ML19290C652
| ML19290C652 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/14/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19290C651 | List: |
| References | |
| PROC-791214, NUDOCS 8001220473 | |
| Download: ML19290C652 (31) | |
Text
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SPECIAL TEST NO. 1 NATURAL CIRCULATION TEST
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1785 226 sooxaco 4 93
SPECIAL NO. 1 e
12/14/79 NATURAL CIRCULATION TEST Table of Contents Page 1.0 OBJECTIVES 1 2.0 PREREQUISITES 1 3.0 PRECAUTIONS 3 4.0 SPECIAL TEST EQUIPMENT 5 5.0 INSTRUCTIONS 6 6.0 ACCEPTANCE CRITERIA 8 DATA SHEETS 9 APPENDIX A - References 13
's APPENDIX B - Deficiencies 14 APPENDIX C - Power Measurement Techniques 15 APPENDIX D - Computer Points 23 1786 227
SPECIAL NO. 1 e .
12/14/79 NATURAL CIRCULATION TEST TEST DESCRIPTION The test will be initiated by simultaneously tripping all reactor coolant pumps while at 3% power. The transient response will be monitored and establishment of natural circulation verified. Core exit thermocouples will be monitored to determine the core flow distribution. Automatic control of pressurizer pressure and level and manual control of feedwater flow will be maintained throughout the test. In the event main feedwater pumps cannot be used at the power level, steam generator level control will be maintained with feedwater supplied by the auxiliary feedwater system.
A
. SPECIAL NO. 1
. Page 1 of 8 12/14/79 e ,
1.0 OBJECTIVES 1.1 To demonstrate the capability to remove decay heat by natural circulation.
1.2 To verify that the pressurizer pressure and level control systems can respond automatically to loss of forced circulation from all four reactor coolant pumps and maintain RCS pressure within acceptable limits.
1.3 To verify that steam generator level and feedwater flow can be controlled under conditions of natural circulation to maintain adequate cooling of the reactor coolant system.
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2.0 PREREQUISITES 2.1 Low Power Physics Testing has been completed to the extent necessary for conduct of this test.
Date 2.2 Reactor is critical and manually controlled at approximately 3% power with control bank D at 6- 160 steps or as specified by test engineer.
(Power determined as indicated in Appendix C).
Date 2.3 All four reactor coolant pumps are in operation.
Date 2.4 Pressurizer pressure control and level control are in automatic, maintaining RCS pressure at approximately 2235 psig and pressurizer level at approximately 27 to 28%.
Date 2.5 Steam dump valves are in the pressure control mode, maintaining steam generator pressure at approximately 1005 psig.
Date 2.6 Steam generator level is being maintained at approximately 33% on the narrow range indicators.
Date 1785 ?.2.9
SPECIAL NO. 1 Page 2 of 8 12/14/79 2.0 (Continued) 2.7 Feedwater and condensate systems are in service in accordance with SOI-2.1 and 3.'l. If main feedwater pump operation cannot be maintained under these conditions, the auxiliary feedwater system will be used in accordance with SOI 3.2.
Date 2.8 RCS temperature (T,y ) is being maintained at approximately 5 50 F.
Date 2' 9 Record the following parameters.
