ML19344A663: Difference between revisions
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0 320 F AUTOCLAVE CHAMBER TEST SET-UP | 0 320 F AUTOCLAVE CHAMBER TEST SET-UP | ||
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Latest revision as of 19:26, 15 March 2020
| ML19344A663 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/14/1979 |
| From: | Delong R, Lawford V, Spady R INTERNATIONAL TELEPHONE & TELEGRAPH CORP. |
| To: | |
| Shared Package | |
| ML19344A659 | List: |
| References | |
| 05991, 5991, R3-580-1, NUDOCS 8008210416 | |
| Download: ML19344A663 (63) | |
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REPORT NO. R3-580-1 l 800821ogIG
l - l l l l' PROCESS INSTRUMENTS AND CONTR'OLS 900 South Turnbull Canyon Road, City of Industry, California,91747 h
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sj CLASS 1E PRE-QUALIFICATION TESTS
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$c REPORT NO. R3-580-1 l Authored by [ w c/ Date(!f79 R. J.70elo [ b u dt Engineer
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Approved by i /9 000b / t.tl Date 6!!4!79 ' ' f V. N. Lawford, Eng/ ineering Mgr. , DPU/DCI ' ?l
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Approved by _Date[I N R. d. y, ector of Engineering I l Approved by /k k }A )1 [ Date / Al M ,s . , 7 9 G. R. Welt. Director of Quality Assurance
t - TABl_E OF C0flTEllTS PAGE NO. 1.0 SCOPE
- 1
2.0 INTRODUCTION
1
- 3. 0 REFERENCE DOCUMENTS 2 4.0
SUMMARY
3 5.0 TEST PROGRAM 3 5.1 . SELECTION 3 5.2 AGING 4 5.3 RADIATION 4 5.4 SEISMIC VIBRATION 5 5.5 POST-ACCIDENT TESTS 5 6.0 PERFORMANCE CRITERIA 6 7.0 g OVALIFICATION TEST 6 7.1 TEST SEQUENCE 6 7.2 AGING 7 7.3 RADIATION 9
, 7. 4 SEISMIC TEST 12 7.5 POST-ACCIDENT TESTS 44
8.0 CONCLUSION
S 52 APPENDIX 53 D2-10-3B DOCUMENT NUMBER SEET REV CODEIDENT I ,I,,I, BARTON CRY OF INOU5TRY,CA.91749 NUMBER R3-580-1 micanationai. vetemone suo vettanAm coneonation 05991 11 i
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y - C_LfS,5 1E PRE-0UALIFICATION TESTS FOR ITT BARi'07: DIFFERENTIAL PRESSURE SWITCH MODEL 580
- 1. 0 SCOPF; The purpose of this document is to record the events and results of a pre-qualification test performed on a differential pressure switch Model 580.
The performance criteria and tests performed were based on normal operating conditions associated with a nuclear power generating station. The unit was subjected to a sequence of tests in accordance with IEEE 323-1974 and IEEE 344-1975. The sequence of tests performed were aging, radia-tion, seismic, LOCA (Loss of Coolant Accident). - An additional test, steam impingunent was perfomed to determina the effects of a steam line break directly on the test instrument.
2.0 INTRODUCTION
The Model 580 Differential Pressure Switch is intended for safety-related Class IE functions in nuclear power generating stations. The Model 580 can be used as a local indicator monitoring differential pressure while internal switches provide circuit actuation for controlling pumps, motors, alams as well as systems critic 21 to the safe shutdown of a nuclear power generating station during and af ter a postulated Design Basis Event (DBE). The test unit is similar in construction to the ITT Barton Model 288A. It utilizes the same differential pressure unit, switch mechanism and meter movement. The primary difference is in the cirtually hermetically sealed D2-10-33 cooE icm l occuMENT NUMBER SMiiET REV I ;IoI, BARTON CITY OF INousTRY, CA. 91749 'UM9Eh R3-580-1 1 tNTERNATIONAL TCLEPHONC AND TELEGRAPH CORPORATION 05991
- h. .
