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Latest revision as of 02:35, 22 February 2020
| ML19290C658 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/15/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19290C651 | List: |
| References | |
| PROC-791215, NUDOCS 8001220493 | |
| Download: ML19290C658 (31) | |
Text
8
-.m b +g SPECIAL TEST No. 4 EFFECT OF STEAM CENERATOR SECONDARY SIDE ISOLATION ON NATURAL CIRCULATION M e
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1785 325 son 12eo -
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- SPECIAL NO. 4 12/15/79 EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATION ON NAIURAL CIRCULATION Table of Contents Page 1.0 OBJECTIVES 2 2.0 3 PREREQUISITES 3.0 PRECAUTIONS 7 8
4.0 SPECIAL TEST EQUIPMENT 5.0 INSTRUCTIONS 9 6.0 ACCEPTANCE CRITERIA 13 APPENDIX A - References 14 APPENDIX B - Deficiencies 15 APPENDIX C - Power Measurement Technique 17
~
APPENDIX D - Computer Points 24 APPENDIX E - Steam line P Safety Injection Blocking Procedure 1785 326 W
SPECIAL NO. 4 12/15/79 TEST DESCRIPTION ,
With natural circulation established at + 3% rated thermal power and reduced reactor coolant temperature, steam generators will be isolated sequentially to determine the effect on natural circulation conditions.
Isolation of up to 3 steam generators will be tested if limitations permit. Steam generators will then be sequentially returned to service to verify that natural circulation can be reestablished.
6
- e-se e ,W . .
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- 1785 327
SPECIAL NO. 4 Page 1 of 12 12/15/79 1.0 OBJECTIVES 1.1 Determine the effect of steam generator isolation on natural circulation conditions.
1.2 Verify that natural circulation can provide sufficient flow to remove decay heat after partial loss of heat sink.
1.3 Verify that natural circulation can b'e reestablished in primary loops after steam generators are returned to service.
= .. . . .
_2_ 1785 328 h
G
. , SPECIAL NO. 4 Page 2 of 12 12/15/79 2.0 PREREQUISITES 2.1 Reactor is critical and manually controlled at approximately 3% power.
(Power level determined as indicated in Appendix C).
/
2.2 All four reactor coolant pumps in operation.
/
2.3 Reactor coolant system pressure is being maintained at approximately 2235 psig and average coolant temperature is being maintained at approximately 520 F.
/
2.4 Steam generator pressure is being maintained at approximately 800 psig using steam dumps in automatic under pressure control.
/
2.5 Feedwater to the steam generators will be supplied by the main feedwater system with manual flow control if possible. If previous testing proves additional control is required, the auxiliary feedwater system will be used. Steam generator levels should be maintained at approximately 33%
on narrow range indicators.
/
2.6 If. auxiliary.feedwatac ie m he.used, at least 190,000 gallons in-the condensate storage tanks are availrble to supply the steam generators.
/
2.7 Steam generator chemistry is in a condition that the absolute minimum steam generator blowdown can be maintained through the test.
/
2.8 The 100 psi steamline differential pressure safety injection bistables have been blocked through temporary conditions as specified in Appendix E.
