ML20050C999

Qualification Test Rept on Exane II Control & Instrumentation Cable Under Simulated Loca/Dbe by Simultaneous Exposure to Environs of Steam Chemical Spray & Gamma Radiation.

ML20050C999
Person / Time
Site:	Sequoyah
Issue date:	03/31/1975
From:	ISOMEDIX, INC.
To:
Shared Package
ML20050C841	List: ML20050C840 ML20050C856 ML20050C859 ML20050C862 ML20050C863 ML20050C873 ML20050C881 ML20050C884 ML20050C891 ML20050C896 ML20050C927 ML20050C958 ML20050C961 ML20050C962 ML20050C963 ML20050C964 ML20050C965 ML20050C971 ML20050C975 ML20050C982 ML20050C988 ML20050C999 ML20050D000 ML20050D003 ML20050D008 ML20050D009 ML20050D011 ML20050D013
References
RTR-NUREG-0588, RTR-NUREG-588 375-02, 375-2, IEB-79-01B, IEB-79-1B, NUDOCS 8204090470
Download: ML20050C999 (21)

Text

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• n y CERTIFIED TEST REPORT

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NO. 375-02 l

i I IS O M E DIX

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1 QUALIFICATION TEST REPORT on '

EXANE II CONTROL and INSTRUMENTATION CABLE under SIMULATED LOCA/DBE by SIMULTANEOUS EXPOSURE to ENVIRONMENTS of STEAM / CHEMICAL SPRAY and GAMMA RADIATION MARCII, 1975 F

perforrned for:

) ITT SURPRENANT DIVISION CLIN' ION a , MASSACHUSETTS 01510

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COMPONENT TESTING

• DIVISION l

ISOMEDIX, INC.

PARSIPPANY, NEW JERSEY .

8204090470 820407 5 PDR ADOCK 05000327 i P PDR  !

Inomedix Inc. 25 Eastmans Road. Parsippany, New Jersey (201) 887 4700 Matling Address: Post office som 177. Pers.ppany, New Je<sey 07054 CHICAGO OtVISION

• 7s28 Nape Ave Morton Geove. tilinost 600$3 (31219661160

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TABLE OF CONTENTS l

Page Section .

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1. Introduction and Summary ......................................

2. Description of Cable Samples................................... 1

3. Test Program ................................................... 2 i

.............. 2 3.1 Discussion.................................. i I

4. Te s t P ro c e d ur e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 l I

3 4.1 Cable Mounting.............................................. l t

4.2 Electrical Energizing and Interconnections.................. 3 I 3

4.3 Dose Uniformity ............................................

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3 4.4 Measurements of Insulation Resistance (IR) .................

4.5 High Voltage Withstand Tests (Hi-pot) ...................... 4

5. Test Results ................................................... 5 5.1 Actual Temperature Profile ................................. 5 5.2 Performance of Test Cables ................................. 6 Insulation Resistance Measurements 6

5. .........................

5.4 High Voltage Withstand Tests (Hi-pot) ...................... 7

6. Conclusion ..................................................... 7

7. Certification .................................................. 8 l

14 Appendix A - Radiation Certification ]

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. 4 LIST OF FIGURES i

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Figure No.

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1. Specified Environmental Exposure Profile .................

2. . Schematic Representation of Energizing Circuitry .........'10

3. Actual Temperature Profile Obtained During Test ..........'11 LIST OF TABLES Page Table No.

1. Summary of Insulation Resistance Measurements of Test Cables ..................................... 12

2. Results of Hi-pot Tests at Conclusion of 37 Day Environmental Exposure .......................... 13 W . . . . . e .

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1. Introduction and Summary Aqualificationtestokelectriccableswasperformedin accordance with the suggestions contained in IEEE. 323-1974, "IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Gen-erating Stations", and IEEE 383-1974, "IEEE Standard for Type Test of Class lE Electric Cables, Field Shlices, and Connections for i Nuclear Power Generating Stations."

One 7/c-12 AWG control cable and one 2/c-16 AWG shielded

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instrumentation cable, both unaged, were subjected to a 7 day simultaneous thermal / radiation aging exposure, followed by a 30 day simultaneous exposure to environments of radiation steam and chemical spray, while electrically energized at rated voltage. and current loading. This loading consisted of a potential of 600 volts (a.c.)

between conductors and a. current of 21 Amps on the 7/c cable, and 15 Amps on the two conductor shielded cable.