2.9.1 Install brush recorders to record data at the following locations.
Brush Recorder No. 1 Connect To: Monitoring Channel No. 1 1-R-1, FP-414B RCS Flow, Loop 1 Channel No. 2 1-R-1, FP-424B RCS Flow, Loop 2 Channel No. 3 1-R-1, FP-434B RCS Flow, Loop 3 Channel No. 4 1-R-1, FP-444B RCS Flow, Loop 4 Channel No. 5 1-R-1, PP-455B Pressurizer Pressure
! Channel No. 6 1-R-1, LP-459B Pressurizer Level Brush Recorder No. 2 Connect To: Monitoring Channel No. 1 1-R-3, PP-514B Steam Gen.#1 Pressure Channel No. 2 1-R-23, LP-501 Steam Gen.#1 Level Channel No. 3 1-R-3, FP-512B Steam Gen.#1 Steam Flev Channel No. 4 1-R-3, PP-524B Steam Gen.#2 Pressure Channel No. 5 1-R-23, LP-502 Steam Gen.02 Level Channel No. 6 1-R-3, FP-522B Steam Gen.#2 Steam Flow Brush Recorder No. 3 Connect To: Monitoring Channel No. 1 1-R-4, PP-534B Steam Gen.#3 Pressure Channel No. 2 1-R-23, LP-503 Steam Gen.#3 Level Channel No. 3 1-R-4, FP-532B Steam Gen.#3 Steam Flow Channel No. 4 1-R-4, PP-544B Steam Gen.#4 Pressure Channel No. 5 1-R-23,LP-504 Steam Gen.#4 Level Channel No. 6 1-R-4, FP-542B Steam Gen.#4 SteamFlow 1785 230
SPECIAL NO. 1 Page 3 of 8
, 2.0 .2.9 12/14/79 2.9.1 (Continued)
Brush Recorder No. 4 Connect To: Monitoring Channel No. 1 1-R-3, FP-510B Main Feed Flow, SG#1 Channel No. 2 1-R-3, FP-520B Main Feed Flow, SG#2 Channel No. 3 1-R-4, FP-530B Main Feed Flow, SG#3 Channel No. 4 1-R-4, FP-540B Main Feed Flow, SG#4 NOTE: If auxiliary feedwater is to be used in place of main feed-water, brush recorder #4 should be installed in the auxiliary control room to record data at the following locations.
Brush Recorder No. 4 Connect To: Monitoring Channel No. 1 F-3-163,TP13,1-L-llB Aux.FeedFlow to SG#1 Channel No. 2 F-3-155,TP13,1-L-llA Aux.FeedFlow to SG#2 Channel No. 3 F-3-147,TP12,1-L-llB Aux.FeedFlow to SG#3 Channel No. 4 F-3-170,1P12,1-L-llA Aux.FeedFlow to SG#4
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NOTE: Record the following on each strip chart:
a) Unit number b) Date c) Procedure number d) Parameter scale and range e) Chart speed f) Name of person recording data g) Recorder ID number 2.9.2 Record on f -computer recorder
- a. Flux
- b. Average wide range T
- c. Average wide range T eold
- d. hat pressure Average Steam generator
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2.10 Trend 4 incore T/C on the analog trend recorder on the main control board.
(Suggest trending the four hottest thermocouples, one from each quadrant.)
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2.11 A steady feed to the steam generators should be set up to minimize temperature variation in the RCS.
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1785 231
SPECIAL NO. 1 Page 4 of 8 12/lk/79
- 3.0
- PRECAUTIONS 3.1 Do not exceed 5% nuclear power.
3.2 Do not exceed any of the following temperature limits.
3.2.1 610 F for any core outlet thermocouple.
3.2.2 65 F for any loop Delta-T.
3 2.3 578 F for any loop T ,yg.
3.3 Do not exceed primary to secondary differential pressure of 1600 psi.
3.h Avoid rapid changes in steam pressure, steam generator level, and feedvater flow to prevent rapid cooling of the reactor coolant.
35 Do not exceed 100 psi differential pressure between any two steam lines.
This will result in a safety injection signal. Refer to AOI-19 should this occur.
3.6 Maintain reactor coolant pump seal and thermal barrier differential requirements as given in SOI 68.2.
3.7 After the reactor coolant pumps are tripped, the normal T and dT indications will become unreliable. A T and T should Seg calculated by taking the difference and the average of th$#l5ot and cold leg temperatures indications respectively.