/
1785 329
, , SPECIAL NO. 4 Page 3 of 12 12/15/79 2.0 (Continued) 2.9 Brush recorders have been set up to monitor test points at the following locations:
2.9.1 Recorder No. 1 (6 Channel)
Channel Parameter Test Point Rack
~ '
1 RCS Flow-Loop 1 FP/414B l-R-1 2 RCS Flow-Loop 2 FP/424B I-R-1 3 RCS Flow-Loop 3 FP/434B l-R-1 4 RCS Flow-Loop 4 FP/444B l-R-1 5 Pressurizer Pressure PP/455B l-R-1 6 Pressurizer Level LP/459B l-R-1 2.9.2 Recorder No. 2 (6 Channel)
Channel Parameter Test Point Rack 1 SG 1 Pressure PP/416B l-R-3 2 SG 1 Level LP/501 1-R-23 3 SG 1 Steam Flow FP/512B l-R-3 4 SG 2 Pressure PP/426B l-R-3 5 SG 2 Level LP/502 1-R-23 6 SG 2 Steam Flow FP/522B l-R-3 2.9.3 Recorder No. 3 (6 Channel)
Channel Parameter Test Point Rack 1 SG 3 Pressure PP/436B l-R-4 2 SG 3 Level LP/503 1-R-23 3 SG 3 Steam Flow FP/532B l-R-4
.4 S Q g sstq _ ._. PF/446B l-R=4 _
5 SG 4 Level LP/504 1-R-23 6 SG 4 Steam Flow FP/542B l-R-4 2.9.4 Recorder No. 4 (4 Channel)
Channel Parameter Test Point Rack 1 SG 1 Main Feed Flow FP/510B l-R-3 2 SG 2 Main Feed Flow FP/520B l-R-3 3 SG 3 Main Feed Flow FP/530B l-R-4 4 SG 4 Main Feed Flow FP/540B l-R-4 If auxiliary feedwater is to be used in place of the normal feedwater supply, brush recorder No. 4 should monitor the following points in the auxiliary control room:
)]0h b
SPECIAL NO. 4 Page 4 of 12 12/15/79 2.0 2.9 2.9.4 (Continued)
Channel Parameter Test Point Rack 1 SG 1 Aux Feed Flow L-3-163, TP 13 1-L-llB 2 SC 2 Aux Feed Flow L-3-155, TP 13 1-L-11A 3 SG 3 Aux Feed Flow L-3-147, TP 12 1-L-11B 4 SG 4 Aux Feed Flow L-3-170, TP 12 1-L-11A NOTE: Record the following on all strip charts:
a) Unit No.
b) Data c) Procedure No.
d) Parameter scale and range e) Chart spied f) Name of person recording data g) Recorder I.D. No.
2.10 Record the following parameters on the reactivity computer recorders:
- a. Flux
- b. Average wide range Teold
- c. Average wide range Thot
- d. Average steam generator pressure
/
2.11 Set up the P-250 computer trend printer to monitor the following parameters at 1-minute intervals, as specified in Appendix D.
a Pressuriz,e,r pressure __ _.
- b. Pressurizer level
- c. Wide range Tcold (all loops)
- d. Wide range Thot (all loops)
- e. Steam generator pressure (all loops)
- f. Steam generator level (all loops)
- g. Power range channels
- h. Additional parameters as determined by the test engineer
/
2.12 Trend 4 incore thermocouples as determined by the test engineer on the analog trend recorders in the main control room. It is suggested that these thermocouples be the hottest responding thermocouple in each core quadrant.
/
1785 331 "4
SPECIAL NO. 4 Page 5 of 12 12/15/79 2.0 (Continued) 2.13 Control Bank D is at approximately 160 steps or as specified by the test engineer to permit reactor power increase up to approximately 3%
(required control bank D position may be determined during the hot zero power test program).
/
2.14 Pressurizer pressure and level control are in automatic, maintaining pressurizer pressure at approximately 2235 psig and level at approximately 25%.
/
2.15 Normal charging and letdown are in service under automatic control.
/
2.16 A determination of the sensitivity of the NIS to changes in T has c id been completed.
/
S*O W&M
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_ .. 1786 332 ._
SPECIAL NO. 4 Page 6 of 12 12/15/79 3.0 PRECAUTIONS 3.1 Do not exceed 5% rated thermal power at any etne while the test is in progress.
3.2 Do not exceed any of the following temperature limits.
3.2.1 Core exit temperature of 610 F 3.2.2 AT as indicated by T -T H C f 100 F 3.2.3 Tavg of 578*F for any loop 3.3 Maintain reactor coolant pump seal and thermal barrier differential pressure requirements as specified in SOI-68.2.
3.4 Avoid any sudden changes in feedwater flow or steam generator level.
3.5 Ensure seal flow to each reactor coolant pump is maintained at or slightly above 6 gpm during the test.
3.6 After the reactor coolant pumps are tripped, the normal Tavg and AT indications will become unreliable. 4 T and Tavg should be calculated by taking the difference and the average of the hot and cold leg temperature indications respectively.
