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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML18065A6161996-03-31031 March 1996 Nonproprietary Consumers Power Co Reactor Vessel Neutron Fluence Measurement Program for Palisades Nuclear Plant - Cycles 1 Through 11. ML18065A6101996-02-29029 February 1996 Non-proprietary Consumers Power Co Palisades Surveillance Specimen Annealing Recovery Program. ML18064A6981995-03-31031 March 1995 Nonproprietary Rev 1 to Palisades Loss of Load Analysis. ML18065A3101994-10-31031 October 1994 Non-proprietary Status Rept on CEOG Activities Concerning Primary Water Stress Corrosion Cracking of Inconel-600 Penetrations. ML18064A5901994-10-19019 October 1994 Non-Proprietary Palisades Loss of Load Analysis. ML18058B8741993-05-31031 May 1993 Reactor Vessel Neutron Fluence Measurement Program for Cpc,Results to End of Cycle 9. ML18057A9661990-11-0909 November 1990 Review & Analysis of SRP Chapter 15 Events for Palisades W/ 15% Variable High Power Trip Reset. ML18057A4981990-09-30030 September 1990 Preliminary ANF-90-078, Palisades Cycle 9 - Analysis of SRP Chapter 15 Events. ML18057A4971990-08-31031 August 1990 Rev 2 to Disposition of SRP Chapter 15 Events for Palisades Cycle 9. ML20197H6231990-02-28028 February 1990 Rev 1 to Palisades Large Break Loca/Eccs Analysis W/ Increased Radial Peaking ML20154J4341988-09-0707 September 1988 Rev 1 to Palisades Cycle 8:Disposition & Analysis of SRP Chapter 15 Events ML20195H0301988-06-13013 June 1988 Nonproprietary Low Flow Trip Setpoint & Thermal Margin Analysis for Three Primary Coolant Pump Operation of Palisades Reactor ML20195H0741988-06-13013 June 1988 Nonproprietary Vol 1 of Palisades Modified Reactor Protection Sys Rept-Disposition of SRP Chapter 15 Events ML20195H3271988-06-13013 June 1988 Nonproprietary Vol 2 of Palisades Modified Reactor Protection Sys Rept:Analysis of Chapter 15 Events ML20206J8261987-04-0707 April 1987 Rev 1 to Thermal Analysis of West Engineered Safeguards Room of Palisades Nuclear Power Plant ML18059A4561986-05-31031 May 1986 Status & Suggested Course of Action for Nondenting-Related Primary-Side IGSCC of Westinghouse-Type Sg. ML20099D4511984-09-30030 September 1984 Analysis of Capsules T-330 & W-290 from CPC Palisades Reactor Vessel Radiation Surveillance Program ML20084F0271984-04-20020 April 1984 Suppl 1 to Analysis of Axial Power Distribution Limits for Palisades Nuclear Reactor at 2530 Mwt:Sensitivity Studies ML20087J8161984-03-0909 March 1984 Cycle 6 Setpoint Verification W/50% Steam Generator Tube Plugging ML20087J8191984-03-0909 March 1984 Plant Transient Analysis for Palisades Nuclear Power Plant W/50% Steam Generator Plugging ML20087J8311984-03-0909 March 1984 LOCA-ECCS Analysis for 2125 Mwt Operation & 50% Steam Generator Tube Plugging ML20078E2951983-08-26026 August 1983 Rod Withdrawal Transient Reanalysis for Palisades Reactor ML17297B1681981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palo Verde 1,2 & 3 Reactor Vessels. ML20039F8581981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Fort Calhoun Reactor Vessel. ML20039F8611981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Calvert Cliffs 1 & 2 Reactor Vessels. ML20039F8621981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palisades Reactor Vessel. ML20039F8631981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCA W/Loss of Feedwater for Millstone 2 Reactor Vessel. ML20039F8661981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Waterford Reactor Vessel. ML20039F8671981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for St Lucie 1 & 2 Reactor Vessels. ML20039F8681981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for