t - case. With this as a basis for the Class 1E Model 580 design comes a proven listorical record of high integrity and documented reliability. This report describes the procedures, testing and on-going references utilized to demonstrate the margin available before initiation of a generic qualification program. Selected margins of test intensity were induced to demonstrate the instruments adequacy to perform required functions after exposure to radiation, seismic vibration and steam environment conditions. Pre-qualification testing of the differential pressure switch Model 580, serial number 778-001 began on 10/24/78 and was completed on 02/26/79 and will hereafter be referred to as the test unit. Quite of ten, a test program of this type requires greater stresses on the test equipment and test set-up than on the unit under test. This will + become evident to the reader during the content of this test report. 4 3.0 REFERENCE DOCUMENTS 3.1 IEEE 323 (1974) Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations 3.2 IEEE323(1971) Standard for-Qualifying Class 1E Equipment for Nuclear Power Generating Stations 3.3 IEEE 344 (1975) Reconnended Practices for Seismic Qualification ( of Class 1E Equipment for Nuclear Power Generating Stations ( 3.4 IEEE381(1977) Standard Criteria for Type Tests of Class 1E ( Modules used in Nuclear Power Generating Stations 3.5 ITT Barton Reports in Appendix 3.6 Model 580 Specification Drawing 0580.1066.3 f 3.7 ITT Barton D.P. Switch Qualification Test Procedure 9999.3083.2 { SHEET REV D 2-10 '5B CODEIDENT DOCUMENT NUMBER I ,!,,!, BARTON clTY or INoVSTRY,CA.91749 NUMBER g INTERNATIONAL TELEPt40NE AND TELEGRAPM CORPORATION 05991 ( a (
i 4.0
SUMMARY
Type tests were performed to determine the margin of safety in the design of the Model 580 before undergoing a generic qualification program. The tests were also tiesigned to obtain information to supplement on-going tests for information to demonstrate a qcalified life with an acceptable margin for most Class 1E applications. TEST METHOD RESULTS Aging: 265 F for 140 hours. Not available because of test ' set-up breakdown. Recalibrated I to 1% full scale. 7 Radiation: 5 X 10 Rads gamma. 3.25% max. after exposure. Seismic: Biaxial Random Motion Totals of 7 OBE's and 2 SSE's. Equalization near same No recalibration required after amplitude for vertical events. and horizontal motion. 0 Steam 320 F 7-day profile Test unit remained within specifi-k Environment: with double ramp for margin. cation. 0 650 F Steam Impingement For information purposes. with doub.le ramp for mar-gin. 5.0 TEST PROGRAM 5.1 Selection The test unit was fabricated from prototype parts using specification controlled documents. Test unit was assembled by ITT Barton lab personnel with Quality Assurance Department personnel verifying 1st article compliance. D 2-10 '5B CODE 10ENT DOCUMENT NUMBER SHEET REV
! ,I,1, BARTON cif Y OF INou$TRY, CA. 9174 9 NUMBER R3-580-1 3 INTERNATIONAL TELEPHONC AND TELEGR AN CORPORATION 05991
A differential pressure range of 0-200 psi and a safe working pressure j of 1500 psi was selected as one of several ranges used in nuclear service. The small bellows construction is taxed to greater extremes when cycled or actuated demonstrating a worse case condition. 5.2 Aging The test instruments were subjected to 2650F (1300C) for 140 hours while cycling between 80 psi and 120 psi at a rate of 12 cycles per minute. This produces 1 X 105 operational cycles. A circuit pro-ducing one (1) amp current at 125 VAC (60 Hz) was applied to each__ __ -._ switch. i ITT Barton is conducting on-going qualification testing of similar units to demonstrate the imunity of the basic bellows / torque tube assembly from long-tem mechanical cycling effects. Interim reports (listed in Appendix) descrih> the long-term mechanical 4 cycling effects at various differential pressure ranges using a variety of cycling rates and temperatures. The same basic bellows / ; I torque tube / meter movement / switch mechanism assembly has been ! utilized in ITT Barton differential pressure switches with operating j history in nuclear power plants for approximately 10 years. 5.3 Radiation After aging, the test unit was subjected to an exposure of 5 X 10 7 Rads gama radiation. A cobalt 60 source was used to provide the gamma radiation. The dose was applied at a conservative rate 1 of 2.5 X 10 6Rads / hour. The rate was selected to provide an I additional safety margin over assumed values of expected release of radiation during a Design Basis Event. l l D2 W cooE :oENT DOCUMENT NUMBER SHEET REV BARTON CITY OP INousTRY,CA.91749 NUMBER , , intaanation=L vetemouc ano Tetconam coneonation 05991 b