3.8 Maintain T at the pretrip temperatures by adjusting the steam dunp setpoint. eold ,
1785 232
SPECIAL NO. 1 Page 5 of 8 4.0 Scecial Test Equipment 12/14/79 Identification Calibration Instrument Scecification Number Verification Strip Chart Recorder Brush 260 or equivalent (3)
Reactivity Computer Westinghouse If test instruments are changed during this test, the instrument information must be recorded here and an entry made in the chronological icg book explaining this change. ,
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1786 233
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SPECIAL NO. 1 Page 6 of 8 12/14/79
. 5.0 . INSTRUCTIONS 5.1 Prepare the plant computer to record data as specified in Appendix D.
Record the initial steady state values for these points on Data Sheet 5.1.
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5.2 Start the brush recorders in the auxiliary instrument room and start monitoring of data points on the computer trend typewriter.
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CAUTION: Continuously monitor main-steam line pressures and carefully control feedwater addition during the transient to ensure that differential pressure between any two steam lines does not exceed 100 psid. This would initiate safety injection. Should this occur refer to AOI-19.
(Feedwater to each steam generator must be equal before tripping the pumps.)
livTE: Steam generator pressure, level, and flow conditions should be held as close as possible to stable conditions through the duration of the transient.
Reactor coolant system cold leg temperatures should be maintained within
+ 5 F of the initial values.
NOTE: At the initiation of natural circulation (RCP trip) the following temperature response is expected.
a) Wide range T hot, increase b) Wide range T cold, slight decrease or constant c) Core exit thermocouple, increase .
d) T indication, unreliable e) Delba-T indications, unreliable f) Pressurizer level and pressure, increase 5.3 Simultaneously trip all four reactor coolant pumps in accordance with SGI 68.2.
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5.4 Maintain RCP seal flow at a minimum of 6 gpm to each pump.
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5.5 Maintain pressurizer pressure control in automatic and manually adjust charging flow to match le'tdown and maintain a constant RCS water volume.
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5.6 Carefully control additions of feedwater to the steam generators to maintain levels at approximately 33%. Do not allow steag generator level to drop below 21% on narrow range indicators.
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SPECIAI. NO.1 Page 7 of 8 , 12/14/79 5.0 (Continued) NOTE: Natural circulation flow will be stable when: a) d T between wide range T and T is constant. cold b) d T between wide range Tcold "" * #* ** ***#888 ***E*#8D"#* is constant. c) Wide range T C2 core exit T/C average temperature. 5.7 Af ter steady state conditions have been reached mark each recorder chart to indicate equilibrium has been reached and continue recording data.
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5.8 Insert control bank D as specified by test engineer until the hot zero power test range is reached.
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CAUTION. Ensure pressurizer spray controller outputs are approximately zero before starting RCP's 1 or 2. 5.9 Af ter reactor coolant pu=ps have been shutdown for at least 30 minutes, restart the RCP #1 in accordance with SOI 68.2. Continue to collect data through the restart.
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5.10 After steady state conditions have been reached, restart reactor coolant pump #2 in accordance with SOI 68.2. Continue to collect data through the restart.
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5.11 After steady state conditions have been reached restart reactor coolant pump
#3 in accordance with SOI 68.2. Continue to collect data through the restart.
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5.12 Af ter steady state conditions have been reached restart reactor coolant pump
#4 in accordance with SOI 68.2. Continue to collect data through the restart.
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5.13 Stop the brush recorders in the auxiliary instrument room, and terminate trend recording on the plant computer.
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5.14 Incorporate the brush recorder charts and computer printouts on Data Sheet 5.2.
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_,_ 1785 235
SPECIAL NO. 1 Page 8 of 8 12/14/79 6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperature does not exceed 610 F.
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6.2 Delta-T for any loop does not exceed 65 F.
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6.3 T fray 1 pd s a t ex e d 578 F. av8
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6.4 Delta-T established between wide Thot and T cold is stable and less than 65 F.
