ML20154N800
| ML20154N800 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/02/1988 |
| From: | Myers C, Prescott R, Renshaw F AMP, INC. |
| To: | |
| Shared Package | |
| ML20154N803 | List: |
| References | |
| 110-11004, 110-11004-RA, NUDOCS 8809290403 | |
| Download: ML20154N800 (16) | |
Text
,
1 .
GUALIFICATION TEST REPORT 110 11004 REL 2-2-82 AMP
- INSULATED TERMINALS AND SPLICES FOR CLASS 1E, INSIDE CONTAINMENT SERVICE ,
IN NUCLEAR POWER GENERATING STATIONS TABLE OF CONTENTS Page 1.0 I N T R O D U C TI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 APPLICABLE DOCUM ENTS . . . . . . . . . . . . . . . . . . . . . . . 1 3.0 C O N C LU SIO N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 4.0 QUALIFICATION TEST PLAN . . . . . . . . . . . . . . . . . . . . . . . . .2 4.1 Test Sample Configuration. . . . . . . . . . . . . . . . . . . 2
- 4.2 Test Sample Preparation . . ....... . .... ..... 3 4.3 Wire ... ... . ...... ... ..... ......... . .4 4.4 Test Sequence ... ............. .... ... . ... 4 4.5 Test Equipment. . . . . . ....... ....... ..... .4 yT 4.6 Test Methods .........
gj 3g 5.0 TEST RESULTS . . . . .
6.0 TEST M A RGIN . . . . . . . . . . . . . . . . . .
... 11
. 14
.5
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i1 4*B .
}k 6 Prepared by: Approved by:
8f f
g Richard W. Prescott Test Engineer Floyd H. Renshaw Product Engineering
- General Products Group General Products Division d i Approved by-
!<g Cleethon Myers ga Product Assurance Manager
, General Products Olvision sy,j Oj' eco'/;?'10403 000'/;?'l PDR ADOCK 0b00 1 P
OtST GENER AL PRODUCT 8 0Roup REV gg AM P INCORPOR ATED. H A R RisB URG, PA. 1710l y.S. A. A
- ,'Tre3emara of AMP INorporated
1.0 INTRODUCTION
This test report contains the results of testing performed between March and October,1961 on AMP Radiation Resistant 150'C PIDG* and PLASTl-GRIP
- terminals and Environmental Seal-ed Splices. Testing was performed in accordance with AMP Product Specification 10811023, Rev. B, which was written by AMP to provide a test plan that woi.id comply with the guidelines set forth in IEEE Standards 323-1974,3831974, and Nu Reg 0588, Revision 1, Category 1 for Class 1E (Safety Related) inside containment service in nuclear power generating stations (PWR and BWR). These products are rated for a 40 year qualified life at 90'C. Visual inspec-1;ons, Dielectric Voltage Withstand, Static Heatlog, Thermal Aging and Pull-Out tests were per-formed in AMP Laboratories. Visual Inspections, Vibration Aging, Seismic Vibration and SLB/LOCA testing were performed by National Technical Systems, Testing Division, Chatsworth, CA. Radiation Exposure was done by isomedix, Inc., Parsippany, New Jersey.
2.0 APPLICABLE DOCUMENTS The following documents of the issue in of fect at the date of qualification testing constituted a part of this test report to the extent specified herein.