4 . f.4 Seismic Vibration After radiation, the test unit was seismically tested by using a sine sweep resonance search followed by biaxial random motion with sequential Operating Basis Events (OBE) followed by a Safe Shutdown Event (SSE). Each sequence was performed on two fixture orientations 90 from each other (see Figure 1). A generic Required Response Spectrum (RRS). was determined from a broad-band composite of currently published spectrums. Testing margins were developed for the Test Response Spectrum (TRS) by using 5% damping and OBE's being 70% of the SSE required response spectrum. Resonance search data was taken for infomation purposes only as an aid for future RRS's whic.h may exceed the generic RRS developed. 5.5 Post-Accident Tests After seismic vibration events, the test unit was subjected to a saturated steam (LOCA) profile consisting of an initial temperature (320 F) transient with 3 minute dwell (for margin), cooling to ambient followed by a 7-day profile of 320 0F transient / dwell and decaying to 220 F simulating accident and post-accident conditions (refer Figure 30). After the 7-day LOCA test, a steam impingement test was performed. This test exceeds the re' uirements of IEEE 323 and simulated a steam line rupture. The t'est unit was subjected to a super-heated steam jet profile consisting of an initial temperature (550 F) transient with 3 minute dwell, cooling to ambient followed by another 650 F transient with 5 minute dwell and decaying to 3400 F, remaining at this temperature for Iba hours followed by a decay to 2500 F for h2 hour. 1 i
; D 2-10-3B CODE IDENT DOCUMENT NUMBER M ET REV
! ,!,,! NUMBER
- BARTON CITY OF INDUSTRY, CA.91749 INTERNATIONAL TELEPHONE AND TELEG A APH CORPCM ATION 05991
f 9 . 6.0 PERFORMANCE CRITERIA Perfomance criteria was not established for purposes cf this test. This program was implemented to verify pressure boundary integrity, radiation effects on no*n-metallics, and set point conditions during a postulated Design Basis Event (DBE). Discussion of results will be presented within this report. 7.0 QUALIFICATION TEST The test unit was subjected to simulated service conditions in accordance with the preferred method of IEEE standards and generally accepted engineering p ractices.
- Qualification " catisfied if the equipment to be tested is aged, subjected to environmental influences and operated ander post-DBE conditions. The type test was a planned sequence of test conditions that took into account
+ both nomal and abnormal operation with an emphasis on demonstrating margin 4
for abnomal operation. The type tests were perfomed (using ITT Barton procedures listed in Appendix) at ITT Barton and vendor test lab facilities. The appendix contains certi-fications and equipment lists. The type tests were performed on Model 580 S/N 778-001 validated by ITT Barton QA to drawings and test procedures. The unit was tested by personnel not directly responsible for the design of the product with assistance from the design group in the formulation of additional demonstration tests. 7.1 Test Sequence A. Aging - Cycling while at continuous elevated temperature. l B. Radiation D2-10-35 cODEIDENT DOCUMENT NUMBER SHEET REV IaInsi' BARTON clTY OF INous1RY, CA.91749 NUMBER R3-580-1 5 iNTERNAriONAL TELENONE AND TELEGRAPH CORPORATION 05991 h ,
Y C. Seismic Vibration D. Post-accident Tests 7.2 Aging The metkod of extending periods at high temperature address an inter-pretation of aging by temperature half-life regressions. 7.2.1 Test Procedure The aging portion of the test was performed at Wyle Labs in Norco, California. The unit was mounted on a typical panel utilizing the wall mounting brackets. A static pressure of approximately 120 psi was applied with a ! differential pressure of 100 psi to provide the unit with a 50% indication. A cormierical cycling fixture was used to modulate the pressure to obtain.the cycling rate and span. The switches were energized with a 1 amp,125 VAC (60 Hz) circuit. 7.2.2 Discussion of Aging ' Sufficient history and on-going tests clearly show negligible effects could be expected by mechanical cycling. Reference j to reports on mechanical cycling are included in the Appendix. Several methods have been used to demonstrate cycling under constant temperatures and varying temperatures along with full scale excursior.s. History has indicated that by various methods of mechanical cycling, the performance is essentially the same. The reports are justified as they represent the effects on instruments using the same bellows configuration which has been used for over 10 years in nuclear service and used on this test unit. D2-lO ~5B cODEIDENT' DOCUMENT NUMBER SHEET REV
-I ,I,iI; BARTON clTY OF INDUSTRY, CA. 91749 NUMBER R3-580-1 7-INTE ANATIONAL TELEPHONE AND TELEG A APM CORPORATION 05991 i 1
4 - 1
t The complex issue of aging non-metallic components was addressed by demonstration and results of on-going tests. Arrhenius and inverse stress models along with correlation to the so called 10 degree rule are under study. Conservatism is desired in selecting the proper activation energies' but test programs on-going at Barton indicated the .5 ev is an overkill to some components. Apparent small changes in activation energies significantly increase or decrease the aging period. The thermal aging period of 140 hours was based on program time available and vendor equipment avail-ability for the required next test sequence. _. The limiting factor of aged projected qualified life in the 4 Model 580 would appoar to be the instruments secondary seals. The primary process pressure boundary seals along with other non-metallic components could easily be replaced at a specified interval if required. However, the secondary seals are of the same materials as the primary process boundary seals and cannot be replaced without complete factory dissassembly. Therefore, by demon:tration and on- l going tests, the unknown radiation effects before temperature
- r. !