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6.5 Delta-T established between wide range T and core exit T/C average temperature is stable and less than 65 F
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- S-1785 236
Unit SPECIAL NO. 1 Date Page 1 of 3 Time 12/14/79 DATA SHEET 5.1 INITIAL CONDITIONS Pressurizer Pressure psig PR-68-340 Pressurizer Level % LR-68-339 RCS Loop 1 Hot Leg Temperature F TR-68-1 RCS Loop 1 Cold Leg Temperature F TR-68-18 RCS Loop 2 Hot Leg Temperature F TR-68-1 RCS Loop 2 Cold Leg Temperature F TR-68-18 RCS Loop 3 Hot Leg Temperature F TR-68-43 RCS Loop 3 Cold Leg Temperature F TR-68-60 RCS Loop 4 Hot Leg Temperature F TR-68-43' RCS Loop 4 Cold Leg Temperature F TR-6 8-60 Steam Generator 1 Level (NR) % (LI-3-42) Steam Generator 2 Level (NR) % (LI-3-97) Steam Generator 3 Level (NR) % (LI-3-110) Steam Generator 4 Level (NR) % (LI-3-110) e Steam Generator 1 Level (WR) ~ . LR-3-43 Pen 1 Steam Generator 2 Level (WR) % LR-3-43 Pen 2 Steam Generator 3 Level (WR) % LR-3-98 Pen 1 . Recorded by / . ,
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Unit SPECIAL NO. 1 Date Page 2 of 3 Time 12/14/79
. , DATA SHEET 5.1 INITIAL CONDITIONS (Continued)
Steam Generator 4 Level (WR) % LR-3-98 Pen 2 Steam Generator 1 Pressure psig PI-1-2A Steam Generator 2 Pressure psig PI-1-9A Steam Generator 3 Pressure psig PI-1-20A Steam Generator 4 Pressure psig PI-1-27A Steam Generator 1 Feedwater Flow gpm (FI-3-35A) Steam Generator 2 Feedwater Flow gpm (FI-3-48A) Steam Generator 3 Feedwater Flow gpm (FI-3-90A) Steam Generator 4 Feedwater Flow gpm (FI-3-103A) Steam Generator 1 Steam Flow lbs/hr (FI-1-3A) Steam Generator 2 Steam Flow lbs/hr b'I-1-10A) Steam Generator 3 Steam Flow _ lbs/hr (FI-1-21A) Steam Generator 4 Steam Flow lbs/hr (FI-1-28A) Loop 1 Tavg F (TI-68-2E) Loop 2 Tavg F (TI-68-2SE) . Loop 3 Tavg F (TI-68-44E) Loop 4 Tavg F (TI 68-67E) Recorded by: / 1785 238
Unit SPECIAL NO. 1 Date Page 3 of 3 Time 12/14/79 DATA SHEET 5.1 INITIAL CONDITIONS (Continued) Loop 1 AT F (TI-68-2D) Loop 2 dT F (TI-68-25D) Loop 3 AT F (TI-68-44D) Loop 4 dT F (TI-68-67D) NIS Channel N-41 % NIS Channel N-42 % NIS Channel N-43 % NIS Channel N-44 % Attach a copy of the computer printout of the Incore Thermocouple Temperature map. Refer to Appendix D for the procedure to print this map. Recorded by / SPECIAL NO. 1 Data Sheet 5.2 Page 1 of 1
. , 12/14/79 DATA SHEET 5.2 Attach copies of the computer trend printout, incore thermocouple map and brush recorder charts to this page.