10811023, Rev B AMP Product Specification for insulated Terminals and Splices l for Class 1E, inside Containment Service in Nuclear Power i Generating Stations l
lEEE 101 A 1974 IEEE Guide for the Statistical Analysis of Thermal Life Test Data IEEE 3231974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations US NRC Reg. Guide 1.89 (For IEEE 3231974)
IEEE 3831974 IEEE Standard for Type Test of Class 1E Electric Cables. Field Splices and Connections for Nuclear Power Generating Stations I
l US NRC Re'g. Guide 1.131 (For IEEE 3831974) i IEEE 3441975 IEEE Recommended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations US NRC Reg. Guide 1,1 (For IEEE 3441975)
UL 486 A, Seventh Edition Wire Connectors for Use with Copper Conductors NU REG 0588 Rev.1, NRC Interim Staff Gosition on Environmental Qualification of Category 1 Safety Related Electrical Equipment MIL STD-45662 Calibration System Requirements
3.0 CONCLUSION
S As summarized in this report,it has been der $onstrated that all terminals and splices were capable of performing their required functions throughout their 40-year qualified life and during the subsequent Design Basis Events (DBE)of Seismic, Radiation Exposure, Steam Line Break (SLBVLoss of Coolant Accident (LOCA) and post LOCA conditions.
This determination is based on the following tests and observations.
3.1 . initial Measurernents and Thermal Ac_ing; Baseline measurements were made of current Carry.
Ing and insulating capabilities of each terminal and splice inillally and after Thermal Aging.
Temperature Rise requirements were taken from UL Standard 486 A, Seventh Edition. The Dielectric Withstand requirement of 2200 VAC tms was established using the industry ac.
cepted practice of testng to twice the rated voltage of a component plus 1000 volts. All ter-minals and splices met these requirements inillally and af ter Thermal Aging, as shown in the Test Results section of this report.
PAGE 10F 15 114 11004
3.2 Vibration Aging and Seismic. During the Vibration Aging and Seismic Vibration, all circuits were monitored to detect electrical discontinuities greater than two microseconds duration; there were none 3.3 SLB/LOCA Exposure. During the SLB/LOCA/ post LOCA conditions, test specimens were energized with 65 amperes AC tms on the #6 AWG circuits and 7 amperes on the other circuits, with a potential of 600 VAC rms between all adjacent circuits. Shortly into the exposure, due to excessive leakage currents, the 600 volt potential was removed from the circuits. All circuits continued to carry their test currents throughout the entire 30-day period.
To determine the cause of excessive leakage current between mutually insulated circuits, Im.
mediately upon completion of the 30-day LOCA exposure, and as soon e the test chamber was auf ficiently cooled and opened, the electncal box, still inside the enamber, was opened and the lead in cables removed from the clicult. A 600 VAC tms potential was applied between all adjacent circuits inside the box. There was no leakage current exceeding 50 microamperes.
Further investigation showed the wire insulation split and some came completely of f of some of the lead in cables outside the electrical box, exposing bare wires touching together.This was the determined cause of short circu!ts, not the components inside the box.
3.4 Post LOCA Measurements and Evaluation.
A. Dielectric' Withstand. All circuits withstood a test potential of 2200 VAC tms applied between all adjacent terminals and splices inside the electrical box. There was no evidence of dielectric breakdown or flashover between any circuit.
All terminals and splices were then removed from the box and subjected to Dielec.
tric Withstand testing as specified in Paragraph 4.2. The minimum breakdown voltage of any terminal or splice was 1106 VAC tms, or more than twice the max.
imum 480 volt service in which this product is used. (See Test Results Section of this report for more complete analysis). ,
Terminals and splices were re. installed in the electrical box as before and a dielec.
tric withstand voltage applied between all adjacent circuits to achieve breakdown.
The minimum breakdown voltage between any adjacent circuits was 7,968 VAC tms.
The above evaluations demonstratt, that all terminals and splices tested are capable of continued performance of their required function with adequate margin for an ex.
tended period of post LOCA conditions.
B. Static Heatino_ Af ter LOCA exposure, all circuits inside the electrical box were energized with their rated currents (See Table IV) and the temperature of each ter.
minal and splice was measured. The maximum temperature rise over ambient temperature of any terminal or splice did not exceed 80'F which would be a max.
imum actual temperature of 260'F if operating under post LOCA ambient conditions
, of 200'F. This is below the normal ir.,ng term operating temperature rating of 302*F for the product and demonstrates that the terminals are capable of handling their rated currents during extended post LOCA conditions. In fact, only one #12 AWG ter.
minal was this high. All other terminal temperatures were less than 44'F above am.
bient. Further analysis of this one higher than normal terminal temperature showed that the cause was the bolted joint connection, not the crimp istmination.
