a simultaneous exposure to steam, chemical 3. By high potential withstand tests spray and gumma radiation (S/C/t ). This exposure performed after bending at the con-was as (0!!ows: clusion of the ' wposure.
1 An initial dwell at >177aC (351*F) at a steam The program was conducted by The Franklin pressure of >70 psig for 10 hours. Institute Research Laboratories (FIRL) during the period of December 1974 through January r r 3
- 2. 4.5 riays at 135'C (273*11 at a steam pressure 1975.
of 31 psig. q t
- 3. A ::6 day dwell at 100'C (210'F) at a tca:n/mr pressure of approximately to peig.
0 s, 1 U. M 1 l , _
t a . . 2 TEST SPECIMENS tested and also shows the energizing voltage and curmr.ts levels. Table 1 presents a description of the specimens Table 1 Test Specimens Specimen Electrical Loadine Voltage Initial Current Description
- Numleri Irneth (ft/ (Vrms - 60 Itz) (Ad Raychem ThermoSt S In-Containment DX 20 600 0 Field Splice Cabic - Raychem Adverse Servico Coaxial Cable. AWG 22 conductor 1st lasulation layer - 8 mil wall of Alkano-imidu polymer 2nd insulation layer - 43 mit wall of Rayolin R" radiation cross-linked polyolefin Braided Copper Shield Raychem Flamtrol" Jacket - 34 mil nominal wall Part No.10481 f
- Run No. J7-5-10-72-6 Splice Components for one splice Raychem ThermofitS WCSF-115-G-N Soldered connection (See Figure 1)
Raychem ThermofitS In-Containment 13 35 2000 70 Field Splices Cable AWG 4 insulated with EPR- g neoprenc (net a Raychem product) W Splice Components for six splices (Note 1) Raychem Thermofite WCSF-200-6-N 2 cach of compression connectors: Burndy !!ylink YS4C-L T&D 2F-4 3M e4 Raychem ThermofitO In-Containment 14 37 1000 65 Field Splices
% Cable AWG G insulated with Raychem Flamtrol" Splice Components for six splices (Note 1)
Raychem WCSF *2 00-6-N G each of compression connectors: Burndy Hylink YS6C-L Raychem ThermontS In-Containment 15 32 2000 25 Field Splices Cable AWG 12 insulated with EPR neoprene (not a Raychem product) Splice Components for six splices (Noto 1) - - Raychem WCSF-115-6-N
' 3 each of compression connectors:
Burndy !!ylink YSV10 T&B 2C-10 Raychem ThermoDt9 In-Containment 16 33 1000 25 Field Splices. Six splices, p. Same construction as Samplc #15 %r except that Raychem Flamtrol" wire - as used 2
l i l Tubic 1 Test Specimens (continued) Specimen Electrical Inading Voltago Initial CurrcA 0 Descri tien- xamsert 1 nees
. 2 cach of compression connectors:
r ,
, Barndy Hylink YS6C-L \
8 and
- Trademarks of Raychem Corporation
- Description of specimens provided by Raychem i Specimens 1 thru 8 and 10 thru 12 were cther test specimens supplied by Raychem. '1he test results on these specimens are parsented in report numbers F-C4033-1 and -2 8 Specimens cut to lengths shown. Appruximately 4 ft of the length extended outside of the test vessel C! ft on each end of the specimen).
# Initial currents were applied at room temperature, and allowed to drop to a lower Invel during com-O-
Luned radiation and thermal aging and simultaneous LOCA-simulation testing. See text for discussion. Rte 1 - Each in-line splice or transition was covered with tinned copper wire mesh to aid in providing a close proximity ground plane as shown in Figuru 2
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Figure 1. Coaxial cable splice with Raychem Thermofit heat-shrinkable tubing splice cover.
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3
- 3. TEST PROGRAM The insulation resistance (lit) of the specimens was measured with a megolunmeter at 50%*
3.1 PRETEST INSPECTION AND PRl:PARATIONS de opplied for one minute. Then the flanged hind with the mandrels and the specimens I '- The specimens were visually inspected upon attached was installed in the vessel. ' receipt. identified with stainicss steel tags. and wound onto two concentric mandrels 3.2 ENV!!!ONML:NTAL TEST FACILITY (Sec FIRL reports F-C4033-1 nnd -0) ns shown in Figure 3. The mandrels were The pressure vessel for the test was a 24-assembled with the Danged head of the 24- inch diameter by 48-inch steel chamber with inch diametcr pressure test vessel and the a flat flange head. in which there were penc-cables were passed through pressure-scaling trations for the specimens (Sec Figures l glands in the vessel head so that electrical and 5) . A perferated steam inlet pipe extended measurements could be made and electric - about 7 inches down from the center of the louds applied during the test expo.vure. heud flange; this was surrounded by a cylin-drical baffle that prevented direct impinge _. g q < g..g , fy ment of steam on the specimens. f V
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% W(" A spray system was provided to spray the
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- specimens uniformly nt un nyeruge rate of g" ' N.2- 1r p glJ%y,9 0.15 gallons per minute (gpm) per square
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foot over the cylindrical area approximately r '
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e was accomplished by locating four wide-
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** . angle sprny no::les at each of two loentions
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along the axis of the mandrel. The spray
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A. . was directed radially outward, part of it h(f.];,. V I ? i'7 G
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'* i '; impinging on the specimens mounted on the 1" . b' (. -> ' ' inner mandrel and part of it passing thrvugh
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b l. 8L the spaces between cable turns to im;>inge
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, .. .e mandrel. If it is assumed that the spray -
is uniformly applied to the interior of an (T , d-Qp;,je;p 2 M $ -..-$ m,gg;h. *g7yy,,; w.r,.. g M 1, . , g , T -' imaginary cylinder midway between the
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33-inch long inner nnd outer mandrels.
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' li 1 J e _-7 .ts.n rz pu e l"r t) 0.15 gpm per square foot is equivalent to
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. - - a total rate of 1.04 gPm. A rate of 2.5 gPm t=ay 'f.7-t-- - . * , " - g
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mately 0.31 gpm per nozzle) .
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The spray solution was collected in the bottom
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g!f.I"'ts[IW.e--@h!.'" 0.h,I h.- h ,- as required. The spray flow rate was mens- I
-.. _ 1 M ured with an orifice plate flowmeter.
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**# D components was installed inside a radiation j 3 #-M Y $ hot cell approximately 6-feet x 11-feet x 1
% 'rDfiNU.TrhI 9-feet high. The cobalt-60 source consia,ted
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of pellets packed in CO-inch long pencils and arranged into a vertical cylindrbN T.rb.$ts/, *rt'.ht""2 rf;c
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array which was moved around the vtuct i during the test to achieve a uniform exposure. Figure 3. Pretest view of specimens on mandrels. J l J
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't- .w it ! Figure 6 is a diagram of the typical energizing
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.. <[.y [1 7 fh ., ', ed initial current loads. Current loads were adjusted to the initial specified values of
{,Fr' ? 'I 'i V[y , Table 1 prior to the start of the environmental
' q q, { exposures. With the specified current the
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, ;j voltage drops (resulting from conductor l
3 resistances) through the test cables and
~ "l ' i shielded extension cables were measured 1{3 and recorded. Thereafter, the currents
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were adjusted as necessary to reestablish the initial voltage drop. The actual currents a.,. , , , . were recorded periodically as part of the f/- ~._ u ' -. . sr-test data.