h 1785 240
i
- SPECIAL NO. 1 Page 1 of 1 12/14/79 APPENDIX A References
- 1. FSAR
- 2. Technical Specifications
- 3. Plant Operating Instructions E0I-5 SOI-68.2 2
i e 1785 241 _, __ _ . _ . _ . . _ _ - - - - - - - - - - - - - ' - ~
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Appendix B 2/6/79 Page of Rev. Page of Test Deficiencies # Test Deficiency Recomended Resolution Final Resolution Originator _ / Signature Date PORC Review of Final Resolution Date Approval of Final Resolution / Plant Superintendent Date 1785 242
SPECIAL NO. 1 Page 1 of 10 12/30/79 APPENDIX C Punchlist:
- 1. Part C - Thermocouplec
- 2. Part B - Address in P-250 for:
- a. Priority scan option selection
- b. Power calibration constant
- c. Calculated power 9
8 f785 243
SPECII NO. 1 Page 2 of 10 12/30/79 , , APPENDIX C (Continued) Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only) 1. Reference (rv 550 F) Calorimetric (Before NC test) a) Output used to adjust M/D Power Monitor Program's power conversion constant. B. M/D Power Monitor Program '
- l. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a % power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.
- 2. Power Monitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 5 or 6 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to once evecy 2 minutes or as necessary to continuously monitor core power.
O 1785 244
SPECIAL NO. 1 Page 3 of 10 12/30/79
. . APPENDIX C CORE POWER DETERMINATION PART A: Primary side calori=stric - Data Sheet C.1 (Forced Circulation)
C.1 Use two DVMs and measure the voltage at the test points specified for each loop as rapid as possible. C.2 Calculate the 21 T; multiply that 4 T by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (Table C-1). (Special Test No. 9 uses wide range ti T so a correction factor is required to compensate for pump heating, refer
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to Appendix D of SI-9A). C.3 Sum the loop heat rates and convert.to a percent reactor power. The output is used in Part B. e 1785 245
SPECIAL NO. 1 Page 4 of 10 12/30/79 APPENDTX C (Continued) Core Power Determination PART B: M/D Power Monitor Program
- 1. Set up the movable detector system for a 1 pass partial core flux map as per TI-53. Select flux thimbles as per the table below for the flux map.
Drive 10-Path Position Core Location A B C D E F These positions may be altered by the test engineer, based upon low-power physics testing results and previous special testing experience. i
- 2. Determine the detector normalization constants and enter them into the P-250 as follows:
a) Enter a value of 1.0 into the P-250 for the addresses shown in the table below. b) With all 5-path selector switches set to normal, run a flux trace. c) With all 5-path selector switches set to Emergency, run a second flux trace. d) Determine the detector normalization constants from Data Sheet C.2. e) Enter these detector normalization constants into the P-250 as shown in the table.below. Drive P-250 Address A K0908 B K0909 C K0910
'D K0911 E K0912 F K0913 1785 246
SPECIAL NO. 1 Page 5 of 10 12/30/79 APPENDIX C (Continued) Core Power Determination PART B: (Continued)
- 3. Verify that the P-250 parameters listed in the following table have the proper value and that the P-250 time and date are current.
Update as required. Address Value Function K0901 1 Set the power normalization factor Selects the modified K5525 1 " Flux Map Print" programs K0900 0 Initiated Pass Number Calibrction Constant for M/D K0864 Variable ( Power Monitor (1) Variable: The value entered is a ratio of the Primary Calorimetric Indicated Power (Item B on Data Sheet C.1) to the M/D calculated power (UO906) times the current value entered in (K0864). If no value has been entered into (K0864) enter 0.25. Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906)
- 4. For power determination, obtain a partial core flux map as per TI-53.
The M/D's need not be withdrawn between passes, and passes may be repeated as often as a power determination is required. NOTE: The calculated power (UO906) is printed af ter each pass and may be trended by the P-250 if desired. The individual detector normalized integrals are also printed. 1785 247 n
SPECIAL NO. 1 Page 6 of 10 12/30/79
. . APPENDIX C (Continued)
TABLE C-1 Temp Cp (1 5" F BTU /lbm F lbm/hr 556 1.260 3.6448 x 10 554 1.255 3.6553 x 10 552 1.250 3.6659 x 10 550 1.245 3.6765 x 10 7 548 1.240 3.6862 x 10 546 1.236 3.6959 x 10 7 7 544 1.231 3.7057 x 10 542 1.226 3.7155 x 10 7 540 1.221 3.7254 x 10 7 3 538 1.217 3.7348 x 10 7 536 1.213 3.7443 x 10 7
. 534 1.209 3.7538 x 10 532 1.206 3.7633 x 10 7 530 1.202 3.7729 x 10 (1)These values are from the 1967 ASME Steam Tables.Values are for a pressure of 2250 psia.