AR Nuclear One- Unit 2 Reactor Vessel. ML14092A3011981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E Nsss. ML20039F8601981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for San Onofre 2 & 3 Reactor Vessels. ML19347F4521981-06-12012 June 1981 Spent Fuel Storage Pool Criticality Safety Reanalysis. ML20009E7281980-10-0303 October 1980 Distribution Control Procedures. ML19323C6371980-04-15015 April 1980 ECCS & Thermal-Hydraulic Analysis for Reload H Design, Nonproprietary Version.Affidavit Encl ML19257A0091979-12-31031 December 1979 Draft Input for Response to NRC Lessons Learned Requirements for C-E Nsss. ML18044A3811979-12-21021 December 1979 Post-TMI Evaluation Task 2,Conceptual Design for Reactor Vessel Level Monitoring Sys. Sixteen Oversize Drawings Encl ML18044A3791979-11-30030 November 1979 Results from Charge Preamplifier Temp Test. ML20126J9381979-10-31031 October 1979 Technical Evaluation of Susceptibility of Safety-Related Sys to Flooding Caused by Failure of Non-Category I Sys ML20117M4411976-12-10010 December 1976 Nonproprietary Palisades Steam Generator Tube Repair Sleeving ML20117M4271974-01-31031 January 1974 Nonproprietary Palisades Steam Generator Tube Exam & Repair 1996-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
[Table view] |
Text
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' November 1979 ATTACHMENT 7 r- . ..._.
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RE SUL TS FROtfl CHARGE PREAMPLIFIER L *TEMPERATURE TEST r*
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Babcock & Wilcox 1912310 S-(J
BAW-1590 November 1979 RESULTS FROM CHARGE PREAMPLIFIER TEMPERATURE TEST by H-. J. Braul Special Products Operation Reviewed by 4J. 'r-\ ~"\_~'tl\.~
M. Cobb -
Special Products Design Approved by: {ff. ~-'2YA A. F. Lexa, . anager <
Special Products Operation BABCOCK &WILCOX Power Generation Group Nuclear Power Generation Division P. O. Box 1260 Lynchburg, Virginia 24505 Babcock & Wilcox
CONTENTS Page*
- 1. INTRODUCTION * * . *
1.2. Objective *
... 1 1
- 2. INSTRUMENTATION *
- 3 2.1. Introduction * . . . . . . .. 3
- 2.2. Calibration
- 3. PROCEDURE AND DATA ACQUISITION
- 4. CONCLUSIONS 6 APPENDIXES A.- Test. Setup Equipment List : A-1 B - Photographs of Test Setup
"\ Figure
- 1. 477F Line Driver Temperature Test ******* 7
- 2. 175 and 288F Line Driver Temperature Test *** 8
- 3. Test Setup, Block Diagram ************ 9
- 4. Chromel-Alumel Thennocouple Calibration Plot 10 Babcock & Wilcox
- ii -
- 1. INTRODUCTION
- This report describes the test of the ability of the Unho1tz-Oickie Model 22CA-2TR remote charge preamplifier (li~e driver) to operate through high tem-peratures. The scope is limited to the work perfonned by the Operations Unit of the Special Products Section *. The requirements for the line drive tempera-ture test have been defined by the Special Products Design Unit.* Al1 data were recorded on magnetic tape. Throughout this report temperatures are ex-pressed iri degrees Fahrenheit {F).
1.1. Background From the Nuclear Regulatory Commission report entitled "TMI-2 Lessons Learned,
- Task for Status Report an~ Short-T~nn Reco1r111endat~ons" (NUREG-0578), came the
,j' requirement for*a valve monitoring system. Lirie drivers are an integral part
\
of the valve monitoring system. These devices exhibit an extremely high input impedance (typically 10 to 100 Mn) and function first to convert the charge signal to a voltage signal, which can be amplified to a usable level. The Model 22CA-2TR is intended to operate with piezoelectric-type transducers; it receives power from the signal conditioning amplifier to which it is connected.