Further evaluation using the UL 486 A technique as for baseline measurements is shown in the Test Results section of this report.
4.0 QUAllFICATION TEST PLAN 4.1 Test Sample Configuration _ The following quantities of ring tongue terminals and on. ,
vironmental sealed splices were tested on the wire sizes shown. The insulating sleeves i on the terminals ar.d splices are extruded from KYNAR material (trademark of Pennwalt l Corporation). This material is a Polyvinylldene Fluoride composition (PVF,).
)
Test Groups 1 through 4 were thermally aged to simulate 40 years at 90'C and Test .
Groups $ through g Aere unaged. l 11411004 PAGE 2 OF 15
- TAB'L E l Sample Product Part Wire Wire Size Crimping Group Tested N o.
Range Tested Quantity Tool 1 PIDG 53425 1 12 10 12 12 5923?-4 2 PLASTI GRIP 53946-1 6 6 8 2 3 Splice 52979 20 16 18 6 59275 4 PIDG 53409 1 22 16 18 12 59250 5 PIDG 53425 1 12 10 12 8 59239 4 (6
) PLASTl GRIP 53946 1 6 6 8
- J7 Splice 52979 20 16 18 4 59275 8 PIDG 53409 1 22 16 18 8 59250 1
(' 9 PIDG 53426$ 12 10 10 8 59239 4 i 2, Tool pen 69120. Head pin 69066. Ove P/N '72371 4.2 Test Sample Preparation. Terminals and splices selected for testing are representative of current production. Preparation of test specimens was conducted in accordance with the applicable AMP instruction Sheets governing assembly and crimping technique.
Terminals were crimped to the ends of 4 Inch lengths of the specified conductors ex-cept for those crimped to the leadin wires and tested in the unaged condition. Splices had a 3-inch length of wire crimped to each end, with a ring tongue terminal crimped to ;
4 each end of those. - _ _ _ _ _ _ _ ___ _ _ _
Af ter initial measurements and Thermal Aging were completed, terminals and splices were fastened to vertically mounted terminal barrier blocks with the wires extending out horizontally from the block. Barrier blocks were General Electric EB-25 (for wire sizes 8 and smaller) and EB 1 (for Size 6), without covers, and were mouated inside a NEMA I
! Type 3 ventilated electrical box.
J (See Photo 1) 1 PHOTO #1 1
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4.3 Wire. The following conductors used for test are cf the type coproved for CI:ss 1E ser.
v6c] in nulear power generating stations except for the siz318 wir3. All conductor in .
sulations are rated at 600 volts.
Wire Size AWG Wire Type 12 Brand Rex Untrol Control Cable, unplated conductors 6 Rockbestos Firewall Ill, XHHW, NEC, Type TC, tin plated conductors 18 Tensollte SNC 726 Z 18, ETFE TEFZEL Insulated, 7 strand, tin plated conductors 10 Anaconda Y UL Type SIS VW 1 4.4 Test Sequence. Testing was performed on all terminals and splices in the sequence shown in Table 11. Test Group I consisted of Sample Groups 1 thru 4 (aged) and Test Group ti consisted of Sample Groups 5 thru 9 (unaged),(,See Paragraph 4.1, Table I).
TABLEil QUALIFICATION INSPECTION Para. Test Group and Sequence Test or Examination oraph I 11 Visual Examination 4.6.1 15111315 1810 4 Dielectric Voltace Withstand 4.6.2 24 -165 2 - 115 Static Heatino 4.6.3 37-176 3 - 125 Thermal Acino 4.6.4 4 Vibration Acino 4.6.5 8 4 Seismic Vibration (OBE) 4.6.6 9 5 Selsmic Vibration (SSE) 4.6.6 10 6 Rad!ation Exposure 4.6.7 12 7 -
SLB/LOCA 4.6.8 14 9 Pull Out 4.6.9 18 13 5 usaiurements were first iaken on tesi noecimens stiii mounted in ine eiectricai box. samoies *ere inen removeo
~~
from the bos and measu'remesti taken in tne normal manner in 'accordance witn Ut. Standard 486 A.
