summary of test report 06-8680-003, revision 1 · pdf filesummary of test report 06-8680-003,...

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.


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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

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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.


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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.


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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.


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Figure 4: LOCA 1st Spike Figure 5: LOCA 2nd Spike


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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


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


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Table 4: RTDs, 0ºC


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


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Test Item Drawings

Figure 6: Model 612

Figure 7: Model N9007

Figure 8: Model 9004

Figure 9: Model 602


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DELIVERING CRITICAL MEASUREMENTS


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.


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