on all seals and other non-metallic components was included as part of the pre-qualification test sequence. No statement of qualified life for generic qualification will be made at this time. A qualified life statement D2-10-3B CODE 10ENT DOCUMENT NUMBER SHEET REV
! ,I,'I, BARTON ctTY OF INousTRY, cA. 91749 NUMBER INTERNATIONAL TELEPHONC ANO TELEQRAPH CORPORATION 05991 A
requires specific inputs in developing a condition of tests to ad!ress or justify life within a specific environment. 7.2.3 Discussion of Aging Results
- There were two test conditions that negated a post-aging I functional test. The first was a malfunction in the cycling fixture that ceased to operate after 5 X 104 cycles. The I
second was when a short circuit developed across a terminal strip of the test set-up that caused an excessive current ' to be drawn through the units lead wires and switches. The excessive current melted the insulation exposing the bare conductors. The unit was reconditioned by replacing the switches and lead wires with ones of equal themal aging. The original p 0-rings were used when reassembled. The unit was recalibrated and data recorded.
- 7. 3 Radiation The unit was transported to Atomics International, Canoga Park, California for the radiation test.
7.3.1 The test unit was exposed to gamma radiation (cobalt 60) at a rate of 2.5 X 106Rads per hour for a total integrated dose of 5 X 10 Rads. The unit was not pressurized. Table 1 is a comparison of linearity data recorded before and af ter radiation exposure. D 2-10-33 CODEIDENT DOCUMENT NUM8ER #EET REV BARTON city 07 INousTRY.cA.91749 NUMBER INTERNATIONAR. TER.EPHONE AND TER.EQRAPH CORPORATION 05991 4 .
; TABLE 1 PRE / POST-RADIATION FUNCTIONAL DATA (UNITS PSI) 0 25% 50% 75% 100% 75% 50% _ 25% 0 Pre-radiation 0 50 102.0 153.0 200.0 151.5 99 49 0 Post-radiation -/5 48.2 98.5 146.5 199.5 147.5 100 50 .5 SWITCH SETTING i
LOW HIGH Pre-radiation 70.5 129.0 i Post-radiation 71.0 132.3 i 7.3.2 Discussion of Radiation Results From Table 1 the linearity change due to radiation exposure is 3.25% of full scale and switch actuation change of .25% of full scale for the low switch and 1.65% of full scale k for the high switch. ( l The tempered plate glass lens turned black and visual contact with the units scale and pointer was rendered impossible. The lens was removed and placed in a chamber 0 at 350 F for 2 hours. Visual clearness was now obtainable through the lens. It was then reassembled to the unit using the same 0-ring seal. l l The test unit could have been recalibrated to original condition, however, it was left in an as-is condition for
- the next test. .
t i D2-10-3B COoEIDENT DOCUMENT NUMBER SEET REV BARTON ClfY CF INDUSTRY CA.91749 NUMBER R3-580-1 10 invennanouai. rei.renonc Ano vctranaes coneonation 05991
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FIGURE 1 INSTRUMENT ORIENTATION ON SEISMIC TABLE D2-10-3B cODEIDENT DOCUMENT NUMBER 3HEET REV BARTON CITY OF INDUSTRY, C A. 9874 9 NUMBER R3- M -1 H INTERNAflONAL TELEPHONE AND TELEGR APH CORPORATION 05991 4 '
Radiation exposure rate of 2.5 X 10 6Rads per hour was selected to provide a margin of approximately double the dosage rate which would be expected according to published DBE conditions. 7.4 Seismic Test Seismic vibration was performed at Approved Engineering Test t.abora-tories, Chatsworth, California using a dual axis hydraulic seismic table to simulate an earthquake event. Input motion was biaxial random motion containing frequencies for maximum G levels over the range of 2.5 to 33 Hz. The test unit was mounted (Figure 1) to a
" bookend" fixture which in turn was bolted to the seismic table.