4.5 Test Egylpment, The following equipment was used to conduct the tests described in this Test Report. All standards used are traceable to the National Bureau of Standards and calibration records are available upon request. Instrument callbration is conducted in accordance with MIL STD-45662.
TMST EQUIPMENT Calibra:' Date
- Test or tion Last Examination Egipment M f r. _ Model Accuracy _ Intenial _ Calibrated ;
Static Heating DC Power Mid Eastern 674 98 NA NA NA Supply Millivoltmeter Weston 1261 1% FS 3 mo 1 13-81
! 10 22 81 Thermocouple 'Doric OS 500 + / 1.5'F 6 mo. 9 10-80 Indicator 91481 Dielectric Dielectric AMP Ser. 999 2% 3 mo 1 30-81 Withstand Tester 11 02 81 Pull Out Tensile Machine Tinius Olsen LOCAP 5000 1% 6 mo 1142-81 Heat Age Oven Blue M POM 566 A + /1'C NA NA i mi Vibrat on Tests were performed by National Technical Systems, Radiation LOCA Test Division, Chatsworth, CA.
l 1411004 PAGE 4 OF 15 I J
f
4 6 Test Methods.
4.6.1 Visual Examination. Prior 13 test, terminals and splices were visually examined for i- evidence of physical damage, improper assembly, or any defects which could render them unsuitable for testing. Upon completion of Thermal Agirng, Vibration, Radiation Ex.
posure and SLB/LOCA, samples were again visually examined prior to measurements.
4.6.2 Dielectric Voltage Withstand.
4.6.2.1 UL Method.
A. Terminals. Terminals were dipped in molten insulating wax to a depth to suf fi-ciently cover and seal the exposed end. Care was taken to insure that the wax did not cover the crimp area. The waxed end of each terminal was then embed-ded in #12 lead shot (.050" diameter) to a depth auf ficient to cover the crimped areas of barrel and insulation support of grip. A test potential of 2200 volts '
tms,60 Hz was applied at a rate of 500 volts per second between the conduc-tive parts of the terminals and the lead shot and held for a period of 1 minute.
B. Splices. Splices were embedded in shot to a depth sufficient to cover the en-tire splice and all seat areas and tested to 2200 VAC tms as specified for ter.
minals.
4.6.2.2 Inside Electrical Box Measurements. The 2200 VAC tms dielectric withstand potential was applied between all adjacent circuits, held for one minute, then in-creased until dielectric breakdown or flashover occurred between circuits.
4.6.3 _ Static Heatin0 4.6.3.1 UL Method. Crimped terminals were bolted back to back, with the bolts not exten-ding more than 1/4 inch beyond the outer surf ace of the nut (See Figure I) and sub-jected to a continuous current of the value specified in Table Ill. Thermocouples were fastened to all crimped wife barrels of terminals and splices for temperature measurement. Measurements were recorded af ter the temperature had stabilized (when three Consecutive readings, within a 15-minute period, were the same).
( FIGURE 1 STEEL BOLT STEEL NUT STEEL FLAT WASHER STEEL SPRING LOCKWASHER E5N1 Y '
TERMINAL TABLE lil Stetic Healing Test Currents and Pull Out Requirements t
- Test Current Pull Out Force Wire Sire (Amoores DC) (Pounds Minimum) 18 17 20 12 25 70 10 40 80 6 95 100 4.6.3.2 in Service Box Measurements. After S2LB/LOCA exposure, before samples were removed from the electrical box, temperature rise measurements were taken on each terminal while energizing all circuits with their rated currents as follows
.TABLEIV
_ wire sire (Awo) current Ratine (Amoores)
~8 1 7 12 20 6 65 Size 10 terminals could not be tested at their rated current because they were only used on lead.in wires and were used to energize smaller wife sizes.