1785 248
SPECIAL NO. 1 . Page 7 of 10 12/30/79 APPENDIX C (Continued) . Data Sheet C.1 . Date Time Unit Power Tavg F Item # Calculation Procedure Units Loop 1 Loop 2 Loop 3 Loop 4 1 Loop d T - Inservice (at test point) Volts R2/TP-411J R6/TP-421J R10/RP-431J R13/RP-441J , 2 - Loop li T = (#1) x F 3 Loop li H = (#2) x Cp (from Table C.1) BTU /lbm 4 Loop RCS Flow (from Table C.1) 10 lbm/hr 6 5 Loop Reactor Power = (#3) x (#4) 10 BTU /hr Total Reactor Power - (#5) 6 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power - (#6) x 0.29307 MWT 8 % Reactor Power = (#7) x 0.02932 % ( Conversion factor for /i T obtained from scaling document. Remarks: w
- d Date By: .
CD W Checked By: N
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- SPECIAL NO. 1 Page 8 of 10 12/30/79 APPENDIX C (Continued)
DATA SHEET C.2 A = B ~ N N b" N N" N" A, = B y
=
C, = D, = _ E, = r, = NA = 1.00 N B
= = Ak =
N N N * " " C N b N D
= = Ch =
9 N N NE =b = DE = N b "E Ny
=p = EE =
N N Definitions: A,B'
'y N N, D N ' b' N
=
Normalized integral from sum =ary map for each detector in a normal path in the first pass A,B' = E E E' E' E' E Normalized integral from summary map for each detector in an emergency path in the second pass N,N' = A B C' "D' E' F Detector normalization factor for each detector Remarks: Data By: Date 1785 250
SPECIAL NO. 1 Page 9 of 10 12/30/79
, , APPENDIX C (Continued)
Part C: Using Thermocouples The incore thermocouples can be used as an indication of both core flow distribution and power shif ts during natural circulation. Prior to running a thermocouple map or trending the eight quadrant tilts (four center line and four diagonal tilts) the following should be verified: K0701-K0765 = 1, For the flow mixing factors K5501 = 0 Indicates the measured core 21 T is unreliable K0791 = 0.075, Core bypass flow fraction K5010 = 8. Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the running frequency of the Thermcouple Averaging Program at 1, 2, . . . . X 8 seconds or 64 seconds for us. The thermcouple programs breaks the core down into eight quadrants--four centerline and four diagonal quadrants (see Figure C-1) . Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot. The quadrant tilts are indicative of power shif ts and should be trended at approximately a 2-minute frequency. The following addressable values are the , quadrant tilts: t Quadrant Addressable Value 1 Ull59 2 Ull60 3 U1161 4 Ull62
, 5 U1151 6 U1152 7 U1153 8 U1154 A Short Form Map should be run periodically or upon request from the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for obtaining thermocouple maps.
The trend output and Short Form Maps should be attached to this procedure at the end of the test. 1786 251
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. SPECIAI, NO.1 "I A.p, :. ., . Page 10 of 10 y, . , i.,t. e $.<
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1785 252
. SPECIAL NO. 1 Page 1 of 4 12/15/79 APPENDIX D Procedure For Use Of Computer System For Data Collection The following parameters will be monitored during this test using the plant computer system.