. Standard mounting brackets as specified were used to secure the test unit to the bookend fixture. 7.4.1 Test Procedure The test unit was pressurized with water (to simulate in-4 service conditions) for a differential pressure of approxi-mately 50% of full scale. The unit and fixture were mounted to the seismic table in the (XY) axis. A sinusoidal resonance search in the X direction was performed over the range of .1 to 40 Hz at 0.2G level using one octave per minute sweep. The test unit output was recorded on an oscillograph during the sinusoidal search. The oscillograph was monitored during testing for changes in output. The table input motion was returned to the frequencies of apparent output rhanges. The table motion was held at these frequencies for a period of approximately 15-30 seconds for a high speed oscillograph record to be taken. The same resonant search was perfonned in the Y direction. D 2-10 ~53 c00E 10ENT DOCUMENT NUMBER 35HEET REV
- BARTON clTY of INousTRY,CA.91749 NUMBER R3-580-1 12 invrawavionat vetemouc ano retranam coneonavica 05991
t The test unit was then subjected to 4 successive OBE events using dual (XY) axis random motion. The test plan called for 3 OBE's, however, the first OBE had shown an operator error in frequency setting which reduced the table response of the low frequency spectrum below 4 Hz. The correct setting was made and 3 successive OBE's were run. The OBE's were 70% of the SSE and based on 5% damping. The SSE was performed after conclusion of the OBE's. The unit and table fixture were relocated by rotating 90 on the seismic table for a YZ axis orientation (see Figure 3). Sinusoidal sweeps were run as previously for Y and X axis at 0.2G level and one octave per minute sweep to 40 Hz. The test unit was then subjected to 3 successive OBE events using dual (YZ) axis random motion. The OBE's were 70% of the SSE and based on 5% damping. The SSE was performed after conclusion of the OBE's. Oscillograph recordings were made to determine contact ch:tter. The test unit was returned to ITT Barton for functional test. Comparison of pre-seismic events calibration and ! post-test functional test is shown in Table 2. l l D 2-lO-1B cooE;OENT DOCUMENT NUMBER l9EET REV I ,Iii iI- BARTON ctTY OF WCUsTRY,CA. 91749 NUMBER intramarionat vetemouc ano vetcamans coneoaatica 05991 4 '
t TABLE 2 PRE / POST-SEISMIC FUNCTIONAL DATA (UNITS PSI) 0 25% 50% 75% 100% 75% 50% 25% 0 Pre-seismic -0.5 48.5 98.5 146.5 199.5 147.5 100.0 50.0 -0.5 Post-seismic 0+ 49.5 98.5 146.5 199.5 147.5 100.0 50.5 0 SWITCH SETTING LOW HIGH Pre-seismic 71.0 132.3 Post-seismic 73.3 127.6 7.4.2 Discussion of Seismic Results From Table 2 the linearity change due to seismic exposure is 0.5% of full scale and switch actuation change of 0.8% of full scale for the low switch and 2.35% of full scale g for the high switch. 4 Resonant searches in the X, Y, and Z axis showed no switch chatter during the sweep to 40 Hz. Units case mounted accelerometers did show some ir:reased amplitudes at 18, 22, and 27 Hz in the 3 axis, however, had no effect on switch chatter. Figure 2 shows the oscillograph records for the X axis, figure 3 shows the oscillograph records for the Y axis, and figure 4 shows the oscillograph records for the Z axis. Figures 5 through 22 show the response spec-trum of the OB_?'s and SSE's followed by an oscillograph record taken during the event. The two chart speeds enable the reader to measure switch chatter and correlate with the actual . unit case motion. It should be noted that a ITT D 2-10-3B CODE 10ENT DOCUMENT NUMBER stet REV BARTON CITY OF INDUSTRY, CA. 91749 NUMBER R3-580-1 14 INTEaNATIGNAL TELEPMONC AND ELEG AAP*4 COR*O'4ATION 05991
l Barton transmitter was tested at the same time and the I
" transmitter output" accelerometer response are not to be i regarded as any part of the units response.
The graphs show evidence of switch chatter at very high G levels. It should be noted that when chatter is evident l for a normal open contact that one occurs at the nomal closed ! contact also. This occurs when the units pointer is undar- i i 1 goir.g oscillation due to the combination of resonant " ' frequencies and high G levels. The switch chatter occurs ; I when the pointer / switch cam oscillates through the switch 6 set point. On-going tests have demonstrated that the switch, without the pointer, does not indicate contact chatter within these frequercies and acceleration levels.