3.7 Do not exceed 1600 psi primary to secondary differential pressure limit. -
3.8 Maintain reactor coolant system cold leg temperatures as stable as possible during system transients. This is required to determine changes in core power level on the NIS channels.
3.9 Because safety injection on high-steamline differential pressures has been disabled, manual safety injsetion should be initiated if the following
- . conditions _ occur- _ _ .
=~ - .
(Conditions to be provided by Westinghouse).
3.10 Do not restart a reactor coolant pump if there is any indication of an excessively high a T in any of the loops.
-7 I785 333 EW* ,
SPECIAL NO. 4 Page 7 of 12 4.0 Special Test Equi;=ent 12/15/79 Identification Calibration Instrument Specification Number Verification 4.1 Reactivity computer 4.2 Brush 260 recorders (3) .
4.3 Brush 400 recorder (1)
A y-,,_- -
If test instruments are changed during this test, the instrument infor=ation must be recorded here and an entry made in the chronological log book explaining this change.0h b
SPECIAL NO. 4 Page 8 of 12 12/15/79 5.0 INSTRUCTIONS 5.1 Start brush recorders, analog trend recorders, reactivity computer and P-250 trend blocks.
- /
CAUTION: Following reactor coolant pump trip Tavg and T indication will be unreliable.
~
5.2 Simultaneously trip all reactor ceclant pumps. Reduce seal water flow to each pump to approximately gpm.
/
5.3 Maintain steam generator level at approximately 33%.
/
NOTE: At initiation of natural circulation the following initial response is expected:
- 1. Wide range Thot, increase
- 2. Wide range Tcold, slight decrease or constant
- 3. Core exit thermocouples, increase
- 4. Pressurizer level, increase
, Natural circulation will be stable when:
- 1. T between wide range That and Teold is constant
- 2. T between wide range Tcoid and core exit thermocouple average temperature is cotstant
- 3. Wide range Thot core exit thermocouple average tenperature 5.4 Adjust setpoint on steam dump pressure controller PIC-1-33 as needed to
. . malatain cold _ leg _gmperatur,,es,ag e .the initial values. - _
/
5.5 Adjust setpoints on atmospheric relief valve pressure controllers for each loop to maintain steam pressure below 1025 psig before isolating any steam generators. This should prevent opening of main steam safety valves.
/
5.5.1 Establish maximum flow through normal letdown path, and manually increase charging flow to maintain a constant RCS water volume. Start an additional centrifugal charging pump if necessary.
/
CAUTION: Monitor primary to secondary differential pressure very closely during the transient and do not allow it to exceed 1600 psi. NOTE: is increased. Allow the pressurizer level to increase when T,yg
SPECIAL NO. 4 Page 9 of 12 12/15/79 5.0 (Continued) 5.6 Close MSIV FCV-1-22. Isolate feedwater flow to steam generator #3. Carefully control feedwater additions to the remaining steam generators to hold the levels at approximately 33%. It will be necessary to adjust the steam dump pressure controller setpoint to reduce T in the uniso-laced loops so that the steam generator pressure in the*2shlated loop remains below the setpoint of the atmospheric relief valve.
/
NOTE: During this transient the following responses can be expected.
- 1. Wide range Thot, slight increase
- 2. Wide range Teoid for Loop 3, increase *
- 3. Wide range Teoid for other loops, decreased using steam dump
- 4. Core exit thermocouples, slight increase 5.7 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop 3 T is approximately zero.
/
5.8 Verify that the calculated value for Tavg for the remaining 3 loops has stabilized. If Tavg continues to increase and cannot be stabilized the i test director should determine whether further testing can be conducted. l -
/
CAUTION: Monitor primary to secondary pressure very closely during the transient and do not allow it to exceed 1600 psi. 5.9 Close MSIV FCV-1-29. Isolate feedwater flow to steam generator #4.
. . Carefully controLfeedyater 2dAf t. ions to the remaining steam generators to hold the levels at approximately 33%. It will be necessary to adjust the steam dump pressure controller setpoint to reduce T in the uniso-latedloopssothatthesteamgeneratorpressureinthe*fs81atedloops remain below the setpoint of the atmospheric relief valves.
