Summary of Test Report 06-8680-003, Revision 1Nuclear Component Qualifi cation Test Report for theGeneric Qualifi cation of Weed Instrument CompanyTemperature Sensor Assemblies
Originally Prepared for Weed Instrument Company
By Southwest Research Institute (SwRI), June 1987
DELIVERING CRITICAL MEASUREMENTS
Nuclear Sensors & Process Instrumentation
UE-11-13-ue swri test report 3.indd 1UE-11-13-ue swri test report 3.indd 1 7/3/13 1:16 PM7/3/13 1:16 PM
The report is a summary of Reference Document Number 06-8680-003, Revision 1, “Nuclear Component Qualifi cation
Test Report for the Generic Qualifi cation of Weed Instrument Company Temperature Sensor Assemblies”. The testing was
performed using the IEEE standards and completed in 1987 by Southwest Research Institute.
An analysis made in 1991 affi rms (refer to document 0010-001-0005) that even though the seismic testing was performed
under IEEE 344-1975, the items are qualifi ed in accordance with IEEE 344-1987.
ConclusionsThe test items were successfully aged to a 40 year end-of-service-life condition. The aging performed included radiation,
thermal, humidity, and vibration. The test items were found to be functioning normally after aging tests were performed.
Resonance searches were performed on the test items in the frequency range of 1-100-1 Hz. The test items underwent
seismic qualifi cation testing, during which the items’ operations were monitored. The test items were monitored before,
during and after each seismic qualifi cation test with no signs of abnormal operation for any test performed. There was no
physical damage due to seismic testing.
The test items underwent temperature, pressure, and chemical spray profi les. The post test inspection revealed discoloration
and residue on the sensors. This is a normal, expected condition due to exposure to the environment and chemical spray.
Although this condition does not affect the operability of the sensors, it is considered a change from the as-received
condition and was documented. There were no failures during the test.
Subsequent to radiation, seismic, and LOCA testing, the items underwent a calibration check. The results of these calibration
checks were compared against the pre-test calibration check. The items passed the required qualifi cation tests.
Nuclear Sensors & Process Instrumentation
2
UE-11-13-ue swri test report 3.indd 2UE-11-13-ue swri test report 3.indd 2 7/3/13 1:16 PM7/3/13 1:16 PM
Test Items
Table 1: Summary of Test Items
Style Model ID NumberNumber of Elements
Aging Seismic LOCA
RTD
612S1-B 1 Y Y N
S1-C 1 Y Y Y
N9007S2-A 1 Y Y N
S2-B 1 Y Y Y
N9004S3-A 1 Y Y Y
S4-A 2 Y Y Y
602S6-A 1 Y Y N
S6-C 1 Y Y Y
TC
N9018S-8C 1 Y Y Y
S9-A 2 Y Y Y
N9013S10-C 2 Y Y Y
S10-D 2 Y Y N
Drawings of the test items are on page 10Model 602 Spring-loaded, tapered RTD/thermowell assembly with single-hub connection head and Al2O3 sheath
insulation.
Model N9007 Direct immersion RTD assembly.
Model N9004 Tapered tip, fast time response RTD/thermowell assembly with single-hub connection head.
Model 612 Spring-loaded, tapered RTD/thermowell assembly with dual-hub connection head and MgO sheath
insulation.
Model N9018 Ambient air/steam leak thermocouple assembly with single-hub connection head.
Model N9013 Strap-on Style Thermocouple Sensor.
Summary of Test Report 06-8680-003
3
UE-11-13-ue swri test report 3.indd 3UE-11-13-ue swri test report 3.indd 3 7/3/13 1:16 PM7/3/13 1:16 PM
Test Sequence
Aging
Radiation
Radiation aging was performed using a number of Cobalt 60 sources. The sources were arranged to give an even dose rate
to the items. The test items were instrumented with twenty dosimeters at the start of the radiation aging to measure the
total integrated dose received by the items. The test items were irradiated for 144 hours, 31 minutes for a total integrated
dose of 3.06 x 108 rads. Radiation aging and accident were combined into a single test.
Thermal
The test items were thermally aged at +140ºC for 32.04 days to a simulated end-of-service life of 40 years. The Arrhenius
equation was used to calculate the aging parameters.
ln (ts/ta) = (ø / 0.8617 x 10-4) (1/Ts – 1/Ta)Equation 1: Arrhenius Aging
Where:
Ts = normal service temperature = 330.2ºK (135ºF, 57.2ºC)
ts = service time = 3.504 x 105 hours (40 years)
Ø = activation energy constant = 0.87 eV
Ta = aging temperature = 413ºK (140ºC)
ta = aging time = 761.7 hours (32 days)
Humidity
The humidity tests consisted of placing the items in a chamber and exposing them to conditions of +120ºF and ≥95% RH for
240 hours.