> The five percent damping was used to subtantiate an adequate d
margin in testing. Figures 23 and 24 show a reduced spectrum which was perfomed for purposes of evaluation of the test unit. This test was run for infomation purposes only, but clearly shows no switch chatter. ' i i ! As a check on table response and a measure of random motion, 1 ! power spectral density plots of the table mounted accelerometers were run. The RMS vibration amplitude can be computed from the square root of the area under the curve at each frequency. These plots are shown in figures 25 i through 28. ) D 2-lO- 1B CODEtoENT DOCUMENT NUMBER 3EET REV IIInIi BARTON ci?y of INousTRY, CA.91749 NUMBER R3-580-1 15 l inreauariount vetemouc ano veteaamm con =onarica 05991 l 4 '
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t 7.5 Post-Accident Tests Saturated steam testing was performed at ITT General Controls, Glendale, California and the super heated steam testing was performed at Approved Engineering Test Laboratories (AETL), Chatsworth, California using two separate LOCA profiles. The 3200F saturated steam profile was performed first and then the 620 0F super heated steam profile after a functional test. The test set-ups are shown in Figure 29. 0 7.5.1 Test Procedures 320 F Profile No recalibration adjustments were performed after seismic vibration and that data was used as pre-test calibratien before the 320 F LOCA profile. The test unit was installed in a steam autoclave with a pressure input line connected to the high side. The low side was vented to the outside atmosphere. The electrical wiring was connected to extension wires and enclosed in a pressure tight conduit which was connected to the test unit. The unit was energized and 50% of full scale pressure applied. The units output was monitored during the total test time of 7 days. Stean and pressure were applied per the profile in Figure 30. 7.5.2 Test Procedures for Steam Impingement Profile No recalibration adjustments were made after the post-LOCA simulation functional test. The test unit was installed in an open chamber, which had one end with an opening which could be manually closed off. A super heated (1203 F) steam line was piped to within 6 inches of the transmitter. The steam was applied per the profile shown in Figure 31. Temperature measurements were made at the nozzle exit, on the D.P. switch case surface, and directly behind the D.P. switch. Since the D 2-10-3B cooEloENT DOCUMENT NUMBER SiEET REV i NUMBER DARTON CITY O' INDUSTRY CA.91749 R3-580-1 44 BNTERNATIONAL TELENONE AND TI. LEG AAPt4 CORPOR ATION 05991 j N
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l chamber was open at the nozzle end and there was a significant temperature drop across the D.P. switch, no ambient pressure was measurable even though the other end of the chamber was closed. The electrical wiring was connected to extension wires and l enclosed in a metal conduit which exited through the side of the chamber. The unit was energized and 50% of full scale pressure applied. Test Results: TABLE 3 TEMPERATURE MEASUREMENTS DURING STEAM IMPINGEMENT Nozzle exit Transmitter- Rear of Surface Transmi tter Maximum Temp. Recorded 6550F U 635 F 545 F 4 TABLE 4 PRE / POST-LOCA FUNCTIONAL TEST (UNITS PSI) 0 25% 50% 75% 100% 75% 50% 25% 0 Pre-LOCA 0 49.5 98.5 146.5 199.5 147.5 100.5 50.5 0 Post-LOCA 2.0 50.5 100.5 150.0 200.0 150.0 102.5 52.5 2.5 SWITCH SETTINGS LOW HIGH Pre-LOCA 73.3 127.6 Dost-LOCA 72.2 130.8 7.5.3 Discussion of Post-Accident Tests D 2-10-33 cooEIDENT DOCUMENT NUMBER SHEET REV I ,I,,I; BARTON CITY OP INDUSTRY, CA.91749 NUMBER R3-580-1 50 inrtanationat vctemouc ano retconAm conaoarrica 05991
t A reference differential pressure indicating instrument located outside the environmental chambers was fixtured f ri
, parallel with the test instrument. This enabled the test technician to record switch set point readings at various time intervals.
The unit was mounted in the test chamber 900 from normal attitude , with the lens facing upward. During the LOCA test, the low switch was rendered inoperative after 9 hours and the high switch became inoperative af ter 120 hours. At the conclusion of the 7-day test, the unit was removed from the test chamber and returned to ITT Barton. Investigation as to the probable cause was determined to be that the scale pointer hung-up at the center portion of the split scale. Whan the pointer was disengaged, a functional check was performed. Results of this functional test is fot.nd on Table 10. The instrument was reassembled using the same parts (0-rings, etc.) The next portion of the Post-Accident test is the steam impinge-ment. An initial spike of 550 F0was performed for 3 minutes. The swf tch set points remained within 3% of the pre-impingement test. A second spike at 650 F0 was induced. D2-10 5B cODEIDENT DOCUMENT NUMBER SiEET REV T BARTON CITY OF INCUS 1RY,CA.98749 NUMBER INTE ANAf TONAL TELEPteONE AND TELEGR apt 4 CORPORATION 05991
t - After 5 minutes at this temperature, the high switch a'ctuated remained actuated throughout the remainder of the test. After the test, the unit was returned to ITT Barton for analysis. It was determined there was insufficient static pressure applied for this temperature. The temperature compensating bellows expanded beyond this elastic limit, causing the pointer to shift up scale, thereby actuating the high pressure switch. The pressure boundary was still maintained.