/
NOTE: During this transient, the following responses can be expected:
- 1. Wide range Thot, increase
- 2. Wide range Tcold for loops 3 and 4, increase
- 3. Wide range Tcold for loops 1 and 2, decrease using steam dump
- 4. Core exit thermocouples, increase 1785 336
SPECIAL NO. 4 Page 10 of 12 12/15/79 5.0 (Continued) 5.1C Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop 4 T is approximately zero.
/
5.11 Verify that the calculated value for Tavg for the remaining 2 loops has stabilized. If Tavg continues to increase and cannot be stabilized, the test director should determine whether further testing can be conducted.
/
CAUTION: Monitor primary to secondary pressure very closely during the transient and do not allow it to exceed 1600 psi. If equilibrium has not been reached within one-half hour proceed immediately to the next step. 5.12 Slowly reduce the setpoint on atmospheric relief valve controller PIC-1-31A and allow steam generator #4 pressure to reach approximate equilibrium with steam header pressure.
/
5.13 Open MSIV FCV-1-29 and close atmospheric relief valve PCV-1-30. Slowly restore feedwater flow to steam generator #4. Carefully control feedwater addition to steam generators 1, 2, and 4 to maintain steam generator levels at approximately 33%.
/
NOTE: During the transient, the following responses can be expected.
~
- 1. Wide range Thot, decreases ~ ~
'27 Wide rahgei T'hofd~fE Loop 4'," decrease
- 3. Wide range Teold for Loop 3, no change
- 4. Wide range Teold for Loops 1 and 2, Increase by using steam du=p 5.14 Allow natural circulation to stabilize. Steady state should be achieved when the calculated loop T's for loops 1, 2, and 4 are approximately equal.
/
i785 337 O
SPECIAL NO. 4 Page 11 of 12 12/15/79 5.0 (Continued) 5.15 Slowly reduce the setpoint on atmospheric relief valve controller PIC-1-24A and reduce steam dump to condenser, allowing steam generator #3 to reach approximate equilibrium with steam header pressure of 1005 psig.
/
5.16 Open MSIV FCV-1-22 and close ' atmospheric relief valve PCV-1-23. Slowly restore feedwater addition to the steam generators to mtintain steam generator levels at approximately 33%.
/
NOTE: During the transient the following responses can be expected.
- 1. Wide range Thot, decrease
- 2. Wide range Teoid for loop 3, decrease
- 3. Wide range Tcoid for loops, 1, 2, and 4, Increase using oceam dump 5.17 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop T's are approximately equal.
/
5.18 Stop recording' test data.
/
5.19 Insert control bank D until the reactor is in the hot zero power test range.
/
CAUTION: Ensure pressurizer spray controllers are at zero output prior to starting the first reactor coolant pump. 5.20 Restart all four reactor coolant pumps in accordance with SOI-68.2.
/
5.19 Return control of the system to operations.
/
1785 338
. SPECIAL NO. 4 Page 12 of 12 12/15/79 6.0 ACCEPTANCE CRITERIA 6.1 Core exit thermocouple temperature does not exceed 610 degrees Fahrenheit.
/
6.2 AT for any loop does not exceed 100 degrees Fahrenheit.
/
.6.3 Tavg for any loop does not exceed 578 degrees Fahrenheit.
/
6.4 Suf ficient natural circulation could be maintained in active primary loops to maintain stable temperatures following partial loss of heat sink.
/
6.5 Natural circulation could be restored to inactive loops when associated steam generators were returned to service.
/
_= - 1786 339 p* e
SPECIAL NO 4 P. age 1 of 1 12/15/79 APPENDIX A References
- 1. FSAR
- 2. Tecinical Specifications .
- 3. Plant Operating Instructions SOI 68.2 E0I 5 i
1785 340 fg* , _ , . .w *
~ --
.. .w.. u. .
, , Appendix B i/6/79 Page of Rev.
