ML20198H326
| ML20198H326 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/29/1997 |
| From: | Hammersley R, Henry R FAUSKE & ASSOCIATES, INC. |
| To: | |
| Shared Package | |
| ML20198H322 | List:
|
| References | |
| FAI-97-88, FAI-97-88-R, FAI-97-88-R00, NUDOCS 9709180010 | |
| Download: ML20198H326 (89) | |
Text
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FAUSKE & ASSOCIATES,INC.
CALCULATION NOTE COVER SHEET SECTION TO BE COMPLETED BY AUTHOR (S):
4 i
Page-I Calc. Note Number FAI/97.tR Revision Number. O i
Title Verineatinn Erneriments for Watarkamnwe Evaa#a in Power Plant Servica Water Svatama 4
l<
NSP #PK53425Q Project Venneation of Sennian Tanta Shop Order WEPCo #MK77543.
Purpose:
Verify the rwults of waterhammer scoping experiments.
Results Summary:
The test twults demonstrate waterhammer events of tens of poi and produce the same conclusions as the scoping tests.
Author (s):
Completion Name (Print or Type)
Signature Date Robert E. Henry k k.
bw 28, /F7
!Q 5
u o
1 SECTION TO BE COMPLETED BY VERIFIER (S):
4 j
Verifier (s):
Completion
^
Name (Print or Type)
Signature Date t
Rnhert L llamawrmlev 1 A.,289 /697
..g g
g y
Independent Review or Method of Verification: Design P.eview
,. "---- C + ' "--r
_. Testh.g,,
Other (specify),_,,,_,
,j-SECTION TO BS COMPLETED BY MANAGER:
Responsible Manager:
Approval Name (Print or Type)
Signature Date b
2I/k2 Robert E. Henry
.a-Q O
4 9709100010 970915 "
PDR ADOCK 05000202 P
p CALC NOTE NUMBER FAI/97-88 REV.
O PAGE 11 (x
CALCULATION NOTE METilODOLOOY CilECKLIST 4
CllECKLIST TO DE COMPLETED BY AUTilOR(S)
(CIRCLE APPROPRIATE RESPONSE) 1.
Is the subject and/or the purpose of the design analysis clearly stated?............................................ h
- NO l
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1 2.
Are the required inputs and their sources provided?
..... h
- NO N/A
+
3.
Are the assumptions clearly identified and justified?.............. h
- NO
+ N/A Are the methods and units clearly identified?.....................h
- NO j
4.
N/A 5.
llave the limits of applicability been identified?.................. -
- NO
- N/A (Is the aralysis for a 3 or 4 loop plant or for a single application.)
6.
Are the results of literature searches, if conducted, or other background data provided?............................... h e NO e N/A 7.
Are all the pages sequentially numbered and identified by the I
calculation note number?................................ 't E
- NO Is the project or shop order clearly identified?................... h
- NO 8.
- h 9.
lias the required computer calculation information been p.evided?....... YES
- NO
- h 10.
Were the computer codes used under configuration control?........... YES NO 11.
Were the computer code (s) used applicable for modeling the physical and/or computational problems identified?...................... YES
- NO *h (Is the correct computer code being used for the intended purpose.)
Are the results and conclusions clearly stated?........,..........h
- NO 12.
13.
Are Open items properly identified........................... h
- NO
- N/A
- NO *b 14.
Were approved Design Control practices followed without exception?...... YES (Approved Design Control practices refers to guidance documents within
{
ENATD that state how the work is to be performed, such as how to perform a LOCA analysis.)
llave all related contract requirements been met?................. h
- NO 15.
+ N/A 1
NOTE:
1O If NO to any of the above, Page Number containing justification V
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FAI/97-88 l
VERIFICATION EXPERIMENTS FOR j
WATERHAMMER EVENTSIN POWER
'1 PIANTSERVICE WATER SYSTEMS
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'l Submitted To:
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!,0 Northern States Power i
a Wisconsin Electric Company l
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Prepared Ly:
l Fauske & Associates, Inc.
16WO70 West 83rd Street Burt Ridge,1111nvis 60521 1
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July,1997 FAI\\97 88; Rev. 0
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l FURPOSE The purpose of this report is to provide QA'ed experiments to qualify the results and i
conclusions of previous scoping experiments, which were performed to evaluate the magnitude of waterhammer events in piping conAgurations similar to those used in nuclear plant service water systems. Specifically, this report describes experiments that were repeated with a similar geometric connguradon as those used for the scoping assessments. As part of this test series, all of the pressure transducers and thermocouples used in this test apparatus were calibrated with sys'. ems that were traceable to the National Institute of Standards and Technology (NIST).