.. . In the valve monitoring system the 1ine drivers. are within a few feet of the accelerometers and are thus exposed to high temperatures. This exposure to high temperatures caused concern for the line drivers' survivability.
1.2. Objective The tests were perfonned to verify the ability of line dri.vers, installed in* a Hoffman NEMA-4X stainless steel junction box, to operate after exposure to ~he following conditions:
- (l) J. M. Cobb to J. M. Brunke, Memorandum, "Line Driver Temperature Test, October 10, 1979; (2) J. M. Cobb to H. J. Braul and A. F. Lexa, Memorandum, 11 Line Driver Temperature Test," October 10, 1979.
Babcock & Wilcox
- 1. Test No. 1 - Steam line break temperatures at 477F for 30 seconds and 175F for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 47 minutes.
- 2. Test No. 2 - Small loss-of-coolant accident temperature at 288F for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Babcock & Wilcox
(
. 2. INSTRUMENTATION In the first test only the line drivers were subjected to high temperatures; in the second, line drivers and one high-temperature accelerometer were tested.
Both tests were performed in a high-temperature (SOOF) bake-out oven.
2.1. Introduction i
- A 1-kHz. 100-mV signal was used to check the line drivers before and after
... tests for signal degradation. During all the tests, an undistorted 100-mV rms, l 1-kHz sine wave out of the function generator and a 1-V output from the line
.* driver and signal conditioner, set at 10 g, were monitored. A periodic im-
.i
' pacting on the oven was visible on the oscilloscope; this confirmed a good signal from the accelerometer.
For recording on- the tape recorder, track select and shuttle :features were used. This allowed for recording in the forward and reverse modes for 32 t
I hours.
2.2. Calibration Each system component was individually calibrated at the NPGD shop before testing commenced. The Honeywell 101 14-track tape recorder was set to record
. at 1.875 ips wideband. The chromel-alumel Type K thennocouple ~as calibrated to the thennoc~uple amplifier (see Figure 4}'. The high ... temperature acceler-
_ometer was shaken at an acceleration of l g nns, and the signal conditioner sensitivity*dial was adjusted to give an output voltage of l V rms.
Checking the thermocouple readings against the oven dial temperature readings, it was observed to be within +20 degrees.
i Babcock & Wilcox i
- 3. PROCEDURE AND DAiA ACQUISITION A line driver was mounted in the junction box. Feedthroughs into the junction box had rubber grommets for insulation. ~!icrodot softline cables were used*
for signal input and output of the line driver. These softline cables came from the line driver through the feedthrough of the junction box to the feed*
through of the oven.and connected to the appropriate electronics.
O~ this first test (477 and 175F) the temperature dial on the oven was set at 477F. When the temperature reached this setting the door was opened and the junction box was inserted into the oven and the door closed quickly. About one minute before the temperature of 4i7F was obtained, the tape ' recorded was started.
After opening the*door, the oven temperature dropped to 320F; it took about 15 minutes to reach 4nF again. This peak was maintained for 30 seconds, then the dial was reset to 175F. When the temperature dropped to 275F, the line driver faileq. The total time this line driver was exposed to high temperatures is summarized:
> 320F 15 minutes
~ 477F 30 seconds
> 275F 20 minutes Test No. 1 Retest The same procedure was followed with a new line driver except that the oven temperature was raised to 550F. When the door was opened, the temperature dropped to about 480F, and the junction box was inserted. After 30 seconds'
- expos~re, the box was removed. No line* driver failure occurred. At this point, the tape recorder was stopped and restarted to'record just before the 175F temperature was atta i.ned. The di a1 was reset to l 75F, and once the tem-perature stabilized, the box was inserted into the oven for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. The sig-nal was monitored, and no failure occurred.