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This method was specified by Rayr' hem to
, be 'n accordance with IEEE Standard 383-
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1974. Parngrnph 2.4.3.1. which states, L . , ,.* P We ,i, ... J "....they should be energized at rated voltage f i ?, I and loaded with rated service current while under the average normal operating condition."
- Figure 4. View of test vessel with specimens installed. j sntLesg Co8e0UCToA
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g C. _' is , For 1/conduetor cable, Spect-nwn 13,14,15,16 and 17 For 1/ conductor coomtal cable, Specirnen 9X. a s- V, and currents per Toble 1 V = 600V rms. Current = 0 A.
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1 Figure S. Diagram of test vesect showing sa-lient features and location of thermocouples. i
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.. &f 3.:) ELECTRICAL ENERGlZING .
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t Shielded extension cables were run from . the exterior of the hot cell to the top of ths , 3 vessel; and connections w. re n.ndo at this , J point with the ends of the maa% ens which r ** re-w:::t P-'u [ 0 extended above the vessel. 'The stitelding 3 t -- ,. -{' on the extension cables served to reduce the effects of radiation on mcoeurcments Figurc 7. View of electrical energizing cabincts. of insulation resistance. 5
m 3.4 . INSTRUMENTATION 3.6 IDSS-OF-COOI. ANT ACCIDENT (IDCA) ENVIRON'. LENT EXPOSURE Chamber temperature and pressJre were monitored continuously on strip-chart Following the combined radiation-thermal h recorders. Thelocutions of the thermocouple oging exposure, the specimens were simul-junctions were as shown in Figure 5. taneously exposed to steam, chemical-spray und gamn'a radiation (S/C/R) as illustrated A list of ths data acquisition instruments in Figurc R. used in the test program is included as Appendix A. A chemical spray consisting of 3000 ppm boron as boric acid. 0.064 molar sodium Radiation Dosimetry dots are included as thiosulfate and adjusted with sodium hydroxide Appendix B. ' to a p!! of 10.5 at room temperature, was applied at the rate of 0.15 gpm per square 3.5 COMBINED RADIATION AND TilERMAL ACING foot (100 ml per second per square meter) EXPOSURE of spray area (See Section 3.2). Fresh heated spray solution was used for the first hour The specimens were electrically energized of the profile. Thereafter. the sprav solution as stated in Section 3.3. while simultaneously was recirculated from the reservoir at thermally aged at 150*C (302*F) and irradiat- the bottom of the chamber. The pit was ed to an air-equivalent dose of 5 x 10' rads. monitored periodically, and was maintained The vessel was electrically heated. During within the range of 9.5 to 11.0 by addition this exposure air was circulated through of fresh solution. the test vessel by an external blower. Insu-Daring the S/C/R cxposure, th.* :<pecimens
~
lation resistance measurements were made during and after this exposure, were energized as indicated in Section 3.3. Note: An air-equivalent dose means 3.7 . MANDREL WRAP AND ll!Gil-POTENTIA!. that the volume occupied by WITilSTAND TESTS the specimens receives an iso-fropic flux of gamma rudiation equivalent to the radiation dose . After the S/C/It exposure, before the test vessel was removed from the radiation hot g that would result if the volume cell. It was filled with tap water and insula-contained only air. tion resistance measurements and preliminary T H E R M A *. , AC:NG B LOCA $1MUL AflCN INCLL;0tNG A&DI Af 80N o EACIAfsoN l 400
\ 200I
' 3S1** tast*C1/* 10 ps.g wtTH"s 5 MtNufE5 350- .
y r-en:Ci TS*F/te r-eq t*,tSo- ;; 3007 ::35.g h i 8 8 I 2So - 230*F/fo sseglNIN) y E 2I2*F/-to pse g 2 I b 100*C) t U no $U % 2co - h IN5tlL Af 8oM PL585TANCE MCASUREMENT
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pl40*F PREH( Af 84o.3--.- A ADI Afl04 CAMMAAAD Aft 04-ItovaA05 So SoM* ADS t - 1 e io s e so 4 1 4 m
"*--168 H ouHi---* , ?.Lc MIN HH DAf$ DAf$
t 7 oavsl T t M C --*- Figure 8. Temperature /nressure profile for simulation of loss-Of-Coolant Accident environment. s ~ 6
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Post-tcat inspection and performante
' high potential withstand tents were mado on all specimens at ambient temperature. test of the spray nossles indicated The test vessel was drained, the mandrels only three of the eight nozzles with the specimens were removed from the t were sprayingt. Therefore. the O vessel and the specimens were visually in-spected. The specimens were then removed spray rate was in excess of 0.15 gpm per square foot of area in front of the working nossles.
from the vessel mandrels and bent around Since the three working nozzles test mandrels 40 times the cables' diameter. The specimens (still coiled from the test were in the upper portion of the chamber (See Figu: e 5), there mandrel) were immersed in water and sub-jected to a high potential withstand test is ressonable assurance that the-for five minutes at the voltages shown in impinging spray splashed and Section 4.4. flowed onto the lower cables.
- Clogging of nozzles and filters and replacements of spray
- 4. TEST ltESULTS solutions are not unusual occurrences for FIRL conducted .
tesis of this type. 4.1 PilETEST ELECTRICAL f.tEASUREMENTS 1The chemical spreys sena The results of insulation resiutunce mamsure- to vaporize into steam when
- ments are presented in Table 2. exiting the nozzles and leave chemical deposits leading
, .2 C011111NED RADIATION AND TilERMAL AGING to possible clogging of spray nozzles.