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The input data related to the experiments and the appilcation of the information to the plant I
systems are as follows.
Consider a design basta less Of-Coolant Accident (LOCA) into containment with the constrainment pressure increasing to about 43 psig and 265'F (Prairie Island
- USAR) with 60 psig and 286*F being the values for Point Beach (WEPCo,1996).
The assumptions related to the experiments and the application of the information to the I
plant systems are as follows.
Conalder that a I.oss Of-Offsite (LOOP) occurs simultaneous with the LOCA condition.
The experimental apparatus must be sufficiently configured for column separation to occur.
t The experimental system should be corstructed to create a steam void from the entire discharge piping given a sufficiently long interruption of the service water pumping capability.
Other assumptions and input data are defined in the text where needed.
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TABLE OF CONTENTS First I.ast Eaga Eags CALCULATION NOTE COVER SHEET i
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CALCULATION NOTE CHECKLIST 11 11 1
l TITLE PACE ill_
ill PURPOSE iv iv 4
INPUT DATA AND ASSUMPTIONS v
y TABLE OF CONTENTS vi vi 4
LIST OF FIGURES vil vil LIST OF TABLES vill vill
.O
1.0 INTRODUCTION
1 2
2.0 EXPERIMENTAL APPARATUS 3
6 3.0 EXPERIMENTAL RESULTS 7
14 4
4.0 CONCLUSION
S 15 15 3
5.0 REFERENCES
16 16 4
i APPENDIX A:
Certificates of Calibration A-1 A5 i
APPENDIX B:
Experimental Data B-1 B-61 1
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FAI\\97 88; Rev. O i
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LIST OF FIGURES I
i f
Figure 21 Experimental configuration for investigating condensation l,
induced water hammer events.............................. 4
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Figure 3-la Measured pressure transients for waterhammer test QA4 for pressure transducer P1.................................. 8 1
Figure 3 lb Measured pressure transients for waterhammer test QA4 for f
pressure transducer P2.................................. 9 I,
Figure 31c Measured pressure transients for waterhammer test QA4 for l
pressure transducer P3.................................
10 i
Figure 3-1d Measured pressure transients for waterhammer test QA4 for pressure transducer P4.................................
11 Figure 3 le Measured pressure transients for waterhammer test QA4 for
'j pressure transducer P5.................................
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i LIST OF TABLES t
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a.ij Table 21 Waterhammer Test Program............................... 6 l
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Table 31 Observed Peak Waterhammer Pressures......................
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' I.0 INTRODUCTION.
l 1
This experiment series repeated previous scoping experimete w!dch were used to I
determine the order of magnitude of waterhammer pressure loads that could be expected to occur in a nuclear plant service water system. Specifically, these experiments addressed the pctential loads that could result from a Design Basis (DB) Loss-Of-Coolant Accident (LOCA) into containment with a corresponding loss-off-site power. Following the power loss, the on site AC power (diesels) would start and sequentially load emergency systems on'.o the AC busses.
l Typically the sequence of power restoration would deliver power to service water pumps after a i
few tens of seconds. Meanwhile, the containment atmosphere would experience an increasing l
steam partial pressure and an increasing rate of heat transfer to the fan coolers causing a potential for steam generation and voiding within the fan coolers. Also, for some designs the fan coolers f
are sufficiently elevated in the containment that the stoppage of service water flow would result in column separation in the service water piping. Consequently, for either or both of these situations, the restart of the service water pumps could involve waterhammer events as a result of collapsing the available steam void (FAI,1996a and FAI,1996b).
Previous scoping experiments (FAI,1996c) demonstrated that the magnitude of these waterhammer events to be tens of psi, instead of hundreds of psi as would be calculated from the 1
waterhammer equation AP = p, a, U.
(1)
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which is the standard waterhammer equation (Wylie and Streeter,1978). Typically this equation 3
is related to the refill velocities in the service water systems where Um is the refill velocity, a, is the velocity of sound and water and p, is the water density. For conditions in which a moving water column impacts a stagnant water column, the pressure increases one half of that calculated by the above equation.
