ML20064A696
ML20064A696 | |
Person / Time | |
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Site: | Cooper |
Issue date: | 12/02/1986 |
From: | Elam G NEBRASKA PUBLIC POWER DISTRICT |
To: | |
Shared Package | |
ML20064A690 | List: |
References | |
PEI-TR-8702-APP, NUDOCS 9009270089 | |
Download: ML20064A696 (12) | |
Text
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APPENDIX I
- Test Procedure ' for - Steam Accident- Test of Limitorque ' Control and Power. Wiring and Okonite Tape Splices n
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December 2, -1986 =;
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" Test Procedure for.
Steam Accident. Test of '
Limitorque Control and Power Wiring
. ' and Olsonite Tape Splices Report No. PEI-TR-870200-01'
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Prepared.for-NEBRASKA PUBLIC POWER DISTRICT.
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Cooper Nuclear Station l
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- 1 P. O. No. 263120
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h 1 Tost Prcccdure No PEI-TR-870200-01 I Page No.,i l 7 TECHNICAL-DOCUMENT t.
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. DOCUMENT TYPE -Test Procedure (REPORT / PLAN / PROCEDURE)-
DOCUMENT No.: PEI-TR-870200-01 December 2, '.986 ORIGINAL ISSUE DATE:
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- TITLE: Test Procedure for Steam Accident-Test of Limitorque Control and Power Wiring and [
Okonite Tape Splices
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'i9~ < s. PREPARATION PROJECT ENGINEER: Gh*\ - -
[- dary J. g\m ,
TECHNICAL' REVIEWS ,
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PROGRAM MANAGER: / [ /
N ENGINEERING VERIFIER: _
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t QtfALITY ASSURANCE:
J m kn .DWA n 1e'eryH.Iftech . (j ( (/
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i APPROVAL
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' GROUP / DIVISION DIRECTOR:
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Johnny F. Jenkins 'Y ~
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PEI Form No. 611 - Rev. 2/1984 .
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N Tes t . Pescedure ? N3. - PEI-TR-870200-01 G ": ,
.tage 50. 11 )
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. TABLE OF CONTENTS
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1.0 SCOPE. ..............................
i 1.1: Test Assembly Description . . ...............
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11.2 Test Sequence . . . . . . . . . . . . . . . . . . . . . . .
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- 2.0' TEST-REQUIREMENTS. .......................
2.11 Instrumentation . . . . . . . . . . . . . . . . . . . . . . 1 2
2.1.1 Calibration . . . . . . . . . . . . . . . . . . . .
2 2.2--Acceptance Criterie . . . . . . . . . . . . . . . . . . . . ,
/1 f.!I 2 3.0 TEST FROCEDURES. ... . . . . . . . . . . . . . . . . . . . . . . .
T- '
% L3.1' Functional Tests. . . .. . .=. . ... . . . . . . . . . . . .
2
I 1.1 .V is ual - Ins pe c t ion . . . . . . . . - . . . . . . . . .-
.g,
.1.2- Insulation Resistance (IR). . . . . . . . . . . . 2 2-.
4 4 3.1.3 -Continuity Yorification . . . . . . . . . . .-. .
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(") 3.2' Stean-Accident Test . . . . . . . . . . . .-.. . . . . . . .
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- 3. 3 . Fun c t iona l Te s t s . -. . . . . . . . . . . . . . . . . . . . . . 3
+ -3.4 Notice'of. Anomaly . . . . . . . . . . . ... . .=. . . . . . 3 3
33.5;- Reports . . . . .... . . . . . . . . . . . . . . . . . . . .
LN LIST OF FIGURES
' Tes't A'ssembly Configuration. . . . . . . . - . . . . .. 4 Figure.l.
. Accident. Test Configuration. . . . . . . . . . . . . . . 5.
~ Figure-2..
g Figure 3. Accident Test Profile. . . . . . . ..... . ,. . . . . 6-m y
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Test' Proccdtare Ns. //t!-TR-870200-01 Page r;.=_1 1
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1.0 SCOPE-1 This test procedure was prepared for the Cooper Nuclear Station (CNS) -for. the steam accident testing ~of Limitorque control and power-wiring and Okonite tape splices.
1.1 Test Assembly Description The test ' assembly shall consist of two cable / splice circuit loops :
inside a NEMA-4 enclosure. The test specimens shall be assembled and provided by the CNS plant staff except that Patel shall install the wiring into the NEMA-4 enclosure. The enclosure shall not have a drilled " weep hole. The test assembly shall be fabricated per Figure 1. The enclosure simulates the Limitorque
' housings at CNS.
The 2' circuit loops shall be labeled loop 1 and loop 2. Loop 1 ,'
shall contain 2 se gments (F and G) of Limitorque torque switch
- tD wire-(black braid) that were naturally ~ aged in service at CNS.. ,
' Segments F and' G were inetailed for 12 years in the CNS steesi.
q in- valve MS-M0-M077 and MS-MO-M078, 1monel operators re spctively. Valve -operators MS-MO-M077 and MS-M0-M078 are.
o located in high radiation and elevated ambient temperature.
O environments. Zoop 2 shall contain 2 segments (5 and C) of Limitorque motor lead wire (yellow braid) that were naturally aged in service at CNS. Segments-B and C were installed for 12 -
' years in the CNS steam tunnel in valve operator MS-MO-M077.