8.0 CONCLUSION
S All pre-qualification tests (with additiona' safety margins over the specified acceptance criteria) were demonstrated. The tests were designed from a composite of known published nuclear power plant postulated DBE's. These % DBE's with nomal nuclear plant operating conditions were demonstrated through a sequence of test conditions recommended by IEEE. The test unit performance was monitored before, during and after the recomended sequence of test conditions. The intent of the pre-qualification test was verified and additional data was obtained to substantiate independent ITT Barton on-going test results. The test also verified independent qualification tests perfomed by licensees for I application to specific requirements and safety analysis. I i l Significant data was obtained dering the pre-qualification test to supplement ITT Barton on-going tests for answering some of the complex questions on aging. l D 2-10-3B ccOEloENT DOCUMENT NUMBEg acct HEV rE NUMBER l BARTON CMY OP tNDUSTRY CA.917J9 R3-580-1 52 l intrasanomat retrmonc nao retroaAm coneonario~ 05991
V i i I l I l l 1
) APPENDIX (
I Ii;I i D 2-10-3B' c0DEIDENT DOCUMENT NUMBER SNEET REV BARTON CITY OF INDUSTRY CA.91749 NUMBER R3-580-1 A-1 INTERNATIONAL TELEPHONC AND TELEGRAPM CORPORATION 05991 l N
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1 l l t 9 ITT BARTON ENGINEERING REPORTS l ON-GOING TESTS l R1-288A-13 Stability tests of snap switches. l 150,000 cycles through set point. 1,000 cycles 1.2% F.S. change in set point. 100,000 cycles 5.0% F.S. change in set point. 150.000 cycles 6.5% F.S. change in set point. Set point repeatability .25% F.S. R1-288A-16 Temperature effects on switch set points. ! l 0 j 75 to 212 F 5% F.S. change in set point. l R1-288A-19 Radiation effects on materials. 4 2 X 10 Rads No significant effects. k R1-396-1 Seismic tests. 10 G's at 10 Hz No effect on mechanical performance. 1 R1-322-7 Seismic qualification per IEEE 344-1975 Peak G's > 50 G's No contact chatter. R1-764-1 Pre-qualification tests for ITT Barton Pressure Transmitter, ! Model 764. I Aging, radiation, seismic, LOCA, steam impingement.......... ! per IEEE 323. 1 1 l i D2-lO-3B cODEloENT DOCUMENT NUMBER ' SHEET REV ! I ,I,,I; BARTON CITY CF INDUSTRY,CA.91749 NUMBER intcanariount vetemouc ano veteca4m conson=rica 05991 R3-580-1 A-3 1
~
TEST EQUIPMENT LIST USED FOR PRE-0VALIFICATION TESTS TEST , EQUIPMENT SOURCE
- Aging
- Edison cycles Wyle Labs.
Temperature chamber Radiation: Cobalt 60 Atomics Interna-i _. - tional (See Test chamSer Certification) . Seismic: See letter AETL LOCA: Autoclave ITT General Steam generator Controls 4 S te.am Impingement: Test set-up AETL Steam generator b D 2-10-3B CODEIDENT DOCUMENT NUMBER SHEET REV I ,I,,I, BARTON CITY OF INouSTRY, CA.9f 749 NUMBER R3-580-1 A'-4 INTERNATIOttAl. TELEPHONE ANO TELEORAPM CORPORATION 05991 N '
j$. . ' . Report No. 5480-8254 Y, ! AWHOVED LNGINCEluNG TEsi L AUOR ATOnits c,, a n.s i mu.s. u...n...s....v..u. ACTL .Date: 30__ January 197_9_ 44 Page Report ITT Darton 900 So. Turnbull Canyon Road City' of Industry, CA 91749 . TEST SPECIMENS One (1) Pressure Transmitter, Model 764, and one (1) Pressure Switch, Model 500.