The e pecin ens were exposed to the aging environment described in Section 3.5. The The specimen energizing data and the re-average temperature near the specimens ' sults of electrical tests made during the approximated or exceeded 150'C (302'F). exposure are summarized in Tables 2 The specimens maintained the c!ectrie loads and 3. "3 h demeribed in Seetion 3.3 und Table 3. Insula-tion resistance measurements are included 4.4 FINAL INSPECTION AND ELECTRICAL TESTS in Table 2. Immediately nfter the S/C/R exposure, the LOCA ENVin0N311;NT ENPOSURE test vessel was filled with water, insulation
- 4.3
' resistance measurements and one-minute Tne specimens were exposed to a simuttaneous high potential withstand tests were made , n team, chemical-spray und radistion environ- at ambient temperature before the vesse! ment in general accordance with Figure 8. was removed from the radiation hot cell. I. 3hnor deviations occurred as follows: The results indicated that all specimens t except 13.15 and 1G were capable of with-a) The temperature of 250'F was standing appropriate high-voltage test obtained in 25 seconds instead potentials, of 10 seconds. After removal of the vessel head and speci-The tempernture drop from 357*F men mandrel from the vessel, further ding-b) nostic tests indicated the insulation on speci-to 275'r was accomplished in two hours instead of one hour. men 16 was faulted in the area of the chamber penetration. This specimen was severed After nine days of the S/C/R envi- immediately below the penetration before c) conducting the finalinspection and electrical i ronment, occasional clogging . of the spray no:zles and filters tests . from ehemical and other depo-sits (possibly specimen materials) The results of the mandrel wrap tests caused spray rate reductions *, and high potential withstand tests which which were periodically corrected followed the 30-day S/C/R environment by cleening of filters and two are included in Tables : and 4. Figure 9
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' O solutions, with a specimen. Figure 10 shows the high-7 s
Table 2. Suminary of Insulation Resistance Measurements Insulation resistanec (ohmg)* sif alwimen numl=.r A g , IDCA Temperature Pressure 9% 13 14 15 , 17
'l lm e (*F) (paig )
Pre-Test Ambient 0 >1.0x 10" 1.5xtui' 5.0x1058 4.0x10" 2.5x1013 5.5x10" Amtnent o 2.7m i n" 5,unin' 2.7x t u'8 1.2m ist" 2.12 8 p" 5.9xle" ' Note b 302 0 1.4x10' 7.3x10' 3.5x to' s5.ex to'9 d .0x 10** 4.7x10' 262 0 6.2xt0' 4.#x t p* 8 5.4xin* s5. th l t,et J .uxto*9 6.5x10* 8 140 0 1.5x10' C.0x10 ' 7.cx10' 4.0x10d 4.0x108 ' 6.4x10' 120 0 1.4ala' .5.ex to'l n.5xin' s5.nz lu4 %5.c m in't is .ex t o' 2.2 hr 353 130 1.5x10' 4.0x 10'S 2.ox108 4.ox10'l <l.0x10'l 1.0x10' 9.2 hr 358 135 1.5x10'
- J .ni g o'l 1.2xlpe ,.l.nxtn't ..l.038u83 4.5 min'
' 14.8 hr 275 31.0 1.5x10' *3.Da t o'l 1.4x10' <1.0xlU'l d .0x10'l 5.0x10' 4.0 da 274 J1.0 1.0x10' *3 . 0x i n*I 9 5:10' <t,05104 ..1.ns t n't 3.3xin' 4.1 da 212 6.3 1.salo' 4 .Uxtus5 ' 5.0x10' st .ex tu'l st .Ux10*l 2.2x10' 7.9 da 212 11.0 1.5xto' <1.0xins t s.psto' <l .0xin*I 1.oxin't I.9slue 13.6 da 220 10.0 1.7xto' st .nx io'l 4.2xig' s! .ex tu*5 <! .cxicH t.2x10' 17.0 da 212 12.n 1.6x10' <l .cu l n'l 1.4x t ee l , g ,,, g os t .,.l .ns in't p.9 lo' 21.6 de 212 12.0 1.6xto' <l . 0x 10'l 2.6 x t 0' O .Dxto'l <1.0xto'l 5.5x10' 24.8 da 212 15.0 1.7x10' *J .0m in't 2.5xt0' 4 .0510'l 3.5xin4 4.3sto' 23.5 de 212 15.0 8.0xth' *1.ca tu'l 2. ! auto' .:t.inslo'l l.exlu'l 4.oxto' INat Tcut Amtnent 0 3.0mlu" Note e 1.4x10' Nuty d <1.0x 10'l 1.tx10' E NOTES:
'Aleasurements made at 500V d-c helst far one sninute unless otherwise indicated.
Sleasurements made during the combinal radiation / thermal acing and SIC /R include the Ill e6ccta n( the te t extensioen len.Is. Tin. lit .4 a etummy wt .4 extension leads me:anured as low as 1.5x!U' chms. bDuring combined Thermat .arul 14a.liation aging. C 11eowrement not risde, dalvusurement wais nnt made. .ee T.ible 4. Section 4.4 asas 5. for lumt test daelectric wathstand data.
'Messurements at 10V d-c lateasurementa et 50V d c Table 3. Electrical Loading Resu'ts .
Actual Icrergirin:: Current .'M
- 1:ncr.12 int; ,
5preimen Vcitasy Conductor Room At At At At* Ahllity to Ifold Electric Imad Number Nrm 9 l'em n 3r* l* 353* F 27*.* I' 212 t' thrine ?ti. It Wposure SX Con i No eurrent fiel.1 lu.ul for 30 da3 w 13 2004 1 in C.1 o o e inml rrmweet aller 3 dau .nsring rumbirwil radiation' thermal agtne armf lx fore S/C/R.T 14 1000 1 65 31 f.'s 60 C2 llelit lo:nl for :h) days. 15 2000 1 25 0 0 0 0 Imad removed sRet 30 mirades during rutnideel radistinn/ therm:al a.dne armt Isciurc S'C/R.? 16 1000 1 25 0 0 0 0 laimi rem.ned afict 1,5 dn re eluring etd14ned raillstion / thermal aging amt lefore S/C/R.' 17 1000 1 AS 31 Sa ,;0 02 lict 1 load for 30 days.
*5 ice corstant.vnitace drnp unell.nl diacum=1 fn .%velan 3.3
- Rated service currents are not requires! tiuring it'e thermal aging phase' '
Reduced currents prevented best input (resistive beanng from current Inastinr) frnm erreewling tent lammen. hice bection 4.4 and T for discusslun of results. 8
Table 4. !!caults of Mundre! Wrnp nnd Iligh-Potenti31 Withstand Tests. fiumber of %1thstand %1thstand Cable Mandrel Mandrel
- 0. I). O. D. ta Cabin Turna nn lwtential' 11onential o n.) fin.) O.D. Ratio M andrel__ Visual Arrearance of Cable (Vrrne P.esult s C able 39.6 2. 5 Cable flexible. Spbce intact. 2000 %1thstood potential for 9X 0.24 9. 5 5 min. Charging / leakage Cable surfaco crinkled current less than 10 saA Jacket falling off in large O Could not be era,rgised 13 0.413 Dend test not condu. .ud.
strips; insulation cracked due to faulted cable through to conductori insulation
- sphcos apparentlyintactI 7.5 Cable flexibles surface pitted; $000 Withstood potertial for 14 0.277 Il 39.7 surface cracks in some areas. 5 min. Charglag/ leakage Sphces appear intact; marldng current less than 10 mA sleeves intact with some surfaces crtnkled.
Jacket and insulation brittle O Could not be energized 15 0.190 Dend test not conducted. and fa!!!ng away from con- di. to faulted cable ductors ute gauge breaking insulation away from splices. Splicos apparently intactI 33,9 10.5 Metal gauge over sta-splices 3600 Withatnnd potentla! for 16 0.18A 7.5 weak and brealdrg 05; mart- S trJn. Chart. 'ag/ leakage
- . fr.g sleeves intact and finxible current less than to mA 3.5 Cable flexible; metal gauze 3600 withstood potential for 57 0.279 11 39.4 s
over splices weak and breaking 5 min. Charging /leakate off. 1;o apparent d.tmage to current less than 10 mA cablu or himic splaceI 18otent121s we re awlied between the cable cormluctors and a 5*,-gal metal drum of room tempernrur, tap water (at ground potentiall in uhach the ta'nt scutled) 5crtion of the cables was imrnersed. Conductor shields, if present, were at ground poten:1st. i.%v Sertion 4,4 for fliticussion. A h W,,r,,, g % V 7 ,3 . 4, 4
%;yh. I ,;
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e . s 8 p a. s . -5 e, g. 3 (43 j.g , - - N, _.y .A* Figure 9. Mandrel being wrapped with a Figure 10. View of high potential withstand testing. specimen following removal from test. 0 9
l potential withstand test. Post-test photo- Q g.f Q,;, -- ~ - . .*** Q,';jp'P.".jQT*'*(.'t graphs of the specimens are presented as . j,y,. '.f yy .; } Marinwn la - In line vpfiw W.sy.f
- 3. ; cowrrd u a h incial in. h p.