Approximately 35 feet of each cable was subjected to the exposure environments. The samples were irradiated in a cobalt-60 field of gamma radiation at a rate resulting in a total accumulated exposure of 200 megarads, air equivalent, over the entire test period.

- Measurements of insulation resistance were made periodically during the exposure period at 500 volts (d.c.). High voltage with-stand tests were conducted at the end of the exposure period following a 40 diameter nandrel bend test with the cables Lmmersed in water.

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Both samples survived the entire test exposure and success-fully withstood the hi-pot test at the end of the program. The test program was conducted during February and March-of 1975 at the test facilities of Isomedix, Inc., in Parsippany, New Jersey.

2. Description of Cable Samples The samples were wound in coils approximately 20 inches in diameter and were thirty-six feet long. The 7/c cable was identified as sample number 20 and the 2/c cable as number 21.

The samples are further identified as follows:  ;=

Sample No. 20 h

Seven-Conductor #12 AWG Control Cable 600 Volts 12 AWG 7/.0305 tinned copper, .030" nominal Exane II insulation, 'I twisted, silicone glass barrier tape .005, .065 nominal Exane jacket. i

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Sa=ple No. 21 Two-Conductor #16 AWG Signal Cable 600 Volts _

16-AWG 7/.0192 tinned copper, .030 nominal Exane II insulation twisted, with a 7/.0152 bare copper drain wire, 2 mil aluminum mylar tape shield, with one .083 fiberglass filler, silicone glass barrier I tape .005, .045 nominal Exane jacket.

3. Test Program 3.1 Discussion 3.1.1 Phase I - Thermal / Radiation Aging The cable samples were installed inside a pressure vessel and placed in a radiation chamber and subjected to a seven day thermal / radiation aging environment with the temperature inside the vessel maintained at 300 F. Radiation was from a cobalt-0 60 source of gamma radiation at an exposure rate resulting in an accumulated, equivalent air, dose of 50 megarads during this period.

3.1.2 Phase II and III - LOCA Simulation and Post-LOCA Cooldown At the conclusion of this simulated installed-life aging cycle, the samples were exposed to a simulated loss-of-coolant accident (LOCA) environment by simultaneous application of radiation / steam and chemical-spray for a period of 30 days in accordance with the temperature profile shown in Figure Al of The samples Appendix A of IEEE 323 and as shown on Figure 1.

• were continuously sprayed with a chemical solution consisting of 3000 ppm boron as boric acid in solution with 0.064 molar

• sodium thiosulfate and buffered with sodium hydroxide to a pH between 9 an 11 at room temperature. The spray rate was 2 of the surface approximately 2 gpm corresponding to 0.15 gpm/ft area of the mandrel.

The cable samples received an additional radiation dose of 150 megarads, air equivalent, during this portion of the test program. . .

3.1.3 Post-LOCA Tests At the conclusion of the simulated LOCA event, the vessel was taken out of the radiation chamber, the samples were removed i from the mandrel, straightened and recoiled aroundWhile a mandrel so wound, I whose diameter was 40 times the cable diameter.

the cables were inspected for cracks, immersed in water and subjected to high voltage withstand tests at 80v/ mil (a.c.) of insulation.

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4. Test Procedure 4.1 Cable Mounting The cable samples were. mounted on holding rods positioned between two end cap flanges of a vertically held metal mandrel, g approximately 20 inches in diameter. Steel wire was used to hold the cables in position relative to the vertical rods.

Approximately four feet of each cable end was brought up through the middle of the mandrel. These ends were brought through head penetrations in the pressure vessel, sealed, and connected to the energizing lead wire. Sealing was effected by securing the cable ends in aluminum tuhes with an epoxy compocnd The tubes were secured to the vessel by standard tube fittings.

4.2 Electrical Energizing and Interconnections The cable ends were secured to terminal blocks mountei on the vessel head. The lead wire, supplied by ITT, connected the energizing switch box with the test cables at the terminal block on the vessel head. The switch box contained knife switches arranged so that the cables could be individually monitored, removed from the circuit if a failure occured, or isolated during measurements of insulation resistance.

Figure 2 is a schematic diagram showing the energizing

' circuitry and cable connections. 9 4.3 Dose Uniformity Dose uniformity was obtained by repositioning the cobalt-60 ~

source at various stages throughout the exposure cycle and by rotating the vessel. Rotation was performed 3 days after-initiating the seven day thermal / radiation aging and again fifteen days after the' initiation of the steam exposure cycle.

Appendix A contains the certification of radiation exposure and describes the dose distribution and source positioning.