PAGE S OF 15 110 11004
e 4.6.4 Thermal Aging. All Test Group i test specimsns wsre prs agsd prior to radiation exposure by subjecting thsm to a temperature of 165'C (+ 2,0'C)in an air circulating oveit for a period of 21 days to correlate to their quallfled life of 40 years at 90'C. This temperature / time relationship was extrapolated from the Arrhenius equation, log Y = A
+ B/7, with the intercept being 9.2020455 and the regression coef ficient B as 5964.3978.
This equation Was derived from isothermal gravimetric data generated by Pennwalt Cor.
poration.
4.6.5 Vibration Agh The electrical box containing the terminals and splices under test was rigidly mounted to the vibration shaker table (See Phoio #2). Suitable lead-in wires were connected to the test leads in series fashion so that all terminals could be monitored throughout the test for electrical discontinuitles exceeding 2 microseconds duration. The entire test assembly was subjected to 90 minutes of sinusoidal vibration in each of the three major orthogonal axes, at an applied acceleration of 0.75 g peak over the frequency range of 5 Hz to 100 Hz. The sweep rate was one octave per minute and input levels were as follows:
Frequency (Hz) Levels 5 7.75 0.025 inch double amplitude 7.75 100 0.75 g i
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- l thogonal axes, the monitored electrical box was subjected to five blaxial seismic events I j at the Operating Basis Earthquake (OBE) level followed by one blaxial event at the Safe 4
Shutdown Earthquake (SSE) level. Each seismic event consisted of random motion which l was amplitude co'1 trolled in il34ctave bandwidths from 1 Hz to 35 Hz. Each event was 30 j seconds in duration 11M 104 PAGE 6 OF 15 l
1
The electronic signals from two piezoresistive accelerometers mounted on the seismic simulator in the two active axes, were analyzed in 1/12 octave bandwidths between 0.1 Hz and 100 Hz, with a spectrum analyzer, at a damping ratio of 5 percent.The Test Response Spectra (TRS) met. or exceeded, the OBE and SSE Required Response Spectra (RRS). See Figures 11 and lit for examples of one event each, OBE and SSE.
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I I I ] I I 1 10 100 FREdUENCY (Hz) 4 6.7 Radiation Exqosure. Test specimens were exposed to gamma radiation from a Cobalt 60 source to a total accumulated (equivalent air) dosage of 259 megarads at a rsominal dose i rate of 0.34 megarad per hour. This dosage accounts for 50 megarads throughout the not. 1 mal 40 year operating life, plus 209 mearads during DBE and post.0BE conditions. l 1
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i 114 11004 PAGE 8 OF 15 l
4.6.8 Steam Line Break (SLB)/ Loss of Coolant Accident (LOCA). Test specimens were energiz.
ed with 600 volts AC rms between adjacent terminals and carried test currents of 7 amps on the 18,12, and 10 AWG circuits, and 65 amps on the #6 AWG circuit to monitor for elec.
trical short circuits and circuit centinuity.
The electrical box containing the test specimens was placed inside the LOCA autoclave and subjected to Loss of Coolant for a period of 30 days in accordance with IEEE STD 3231974. A simulated Steam Line Break (SLB) and an additional peak transient were also included as shown in Figure IV. Test conditions encompassed both the PWR and BWR profiles, using the temperature /ptessure profile specified for BWR's and the chemical spray specified for PWR's except 50 ppm hydra 2ine was included in the solution. Also, NaOH was added to yelid a pH of 12.5 for the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the pH decreased to 10.5 for the remainder of the test exposure.