Figures 11 and 12 The specimens werc . . r0 turned to Raychem for additional testing N, d'tj 7.b @ 8- N 'II*37
.,.g,*,'.969~.w, a r -
-. . M *7Eb'I'~~ E D ~b.'hig -
se.
/'\
t1
- m. rs;;.. ny.-- .
- p -
_- Ju.%_ ._. 5:p.gW by Itaychem. ,
- 0 --** .
Subsequently. specimens 13.15. and 17 were p, -- . m M
.m
-~~"
'[' ,,
~~~ ['
returned to FIltL by llaychem for additional .e~~"' f" *'#I""" " g~ M,, . a. , ' examinations and tests of the splice arens. M 4[M# M.] MP @,..- a e b J'1
*~ ' <
A The splice areas were cleaned. Some of . %.e s ".s N'. .: i.l the cplices wem flexed both with Dngers.
}, .' r# p%..
a--- -- W-i: i
'# "' m 4W. - I as shown in Figure 13. and aruund a' mandrel .-e:-:.
y u m.,j, g g ;gic:. A " m ...-yy,iamah;4g
~45-- r*
na ghown in Figure 14.' .'*,.g r.G:?w. . - - <. ;6..g . . -r' N::'M
!!!gh-potential withstand testing of the splices CA('.
y*j g' M ,E; F'.;- , M ~J.~. N arr. T'"*',,. ,,, ,j s" M'. h .i.: s-W
.e.c;th,, t<
h ..-:[ g ${l' y.ijjf / ***.,g
.5 -- .
was performed b./ wrapping the splice with ,m.a. y" , u.a .t. g . 1 e wet cotton cloth saturated with water ;a;d! n: t. . ,g".c, p.2. pr.,...j ; ,.,';,..'
* *v
~~^
sh., .T., c t' cs the ground electrode and then hending s-p.... ". N=w men 1 t r. int iii. v the splice around the curved surface of c, 23 L .F'g.:; , g n mi N m. a -
.. d e test mandrcl as shown in Figure Irs. A lc ' ,.%.,.' --...u-high potential was applied between the OO'~d. l c2 h, m.
- c -
i3, - .
, b...
c:
..h M rr
. : ", N .:-- .7 -
- p. ,.J s w . .
- 3'
. ,..c, , ,
**b; ;, . . -
, specimen conductor and a bare
-d --
per wire v rapped around the wet cloth. Figure 12 CIO8e-u? View of SPeeimens
\ e results of these examinations and tests n test mandrcl.
are presented in Table 5 _ _ n.. 3,-c--,. r- - .
;y . ,&. .,.]
w i *:
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r
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. M*. ' q D m ==#; .; ',.-
e. M.EQ W,h'W; .m . t.. . . . .. . .R.. . .,@. ;.=*m,"c' I. ~ i ,@ M.. j:;.J ata)?. A M.s
-_V.,.1.., C . .
.e Figure 13. View of one splice in specimen 13
' ...' . .P'.
.w .
Ed ,D E 7d. .A' s . f, _[WD.,
. ."7.e..%. c. .
1
.a/. being flexed by fingeri.
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Figure 11. Post test view of specimens on vessel l'igure 14. View of one splice in specimen 1: 8 mandrel. being flexed around mandret. 10
Tnble 5. Her.ulte. of Additional Testing
. specimen Mandrel withstand withstand and Sphee O. D. Potential Patertial No,a on3 Visual Appenennre of cable (Vrma)b Romulta 13A 17C 5000 ISB 17C All optices appeared stiff tmt could be bert withnut 5000 All splices withstood 13C 17 e.vklemo s.f e rsu Idng. Ihas apliev was lent to an LOOO gelundal for 6 snia, 13D 17C included angle of 90 without evidsrce of cracking. 5000 Charging / leakage 13E 17 C (Only one splice was bent fra this fashion.) E000 entreats less than 13F 17C $000 1.0 mA 15A 6.6d 4000 Alt splices were flexible. No evidence of cracking All sp!!ces withstood ISR 6.cd poteesial for 5 snia.
- hen bent around mandal. Adbesive which extruded g ISC 66 d from end of splice skere showed separation between Charging / leakage 15D 86 d g cupats less man destve and end of sleeve. (only one sphee was in- 4000 15E 6*6d g d spreted to this lattor dotall.) 1.0 InA g3y 17 -- Wire gauze had Imen rernoved previously. Spuce ma- - cal'.3 mith splicos terial showed no evidence of cracking. Sphce was act provtously tested flexed ag:dn per client's direction . we Table 4 for successfully. See mandrul bend test resuks) tut there was no obviouc Tal.le 4.
Indication that it could not tas (bant agnin wittumt cracking. Splies could be depressed with fir:gerna!!. aSplices artitrarily identsted by suffix letters A through F added to erecimen numbers. bbee Section 4.4 for discussion of method. CMamtre! dianneter to cable-diameter rattu was 41; rnarajrcl-diameter to sphee-diameter ratio was much less (sphee diameter not messarctD. dMandrvi-dl.uncter to calek-diameter raue was 35; mandrel-diameter to spheo-diameter ratio was much loss (sphes diametor not mems'urd), and a subsmuent simultaneous steam. chemical-
,j.c ' (g q Mc '
*.,.31$.'.s: spray und radiution exposure (S/C/R) with an additional 1.5 x 10' rods of irradiation. Throughout
.f.kNY7.I., .a Lhf ,,.p q;l' M P A[ the exposures, the specimens were energized (except V N ): $ 7*[,$..jd) f g [jk{I. specimens which were removed from the circuits) with potentials and currents simulating field service f U !$ M .',.'. Y O 'U d 7.Ne' Y.j $ D '3 .
use. At the conclusion of the above sequence of
, W v.3 3'y g.l'a .
. 'J ',
%.Q .;* Q3 g ,
exposures , esch specimen was subjected to a bend
.w.-p. /MW. ? y y..t @. b. ,M. ..j.?@ m 9,..'y 9 7 c...,yq'.g.r.
and high-potential withstand test.
. v . g f. , r -o.g h, A . Pen.1 - *
.,9{ . E.:el Every specimen except 13.15 and 16 demonstrated m 'k %V.f. WM.d.I j @P 'M [y " ' [ satisfactory performance during the exposures Y y M ]D simulating normal service, a LOCA and associated
[F
'b,.
p:(D* . Qg%a g4 'ld.M; E t *h
,pM;ef couldown; plus demonstrating a substantial margin of life remaining in the specimen by withstanding i . '.z%NI 9 $ N-]*[h 0,h .pj a post-LOCA bend and a high-potential withstand l
,f .' d M N [b h k..-c.f $.,'@E,N g j g . w w .m-M t Jh P$ $i Specimens 13 and 15 failed within 5 days of the l'igure 15. View of method of high e iltage testing start of the combined thermal and radiation
*J splices in specimens 13 nnd 15. oging. Post-test analysis indicated that the fail-urcs were probably due to the associated cable ruther than failure of the splices. Further
- 5. CONCLUSIONS analysis of those specimens determined that the splices were capable of withstanding a high-potential test while bent around a mandrel approxi-Six specimen loops containing in total two Thermofit mately 40 times the cables' diameter. The splices in-containment transition field splices and 25 Thermofit on these specimens therefore also appear to be ,
in-line field splices submitted by Raychem were sub- catable of demonstrating satisfactory performance jceted to a test program bamt e the guidelines of during the exposures simulating normal service,
- 8 and 3S3' The program was a LOCA and associated cooldown; plus demonstrating h !!'EEstesignedStandards 323 ..u . . .:. a. Loss -Of-to simulate norm.ni a substantial margin of life remaining in the Coolant Accident (LOCA) and ths noldown follow- specimen by withstanding a post-IDCA bend and ing the LOCA and included combined radiation and a high potential withstand test with the specimen therm.it uging with 5 X 10' rWs of g.imma irradiation; immersed in water.
