ML19290C659

Natural Circulation at Reduced Pressure, Special Test 5

ML19290C659
Person / Time
Site:	Sequoyah
Issue date:	12/15/1979
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19290C651	List: ML19290C650 ML19290C652 ML19290C653 ML19290C656 ML19290C658 ML19290C659 ML19290C660 ML19290C661 ML19290C662 ML19290C663 ML19290C664
References
PROC-791215-01, NUDOCS 8001220499
Download: ML19290C659 (30)

Text

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/s SPECIAL TEST NO. 5 NATURAL CIRCUIATION AT REDUCED PRESSURE

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SPECIAL NO. 5 12/15/79 NATURAL CIRCULATION AT REDUCED PRESSURE Table of Contents Page 1.0 OBJECTIVES 1 2

2.0 PREREQUISITES 3.0 PRECAUTIONS 4 4.0 SPECIAL TEST EQUIPMENT S

5.0 INSTRUCTIONS 6.0 ACCEPTANCE CRITERIA 7 8

DATA SHEETS APPENDLX A - References APPENDIX B - Deficiencies

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APPENDIX C - Power Measurement Technique APPENDIX D - Computer Points

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1786 357

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' SPECIAL NO. 5 Page 1 of 7 12/15/79 1.0 OBJECTIVES 1.1 Verify the ability to maintain natural circulation at reduced power levels.

1.2 Verify the accuracy of the saturation margin indication from the plant computer.

1.3 Provide operational experience at lower saturation margins and the affects of charging and secondary steam flow on the control of the saturation margin.

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Page 2 of 7 12/15/79 2.0 PREREQUISITES NOTE: This test can be done in conjunction with Test III, Natural Circulation With Loss of Pressurizer Heaters.

2.1 The reactor is critical at es, 3% power and under manual control with control bank D at e- 160 steps or as specified by Test Engineer. (Power determined a,s indicated in Appendix B.)

. Date 2.2 All four reactor coolant pumps in operation.

Date 2.3 Steam generator level maintained at approximately 33% on the narrow i range indicators by the main feedwater pumps. (Auxiliary feedwater may be used if main feedwater proves to difficult to control.)

Date 2.4 Pressurizer pressure and level being maintained automatically at approximately 2235 psig and 27% respectively.

' Date 2.5 RCS temperature (Tavg) approximately 550 F.

Date 2,6 Low Power Physics-Test Progrer-hae-been completed to the eitent necessary for conduct of this test.

Date 2.7 Steam generator pressure at approximately 1000 psig and being maintained by steam dump to the condenser on pressure control.

Date

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SPECIAL NO. 5 Page 3 of 7 12/15/79 2.0 (Continued) 2.8 Connect brush recorders to the following test points:

Brush Recorder 1 Connect To: Monitoring:

Channel #1 1-R-1, FPhlhB RCS Flow-Icop 1 Channel #2 1-R-1, FP42hB RCS Flow-Loop 2 Channel #3 1-R-1, FPh3hB RCS Flow-Loop 3 i Channel #4 1-R-1. FPkkhB RCS Flow-Loop h Channel #5 1-R-1, PPh55B Pressurizer Pressure Channel #6 1-R-1, LP459B Pressurizer Level Brush Recorder 2 Connect To: Monitoring:

Channel #1 1-R-3, FPS 10B Main Feed Flov, SG #1 Channel #2 1-R-3, FPS 12B Steam Gen. #1 Steam Flow Channel #3 1-R-3, PP51hB Steam Gen. #1 Pressure Channel #4 1-R-3, FPS 20B Main Feed Flov, SG #2 Channel #5 1-R-3, FP5223 Steam Gen. #2 Steam Flow i Channel #6 1-R-3, PP52hB Steam Gen. #2 Pressure

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Brush Recorder 3 Connect To: Monitoring:

Channel #1 1-R-4, FP530B Main Feed Flov SG #3 Channel #2 1-R h, FP532B Steam Gen. #3 Steam Flow Channel #3

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1-R-4, PPS3hB Stieam' Gen. #3 Pressure

! Channel #h 1-R 4, FP5kOB Main Feed Flow SG #h Channel #5 1-R h, FP542B Steam Gen. #h Steam Flow Channel #6 1-R k, PP5hhB Steam Gen. #4 Pressure

' Brush Recorder k Connect To: Monitoring:

Channel #1 1-R-18, FP121A RCS Charging Flov

.- Channel.#2 .1 M 3r FP132 RCS Intdown Flow Channel #3 1-R-5, PPkO3A Wide range RCS Pressure Channel #h 1-R-22, TP45h Pressurizer Steam Temp Channel #5 1-R-20, TPh53 Pressurizer Liquid Temp.

NorE: Record the following on each recorder chart.

a) Unit #

b) Date c) Procedure #

d) Parameter Scale and Range e) Chart Speed f) Name of person recording data g) Recorder I.D. #

29 Record on [ -computer recorder a) Flux b) Average vide-range T eold c) Average vide-range T d) Averagesteam-generabrpressure Date 1786 360

4 4

1. h153*

1. ___ k.?k TEST TARGET (MT-3) 1'0 " EM N

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1.25 1.4 1.6

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MICROCOPY RESOLUTION TEST CHART

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MICROCOPY RESOLUTION TEST CHART

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MICROCOPY RESOLUTION TEST CHART

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TEST TARGET (MT-3) 1.0 l9 BH IBM 5 ff LE 1.1 ie m

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• MIC90 COPY RESOLUTION TEST CHART

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SPECIAL NO. 5 Page h of 7

- 12/15/79 2.0 (Continued) 2.11 Set the trend recorders and computer trend printer in the main control room to monitor the parameters indicated. in Appendix D.

I Date 3.0 PRECAUTIONS 3.1 Maintain. reactor coolant pump seal and ther=al barrier differential pressure requirements as given in SOI 68.2.

3.2 Do not exceed 5". nuclear power at any time while ;he test is in progress.

33 Do not exceed any of the following temperature limits:

. 3.3.1 Core exit temperature of 610 F.

3.3.2 4 T as indicated by T 3 -T C f 65 F.

j 3.3.3 Tavg Temperature of 578 F.

3.4 When equilibrium has"been established after the in'itial transient, -

avoid any sudden changes in feedvater flow or in steam generator water level.

' 35 After the reactor coolant pumps are tripped the normal Tavg and d T indications vill be cone unreliable. 6 T and Tavg should be calculated by taking the difference and the average of the hot and cold leg temperature indications respectively.

.. .. _ . _ _ ,. - _ - - = - .

3.6 Maintain saturation margin greater than 10 degrees Fahrenheit at all times.

3.7 Maintain Teold at approximately the pretrip temperature to maintain accurate NIS power level monitoring.

. 1787 001 M e

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SPECIAL NO. 5 Pa6e 5 of 7

. 12/15/79 50 TEST INSTRUCTIONS 51 Ensure the pressurizer backup heaters lA,1B, and 1C re=ain off by moving handsvitches 1-HS-68-3hlA and 341D to the 'Stop' position and moving 1-HS-68-3hlH to 'Stop-Pull to Lock'.

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52 Record the data f ndicated on Data Sheet 51.

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53 Start the computer trend printer printing at the fastest interval possible.

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5.h Shutoff the pressurizer control heater group by moving 1-HS-68-341F to 'Stop' .

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55 Record the time, on the data recorder charts in the auxilinry instrument room and then start then at 125=m/ min.

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CAUTION: Continuously monitor main steam line pressures and carefully j control fesdvater addition during the transient to ensure the differential pressure between any two steam lines does not exceed 100 psid. This vould initiate a safety injection.