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4.4 Measurements of Insulation Resistance (IR)

IR measurements were made peridically during the exposure cycle as a means of monitoring the relative electrical degradation

- of the samples.

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Specifically, measurerents were made at the following times during the program:

1. Upon receipt of samples, prior to radiation aging.

2. Halfway through the seven' day thermal / radiation aging period.

3. At the end of the thermal / radiation aging period.

4. At each dwell during the high temperature phases of the Steam / Chemical / Radiation exposure period.

5. Once each day during the four day dwell at 265 F.

6. Twice per week during the balance of the 30 day period and at the conclusion of the exposure cycle.

The measurements were made after application of 500 Vdc held for one minute, unless specifically noted,by reading the odd conduc-tors against the even conductors for the 7/c cable and between each conductor separately, and both conductors against the shield for 2/c cables.

Prior to actually making the measurements, the current and potential load were removed for approximately ten to fifteen minutes.

At the conclusion of the IR measurements, the cables were put back into the circuit.

4.5 High Voltage Withstand Tests (hi-pot)

At the conclusion of the environmental exposure period, the samples were removed from the vessel, straightened and wound around a mandrel having a diameter 40 times the cable diameter.

The samples, while wound on the mandrel, were immersed in water with the ends free. The required test voltage was 80 v/ mil (a.c.) of primary insulation thickness, in accordance with section

2. / . 4 of IEEE 383-1974.

The procedure for performing these tests was as follows:

a) 2/c-shielded cable - one conductor connected to high voltage lead and other conductor connected to ground wire; each conductor, alternately, connected to high voltage lead with the shield grounded.

1 b) 7/c cable - odd conductors taken together to high voltage lead ' i and even conductors taken together and grounded; all conductors taken together to high voltage lead against ground wire.

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The specified voltage level was applied for a period of

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5 minutes after which time the charging current was' recorded.

5. Test Results 5.1 Actual Temperature Profile 5.1.1 Thermal / Radiation Aging -

The temperature profile obtained during the actual test phases is shown in Figure 3. The test was initiated by ener-gizing the cables and placing the cobalt source in position.

Strip heaters on the vessel were turned on approximately 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before actually starting to raise the temperature from room ambient. The vessel temperature was 240 F at the start and increased to 3110 F within the next half hour. Heat from the cable current load raised the temperature to a maximum of 334 F 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> after starting. Heater controls and current l0 loads were adjusted so that the temperature remained at 300 +_ 5-F throughout the remainder of the seven day period. Three And one-half days after starting, the system was shut down so that IR measurements could be made and the vessel rotated.

The thermal / radiation aging exposure period was concluded after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> had elapsed and 50 megarads, equivalent air dose, had been received. The system was shut down in order for the temperature to return to ambient prior to starting the next exposure period.

5.1.2 Phase II and III - ICCA Simulation and Post-LOCA Cooldown At the start of the steam exposure, the cables were ener-gized and the_ ambient temperature was 152 F. The cobalt source remained down until the exposure was underway.

To initiate the exposure, steam was rapidly admitted causing the temperature to rise to 2800 F within twelve seconds and to 3460F within 5.4 minutes. The spray was turned on with-in one minute of starting at a rate of 2.5 gpm and was'recircu-lated within seven and one-half minutes. The spray solution pH was between 9.5 and 10.5.

At an elapsed time of thirteen minutes, a pressure fitting blew out causing a rapid drop in pressure to atmospheric. The fitting was repaired, the penetration resealed and the test .

resumed. }

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The test was restarted with a slow rise in temperature and pressure reaching 346'F within 6.3 minutes.

The radiation source was raised and the exposure resumed.

One and one-half hours after starting, the power was turned off to make IR measurements. At the end of the measurement period, the cables were re-energized.

At an elapsed time of 171.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (ET) from the start of the thermal / radiation aging (corresponding to an ET of 3.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> from the start of the simultaneous exposure), the specified drop to 140 0F was begun. This drop was completed by an ET of 172.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Preparations were made to initiate the second transient.

The cable energizing was checked,and remained on; the spray remained on and the temperature was stabilized at 138 F. Steam was again rapidly admitted increasing the temperature to 280 F within 32 seconds and to 346 F within 2.6 minutes.

The remainder of the temperature profile was followed, as shown on Figure 3.

At an ET of 527.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, the system was shut down and the vessel rotated 1800 to maintain uniformity of the dose distribu-tion.

At an ET of 887.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (37 days total test time), the last set of readings were made and the system shut down. The vessel was removed from the cell, the samples removed from the vessel, inspected and measurements of withstand voltage made.