11
Based on the discussion presented below. specimen REFERENCES 16 appeared to be cabable of demonstrating satisfac-tory performance during the exposures simulating 1. IEEE Standard 323-1974. IEEE Standard normal service, a LOCA and associated cooldown; for Qualifying IE Equipment for Nuclear plus demonstrating a substantial margin of life Power (icnerating Stations. The institute remaining in the specimen by withbtunding a post- of Electrical and Electronics Engineers. LOCA bead and a high potential withstand test Inc. , New rew k. N. Y. 197l. with the spceimen immersed in water.
- 3. IEEE St.mdard 383-1974. II:EE 8tandard Specimen 16 was removed from its energizing for Type Test of Class IE Electric Cables, circuit ufler 38 hours of combined thermni und g ictd Splices. und Connections for Nucicar radiation aging. However, a post-test inspection Powet- (icnerating Stations. The institute and analysis indicated the specimen was fuulted of gggeg,.ical and Electronics Engineers, '
at the point of vessel penetration and the remaining Inc. , New Yorie. N. Y. ,197.l. portion of the specimen within the vessel was capable of withstanding a high-potential test after being subjected to the required test mandrei bend. In addition. the vessel penetrations probably were not representative of an actual installation in a generating station.
- 6. CERTIFICATION O
The undersigned certify that this report is a true account of the tests conducted and the results obtained. kOlb I. . E Witcher Test Engineer s a D.V . Paulson. P.E . Project Leader 4 APPROVED M QUM -
' enons Zudans. Director W.ll. Steigelmenn. P.E., Manager
- 1. gineering Detortment Energy Engineering Laloratory 0
12
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$$[5 e-.- NOdh:MMih) th!NEY*I5?N Appendix 0
B CERTIFICATION OF RADIATION 0 . 000 THE FRANKLIN INSTITUTE RESEARCH LABORAT
e y e
/
e O O ;- O N011
.._..,B. _. l t .y w.. l.. f.re.. .. i ng . .l .t .. . . tad.1 ,. , ,nt... .t l.g inse rate Meter ord Psal,e. The unit was calibrated on January February 20, 1975 IS, 1984 by the vsetoreen Insta=*wnt Cusapemy, wolag cobalt.69 eat coelue-Il7 sources whose calibrettone ese traceshle to the U.g. Mot ional Dereas of Standards. A ecpy of the cellbration contifieste le evellable. Bioekup desteetry veing a Red Perspew Pr. willlee Stelgelmann eyeare provided by Ateele Energy of Canada. I,td. confirmed the Performente Ovalificat lon I.at,oratosy Victoseen seedings.
FranklBa Institute mesearch labosoferlee nurlag the segwence. Isonedle recorded the Tarlees test parameters * , 20th and Cherry Street and In readings ao designated in your test plan. Ttwene, together Philadelphia, Pennsylvania 19108 with other recorded dat a, were providad to you under seperate cover.
Dear Mr. Stelgelmanne ' span copylet tee of 1ssedletion,
the chenhor wee removed f ree the This will eventalso the ravaretore portinent to the verwnt levedsetor by your personnel et manicin time our role wee reeg*Reted. elmsttaneees steam, cheetcal eptay ape radletion espoewee test condected for the Daychee Corpeny, under your taeject very truly yours. C-eell, . t' '% Test cables were townted on a mandsel by FIPL. assemblei late e pressure eessel, s etalled in t he irrealation eh.ee.er, and ,e d "- Y
- e finorge 3..plets estropriately connected to en electrical load. Irradiation Manager, Sedletion Sereless for the Phase t I day test wee be7sn en Decesber 23,1974anj eencluded om Deceeter 30,3974. Approotmately three days ef ter Emele*****
the start of irraJtetton, we were inattucted to entend the irradiatina over e eine day period, fet still accuselete a CRDake Se neaS average dose. This was acteeplished by moving the source forther free the target lag the romaanleg t i.ne. Trat tag Fhese I, the cablee seeelved a eBaimos does of 40.4 Mrad and masteus of $4.0 nrad. te ese poselble, we utilised the leradiater to procese other psoducts concorrently with the test, whicIt neceseltated oceaeleasi short periode these the gadletion fleid was seda ed to sere. The leg sheet refleeting tiers of so arce esposese le included as tact.1, and the det alle of cour.e peeltleslag, dose rates and tetet dose le shown la rig. 3. These Il of the teet began on December it, 3974 end con-leded on Janeery 30, 197L During the orproutestely 720 heer evposure, cables recelved an adJitional etntmae 4ose of lit.3 nraf and ea steue does of ISS.S Mrad. The Boy sheets soflecting entweere times le in Emel. 2, and d stelle of irradiation in Fig. 2. In eusinery, total doses to the cables over the 39 day period ranged free 197.7 Mred freeltlen F1 to 209.0 maad lpeettien al, witIn en eetleated source positioning error of 9 Se la dose rate. Seessesene tres e se to.ees a.ms,sweses,.ees. ewe ano,_ tioeie.st me.e vos eeeos ee== as-em> ese e==.e t Me8Wh e eSt ense em.. w e.se emmusemeS8,95ED 9ED095e 1 t
A&mgy.g. # f ha-t 2 o f 3 l, . . RAYCEM CORPORATION
. ?RODUCT QUALIFICATION TEST REPORT Product:
EIAT JRRINKAELE FIELD SPLICING SYSTEM FOR CLASS 1E ELECTRIC"CA3LES
- ITPE.tiCSF-N .
*e I ,. -
Specification: ,
. IEEE ST.uTED 333-1974 .
IT*? Standard for Type Test of Class 1E Electric Cables, Field Splices, and
.. Connecticas fer Nuclear Pcver
. Generating Stations" .
- SECTION 2.5 - FLAME TES S
/
- Freparedby:j/
- t. .' [M A/ P ' /-
"R. T. Strombem Technical Services Engineer Ther=ofic Division ,
l f - Appreved by: ,. _ . < -~
. R.F. Kinnune Product Specialist g" -
. Electric Ucilities t - . Ther=ofit Division k) e
- _ . - - - - ... _ . . . - , - ..m-_.---- m -. , , , , - . - - - -
,----,e . -
\ - l l (# 'INTRODUf/ ZION .