Snould this occur, refer to AOI-19 (Feedvater to each steam generator must be equal before tripping the pumps).

5.6 Shutdown the reactor coolant pumps in accordance with SOI-68.2 (simultaneously).

_ - - - . t -

NCTfE: At the initiatiort of natural circulation the following temperature response is expected.

a) Wide range Thot - increase b) Wide range Teold - slight decrease or constant c) Core exit thermocouple - increase d) Tavg indication - unreliable e) Delta-T indication - unreliable f) Prescurizer level and pressure - increase 57 verify natural circulation is established by following the operational guidelines given in EOI-5, Appendix A.

/

NOTE: Natural Circulation vill be stable when:

1) 4 T between vide range Thot and Tcold is constant.

2) A T between vide range Tcold and core exit thermoccuple average temperature is constant.

3) Wide range Thot 0 core exit thermocouple average temperature.

-S-1787 002

SPECIAL NO. 5

• Page'6 of 12/15/79 50 (continued) 57 571 Assume manual control of charging flow and match charging to letdown to maintain a constant RCS vater volu=e.

5.8 Once equilibrium has been established adjust trend printer printout intervals as psecified by the test director.

/

NOTE: A slow cooling of the pressurizer will being at this point and a corresponding decrease in RCS pressure.

5.9 Record the highest T/C temperature indicated on the T/C maps, the lowest of the four pressurizer pressure protection channels, and the saturation margin indicated on the analog trend recorder on data sheet 5.3 at periodic intervals during the depressurization.

/

NOTE: If desired, the depressurization rate can be increased by using auxiliary spray. Once the RCS pressure drops below 1700 psig, the pressure reading for Data Sheet 5 3 should be taken from the RCS vide range pressure indicators.

l CAUTION: Safety injection must be manually blocked when RCS pressure drops below 1970 psig.

5.10 Approximately one hour after RCP trips, reduce reactor power to approximately 1 5% and maintain this power level for the duration of the test.

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5 11 Continue to monitor the core exit T/C temperature to verify natural

' 'tTreulation-is MitttiberA'ii*thT saturation margin is dec'reased. Continue

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pressure drop until the test director indicates sufficient data has been recorded to verify the accuracy of the saturation margin indicated on the trend recorder. Increase charging and/or steam flov to increase the saturation marging at this time.

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NOTE: Do not allow the saturation margin to decrease below 10 F. The cargin can be increased by either increasing RCS pressure or reducing Teold.

5 12 Using 1967 ASME steam tables, determine the saturation margin using the pressure and temperature recorded in Data Sheet 5 3 and plot this value along with the saturation cargin taken from the analog trend recorder vs time on Data Sheet 5.h.

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NOTE: Step 512 can be conducted concurrent with the depressurizatien.

1787 003 g %

SPECIAL NO. 5 Page 7 of 7 12/15/79 5.13 Increase the saturation margin back to above 50 degrees Fahrenheit and stop the brush recorders and trend printers. Attach copies of the print-outs and charts to Data Sheet 5 2.

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5 14 An evaluation of the accuracy of the saturation meter should be done at this time to determine the necessity of reprogramming the computer.

The computer trend should indicate a saturation margin within 3% of the margin determined from the steam tables,.

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5.15 Increase RCS pressure back to 2235 by selectively energizing the pres-surizer backup heaters.

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5.16 Insert control bank D until the reactor is in the hot zero power test range.

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5.17 Restart all four reactor coolant pumps in accordance with SOI 68.2.

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4 . ., .

5 18 Return pressurizer level to approximately 27% and return RCS pressure and level control to automatic.

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NOTE: Conditions can now be established for the conduct of the next test.

6.0 ACCEPTANCE CRITE. IIA 6.1 Core exit T/C temperatures does not exceed 610 P.

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6.2 Delta-T for any loop does not exceed 65 F.

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6.3 T,yg for any loop does not exceed 578 F.