5.2 Performance of Test Cables The cables were electrically energized at a potential of 600 Vac between conductors throughout the entire exposure period except during vessel rotation and periods when IR measurements were made.

The current loads were maintained within + 5% of their test values, 21 Amps on cable 20 and 15 Amps on cable 21, except when these values were lowered during the seven day thermal / =

radiation aging period in order to control the vessel ambient temperature.

5.3 Insulation Resistance Measurements Measurements of IR were made at the times previously men-tioned and the results are shown in Table 1 as a function of the vessel temperature.

5.4 High Voltage Withstand Tests (Hi-pot)

Table 2 presents the results of the hi-pot tests performed at the conclusion of the test programs.

6. Conclusion A 7/C #12 AWG and a 2/C #16 AWG shielded cable, manufactured by ITT Surprenant Division, were subjected to a simulated Loss-of-Coolant Accident (LOCA) test program based on the guidelines of IEEE 323-1974 and 383-1974.

The cables were subjected to a 7 day simultaneous thermal /

radiation aging exposure, followed by a 30 day simultaneous exposure

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to environments of radiation, steam and chemical-spray while electri-cally energized at rated voltage and current loading. The cables received a total of 200 megarads radiation dose during the exposure that included two rapid temperature rises to 346*F and two 3-hr dwells at 346 F.

The insulation resistance was retained throughout the exposure, and the samples withstood a combination bend and high-potential withstand test (at 2.4 and 4.8 kVac) at the conclusion of the test program.

The cables demonstrated satisfactory performance throughout the simulated LOCA exposure and the Post-LOCA cooldown period. The inclusion of two LOCA transients in the temperature profile and the final berd/ voltage-withstand test demonstrated that the cables withstood the test conditions, with margin, as suggested in the referenced IEEE documents.

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7. Certification The u lersigned certifies that this report presents a true account of the st conducted and the results obtained.

's relating thereto should be addressed to same.

Questi t sf f -(

NissenM. Burs [cin Manager, Compcnent Testing o

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i Temperature / pressure profile for simulation of loss-of-coolant accident (LOCA) design basis event (DBE) by simultaneous stean/che-ical-spray / radiation environ-h

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,,- Fig. 2: SCHEMATIC REPRESENTAT2ON OF ENERGIZING CIRCUITRY I

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Current 3d Current Transforter Potential ODD Transformer Trasfomer<>

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CABLE NO. 20 - 7/C #12 AWG 1# 14 Current Current Transformer 3# Transformer

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CABLE NO. 21 - 2/C #16 AWG SHLD.

FIGURE 3 ACTUAL TEMPERATURE PROFILE ODTAINED DURING LOCA SIMULAT PHASE III PHASE I PHASE II Thermal / LOCA Simulation by Simultaneous Exposure to M M Cooldown Radiation Radiation /Staum and Chemical-Spray Environawats MM 34812 nyk-Referto Tcmp 350i2 Table 1 for k k 512 Actual Time 3

340 320+10 n 31612 346 ithin 320 withj n 2.6 min.

I 300 3 0,0+:j.0

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l280 32 sec. h265m i 0 within

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180 3 hrs.

Power Failurc w 4 hrs. ROTATE -

ROTATE t VESSEE

,40 1 VESSEL -' Restart 1s't Fuse blew 120 o transient , a a in heaters b QS/C/R

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I 183 264 485 503 530 100 173 37 0

11 Days 7 Days Days x

ELAPSED TI?iE (HRS.)

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TABLE 1 III MEASUREMENTS OF INSULATION RESISTANCE Elapsed Cable Samples (3)

Time (hrs.) Phase Temp. ( p) PSIG 21 (2/c) 20 (7/c) 5 13x10 5

- Pre- 68 45x105 9xio

' 0 Test 84.1 I 320 0 3.2x102 1.65x10 2 2x102 168.1 Post I 160 0 7.4x102 4x10 2 9x102 170.4 II 354 102 7.8 3.8 11 174.4 II 353 102 1.35xlol 8.5' 1.25x101 177.5 II 335 75 3.0x101 1.45x10 1 2.15x10 1 180.6 II 315 55 5.4x101 2.4x101 2.85x10 1 183.5 II 265 18 2.5x10 2 1.35x102 8.0x101 198.2 II 265 18.5 4.2x102 2.1x10 2 1.6x10 2 222.5 II 265 13 2.6x102 1.32x10 2 12x101 24F.3 II 268 19 2.5x102 1.3x102 1,1x102 265.5 III 212 4.5 9.9x102 5.2x102 7,oxio2 384.3 III 205 1.3 5.0x10 2 3.3x102 3.6x10 2 510.0 III 200 1 8.1x102 4.6x102 7.2x102 582.0 III 205 2.5 1.8x103 12x102 7.5x10 2 678.1 III 205 4.5 2x103 14x102 loxio2 750.8 III 202 11 1.93x103 11xio2 8x102 i 846.5 III 203 ,

