ML20064A696
| ML20064A696 | |
| Person / Time | |
|---|---|
| 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) | |
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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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l 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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P. O. No. 263120 PEI J/N 8702 i
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Tost Prcccdure No PEI-TR-870200-01 I
Page No.,i TECHNICAL-DOCUMENT 7t.
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. DOCUMENT TYPE
-Test Procedure (REPORT / PLAN / PROCEDURE)-
PEI-TR-870200-01 DOCUMENT No.:
ORIGINAL ISSUE DATE:
December 2, '.986 I
Test Procedure for Steam Accident-Test of
- TITLE:
Limitorque Control and Power Wiring and
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Okonite Tape Splices
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PROJECT ENGINEER:
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PROGRAM MANAGER:
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' GROUP / DIVISION DIRECTOR:
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PEI Form No. 611 - Rev. 2/1984 t
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N Tes t. Pescedure ? N3. - PEI-TR-870200-01 G
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. TABLE OF CONTENTS t
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1.0 SCOPE...............................
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1.1: Test Assembly Description..
1 11.2 Test Sequence.......................
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1
- 2.0' TEST-REQUIREMENTS........................
1 2.11 Instrumentation......................
2 2.1.1 Calibration....................
2 2.2--Acceptance Criterie....................
f.!I 2
/13.0 TEST FROCEDURES..........................
T-L3.1' Functional Tests.
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2
I 1.1
.V is ual - Ins pe c t ion........ -.........-
.1.2-Insulation Resistance (IR)............
2 4
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3.1.3
-Continuity Yorification...........-..
2-.
3
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3.2' Stean-Accident Test............-.........
-3
- 3. 3. Fun c t iona l Te s t s. -......................
3 3
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-3.4 Notice'of. Anomaly................=......
3 33.5;- Reports............................
LN LIST OF FIGURES 4
Figure.l.
' Tes't A'ssembly Configuration........ -....
5.
~ Figure-2..
. Accident. Test Configuration......
6-g Figure 3.
Accident Test Profile.............
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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.
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1monel in-valve operators MS-M0-M077 and MS-MO-M078, 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 7.3.26.
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.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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- Tast Pracadure Nr. PEI-TR-870200 j IJ 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 simulation. shall not exceed _30 milliamps-for loop 1 and 300-y 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
will' A ' visual inspection shall be performed.
This -inspection assure that the: equipment has not received' any_ obvious visible k
-damage during shipping-and handling.
Equipment identification L. [J e will also be verified.
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i 3.1.2 Insulation Resistance (IR) y The insulation resistance of the test specimens shall be measured
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f at 500 VDC for 1 minute and shall be recorded. The following IR measurements-shall be taken.
y-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 300'F/15 pais minimum for 1 minute (not including ramp)
E 250'F/10 psig minimum for~ 29 minutes
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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 />
.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
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ailliasp.. IR measurements shall be taken _once during-the first' l
i 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
'y W ry 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.
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Chamber temperature shall be ' recorded using at least 2 thermo '
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couples 'that, are connected-.to a datalogger or strip recorder.
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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.
K'N 3.3 Functional Teses L;
. Subsequent to the steam accidant test, the chamber shall be l1 ~
' opene d -. and
,the - test asstably allowed to cool' to ambient L.
conditions. The test' assembly. shall not ;be removed 'from the
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[F chamber or handled be fore the: functional test. The functional-i 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 occurrence of anomalies encountered during performance of testing. - After verbal notice, a written account of 'the anomaly and its disposition shall be forwarded to Patel.~
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3.5-Reports lir The report shall de scribe the requirements, procedures, and q
results for this cast program.
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ACCIDENT TEST PROFILE
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APPENDIX III Post Accident Visual Inspection, 12/16/86 8
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' J hnny F. Jankins-b Tolophenot Visitt Contact Report oft p
12/16/86 Follow-Up Datet'
- Dste of Contact c..scy(Or
.CCL P.-0. Box 30096.
C=p:ny 0 Raleigh, North Carolina 27622 Addrsss-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.
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- 2. Re-check IR with same results as post accidente annroximately 600 Kohmm.
- 3. No damage =of conduit seal penetratica.
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= 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 j
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-9 touching lef t' side of junction box.
g 6.' Water standing in bottom of junction box - surf ace layer, i
- 7. 71ood level not visually discernable. 'Pete's evaluation of data and other'
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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.
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When cable was-pressed against junction box,'IR went to 0 - dead short..
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-9. B cable /end splice-had similar damage appearance as C cable, but not as.
A extensive.
gl 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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