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6.k Natural circulation can be established and maintain-d at reduced lov RCS gressure.

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6.5 The plant computer calc dated saturation margin is in agreement with margins determined using recorded pl?nt parameters.

q_ If87004 _

Page 1 of 3 12/15/T9 DATA SHEET 5 1 tra it Initial Conditions Date Time Pressurizer Pressure PR-68-340 P818 Pressurizer Level LR-68-339 Red Pen  %

1. 1 Hot leg temp o TR-68-1 F

1. 1 Cold leg temp o TR-68-18 F

1. 2 Hot leg temp o TR-68-1 F

1. 2 Cold leg-temp o TR-68-18 F

1. 3 Hot leg temp o TR-68 h3 F

1. 3 Cold leg temp o TR-68-60 F

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1. 4 Hot leg temp ~ ~

~ o TR-68-h3 F Nh Cold leg temp o TR-68-60 F S.G. #1 Level (narrow range)

LI-3 h2 - -

. .. ,_ _. - _ _ _; . - = - - - -

S.G. #2 Level (narrow range)

LI-3-55  %

S.G. #3 Level (narrow range)

LI-3-97  %

S.G. #h Level (narrow range)

LI-3-llo  %

S.G. #1 Level (vide range)

LR-3 h3 Pen 1  %

S.G. #2 Level (vide range)

LR-3 k3 Pen 2  %

S.G. #3 Level (vide range)

LR-3-98 Pen 1  %

~S.G. #h Level (vide range)

LR-3-98 Pen 2  %

/ 1787 005 Recorded By Date

i SPECIAL NO. 5 i Pqe 2 of 3 t 12/15/79 DATA SHEET 5 1 (Continued.)

Unit ,.

Date Time S.G. #1 Pressure PI-1-2A P516 S.G. #2 Pressure PI-1-9A Psig S.G. #3 Pressure PI-1-20A Ps18 S.G. #h Pressure PI-1-27A P818 S.G. #1 Feedvater flov FI-3-35A _ EPn S.G. #2 Feedvater flow FI-3-h8A gpm S.G. #3 Feedvater :.* low FI-3-90A gpm S.G. #h Feedvater flow FI-3-103A 8Pr S.G. #1 Steam flov FI-1-3A lbs/hr S.G. #2 4 team flow FI-1-10A lbs/br S.G. #3 Steam flov FI-1-21A._- _ . . _ .

lbs/hr S.G. #k Steam flow FI-1-28A lbs/hr Icop #1 T-average TI-68-2E F Loop #2 T-average o,

TI-68-25E #

Loop #3 T-average TI-68-hhE F Loop #h T-average op TI-68-6TE

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Recorded By Date

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1787 006

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SPECIAL NO. 5 Page 3 of 3 12/15/79 DATA SHEEI 51 (Continued)

Unit Date Time Icep #14 T TI-68-2D F Loop #24 T TI-68-25D F Loop #34T TI-68 khD F Loop #44 T TI-68-6TD F (0-100". = 0-55 F A T)

NIS Channel N kl  %

NIS Channel N h2  %

NIS Channel N h3  %

NIS Channel N-44  %

NOTE: Attach Computer Printout'or Incore Thermocouple T Eperature Map.'~

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Refer to Appendix A for the procedure for prirting out of tnis map.

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Recorded By Date

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1787 00T

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i i SPECIAL NO. 5 i Pa6e 1 of 1

! 12/15/T9 DATA SHEET 5 3 Unit Date Time Lowest of PI-68-3hA, 33kA, 323A or 322A (PI-68-66A if below Highest Incore Computer Saturation 1700 psig) T/C Margin on Trend Time = 0

.~. .. . . _ _ _ _ , , - . - -

1787 008

1 SPECIAL No. 5 I Page 1 of 1 i

12/15/79 i

DATA SHEET 5.4 l

(To be plotted on graph paper and attached) l 1787 009

. _ _ , _ . . _ _ - . . _ _ . _.._._ a..-..-- -- - -- . - ---

SPECIAL No. 5 Page 1 of 1 12/15/79 APPENDIX A References

1. FSAR

^

2. Technical Specifications

3. Plant Operating Instructions E0I-5 SOI-68.2 i

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1787 010 og t

_ , _ .. . .. . . . ~ . - - -

- .g - ,, , ,,z, Appendix B 2/6/79 Page of Rev.