Parameter Computer Point Pressurizer Pressure PO480A Pressurizer Level LO480A RCS Loop 1 Hot Leg Temperature T0419A RCS Loop 1 Cold Leg Temperature T0406A RCS Loop 2 Hot Leg Temperature T0439A RCS Loop 2 Cold Leg Temperature T0426A RCS Loop 3 Hot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Hot Leg Temperature T0479A RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressura P0400A Steam Generator 1 Narrow Range Level LO400A Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level LO420A Steam Generator 3 Pressure PO440A F Steam Generator 3 Narrow Range Level LO440A Steam Generator 4 Pressure P0460A Steam Generator 4 Narrow Range Level LO460A Power Range Channel 1 (Quadrant 4) N.0049A Power Range Channel 2 (Quadrant 2) N0050A Power Range Channel 3 (Quadrant 1) N0051A Fever Range Channel 4 (Quadrant 3) N0052A Incore Thermocouples T0001A through T0065A 1785 253
SPECIAL NO. 1 Page 2 of 4 12/15/79
. s APPENDIX D (Continued)
The computer trend typewriter will be used to monitor the following computer points. (Additional points may be added as required by the test director). BLOCK 1 Column Point Column Point Column Point 1 PO480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 P0400A 17 PO460A 6 T0426A 12 LO400A 18 LO460A BLOCK 2 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A 4 N0051A 10-13 Hottest T/C from e2ch core Quadrant 5 T0002A 14-18 As Required 6 T0013A
, To initially clear each data block perform the following step for each block to be used.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 2 button
- 6. Push STOP button Repeat the above 6 steps for each data block to be used.
NOTE: A Block Trend Error message will occur if the data block is initially clear. To set up the data blocks, perform the following series of steps for each point to be monitored.
- 1. Push the DIGITAL TREND button
- 2. Select the point address (i.e. PO480A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select block number (1 to 6) on keyboard.
- 5. Push VALUE 1 button
- 6. ' Select column number (1 to 18) on keyboard
- 7. Push VALUE 2 button
- 8. Push START button
}7bb 254
orsvunu av. A Page 3 of 4 12/15/79
, , APPENDIX D (Continued)
Once the blocks are set up they can be initiated by performing the following steps for each block.
- 1. Push DIGITAL TREND button.
- 2. Select block number (1 to 5) en keyboard
- 3. Push VALUE 1 button
- 4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 - 2 minute, etc.) The 30-second interval is recommended for the duration of the test transient
- 5. Push VALUE 3 button
- 6. Push START button If it is necessary to change the trend interval of a block or trend, perform the following.
- 1. Push DTGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
, 4. Select new interval number (0 = 30 sec. ,1 = 1 min. ,
2 = 2 min., etc) on keyboard
- 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select C on keyboard
- 5. Push VALUE 3 button
- 6. Push STOP button In addition to the data recorded on the trend typewriter, the following points will be monitored on analog trend recorded.
T0056A (Core exit temp). Others as needed (Recommend pressurizer pressure, steam generator level (WR) and steam generator pressure). After selecting the per to be used to record a value, ensure that it is cleared by performing the following steps.
- 1. Push ANALOG TREND function button
- 2. Select per number (1 to 12) on keyboard .
- 3. Push VALUE 1 button
- 4. Push STOP button 1785 255
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. 12/15/79 APPENDIX D (Continued)
To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select per number (1 to 12) on keyboerd
, 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the minimum value of the parameter to be monitored
- 7. Select range on the keyboard O. Push VALUE 3 button
- 9. Push START button Repeat these steps until all of the desired analog points are being recorded.
Prior to initiation of the transient, and at 15-minute intervals thereafter, incore thermocouple maps will be recorded at the programmers console in the computer room. To initiate an incore thermocouple map at that location, perform the following steps.
- 1. Push IN-CORE T/C MAP function button
- 2. Select 25 on keyboard for short-form current map
- 3. Push VALUE 1 button
- 4. Select output device code nun 3er 20 for programmers console on keyboard.
- 5. Push VALUE 2 button 6 Selec 1 on keyboard for a short-form map
- 7. Push VALUE 3 button
- 8. Push START button
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