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2 Another aspect of the previous experiments that was judged to be influential is the Froude
,al number chancterizing the refill velocity. This dimensionless number is defined by U,a i
Fr =
(2)
SE l
where g is the acceleration of gravity and D is the diameter of the pipe undergoing the refill process. As discussed by Bjorge and Griffith (1984) when this number exceeds approxiniately 0.5, the piping configuration would refill in a plug-like configuration instead of a stratified configuration. For the former case the surface area limits the availability of a strong condensing event and this is used as,a criteria for preventing condensation induced waterhammer events in horizontal flow. More WMiy, a Froude number of unity or greater is the typical value used l
to characterize a situation where condensation induced waterhammer events would not occur for water flowing into a steam void in a horizontal conduit. Therefore, the Froude number using the refill velocity was varied for these experiments since this was an important parameter related to the previous scoping test.
The scoping experiments were performed using goad engineering practices but did not use instrumentation that was calibrated with devices with current and traceable documentation to the National Institute of Standards and Technology (NIST). The experiments reported in this document repeat the major phenomenological behavior using instrumentation which has a calibration that is current and traceable to the NIST. Hence, the major reason for these experiments is to assure that there was no misleading information developed from the scoping experiments and applied to nuclear power plant analyses.
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j FAI\\97-88; Rev. 0
j 2.0? EXPERWENTAL APPARATUS
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I The experimental configuration used for these qualification tests is illustrated in Figure 2-1.
I As shown, it is made up of the water supply vessel, the steam generator, the evacuated receiver i
vessel and connected piping which is composed of both one-inch and two-inch diameter segments, i
With a vertical height of 20 feet, there is a sufficient elevation change to generate column 4
separation if the pressure in the evacuated receiver vessel is less than 4 psia. Furthermore, the steam generator enables steam to be added to the apparatus to simulate the energy transfer that would occur in a DBA LOCA event into the containment atmosphere.
!l For the apparatus shown in Figure 2-1, the solenoid operated ball valve immediately 1
downstream from the water supply vessel is the principle element used to initiate the transient.
Specifically, this closes to isolate the water supply and simultaneously the solenoid operated ball valve connecting the steam generator with the piping arrangement simulating the fan cooler is opened. The steady-state flow resistance through the piping configuration is determined by the frictional pressure drop in the various lengths of one and two-inch piping as well as the gate valve immediately upstream of the manual ball valve on the evacuated received vessel and the gate valve that is between the water supply vessel and the solenoid operated ball valve. These two gate valves provide a flexible arrangement to set the desired velocity through the two-inch piping and also the system pressure in the simulated fan cooler during the steady < tate portion of each test.
The response of the system during the steam addition is monitored by therT,muples and i
pressure transducers shown in Figure 2-1. One of the principle variables between experiments is the duration that steam is added to the apparatus. Longer steam addition times represent more extensive steam voiding in the apparatus, particularly in the direction of the evacuated receiver vessel. Once the duration of steam injection was completed, the steam supply ball valve was i
closed and the solenoid ball valve immediately downstream from the water supply vessel was f
opened such that water was introduced back into the test apparatus (refill transient). This water O
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8 slug condensed and pushed the steam void into colder piping regions resulting in the waterhammer gO events of interest. The parameters for the vanous expenments used in this set of qualification I
experiments are given in Table 21, As shown, the refill based Froude number is varied from i
unity to 0,3 to investigate the magnitude of waterhammer events when the refilling velocities are less than those where the pipe could fill in a one-dimensional (plug-like) manner.
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i Table 2-1 WaterhamnaerTest Program Stemma NoennelInitial Noammal Water Neanimallaatial Nomanal Receiver Initial Water Steam Fkm Refill Test Orifice Siao WeserTemp Reservoir Stea m T, A.