9 2.05x103 1.08x103 8x103 887.5 III 206 9 2x103 12x102 7,9xio2 (1) All measurements made at 500 Vde, held for 1 minute, and all resistance values in megohms, unless otherwise noted.

(2) Elapsed Time (ET) total test time from the start of T/R aging.

(3) Sample 21 read between conductors first then between the shield against the conductors taken together: Sample 20 read taking odd conductors against the even conductors.

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TABLE 2 Results of Hi-Pot Tests at Conclusion of 37 Day Environmental Exposure Voltage (KVAC) Charging Sample No. Required Actual Current (MA) Coccents 20(7/c) 1,3,5,7, to 2,4,6 4.8 4.8 10 sold for 5 min.

All cond to gnd 4.8 4.8 0 Held for 5 min.

21(2/c) cond 1-to-cond 2 4.8 4.8 0 Held for 5 nin.

cond 1-to-shld 2.4 2.4 0 Held for 5 min.

cond 2-to-shld 2.4 2.4 0 Held for 5 min.

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APPENDIX A RADIATION CERTIFICATION I

1 Isomedix Inc. 25 Eastmans Road.Parsippany New Jersey (201) 887 4700 Ma6eine Address Post OfHce som 177. Persippany. New Jersey 07054 CHICAGO DIVISION e to28 Nagte Ave.,64erlen Grove. Illinels 60053 (312) 9661360

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May 8, 1975 i Inter Company Memo ,

To: Nissen M. Burstein Manager, Qualification Testing From: George R. Dietz Manager, Service Irradiation This will su=marize the parameters pertinent to the recent simultaneous steam, chemical spray and radiation exposure test conducted for ITT Surprenant.

Irradiation for tha Phase I 7 day test was begun on February 14, 1975 and con-cluded on February 22, 1975. During Phase I, the cables received a minimum dose

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of 52.5 Mrad and maximum of 54.0 Mrad. Where possible, we utilized the irradiator to process other products concurrently with the test, which necessitated occasional short periods where the radiation field was reduced to zero. The details of sc..ce positioning, dose rates and total dose is shown in Figure 1.

Phase II of the test began en February 22, 1975 and concluded on March 27, le,75.

During the approximately 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> radiation exposure, with simultaneous steam /

chemical spray per your profile, cables received an additional minimum dose of 148.9 Mrad and maximum dose of 155.2 Mrad. The details of irradiation are shown in Figure 2.

In summary, total dose to the cables over the entire test period ranged from 201.4 to 209.2 Mrad, with an estimated source positioning error of + 5% in dose rate.

Dosimetry was performed using a Victoreen Model 555, Integra*ing Dose Rate Meter and Probe. The unit was calibrated on January 15, 1974 by the Victoreen Instrument Company, using cobalt-60 and cesium-137 whose calibrations are traceable to the U.S. National Bureau of Standards. Backup dosimetry using a Red Perspex system provided by Atomic Energy of Canada, Ltd. confirmed the Victoreen readings.

W George R. Dietz AO$ 1 Manager, Radiation Serrices l

Enclosures - I GRD:km l Isomedix Inc. 25 Eastmans Road, Parsippany, New Jersey (201) 887-4700 Malung Address: Post offue Bos 177. Pseslepany New Jersey 07054 CHICAOO DIVisf 0N .' 78 28 Nasie Ave.. Morton oro.., ininois 60053(3323 966 1160 l

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Do30 Ratos and Total Dons C. 330 D 6 Source centerline E.. ;.25 A. .700 i

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. .0 Numbers on figure represent dose rates (kilorad/hr) at lettered points when the source is located as shown, relative to the cables. .

Irradiation was conducted by locating the source at 4 quadrants of the irradiation chamber, with a typical location shown above. When equal irradiation times are administered in each of the source locations, the average dose rate at a point is the average of the sum of the dosa rates received in each position. Rotation of the vessel and positioning the source in two quadrants each time had the same effect as if the source were relocated four times.