Page of Test Deficiencies # Test Deficiency
~
I t e i Recot:: mended Resolution 4 l t i J Final Resolution Originator / Signatu';e Date PORC Review of Final Resolution 1785 341 Approval of Final Resolution _ / - Plant Superintendent Date
. . . ~ .
__ _, : 5 ._
SPECIAL NO. 4 Page 1 of 10 12/30/79 APPENDIX C Punchlist:
- 1. Part C - Thermocouples ,
- 2. Part B - Address in P-250 for:
- a. Priority scan option selection
- b. Power calibration constant
- c. Calculated power i
i _16- 1785 342 . 4
,. , . . . = = = - -
------.4 SPECIAL NO - Page 2 of 10 12/30/79 APPENDIX C (Continued)
Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)
- 1. Reference (m 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
- 1. Power Conversion Constant Adjustment, a) The output of the REF primary calor 1=etric will give a % power outpuc; 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 every,2 minutes or as necessary to continuously monitor core power.
_ = _ - - - 1766 343 17_ m Q 9 b
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SPECIAL NO. 4 Page 3 of 10 12/30/79 APPENDIX C CORE POWER DETERMINATION PART A: Primary side calorimetric - 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 A T; multiply that A 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 A T so a correction factor is required to compensate for pump heating, refer to Appendix D of ST-9A). C.3 Sum the loop heat rates and convert to a percent reactor power. .The output is used in Part B. f 1785 344 O
SPECIAL NO. 4 j j Page 4 of 10 i 12/30/79 l APPENDIX C (Continued) . Core Power Determination ' PART B: M/D Power Monitor Program i 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 i A B 6
' D E
F These positions may be altered by the test engineer, based upon low-power physics testing results and previous special testing experience.
- 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.
~
~ ' - ~ ~ ~
- ) With'a11 5-path se" lector 3v1tches 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 KO908 B K0909 C K0910 D K0911 E K0912 F K0913 }g}
- e. -o, e g. wee
SPECIAL NO. 4 Page 5 of 10 i 12/30/79 APPENDIX C (Continued) Core Power Determination 4 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 gr900 0 Initiated Pass Number Calibration Constant for M/D KO864 Variable (1) Pcwe.r Monit.;r (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) = Curre .: (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
- ormalized integrals are also printed.
- . ,- . . . _ , _ - - _ = - -
1785 346 M %*q 9
~
SPECIAL NO. 4 Page 6 of 10 12/30/79 APPENDIX C (Continued) TABLE C-1 femp Cp m F BTU /lbm F lbm/hr 556 1.260 . 3.6448 x 10 554 1.255 3.6553 x 10 7 ! 552 1.250 3.6659 x 10 7 550 1.245 3.6765 x 10 i 7 548 1.240 3.6862 x 10 546 1.236 3.6959 x 10 544 1.231 3.7057 x 10 542 1.226 3.7155 x 10 540 1.221 3.7254 x 10 7 538 1.217 3.7348 x 10 l 536 1.213 3.7443 x 10 7 534 1.209 3.7538 x 10 532 1.206 3.7633 x 10 7
. .. .,_ 530,_ _ _ _ _ JQL . 3.7729 z_10_
(1}These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia. 1786 347
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SPECIAL NO. 4 Page 7 of 10 12/30/79
. APPENDIX C (Continued)
Data Sheet C.1 Date Time Unit Power Tavg F
.I 1
Item # Calculation Procedure Units Loop 1 Loop 2 Loop 3 Loop 4 1 Loop ti T - Inservice (at test' point) Volts R2/TP-411J R6/TP-421J R10/RP-431J R13/RP-441J 2 Loop 21 T = (#1) x (I ' F 3 Loop 21 H = (#2) x Cp (frog Table C.1) BTU /lbm ' l 4 Loop RCS Flow (from Table C.1)l 6 10 1bm/hr 5 6 ' Loop Reactor Power - (#3) x (# s) 10 BTU /hr Total Reactor Power = (#5) i 6 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr i j 7 Reactor Power - (#6) x 0.29307' MWT f t 8 % Reactor Power = (#7) x 0.02932 % Conversion factor for 21 T obtained from scaling document. Remarks: 8 I i
*%d t CE) Date By: '
Checked By: ! j L/4
- b CI) -22
SPECIAL NO. 4 i Page 8 of l0 12/30/79 AP T TIX C (Continuad) A = B = C = D = E ~ I ~ N N N N N -- N A, = B, = C, = o, = E s
=
F, = NA = 1.00 - N =b = Ak = B B
- N N N ~ " "
C N N N " " D" D N N N E =b- = bE = N N A N ' N =N = EE = F F N N Definitions:,, _ . _ _ _ = , , - -- A,B,C,D,E,F N N N N N N
= Normalized integral from su= mary 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' = Detector normalization factor for each detector B C' D' E' F Remarks:
R Data By: Date 1785 349 3 ...