- I This report docunents a progrs= of vertical tray fisse testing. The program constitutes a Type Test for qualification of a heat shrinkable field splicing system (Type WCSF-M) for Class 1E electric cables for nuclear power generating s tation's. -
Testing was conducted in the flane chinber of the Raychem Corporation in accordance with IEEE Standard 383-1974, Section 2.5, "Flane Tests". CONCLUSIONS .
~ .
Both spliced and unspliced cable sc=ples were -self-extinguishing when subjected to the vertical tray fisme test with a 70,000 ~ BTU / hour propane burner heat source t as required 'uy ir hos-1974,Sae.cica2.5. !n addition, all sasplas vera self-extinguishing when tested in accordance with IEEE 333-1974 procedures and a 210,000 BTU / hour prrpane burner hest source. On the basis of the test results, best shrinkable'k'CSF-N cenponents are fla e test qualified as a field splicing syste= for Class lE electric cables in accordance with IEEE Sensdard 383-1974. ( .
/ ,'
SAMPLE *DESCRI? TION Tield splices were installed on eight foot. lengths of seven conductor, 12 AWG Raychem 71.mtro1TM insulated and jacketed control c ble utilicing appropriate WCSF-N heat shrinkable splicing sleeves. h detailed senple description is giten in Appendix I. The splices were installed in accordance with Rayche= Insta11ctic-Cuide, Number IG-1060 for.WCSF Type In-Line Multiconductor Field Splices. (, i Q) .
l i Each test run consisted of three spliced cables and fodr identical unspliced chbles to produce the tr,y fill required by the specification. . a
' A 12 inch cable tray with 6 inch rung spacing was used to support the sanples.
Tbc spliced cables f'or a given test were positioned either at the center of the tray or . alternated with u= spliced cables across the. tray. In all cases an un-spliced cable was pla::ed at each side of the group of sa ples. TEST PROCEDUp.E A propane burner, as described in the Standard was utili=ed as the heat source. ylcu =cters calibrated by actual weight ar.d gas consuned were utili:cd to achiave either 70,000 or 210,000 3TJ/ hour gas censu=ption. The burner was positioned , approxi=ately two feet above the bo:::= af the vertical tray with the splices [, located so that the point of fin =e i=pinge=ent was locnted at the icwer end of the splice area. The bur:er-en time for all tests was 20 minutes.
. Separate'240/100 volt failure detection circuits were provided for the spliced and unspliced cable sa=ples. Both vire-to-wire and vire-to-tray failures were indi ste by the circuits. ,
/ Three separate tests were run a: each burner setting utili:ing different sa=ples cf cable and splicing cenponents (Appendix I) to demonstrate reproducibility as t
required by Section 2.5.4.3 of the standard. - D e s O e
\s .
r . . d .
~_ TEST RESULTS t.s - ii)atsforthe70,000 BTU /hourtests(461,462,463) are shown in Table 1. TABLE 1 i 70,000 BTU / hour 71sme. Test Data, Test No.: 16.1. 162 463 ,
~
Ti=c to initial spliced 6-40 9-15 7-30 electrical failure U: spliced 7-45 3-20 8-10 (Min..- Sec.) Ti=e to Ceeplete spliced 7-00 11-20 7-30
- electrical failure 8-45 10-35 8-10 Unspliced 04.in. - Sec.)
. Time to self-i extincuish
\ 12 23 7 (Sec.)
Insulation Ds: ge 18 16 17 Distanca (Is.) 3 Jacket Char 36 32 35 Distance (In.)
/ .
O
'~
g Af . U .
- 6
. . . o o
(s . . Test data for the 210,000 3IU/ hour tests (464,'465, 466) are shown in Table 2. TABLE 2 . 210,000 BTU / hour Fin =2 Test Data Test No.: 464 464 466 Ti:se to 1~d '*1al ' Spliced 5-45 5-55 6-10 electrical failure Unspliced 3-20 . 5-55 5-50 (Min. - Sec.) T1=e to ce=plete Spliced 5-45 5-55 6-10 electrical failure Unsp11 cad 6-10 6-10 6-10 (Min. - Sec.) , T1=e to Self -
'- cr.tinguish .
k,,j (Sac.) 0 0 60 , Insulst' ice D*- ge - 36 43 40 Distance (In.) . Jacket Char 56 46 53
- s. Distance (In.) . ,
/
1 1 . l
=
U l
EVALUATION OF PISULTS g- .
~3e following observations can be made with reference to the above test data und typical test sequence photographs (Appendix 2 - Test 462, Appendix 3 -
Tes: 464):
- 1. All'sa=ples self-ez:inguished and, vere classified as non propagating
- 2. The WCSF-N splices had no effect on either jacket char or insulation damage lengths.
- 3. The splices had no censurable effect on circui: failure times.
.- 4. Portions of splicing sleeves r- 4ned intact on the cable below the flana .
i=pinge=en: point as shown in the close-up photographs in Appendices 2 and 3.
- 5. The 210,000 310/ hour burner set:ing car;ed more rapid circuit failure en both
. spliced and unspliced cables and granter jache: char nnd insuistion dcage lens:h due to the greater quantity of burning gases surrounding the cables.
e
\ . .
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e G O e d O
~
s C
~
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j- . .
- {,- s s 1
. . APPENDIX 7 ,
- TEST SAMPLE DESCRIPTI0 tis ,
IIEAT SilRINKABLE FIELD SPLICE COMPollEllT RAYCIIEH F1.AHTROL CABLE , Jacket Replacement Sleeva Conductor Splice Sleeve UCSF-070-3-N
~
WCSP-500-20-N Run Ho,_ Run No. Run No. j'est No,_ Part No. J14-08-19-74-07 E202(2)/K072(1) Kl82 461 J7TC12B10-01 ~ E202 E102 462 J7TC12 BIO-C1 J14- 08-19-74-06 . . , K072 A093 i 463 J7TC12R10-C1 J14-07-15-74-02 K072 A093 464 J7TC12B10-C1 J14-07-15-74'-02 l E202 E102 J14-08-19-74-06 l 465 J7TC12B10-C1 E202(1)/K072(2) K182 I 466 J7TC12B10-C1 J14-08-19-74-07 .i e
}
) . j ' J '- . l , s . . , 4
~
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9ffhamcur af ht 3 c[3 RAYCHEM n %3 To Whom It May Concern:
Subject:
Addendum Raychem Report #71100, Revision 1 Heat Shrinkable Products for Nuclear Power in order to clarify certain product testing (WCSF), the following notation to subject report should be added:
, All WCSF* type parts tested in accordance with Raychem
's Report No. 71100, Revision I were coated type -N adhesive designated by Raychem type 5-1024. ,
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' Dr. V, Canady V' l
< Thermofit Materip} Development Manager l l j o
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( _ 1, c , i' Lll?'- Al Anderson Market Manager Power Distribution Products g
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*Per our Thermofit Specification #1508 dated May,1974, Revision 1.