To accomplish the Steam Line Break and provide margin to the specification parameters, the following profile was performed; FIGURE IV (A) sLs/LOCA Temperature Profile 500-16 sec /--470'F for 10 min.
1 r-400'F for 10 min 25 sec r e pray s on 400- -
350'F for 6 hr.
( , . . .
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l 340 F for 3 hr.
j---320 F for 2 days 6[ ' -
l.y .- - .....
l [280'F for 8 days 300- / .
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.. 20 F f or days g .
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Actual Levels
.E equired .
H 200- Levels of AMP Product . . ,
Spec. ,
106 11023, -
100- b* I' -
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10 10 X 10 10 6 9 2 10 30 sec min sec min hrs his days days days TIME PAGE 9 OF 15 11411004
FIGURE IV (B) sLB/LOCA Pressure Profile Spray On Actual Levels 74.5 psig 80- / 74.0 / equired R
16 sec/ 25 sec / / Levels of AMP Product 70- f r3 C,._4i Spec.108 Ho73, Rey. B.
60- 1 i I
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0 . . . . i i i i i i i i i 10 10 X 10 10 6 9 2 10 30 sec min sec min hrs hrs days days days TIME As shown in Figures IV(A) and IV(B), the following time / temperature / pressure profile was followed. For the Steam Line Break, superheated steam at 74 psig was used.
NOTE: The required specification peak transient levels were to be 382'Fi65 psio. Actual levels were 470'F/74.5 psig and 400'F/74 psig.
- l Step _ _ Time (Progressive) _ Temperature ('F) Pressure (PSIO)_
Margin Transient:
1 0 see to 16 see 117 to 470 0 to 74.5 2 16 see to 10 min remain at 470 74.5 3 Unspecified decrease to 106 decrease to 0 LOCA:
4 X to 25 see 106 to 400 0 to 74 5 25 see to 10 min remain at 400 remain at 74 '
6 10 min to 6 hr remain at 350 remain at 74 7 6 hr to 9 hr remain at 340 remain at 74 8 9 hr to 2 days remain at 320 remain at 74 9 2 days to 10 days remain at 280 remain at 35 10 10 days to 30 d.ys remain at 260 remain at 19
)
110 11004 PAGE 10 OF 15
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- 4.6.9 Pull Out Force. Test specimens were placed in a tensile testing machine. An axial force j ' was apphed to the terminals at a rate of 1 inch per minute until the f >rce specified in j
Table til was reached. The force was maintained for 1 minute and then released.
! 5.0 TEST RESULTS I
5.1 Visual Eramination. When examined prior to test, all test specirnens were free from any i defect., or damage and were properly assembled to their respective lengths of wire. Visual ex.
i amination af ter Thermal Aging, Vibration Aging, Seismic Vibration, Radiation Exposure, and e SLB/LOCA Exposure, showed all insulating sleeves in place and no evidence of splitting, blistermg, cracking, or any type of deterioration of any sleeves on terminals or splices except for creases on the underside of some terminals after LOCA, where they were pressed againbt
- the barrier block corners (see Paragraph 5.2, Table V, Note 3 for more complete description).
l PHOTO #3 AFTER SL8/LOCA EXPOSURE
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O 5.2 Dielectric voltage Withstand.
5.2.1 UL Method. Initially and af ter Thermal Aging, all terminals and splices withstood tho 2200 VAC tms test potential with no erdence of dielectric breakdown or flashover.
When tested as specified in Paragraph 4.6.2, af ter the SLBILOCA exposure, all terminals and splices withstood the 2200 VAC rms test voltage except the following:
TABLE V No. of Specimens Minirium Breakdown Visual Description Less than 2200 VAC Vohege (VAC tms) Observations
- 6 Term. (aged) none NA (unaged) none NA
- 12 Term. (aged) 2 1563 3 (unaged) 3 1243 3
- 18 Term. (aged) 4 1648 1 (unaged) 2 1407 3
- 18 Spilces (aged) 4 1766 2 (unaged) none NA
- 10 Term. (unaged) 4 1106 1 1 Puncture in crimp area.