Vessel Pnesure Flow insesval Inserval Froude (Run#)
(in)
(*F)
Pnesure (psig)
(*F)
(in Hz)
(secs)
(sec)
N umber 1
QAl Nome 68 to 350
-27.3 10 20 1.20 QA2 Nees 68 80 345
-26.5 10 30 1.12 QA3 None 68 80 365
-25.8 10 40 1.20 QA4 Nome 68 80 343
-25.3 10 30 1.16 QA5 Nome 68 30 N/A
-25.2 10 N/A 1.16 p
QA6 Nome 68 80 363
-25.6 10 20 0.60 QA7 None 68 80 351
-25.4 10 30 0.60 QA8 None 68 80 356
-25.0 10 40 0.56 QA9 None 68 80 342
-24.2 to 50 0.56 QA10 Nome 68 80 N/A
-23.6 10 N/A 0.60 QAll None 68 80 346
-23.5 10 20 0.30 QAl2 None 68 80 332
-23.2 10 50 0.26 l
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)<,9 3.0' EXPERIMENTAL RESULTS fI As stated previously, the single focus of these experiments was to determine the validity
!j of earlier scoping experiments that were performed using good engineering practices but without l
traceable calibration to NIST standards for the pressure and temperature measurements. These experiments were performed in the configuration that was previously observed to have the most 4
l dynamic conditions with respect to waterhammer events (largest pressure increases). A typical pressure transient for one of the experiments performed in illustrated in Figure 3-1. This is test f
QA4 and the different pressure measurements in the test circuit are illustrated in Figures 3-la through 3-le. (All of the experimental data is given in Appendix B.) Furthermore, Figure 3-la
!j annotates some of the major intervals during the transient including the steady-state portion of the l
test which lasted approximately 10 seconds, the initiation of the transient, including the onset of i
steam addition, the part of the voiding phase interval in which the steam bubble was growing r
through the 20 foot long "down leg", the time at which refill of the test apparatus is initiated, which defines the end of the voiding phase and the time at which the refill is completed. I.astly, j
the point of" flow stop" is also shown, which gives a dynamic calibration point for the pressures l*
measured for each transient. As part of this dynamic response, the time at which steam addition jt is initiated causes a pressure transient in the system since the entire flow circuit is filled with water I
and the steam source has a saturation pressure of approximately 130 psia. Therefore, valving in the steam source at the beginning of the transient causes a pressure event which is not the t
l waterhammer of interest here. Consequently, the pressure occurrence at the time of initial steam
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- addition is not evaluated as the pressure transient associated with condensation induced
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waterhammer. For a fan cooler existing in a DBA LOCA environment, the steam addition would il be mere smooshly initiated as a result of heat addition to the fan cooler tubes as the steam partial i
pressure in containment increased over a number of seconds.
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!'l Once voiding has been initiated, the hydrodynamic transients associated with condensation f
i induced waterhammer are evident. In particular, the time between approximately 15 seconds and 25 seconds is the time that the steam volume increases from the bottom of the "U-tube" FAI\\97-88; Rev. 0
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I Figure 3-Ic Measured pressure transients for waterhammer test QA4 for pressure transducer P3.
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l - l configuration to the highest point in the test apparatus and across the horizontal run at this high j
elevction.' De rapid decreases associated with steam void ingression into cold piping is clearly I -
evident. However, once the steam bubble begins to grow in the "down leg", which is 20 feet in leryth, the condensation events are absent, which is in keeping with the stable configuration of l
steam over water. However, once the steam column reaches the bottom of the "down leg" and begins to move through the long horizontal pipe at the bottom of the apparatus, the condensation pr-involving pressure decreases to 5 to 7 psi are again evident. This is the same behavior that was observed in the previous scoping experiments. Furthermore, the comparison of the various figures shows that the early transients in a timeframe between 15 and 35 seconds are observed in a similar manner for all pressure measurements. In contrast, when the steam bubble begins to move through the lower horizontal piping, the pressure measurements in the upper l
regions of the apparatus only see slow pressure decreases and increases as the condensation event oscillates whereas pressure transducer P5 records small waterhammer events after the rapid decrease in pressure. His is again in agreement with the observations from the numerous scoping experiments that were perfonned.
- O When the refill is initiated, there is a large steam column separating the upper regions of the test apparatus and those in the lower region. Hence, the events that are initiated upon refill
+
in the upper regions as measured by pressure transducer P1, are separated from the remainder of the pressure measurements by a large steam volume. Consequently, the events detected in the l'
upper region are not transmitted downstream through this large steam column. When the system eventually becomes filled with waar, the pressure rises to the steady-state condition, which slows A
the water flow rate through the test apparatus from the refill velocity, typical of a pressure differential between the water supply vessel and the test apparatus that has a pressure of about 5 psia. When this flow encounters the throttle valve upstream of the evacuated received vessel,_the flow must decelerate to the steady-state value and this is accomplished by essentially a single pressurization that propagates back through the piping circuit. This again is the same behavior observed in the scoping experiments.