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RAYCHEM ' \.1 ABSTRACT Raychem Corporation is in the process of evaluating many of its products for use in nuclear power plant containments. Using the Institute of Electrical
& Electronics Engineers " Proposed Guide for Type Tests of Class I Cables and Connections Installed inside the Containment of Nuclear Power Generating Stations" as the test basis, 5 and 15KV high voltage terminations (HVT's) and 600-2000 volt in-line splices were found to withstand loss of coolant accident (LOCA) conditions of a design basis event (DBE) either early or late in their anticipated use life. HVT's remain usable, having excellent tensile strengths and elongations, even af ter 2,00 Mrads (2 x 10 0 Rads) of gamma radiation in ai r. Properly ' applied HVT's form an envi ronmental seal around the cable protecting it f rom high pressure s team, mois ture, and boric
' FL) acid spray. l (. Thernofi t Report 71100 Revision 1 s~ l te m fd vet . YG'ssshMC*.is&n. s ~
RAYCHEM INTRODUCTION The current energy crisis and increased power consumption have created a demand for more power planu. When these factors are combined wi th our current ecological awareness and the need to prevent additional damage t6 the environment, nuclear power plants emerge as viable candidates to satisfy our power needs. As cf September 30, 1971, 10,040,800 kilowatts of electricity could be generated in the United States by nuclear power plants; additional capacity of 45,779,000 kilowatts were being built; and 51,571,000 kilowatts of nuclear power were being planned l . This growth attests to the increased { . attention being given to nuclear power as a source of energy. While the ultimate purposes of a nuclear power plant are the same as those of a fossil fuel plant, the requirements and demands placed upon electrical insulating materials are different, in a fossil fuel plant, the engineer needs to know M the electrical properties of the insulating materials, how these properties change with time, and the effects of moisture and oxygen upon electrical and physical properties. For nuclear power plant use, in addition to the aforementioned properties, the engineer also needs to know how the materials are af fected by nuclear radiation over a 40 year lifetime. Virtually all organic materials are known to be affected by radiation. In some cases where the radiation can be controlled, the property profiles of many organic materials are improved by exposure to radiation. In these cases, the material is exposed to gamma or electron beam radiation under t i I " Nuclear Reactors Built, Being Built, or Planned in the. United States as of December 31, 1971", National Technical Information Service, Report '4 umber TID-8200 (25th Revision) .
$*# $ 75, M ' O YA7ss h v a n is L n
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RAYCHEM r C carefully controlled conditions for specific lengths of time and a material with an improved property spectrum results. These improved materials have greater tensile strength, greater stress crack resistance, lower moisture vapor transmission, greater elastic memory, in addition to the other improve-ments over their non-irradiated counterparts. in a nuclear power plant, the exposure of materials to radiation cannot be fully controlled, nor can the length of exposure be reasonably controlled. The materials installed in a nuclear power plant must have the highest possible resistance to the long-7 term effects of heat and radiation. In addition to inherent radiation resistance, the materials used in a nuclear power plant must also provide assurance that in the event of an accident, they will maintain their integrity so that the plant may be safely e, (,,) shutdown. This is true i f the accident were to occur during start-up or af ter the plant had been operating for many years. Consequently, materials designed for use in nuclear power plants must be evaluated under accident conditions before and af ter their exposure to nuclear radiation. t Raychen Corporation has extensive experience in the irradiation of ( i organic materials. For over 15 years, our principal business has been the irradiation of organic materials to enhance their balance of properties. Some of the products developed in our laboratories and extensively tested I in use are our heat recoverable high voltage terminations (hVT) and 600-2000v In-line splices (WCSF). This report describes the evaluation of these products
~ '
for use in nuclear power plants. e e W2 2=%". tras h T m idn.m. l \ - - - _ _ - - _
RAYCHEM 3 PP.0 GRAM OUTLINE HVT and WCSF evaluatiens were divided into two phases: materials evaluation and systems evaluation. The materials evaluation consisted of an in-depth look at how the materials of construction behaved as a result of nuclear radiation. Systems evaluation consisted of an in-depth analysis of how the completely assembled parts behaved as a result of nuclear radia-tion and how well it withstood the ef fects of a loss of coolant accident before and af ter exposure to nuclear radiation. ( , The evaluation was based upon the institute of Electrical and Electronics Engineers " Proposed Guide for Type Tests of Class I Cables and Connections Installed inside the Containment of Nuclear Power Generating Stations". The test sequence for materials consisted of: "
.]
- 1. Heat aging the materials in a forced air oven at 1210 20C for 6 168 hours.
- 2. Irradiation of the materials in a cobalt 60 gamma source at 0.52 Mrads per hour to total doses of 100 and 200 Mrads.
The test sequence for assembled high voltage terminations and in-line low voltage (i.e., 600-2000v) splices consisted of:
- 1. Heat aging high voltage terminated cables at 1210 1 30C for 168 hours in a forced air oven.
r
- 2. Irradiation of assemblies with cobalt 60 gonna radiation at 0.50 Mrads per hour for HVT's and .27 Mrads per hour for WCSF to total doses of 100 and 200 Mrads.
- 3. Subjecting irradiated assemblies maintained at maximum rated 9
mETHE&h!TwninLm es l
RAYCHEM D voltage to LOCA tests in a pressurized autoclave according to the following schedule:
- a. 5 hours at 3600F, 70 psig steam.
- b. 6 hours at 3200F, 70 psig steam, c .' 24 hours at 2500 F, 21 psig stean, 0.2% boric acid spray, buffered to pH of 10.
- d. 12 days at 22107, 2.5 psig steam.
- c. 100 days $2120F 2.0 psig stean.
TEST RESULTS
. Tables I and 2 shat the results of the materials evaluation of Raychem HVT's and WCSF sleeves. These data show that even af ter 168 hours at 1210C in a forced air ovan and subsequent irradiation to 200 Mrads cobalt 60 gamma radiation in air, the products have maintained a very high degree of mechanical I ')
s< integrity. As an example the outer hip.h voltage tubing and stress grading noterial have ruintained at least 800 and 700 clongations, respectively. This, coupled with the excellent tensile strengths, indicates that these materials have suf ficient toughness and radiation resistance to withstand ( 200 Mrads gamma radiation. Table 3 shows the electrical performance of 15KV HVT's during LOCA tests. From the data, it is evident that all HVT's, those irrcdiated to 100 or 200 Mrads, as well as those not irradiated at all, are capable of performing during a loss of coolant accident. Applied voltages for the 15KV HVT's during LOCA tests varied between 8.7 and 15KV, phase to ground. Table 4 yields similar data for SKV HVT's. Here again, the Raychem
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O- e RAYCHEM 9 HVT's successfully withstand LOCA tests before and after irradiation. The SKV HvT's were subjected to applied voltages between 5 to 8.6KV phase to ground during the LOCA sequence. Table 5 shows electrical performance of a series of in-line splices i made on 600,1000 and 2000 volt class cable and subjected to continuous maximum cable rated voltages.