SUMMARY
This report certifies tha' f.he t test specimens identified above have been subjected to Seismic Qualification Testing, in accordance with customer instructions _and ITT Barton Document 9999.3093.2. Below the frequency of 2.5 Hz, the Test Response Spectra (TRS) did not meet the Required Response Spectrum (RRS) IcVels specified in ITT Barton Document 9999.3093.2 .throu9hout seismic testin9 The customer was notified, and determined that the TRS levels were acceptable.. TEST EQUIPMENT AETL No. Manufacturer Instrument D519V Spectral Dynamics Sweep Oscillator; M/N SD-104A-5 0613V Unholtz-Dickie Servo Prograrmier; M/N SP-5 D624V Spectral Dynamics Dynamic Analyzer; M/N SD101A-1 D748V Moseley X-Y Plotter; M/N 135A D818V G. L. Collins LVDT; M/N LMT-719T31 D932V Shore Western Servo Controller; M/N SCl329C 0935V G. L. Collins LVDT; M/N LMT 719T31 D960V Precision Instruments Tape Recorder; M/N 2114 ! 0989V Exact Electronics Function Generator; M/N 129G D991V Spectral Dynamics X-Y Display; M/N 13116
'0992V Spectral Dynamics Shock Spectrum Analyzer; M/N 132:- l D993V Spectral Dynamics Transient Memory; M/N 13192 ,
01061V' .Bruel & Kjaer Accelerometer; M/N 4335 l D1063V Bruel & Kjaer Accelerometer; M/N 4335 D1071V Bird. Enterprises Signal Synthesizer; M/N None D1078V Bird Enterprises Signal Synthesizer; M/N liono j D10BlV MB Electronics Cal. Exciter; M/N CllC ' 1 R3-580-1 A-5 a.s ,
rr.h - Y3, j APPnOVED ENGINEERING TEST t.ACOnATOHIES Report !!o. ~ 5480-8254 4 f.y a u,s ..m.s. , i s . .n . . .. . .i . v i a. . < n . _ AUY E, TEST _E_QUIPf1EllT (Continued) AETL l'0. Manufacturer Instrument 01093V AETL Biaxial Seismic Sim.; M/il!!cne D1097V Endevco Corp. Accelerometer; f t/r! 2262-25 01103V - Unholtz-Dickie Corp. Charge hap 11fier; l'/tl 8 P."CVA D1104V- Unholtz-Dickie Corp. Charge Amplifier; M/il 8 Pi'CVA D110CV Endevco Corp. Accclercr.ictor; M/M 2262-25 E1032V J. Fluke Mfg. Co. Digital l'ultimeter; M/il 8120A E1057V Cal. Instrument Corp. Bridge Exciter & Balance; il/i! G 1-E1058V- . Shore Ucstern Servo Controller; M/l! SC11?.5SP E1107V Valhalla Digital Multimeter Counter; M/l! Elll8V Honeywell, Inc. Oscillograph, M/tt 1012 E1162V Honeywell, Inc. Oscillograph Visicorder; M/N 11-206780 Ell 64V CEC Galvo Amplifier; M/tlifone E1220S Tektronix, Inc. Oscilloscope, M/ft 535 G614V Panasonic Closed Circuit TV; M/ft UV-401 G617V Panasonic Video Monitor; M/li UV-411 G618V ~Panasonic . Remote Control Box; M/N UV-433 G619V Panasonic Panning Head; M/fi UV-431 E539V Tektronix, Inc. Osc. Plug-in Amplifier; M/!! CA
- Rental Spectral Dyncaics Real Time Analyzer; !!/i: SD114A
~* Rented;from U.-S. Instrument Rentals NOTE: The equipment listed.above was calibrated, as required, in accordance with !!IL-C-45662A, with traceability to the !ational Bureau of Standards. The f4BS traceability records are maintained on file in' the AETL Ouality Control 0ffice.
R3-580-1 A-6 g-
4 Alornics In*6tns.tlar..sl Divl:lon Lf 0J l'a 0:4 Avena ggg. g' Canoga Park, Caloc<n'a 91304 (213) 341 1oco. lIllefi10!iOilal . 9 e CERTIFICATE OF GAMMA RADIATION DOSE
- CUSTOMER T77 SA'n'70s/
PURCHASE ORDER NO. /36A7 DATE IN /o 7B TIME IN 13.70 i DATE OUT /o - f- 7 f TIME OU T OS30 7 MINIMUM DOSE 4 0y/o (Ar OJ i MAXIMUM DOSE 7.Ax o //'40J Signature [ eva a/[ ni ai,, , ,, osa o re - 3.vmo 'idu/m i EAcH Idf0Aharted WatcD was yo, r iM'.T s
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