m. SPECIAL NO. 4 Page 9 of 10 i 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 shifts 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 A 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 cuadrants 5-8 cannot. The quadrant tilts are indicative of power shifts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts: I gadrant Addressable Value 1 U1159 2 U1160 3 Ull61
's . U1162 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. 086 350 4 e
, SPECIAL NO. 4 Page 1 of 4 12/15/79 i
APPENDIX D Procedura For Use Of Computer System For Data Collection The following parameters will be monitored during this test using the plant computer system. Paramater Computer Point Pressurizer Pressure PN80A Pressurizar Level 0480A 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 Temperoture T0426A RCS Loop 3 Hot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Hot Leg Temperature 'TJ479A RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressure 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 Steam Generator 3 Narrow Range Level LO440A Steam Generator 4 Pressure PO460A Steam Generator 4 Narrow Range Level LO460A P .er Range Channel 1 (Quadrant 4) N0049A Power Range Channel 2 (Quadrant 2) N0050A Power Range Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A Incore Thermocouples T0001A through T0065A 1786 351
=
p~ SIECIAL NO. 4 l ;p;j'f.[ i i .. Page 10 of 10 l
" . .' 12/30 , jI APPENDIX C y, (continued)
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CENTER UNE QUARTER-CORE SYMMETRY '
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d: Figure 3. Quarter-Core Defer.itions of Symmetry ' s 1786 352 .
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SPECIAL NO. 4 Page 2 of 4 ' 12/15/79 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 Colu=n Point Column Point Column Point 1 P0480A 7 T0459A 13 PO429A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 PO400A 17 PO460A 6 T0426A 12 LO400!. 18 LO460A BLOCK 2 l Column Point Colu=n Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A 4 N0052A 1 0- 13 Hottest T/C from each 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 '.o 6) on keyboard
- 3. Push VALUE 1 button
- .- 4. -Select +orriteytroard- - - --
- 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 bir.ck is initially clear. To set up the data blocks, perform the following series c; steps for each point to be monitored.
- 1. Push the DIGITAL TREND buttor
- 2. Select the point address (f .e. PO480A) on the alphanu=eric 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 keyboarJ
- 7. Push VALUE 2 button
- 8. Push SIART button
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SPECIAL NO. 4 Page 3 of 4 12/15/79 APPENDIX D (Continued) Once the blocks are set up they can be initiated by perfoming the following steps for each block.
- 1. Push DIGITAL TREND button.
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 = 2 minute, etc.) Th'e 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 DIGITAL 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 butten ,
- 6. Push STOP button In addition to the data recorded on the trend typewriter, the following points will
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be monitored on analog-trend-reecrdeu. -- - - T0056A (Core exit temp). Others as needed (Recommend pressurizer pressure, steam generator level (WR) and steam generator pressure). Af ter 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 1786 354
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SPECIAL NO. 4 Page 4 of 4 12/15/79 APPENDIX D (Continued) To start an analog trend perfom 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 keyboard
- 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
- 8. 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 thereaf ter, incore thermocouple maps will be recorded at the progra=ers 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-fom current map
- 3. Push VALUE 1 button
! 4. Select output device code number 20 for progra m ers console on keyboard.
- 5. Push VALUE 2 button
- 6. Select 1 on keyboard for a short-f am map
- 7. Push VALUE 3 button
- 8. Push START button
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