Vibration
The test items were mounted in a fi xture and vibration aging was performed in each of their three axes. Each axis consisted
of 90 minutes of logarithmic sine sweeps in the frequency range of 5-200-5 Hz. The input excitations used were 0.025 inches
peak-to-peak displacement from 5-25 Hz, crossing over to 0.75 g peak acceleration from 26-200 Hz. The sweep rate used
was 2.0 octaves/minute.
SeismicThe test items were mounted in the fi xture just as they were for vibration aging.
Resonance Search
Resonance searches were performed by inputting uni-axial excitation into the items’ three principal axes. The orientation of
the test items was such that only two input axes were used to cover the three required test axes. This was possible because
of the twelve items, there were two of each model. The resonance searches were performed using a 0.2 g peak input with a
logarithmic sweep of 1-100-1 Hz, at a sweep rate of 0.5 octaves/minute.
Nuclear Sensors & Process Instrumentation
4
UE-11-13-ue swri test report 3.indd 4UE-11-13-ue swri test report 3.indd 4 7/3/13 1:16 PM7/3/13 1:16 PM
Random Motion
After the resonance searches, full level seismic tests of 30 seconds duration were conducted for each of the test items’ two
orientations. The seismic tests were conducted with a +10% margin added to the required response spectra (RRS) shown
below. During the seismic qualifi cation testing, the items were monitored for operation.
Five Operating Basis Earthquake (OBE) level tests
Figure 1: OBE RRS
One Safe Shutdown Earthquake (SSE) level test.
Figure 2: SSE RRS
Sine-Beat Random Input Motion (RIM)
After the OBE and SSE tests, the test items underwent sine-beat testing in each of their three principal axes. The sine-beat
testing was performed in the frequency range of 1-50 Hz at 1/3 octave increase in frequency. Acceleration levels used at
each frequency were obtained from the curve below. The test items were monitored for proper operation.
Summary of Test Report 06-8680-003
5
UE-11-13-ue swri test report 3.indd 5UE-11-13-ue swri test report 3.indd 5 7/3/13 1:16 PM7/3/13 1:16 PM
Figure 3: RIM RRS
Loss Of Coolant Accident (LOCA)
The test items were installed in a single test vessel measuring 39” long and 24” in diameter. Two temperature and pressure
spikes were applied following the profi les shown below. A suffi cient quantity of chemical solution for the chemical spray
was pre-mixed and stored in a holding tank. The solution consisted of 2750 ppm Boron dissolved in water and adjusted to
pH of 10.7 with sodium hydroxide. The chemical spray fl ow was from 0.1 to 0.2 gpm. It was initiated as shown in Figure 5
and provided a 104-hour exposure.
The profi le also simulates 2 years post-LOCA operational service condition.
Nuclear Sensors & Process Instrumentation
6
UE-11-13-ue swri test report 3.indd 6UE-11-13-ue swri test report 3.indd 6 7/3/13 1:16 PM7/3/13 1:16 PM
Figure 4: LOCA 1st Spike Figure 5: LOCA 2nd Spike
Summary of Test Report 06-8680-003
7
UE-11-13-ue swri test report 3.indd 7UE-11-13-ue swri test report 3.indd 7 7/3/13 1:16 PM7/3/13 1:16 PM
Observed ChangesChanges in the sensor calibrations as the tests proceeded are tabulated below.