Circuit Loops -1 and 2 each contain three bolted okonite T35/T95
".. . tape splices. The lead wires for loops 1 and' 2 shall be Rockbestos Firewall SIS 16 AWG 600V Nuclear Cable. . The splices "
- - were assembled by CNS personnel in accordance with CNS procedure
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j .1,. 2 Test Sequence C. Testing shall be. performed as follows:
o Functional Tests o Steam Accident Test o Functional Tests 2.0 - TEST REQUIREMENTS
- 2.1 Instrumentation
- All test equipment to be used in the performance of this program shall be' calibrated in accordance with applicable portions of ANSI N45.2, and ' 10CFR50/ Appendix B. Standards used in performing
- all calibrations shall be traceable to the National bureau of
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IJ - Tast Pracadure Nr. PEI-TR-870200 Page No.'2 .
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- . g 12.1.1 Calibration Test equipment _ serial numbers , calibration dates , .and accuracies shall be annotated and verified on the data sheets prior to test
- initiation. >
-2.2- Acceptance- Criteria c
';,1 The individual leakage current readings during the accident -l y simulation . shall not exceed _30 milliamps- for loop 1 and 300- $
milliasps for loop 2.
.3.0- TEST PROCEDURES The test specimens shall be subjected to the tests as described Em in the test sequence in Paragraph 1.2. The tests are described below.-
N -3.1 Functional-Tests p.j >
3.1.1 Steusl Insoection O _
A ' visual inspection shall be performed. This -inspection will' '
k assure that the: equipment has not received' any_ obvious visible
-damage during shipping- and handling. Equipment identification L . [J e
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will also be verified.
i 3.1.2 Insulation Resistance (IR) y ~
The insulation resistance of the test specimens shall be measured f at 500 VDC for 1 minute and shall be recorded. The following IR y- measurements-shall be taken.
OO Loop 1 to Ground lL
' Loop 2 to Ground 3.1.3 Continuity Verification Circuit continuity shall be verified by measuring and recording
' the circuit resistance of loop 1 and loop 2.
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' It 23.2. Steam Accident' Test -
The test assembly shall be installed in the test chamber with 'the L c'onduit ' opening oriented downwa rd . - The enclosure door shall be clasped' shut using the enclosure sounted hardware. The test specimens shall- be _' electrically energized as shown in Figure ,2. -
With the test assembly- energized, the test assembly shall be
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subjected = to the following steam profile (see Figure 3):
b 150 to 300'F in 30 seconds E 300'F/15 pais minimum for 1 minute (not including ramp) 250'F/10 psig minimum for~ 29 minutes ,
230'F/5 pois, miniava for 99.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
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.During the accident test, leakage current shall_ be recorded on a detalogger- every 10 seconde for the first 5' minutes, every minute - J '
for the next 30 minutes and .every 20 minutes thereafter. The leakage .cerrent monitoring loop shall be capable of asasuring i i l
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ailliasp.. IR measurements shall be taken _once during- the first' i
'y 30' minutes and at approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 8 houre and W ry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. !
O t' Chamber temperature shall be ' recorded using at least 2 thermo '
LO,, couples 'that, are connected-.to a datalogger or strip recorder. [
The thermocouples shall be located within 2. inches of the test assembly. Pressure shall be measured by using pressure trans- l ducers of 3% or better accuracy. .;
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'N 3.3 Functional Teses L;
. Subsequent to the steam accidant test, the chamber shall be
' opene d - . and ,the - test asstably allowed to cool' to ambient .
l1 ~ conditions. The test' assembly . shall not ;be removed 'from the 'I L. i
[F chamber or handled be fore the: functional test. The functional-h tests described in Paragraph 3.1 shall be repeated, op
'3.4 . Notices of Anomaly Patel Engineers _shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the encountered during performance of occurrence of anomalies testing. - After verbal notice, a written account of 'the anomaly
, and its disposition shall be forwarded to Patel.~ f n .
3.5- Reports ,
lir The report shall de scribe the requirements, procedures, and q results for this cast program.
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FIGURE 2 k' ACCIDENT TEST CONFIGURATION 4
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FIGURE 3 l'
ACCIDENT TEST PROFILE
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Post Accident Visual Inspection, 12/16/86 8
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Contact Report oft p Follow-Up Datet' 12/16/86
- Dste of Contact c..scy(Or .CCL C=p:ny 0 P.-0. Box 30096.
Addrsss-Raleigh, North Carolina 27622 I -
l- Phtno Peta-Rutten. Technician horson(s) Don Hatmaker, Test Engineer Contacted and Title' Limitorque Wire Post Accident Inspection hrme .
Discussion 1. Reviewed test data and ROAs - oraliminary conien nrovided.
- 2. Re-check IR with same results as post accidente annroximately 600 Kohmm. 'I
- 3. No damage =of conduit seal penetratica.
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In = 4. IR taken uoon removal f rom chamber 4-600 Kohan.
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- 5. "C" cable appears to have some dearee of damane (fraving) where it is
-9 I touching lef t' side of junction box.
g 6.' Water standing in bottom of junction box - surf ace layer, ,
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(- 7. 71ood level not visually discernable. 'Pete's evaluation of data and other' observations have convinced him that water level was above thermocouples
-which is higher.than test specimen, 1.e., specimen was completely submerged.
' ' 8. ' C cable was separated from side of junction ~ box - no change in IR. ~!
'! When cable was- pressed against junction box,'IR went to 0 - dead short. .
i A -9. B cable /end splice-had similar damage appearance as C cable, but not as.
gl extensive. -
10.-When Soecimens "B" and "C" were both seoarated from the enclosure-walls.
the IR increased to 40 Mohma.
i Action Ite:::
1 Co\-pSes To PEI-TR-870200-02, Bob Minadeo, Gary Elam 4
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~PEI Form No.,625 - 6/ d2?
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