O FAl\\97-88; Rev. 0
14 Lastly, the flow stop condition is obtained by rapidly closing the ball valve next to the evacuated receiver vessel. When this occurs, the entire flow through the circuit is reduced to zero causing a pressure increase associated with the flow stoppage. As illustrated, this pressure increase is observed on all the pressure measurenants in the test apparatus and is indicative of the capabilities for the pressure measurements to observe rapid preuure changes such as condensation I
induced waterhammer events.
1 Table 3-1 summarizes the peak waterhammer pressures observed in the various experiments performed in this test series. As illustrated, these peak waterhammer events are tens
,tl[
of psi, instead of hundreds of psi, which is the same conclusion produced in the numerous scoping experiments.
Consequently, the qualification experiments performed with pressure and i
temperature measurements obtained using instrumentation that has a traceable link to the NIST show the same behavior as determined in the scoping experiments. Consequently, the insights gained from the scoping experiments are validated through these additional experiments done in compliance with the quality assurance requirements of the FAI Test and Calibration procedures.
l Table 3-1 Observed Peak Waterhammer Pressures Test Refill Peak Waterhammer Time of i
(Run #)
Froude No.
Pressure (psig)
Peak Pressure QA1
.1 50 During refill QA2 1
55 During refill QA3 1
38 At the start of refill QA4 1
10 At the start of refill QA5' 1
28 At the start of refill 3
QA6 0.5 10 At the start of refill QA7 0.5 10 During refill i
, QA8 0.5 12 During refill QA9 0.5 15 During refill QA10*
0.5 4
During refill QAll 0.3 15 During refill QA12 0.3 29 During refill i
'No steam addition, column rejoining only.
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ti 4.0 LCONCLUSIONS.
I 1
The experiments had the single objective of determining whether the previous scoping l-experiments provided the appropriate insights for assesung the potential for condensation induced waterhammer events in service water systems for nuclear power plants. These tests were performed using pressure and temperature measurements that had been calibrated with systems in a manner traceable to the NIST.
l The resulting experiments performed showed the same type of behavior observed in the i
scoping experiments, including the variation in condensation rates with the geometric orientation of the piping in the test apparatus. Most importantly, these experiments registered waterhammer i
events that were tens of psi and are in agreement with those produced through the scoping experiments.' Therefore, the same conclusions are derived from both sets of experiments.
Specifically, there was no misleading information developed in the scoping experiments.
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5.0 REFERENCES
)
Bjorge, R. W. and Griffith, P.,1984, ' Initiation of Waterhammer in Horizontal and Nearly i
Horizontal Pipes Containing Steam and Subcooled Water," Transactions of the ASME, Journal of Heat Transfer, Volume 106, pp. 835 840.
Fauske & Associates, Inc. (FAI),1996a, " Evaluation of Possible Water Hammer Loads in the Service Water System for DBA Conditions," Fauske & Associates Report FAI/96-75.
I Fauske & Associates, Inc. (FAI),1996b, " Evaluation of Possible Water Hammer Loads in the Prairie Island Service Water System for DBA Conditions," Fauske & Associates Report FAI/96-89.
Ii Fauske & Associates, Inc. (FAI),1996c, " Experimental Data to Simulate Possible Water-Hammer Loads in the Prairie Island Servict Water System for DBA Conditions," Fauske &
Associates Report FAI/96107.
Wisconsin E ectric Co. (WEPCo),1996, ' Containment Fan Cooler Service Water Throttle Valve Setpoints for Three Service Water Pump Operation," WEPCo Calculation 96-0117, Rev.
1, also in FAI QA File 5.32.
- O Wylie, E. B. and Streeter, V. L.,1978, mid Trandants, McGraw-Hill International Book Company.
4 i
I FAI\\97-88; Rev. O
A1 1
APPENDIX A
,j Certincates of Calibration l
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2 REPORT NO:
1122197 E.I.L. NUMBER:
E186206 9.
MANUFACTURER: ASHCROFT PROCEDURE:
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PT INTERVAL:
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.7 DESCRIPTION:
DIGITAL PRESSURE CAL DATE:
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SERIAL NO:
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TEMPERATURE:
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REPORT NO:
1122199 E.I.L. NUMBER:
E186208 4
MANUFACTURER: OMEGA PROCEDURE:
33K5-4-139-1/SP-
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OMNI-CAL-8A-110 INTERVAL:
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DESCRIPTION:
CALIBRATOR CAL DATE:
04/01/97
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TEMPERATURE:
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