2 Puncture in crimp or window area of the splice.
3 Visualinspection of the insulating sleeves of these terminals showed a sharp, indented line across the sleeve where it was pressed down against the sharp edge of the barrier block (See Figure VA). This could have been caused during instkilation or by subsequent handling during testing. The specified maximum SLB temperature was to be 382'F;the actual temperature on the first transient was 470*F for 10 minutes. Temperature on the second transient was 400*F for 10 minutes. (See Figure IV and SLB/LOCA profile).
A precaution to minimize this condition would be to make sure that when installing ring tongue terminals, the tongue is not bent backwards, causing the wire barrelinsulation in 4
be forced down onto the edge of the barrier block. Also, care should be taken during the wiring of electrical boxes to avoid jamming terminal bar' tis down against the barrier block edges (See Figure VB).
FIGlikE VA FIGURE VB w r Vy o Nhh M k$
Wes em As seen from the above data, all terminal and splice insulating sleeves exhibited .
minimum breakdown voltage of 1106 VAC rms, or more than twice the maximum 480 volt service in which they are used.
5.2.2 Intde Electrical Box Measurements. Post.LOCA testing was also per'ormed on p" w minals and splices mounted on the barrier blocks inside the electrical box, as t.< M e at.tual service. A test potential of 2200 VAC rms was applied between all adjarr t s' -
cults and held for 1 minute. The voltage was then increased to breakdown. The m w am voltage breakdcwn between any adpcent circuits was 7,968 VAC rms.
g The test results have demonstrated that all terminals when installed and used as descrit>
ed in this report performed their required functions with adequate margin, even without taking the precautions stated in Paragraph 5.2.1.
110 11004 PAGE 12 OF 15
5.3 Static Heatina. -
i* 5.3.1 UL Method. The following temperatures were measured on terminal and splice wire bar.
reis while carrying their specified test currents as determined by UL 486 A, Seventh Edi-tion. The values recorded are the temperatures in 'F of terminal barrels above ambient temperature while conducting the specified telt current.
TABLE VI -
Temperature Sample Wire Test Current Rise After After Radiation Group Site (Amperes DC) _ Initial Thermal Aelne and LOCA _
1b 12 25 min. 22 22 22 max. 30 29 30 avg. 26 26 24 2b 6 95 min. 37 34 28 max. 43 38 59 avg.. 40 36 38 3b 18 17
- min. 21 26 25 max. 28 34 36 avg. 24 31 31 1 4b 18 17 min. 24 21 23 max. 31 46 42 avg. 28 31 32 5b 12 25 min. 23 NA 29 max. 37 93 1
avg. 29 59 I
6 6 95 min. 28 NA 41 max. 40 122
, ( avg. 34 67 7 18 17 min. 22 NA 31 l max. 30 68 avg. 26 49 8b 18 17 min. 16 NA 31 j max. 25 71 i
avg. 20 48 9b 10 40 min. 20 NA 36 max. 26 73 avg. 22 48 I @ PIDG Terminals, thermally aged ~*
@ PLASTI. GRIP Terminals, thermally aged
@ Enviromental Sealed Splices, thermally aged
@ PIDG Terminals, unaged I
@ PLASTI. GRIP Terminals, unaged
@ Environmental Sealed Splices, unaged j
These measurements show that all terminal and splice wire barrel temperatures were less than the UL requirement of 90'F eine used as baseline reference, except one #12 AWG unaged terminal which had a temwrature rise of 93'F and one A terminal on one i
of the lead.in wires, with a rise of 122'F while carrying 146 percent rated current.This lat.
ter terminal was severely bent and deformed, apparently from handling sometime during installation er disassembly operations. This data, in conjunction with the following j
measurements, show that terminals and splices as installed in the electrical box or bar.
riet blocks are capable of handling their rated currents during extended post LOCA con-ditions without damage or degradation to any components.