Table 2: RTDs, 290ºC
Model ID NumberPre-test(ohm)
Post-radiation(ohm)
Post-seismic(ohm)
Post-LOCA(ohm)
612S1-B 0.0 -0.08 -0.09 not tested
S1-C 0.0 -0.01 -0.01 -0.08
N9007S2-A 0.0 -0.03 -0.04 not tested
S2-B 0.0 +0.02 -0.02 -0.04
N9004
S3-A 0.0 0.0 0.0 +0.01
S4-Aa 0.0 0.0 0.0 -0.02
S4-Ab 0.0 -0.01 0.0 -0.02
602S6-A 0.0 -0.02 -0.01 not tested
S6-C 0.0 -0.02 +0.03 -0.01
Table 3: RTDs, 100ºC
Model ID NumberPre-test(ohm)
Post-radiation(ohm)
Post-seismic(ohm)
Post-LOCA(ohm)
612S1-B 0.0 +0.01 -0.02 not tested
S1-C 0.0 0.0 -0.01 -0.02
N9007S2-A 0.0 -0.01 -0.02 not tested
S2-B 0.0 -0.01 -0.06 -0.02
N9004
S3-A 0.0 -0.01 -0.02 -0.01
S4-Aa 0.0 0.0 -0.01 -0.01
S4-Ab 0.0 0.0 -0.02 -0.01
602S6-A 0.0 -0.01 -0.03 not tested
S6-C 0.0 0.0 -0.01 0.0
Nuclear Sensors & Process Instrumentation
8
UE-11-13-ue swri test report 3.indd 8UE-11-13-ue swri test report 3.indd 8 7/3/13 1:16 PM7/3/13 1:16 PM
Table 4: RTDs, 0ºC
Model ID NumberPre-test(ohm)
Post-radiation(ohm)
Post-seismic(ohm)
Post-LOCA(ohm)
612S1-B 0.0 0.0 0.0 not tested
S1-C 0.0 0.0 0.0 0.0
N9007S2-A 0.0 -0.02 -0.03 not tested
S2-B 0.0 -0.02 -0.02 -0.03
N9004
S3-A 0.0 0.0 0.0 0.0
S4-Aa 0.0 -0.01 0.0 -0.01
S4-Ab 0.0 0.0 0.0 0.0
602S6-A 0.0 0.0 0.0 not tested
S6-C 0.0 +0.01 +0.01 +0.01
Table 5: Thermocouples, 100ºC
Model ID NumberPre-test
(ºC)Post-radiation
(ºC)Post-seismic
(ºC)Post-LOCA
(ºC)
N9018
S8-C 0.0 +0.4 0.0 +0.1
S9-Aa 0.0 0.0 -0.3 -0.6
S9-Ab 0.0 0.0 -0.2 -0.5
N9013
S10-Ca 0.0 +0.1 -0.1 0.0
S10-Cb 0.0 +0.1 +0.2 -0.1
S10-Da 0.0 +0.5 +0.3 not tested
S10-Db 0.0 +0.5 +0.5 not tested
Table 6: Thermocouples, 0ºC
Model ID NumberPre-test
(ºC)Post-radiation
(ºC)Post-seismic
(ºC)Post-LOCA
(ºC)
N9018
S8-C 0.0 0.0 +0.3 +0.2
S9-Aa 0.0 -0.2 -0.5 -0.6
S9-Ab 0.0 -0.2 -0.6 -0.4
N9013
S10-Ca 0.0 +0.4 +0.3 +0.1
S10-Cb 0.0 +0.5 +0.6 +0.1
S10-Da 0.0 +0.1 +0.1 not tested
S10-Db 0.0 +0.4 +0.5 not tested
Summary of Test Report 06-8680-003
9
UE-11-13-ue swri test report 3.indd 9UE-11-13-ue swri test report 3.indd 9 7/3/13 1:16 PM7/3/13 1:16 PM
Test Item Drawings
Figure 6: Model 612
Figure 7: Model N9007
Figure 8: Model 9004
Figure 9: Model 602
Nuclear Sensors & Process Instrumentation
10
UE-11-13-ue swri test report 3.indd 10UE-11-13-ue swri test report 3.indd 10 7/3/13 1:16 PM7/3/13 1:16 PM
Figure 10: Model N9018
Figure 11: Model N9013
Summary of Test Report 06-8680-003
11
UE-11-13-ue swri test report 3.indd 11UE-11-13-ue swri test report 3.indd 11 7/3/13 1:16 PM7/3/13 1:16 PM
DELIVERING CRITICAL MEASUREMENTS
Nuclear Sensors & Process Instrumentation
Ultra Electronics reserves the
right to vary these specifications
without notice.
© Ultra Electronics 2013.
Printed in USA
Rev 1, Pub. 0015-002-1119
07/13
Ultra ElectronicsNUCLEAR SENSORS & PROCESS INSTRUMENTATION707 Jeffrey Way, PO Box 300Round Rock, TX 78680-0300 USATel: +1 512 434 2800Email: nuclear@ultra-nspi.comwww.ultra-nspi.comwww.ultra-electronics.com
This document is not intended to serve as a design document and
is subject to change. Actual specifications are per customer order.
UE-11-13-ue swri test report 3.indd 12UE-11-13-ue swri test report 3.indd 12 7/3/13 1:16 PM7/3/13 1:16 PM