Avartge Dose rates at A,C,E and G are:

1/4)(A,C,E,G = 1/4),700+33&+33O+225 = 1585 = 396 Krad/hr 4

cnd at B,D,F and H 1/4)I B ,D,F and H, = 1/4 505+265+505 = 1540 4

= 385 Krad/hr Considering irregularities in the actual containment vessel, a 12% absorption factor was applied. Hence actual dose rates at A,C,E and G were .88x396 or 348.5 Krad/hr (maxbmum H dos @ rate)'and at B,D,F and H, .88x385 or 339 Krad/hr (minimum dose rate) . .

e se The minimum dose administered over the 7 day period to positions B,D,P and H from the 155 hour0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />, exposure was 155 hr x .339 Mrad - 52.5 Mrad hr and the maximum dose, to positions A,C,E and G, was l

155\ hr x 348.5 Mrad = 54.0 Mrad hr .

Attsnuation or buildup factors for the contents of the chamber (mandrel, cables, etc.)

w;ro not considered in the above because of the randomness of their locations.

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DAA 1037A - Addendum B O .

EXANE Il 600 VOLT S1HCLE LAYER

1.0 Insulation

Exane 11 The insulation shall consist of i rradiated c ross-l inked thermoset t ini; l compounds with wall thickness shown in Table I. The insulatien layer

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shall fit snugly over the conductor, but shall strip freely in at least a half-inch length using either automotive or manual stripping tools. l

a. Physical _ Properties - Unaged When tested in accordance to par. 6.4.11 of IPCEA S-66-524 the minimum values measured on the insulation removed from the con-ductor shall be as follows:

Minimum Tensile Strength, psi .1500

!!inimum Elongation, % L50

b. Pig,s_ical properties Af ter Air Oven Aging at 121"C When tested according to par. 6.4.12 of IpCEA S-66-524, the p insulation which has been. removed carefully from the conducter and then aged in a circulating air oven for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at L21 C shall retain the following minimum physical property values:

Tensile Strength Retention (% of ' unaged) 90 Elongation Retention (% of unaged) 75

c. Heat Distortion at 121"C When tested according to par. 6.4.14 of IPCEA S-66-524, distortion of the insulation shall not exceed 30% of the unaged value.

d. C_opper Mirror Corrosion Test - Corrosivity by Insulation When tested in accordance with the procedure outlined in AST11 267-1, the insulation shall not create suff.icient corrosive outgassing products to remove any copper f rom the test mirror af t er 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> at 175"C. -

2.0 Insulated Conductors

a. Dimensions: The insulated conductor dimensions shall be as specified in Table 1.

b. 1002 Dielectric Test: 100% of all footage made to this specifi-O cation shall either withstand a he water immersion test of par. 'i . 2

., e'meme l i- -

• of shall withstand a 100% impulse dielectric test using an I impulse dielectric test using an impulse test voltage of 17.5 KV I

(*5 shall consist, of a Slaughter Co. Series 656 Pulse Ionization 1 ester or equivalent. l

c. Insulation Resistance - 25 C k' ster: Any 25. foot sampic, chosen at random f rom production, shall pass the dielectric test and the insulated conductor shall have an insulation resistance not less than the value of R calculated as follows:

• R = K log 10 E d

Where:

R = Insulation resistance in Megohms - 1000' K = Constant for the insulation D = 1)lameter over insulation d = Di.ameter under insulation The minimum value of K is 20,000 015.6 C (60 F)

IR Test Method: The center 20 foot section of 25 foot coils shall be immersed in a 5% salt water solution at a bath temperature less than 25 for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Use Table 6-10 of IPCEA S-66-524, column 1.03, for temperature correction factors for Insulation Resistance,

d. IPCEA Vertical Flame Test I

When tested according to the vertical flame test of par. 6.19.6, IPCEA S-19-81, the requirements of par. 6.19.6.3, IPCEA S-19-81 shall be met.'

e. Gravimetric Water Absorption When tested in accordance with the procedure of par. 6.7.3 of IPCEA S-61-420, the finished wire shall have a maximum water absorption of 5 milligrams per square inch. .

f. 75 C Capacitance Stability When tested according to para. 6.9.2 of IPCEA S-19-81, in water

. which is maintained at 75 C + l C, the following minimum require-ments shall apply:

Maximum Initial SIC = 3.3 Maximum Change 1 to 14 days - 3.0%

Maximum Change 7 to 14 days - 1.5% 1

, . Stability Factor (Maximum) - 1.0% '

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