4 PA*E 13 OF 15 110 11004
____-__---_-______--_-__-____---___-__0
g 5.3.2 in Service Bor Measurements, The following temperatures were measured on thermally aged and unaged terminals as Instdled on barrier blocks, inside the electrical box.
Overall temperature is now influenced by the crimp interface of the wire to the terminal barrel and the bolted joint interface of the terminal tongue to the barrier block pad. The values recorded are the *F of terminal barrels above ambient temperature while conduc-ting the rated currents shown belo.v.
TABLE Vil Temperature Rise ('F)
Wire Slee Rated Current inillel After LOCA (AWG) (Amperes DC) 6 65 min. 12 14 max. 16 44 avg. 14 23 12 20 min- 5 9 max. 28 80@
avg. 17 24 18(terms.) 7 min. 0 0 max. 6 9 avg. 1 3 18 (splices) 7 min. . 2 max. . 9
~~
avg. .
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6 NOTES:@ Only o$e~out of tt5e 20 terminals in this group was high. The max temperature rise of the next highest terminalin the group was 359. Further analysis showed that the heating was being generated at the bolted connection, not the crimp termination.
- 10 AWG lead in wires not included in these measurements.
5.4 Pull Out. The mechanicalintegrity of the crimped terminals and splices after all environmental exposures was demonstrated by the Pull Out test. All terminals and splices withstood for one minute the forces required to UL Standard 486 A. Seventh Edition, shown in Table 111 of this report.
6.0 TEST MARGIN This test report describes the tests which were conducted to demonstrate the product's ability to function satisf actorily under the required conditions. All of the tests described in this report were designed to accelerate, of"over test", the product to assure that an adequate margin does exist between irupected or possible operating conditions and the test conditions. These judgements are based on accepted engineering and test practices as follows: (Reference Paragraph 5.6 of this specification for a list of tests and their sequence.) ,.
6.1 Static Heating Temperature measurements were taken on each terminal barrel with the specified test current passing through the crimp connection to determine the heating effects ,
caused by this current. The method use and the performance criteria for initial or baseline '
measurements are derived from Ul Standard 486 A, Seventh Edition. Measurements were also taken af ter exposure to simulated aging and accident conditions to demonstrate electrical in-tegrity and the ability of the terminals to carry their rated currents during a nuclear accident and throughout an extended post LOCA period.
6.2 Radiation Exposure. IEEE Standard 383 1974, Paragraph 2.4.2 states that test specimens should be subjected to gamma radiation to a dosage of 200 x 10' rads (50 + 150 Mrad). This report specifies a total accumulated dosage of 259 x 10' rads, which is considered adequate f margin. _ ,
6.3 LOCA/SLB. Paragraph 1.3.5.3 of IEEE Standard 383 1974 states that margin shall be demonstrated by application of multiple transients, increased level, or justifiable means. The :
test profile shown in Figure IV of this report is based on the profile for Environmental Sirnula. I tion (combined PWR/BWR) shown in Figure A1, Appendix A of IEEE 3231974, with the addition l
of a simutated steam line break to 470'F on the first transient,400*F on the secono transient, i plus higher temperatures on all plateaus after the LOCA. i
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110 11004 PAGE 14 OF 15
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t 6.4 Dielectric Volta 0e Withetand. Dielectric testing at 2200 VAC rms,60 Hz in accordance with the UL Standard 486 A provides sufficient margin over normal service conditions for baseline measurements. Terminals of this type are normally applied to 300 or 600 volt rated wire or cable and used in systems not exceeding 480 volts rms.
6.5 Pult Out Force. The Pull Out requirements of this report are derived from commercial specifica-tion, UL Standard 486 A, Seventh Edition. These values are the accepted standard for this type of wife termination and are considered to provide adequate margin of safety over normal ser.
vice conditions.
Ref: 3029400 (17) f
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