SUMMARY
[ Da:a supplied in this report show that when properly assembled, Raychem high voltage terminaticns and in-line low voltage splices may be recomnended for use in nuclear ocwer plants. The assembled terminations and splices have successfully withstood DBE and LOCA tests and remain functional during S the accident. They will perform so as to permit a safe and orderly shut- . down of equipment in the event of a loss of coolant acciddnt. 4 gy*mjgy;; ?Kisuih!"V2,? 1n.ma
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TABLE I EFFECTS OF I;UCLEAR RADI ATION UDON RAYCHEM HVT MATERIALS Outer Stress Tubing Crading 260 236 Initial elongation, % Elongation af ter 168 hours at 126 , 140 121*C plus 100 Mrads, % Elongation after 168 hours at 80 70 121*C plus 200 Mrads, % Initial tensile strength, psi 2290 1560 ( Tensile strength after 168 hours 3025 2015 at 121*C plus 100 Mrads, psi Tensile strength af ter 168 hours 3020 1665
,s at 121*C plus 200 Mrads, psi V Initial hardness, Shore D 43 37 Hardness after 168 hours at 57 50 121*C plus 100 Mrads, Shore D Hardness after 168 hours at 60 50 121*C plus 200 Heads, Shore D k
9 l l I 1
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- RT M 51s H t;'h?n % .
i -
RAYCHEM 9 TADLE 2 I EFFECTS OF NUCLEAR RADI ATION UPON RAYCHEM WCSF MATERIALS WCSF WCSF Slab Sample Tubing Samples @.125" Thickness initial elongation, % 565 440 Elongation after 168 hours at 1210C plus 100 Mrads, % -- 145
- Elongation af ter 168 hours at 121 C plus 200 Mrads, % 100 70 initial tensile strength, ps) 2180 1600 Tenslie strength af ter 168 hours at 1210C plus 100 Hrads, psi -- 1745 Tenslie strength af ter 168 hours ,I at 1210C plus 200 Mrads, psi 1500 1685 .
initial hardness, Shore D 37 43 Hardness af ter 168 hours at 1210C plus 100 Mrads, Shore D -- 46 Hardness af ter 168 hours at 1210C plus 200 Mrads, Shore D 42 52 (
- Tubing samples were exposed to simultaneous heat aging and irradiation Yiian'ih?'CVsili.in.
~
RAYCHEM TABLE 3 I PERFORMANCE CHARACTERISTICS (CORONA EXTINCTION VOLTAGE) 0F RAYCHEM 15KV HIGH VOLTAGE TERMINATIONS I DURING DBE/LOCA TESTING HVT HVT HVT HVT HVT HVT i #1 #2 #3 #4 #5 #6 Initial CEV, KV 20 17.5 20 19.5 21.5 21 CEV af ter 168 hours at 121oC 30 25 25 24 31 19 CEV af ter 168 hours at 1210C plus 100 Mrads 2 15.5 -- -- 14 CEV after 168 hours at 121oC (' ~ plus 200 Mrads 2 .. .. .. -- 19.5 16 CEV af ter 35 hours DBE3 17 15 20.5 21 16 16 '(')
- s.
Notes
- 1. Crosslinked polyethylene cable, conper tape shield, extruded
( semiconductive layer.
- 2. Ccbalt 60 gamma radiation, dose rate of 0.50 Mrads per hour.
3 5 hours at 3600F, 70 psig steam; 6 hours at 320oF, 70 psig steam, 24 hours at 2500 F, 21 psig steam, 0.22 boric acid spray at pil of 10, 12 days at 221oF, 2.5 psig steam, 100 days at 212cF 2.0 psig steam. O m
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TABLE 4 PERFORMANCE CHARACTERISTICS (CORONA EXTINCTION VOLTAGE) 0F RAYCHEM SKV HIGH VOLTAGE TERMINATIONS I DURING DBE/LOCA TESTING
' ' HVI HVT llVI . HVI 115T IIVT
#1 #2 #3 #4 #5 #6 Initial CEV, Ky 4.8 4.2 5.5 5.5 5.8 5.8 .
4.5 4.3 4.6 4.0 4.8 4.4 CEV af ter 166 hours at 121*C CEV after 168 hours at 121*C --- --- 5*2 4*3 -- --- plus 100 Mrads-(_ ~ . CEV after 168 hours at 121*C - --- --- --- 4.2 5.0 plus 200 Mrads-4.5 4.1 4.7 4.5 4.8 (4) CEV af ter 35 hours DBE 3 f} .. [ k Notes
- 1. EPR cable, copper tape shield, tape semiconductive layer.
- 2. Cobalt 60 gamma radiation, dose rate of 0.50 Mrads per hour.
3 5 hours at 3600F, 70 psig steam; 6 hours at 3200F, 70 psig steam: 24 hours at 2500F, 21 psig steam, 0.2% boric acid spray at pH of 10, 12 days at 221"F, 2.5 psig steam, 100 days at 2120F 2.0 psig steam. 4 Specimen mechanically damaged before being placed in autoclave. [ 9 . m=x=v:. fis7 5 Yh M % n .?!! L m
RAYCHEM O TABLE 5 PERFORMANCE CHARACTERISTICS OF RAYCHEM 600-2000 VOLTS IN-LINE SPLICES TYPE WCSF DURING DBE/LOCA TESTING Per. Table 2 Aged 168 Hours New Material @l210C & 200 Mrads Electrical Strength 5 Samples - Volts / Mil Minimum 312 318
'r Maximum 491 355 Y 380 334 Wall Thickness .084" .086" Volume Res is tivi ty OHM-CMS 2.5 x 10 13 1.2 x 1014 t]1 Flamnabili ty Per A.S.T.M. D-2863 0xygen Index Note Slab Data Only 35.0 37.0
[\ Notes
- 1. Cable types for testing A. 600 volt FlamtrolTM B. 2000 volt EPR/ Neoprene
- 2. All samples were continuously operated at maxim.Jm current and voltage per cable class. Current levels per I .P.C.E.A.
- 3. Cobalt 60 ganrna radiation, dose rate of 0.27 Mrads per hour.
- 4. 5 hours at 3600F, 70 psig steam; 6 hours at 3200F, 70 psig steam: 24 hours at 2500F, 21 psig steam, 0.2% boric acid spray at pH of 10, 12 days at 2210F, 2.5 psig steam, 100 days at 2120F 2.0 psig steam.
5 All samples passed, fin electrical or mechanical failures, n
., 1 Coni ve M T/iA*ih M W n ?s n i.u n "'"'"'"'
- u. .~ .- . - .--. . . - . . . . - _ _ _ ....._.
AheAmu+ bz
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/' .
./. o , TEST NO. N11/5-2
#' 1 . .
(/ . l ACTUATOR STEAM INJECTION TEST _
'USING THICK (FLP) TRANSFER BUSH f
i O-e RELEVANT PARTS * {s APPROVED BY:- APPROVED BY:- NAME G BLACKER NAME B GREGORY
. STATUS APPLICATION ENGINEER STATUS CHIEF APPLICATIONS . ENGINEER 1
DATE 17TH APRIL 1972 DATE 17TH APRIL 1972 9
. . . . 'L .
g'S L
- .. PURPOSE ,
To deter"mine the effect of injecting high pressure steam into the terminal box on the sealing of the electrical enclosures under condition's of. ineffective cable gland sealing.
SUMMARY
The sealing arrangement with thick transfer bush successfully withstood the test. 1 TEST FACILITY c The containment simulation equipment in the Rotork Development , Laboratory, set up as per sketch. 2SoV SEAL S tral , O
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h (' PROCEDURE The test followed the pressure / temperature parameters of the IEEE, JCNPS, SC2.3 Draft.9. A Rotork flameproof terminal bung was used for this test. Visual inspection was
- s. ,
un eri to ennitor sealing capability
- a. . ~ u f .1- ,
Throughout this test the leakage current between terminals at 250V 50H2 was continuesly monitored. RESULTS I eues Mw's bib 507 __' .' W E-- (Tcf_f.w/Ats (nrEMirJAL OBSc2dA-{Teld. C.,
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