Babcock & Wilcox Test No. 2 required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' exposure to 288F for two new line drivers (one in *each box) and one accelerometer. Once the oven temperature stabilized at 288F, the same procedure was followed. The test was started at 14:09 on oc~
tober 12, 1979, and completed the next day at 14~45. A power failure, which occurred at GS:OO, failed to activate the Deltec power supply for the tape recorder. The Deltec was supposed to supply power to the tape recorder in case of power failure. {Another Deltec power supply activated to maintain power to the oven.) Thus, recording stopped at OS:oo: By checking at 14:00, after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the oven, a signal was.still present on the oscilloscope.
Playing back the tape confirmed the presence of signals from 14:09 to 05:00.
From this it was concluded that the line driver did not fail.
Test No. l Retest October 15s 1979 .
The same procedure was followed as for the first retest of Test No. l. No line driver failure occurred.
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Babcock & Wilcox
- 4. CONCLUSIONS
- 1. One line driver failed when exposed to temperatures in excess of the re-quired values.
Reason: Exposure to high temperatures (320 to 477 and back to 275F) for too long-at 1east 36 minutes.
Note: In reality for the 30-second temperature retest as
--.-- shown in Figure 1, the line driver was exposed to a temperature of 446 to 477F for at least 80 seconds.
- 2. During all the other tests, no line drive failures occurred.
- 3. The bias voltages on the signal conditioner were closely monitored; variations of 15 ta 60% occurred.
4.* All data are* traceable as to time and temperature.
- 5. No deterioration of the gro11111ets~ the rubber seals on the junction boxes, or the softline cables was observed in visual inspection
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F1gure 1. 477F Line Dr1ver Temperature Test II I I 40 50 60 90 10 20 30 70 80 100 Time, seconds m
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Figure 3. Test Setup, Block Diagram Bake-Out Oven
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Figure 4. Chromel-Alumel Thermocouple Calibration Plot r ..
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Type K Thermocouple Clevite Amplifier Rar,ge: 40-50
'. Sens. Vernier: 0.00
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Babcock & Wilcox APPENOIX A iest Setup Equipment List Babcock & Wilcox A-1
No. of units Description 2 Unholtz-Dickie Model P22MHA-l signal conditioner, Serial Nos.
1247 and 1255.
1 Endevco accelerometer, high-temperature, Serial No. AB-12.
5 Unholtz-Dickie remote charge preamplifier (line driver), Model 22CA-2TR, Serial Nos. 2408, 2856, 2433, 2391, and 2861.
1 Endevco 997 pf precision capacitor, Model 29478-1, Serial No.
PH24.
1 Tektroni'x function.generator, Model FG-504, Serisl No. 8042014.
1 Tektronix digital multi-meter, Model DM-501, Serial No. 81~1333.
1 Tektronix oscilloscope, Model SC-504, Serial No. 6011047.
1 Datum time code generator, Model 9300, Serial No. 1178.
1 Clevite thennocouple amplifier, Serial No. 249.
1 Chrome l ~a 1ilme l type K thennocoup le.*
1 Honeywell 14-track tape recorder, Model 101, Serial No. 1300333EC79.
1 Applied Test System high-temperature furnace and control, Serial No. 2912.
2 Deltec uninterruptable power system, Models DSU 1810 and 1210, Serial Nos. 3387 and 3009.
2 Hoffman stainless steel junction boxes, Model A-8064 CHNFSS NEMA-4X.
- 2. Endevco microdot softline cable, No. *3090 (rating SOOF).
l Unholtz-Dickie shaker table, Model 1602-6, Serial No. 1602-6.
' t Babcock & Wilcox A-2
APPENDIX B Photographs of Test Setup
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Babcock & Wilcox B-1
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Junction Box With Line Driver Tape Recorder OJ I
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Test Setup Test Setup With Bake-Out Oven I
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B-3 Babcock & Wilcox