Page of Test Deficiencies #

Test Deficiency Recom. ended Resolution

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Final Resolution Originator /

Signature PORC Review of Final Resolution 1787 OHa e Date Approval of Final Resolution /

Plant Superintendent Date

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_14_ _

SPECIAL NO. 5

. 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

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1787 012

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SPECIAL NO. 5 Page 2 of 10 i 12/30/79 APP 3 DIX C (Continued)

Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)

1. Reference ( ^ 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 Conversian 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 Progran 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 i

rerun up to once every 2 minutes or as necessary to continuously monitor core power.

n . . _ . _ _ _ . _ - - . . - .

Y 1787 013

SPECIAL NO. 5 Page 3 of 10 12/30/79 APPENDIX C CORE POWER DETE1011 NATION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation)

C.1 Use two DVMs ani measure the voltage at the test points specified for each loop a.s rapid as possible.

C.2 Calculate the A T; multiply tha't 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.

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1787 014 9

- 8 e b

SPECIAL NO. 5 Page 4 cf 10 12/30/79 ,

APPENDIX C (Continued)

Core Power Determination PART B: M/D Power Monitor .*rogram

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.

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'al15-pat [5Hlector76 itches set to O ergency, run a

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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 100908 B KO?O9 C K0910 D K0911 E K0912 F K0913 1787 015 _

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m =m =

.m,

SPECIAL NO. 5 Page 5 of 10 12/30/79 APPENDIX (< _ i)

Core cswer I. .ation 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 ValIue Function K0901 1 Set the power normalize. tion factor Selects the modified K5525 1 " Flux Map Print" programs K0900 0 Initiated Pass Nu=ber Calibration Constant for M/D K0864 Variable (1) 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 (K0064) - Current (K0864) x (UO906)

4. For power determination, obtain a partial core flux cap as per TI-53.

The M/D's need not be withdrawn between passes, and passes may be repeated as of ten 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. -

u,,---

m 1787 016

SPECIAL NO. 5 Page 6 of 10 12/30/79 APPENDIX C (Continued)

TABLE C-1 Cp( m femp lbm/hr F BTU /lbm F 7

556 1.260 3.6448 x 10 554 1.255 3.6553 x 10 552 1.250 3.6659 x 10 7

550 1.245 3.6765 x 10 548 1.240 3.6862 x 10 546 1.236 3.6959 x 10 7

544 1.231 3.7057 x 10 7

542 1.226 3.7155 x 10 7

540 1.221 3.7254 x 10 538 1.217 3.7348 x 10 536 1.213 3.7443 x 10 534 1.209 3.7538 x 10 7

532 1.206 3.7633 x 10

- - .- 530.- - --1v201 -- - - 3.7729 r10 -

These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia.

1787 017 _

SPECIAL NO. 5

. Page 7 of 10 12/30/79 APPENDIX C (Continued)

Data Sheet C.1 Tavg F Unit Power Time Date l

Loop 3 Loop 4 Loop 1 Loop 2 Units Item # Calculation Procedure R2/TP-411J R6/TP-421J R10/RP-431J R13/RP-441J Loop 2L T - Inservice (at test point) Volts 1

Loop A T = (#1) x II} F' 2

3 Loop /L 11 = (#2) x Cp (from Table C.1) BTU /lba Loop RCS Flow (from Table C.1) 100 lbm/hr 4

6 Loop Reactor Power - (#3) x (# ) 10 BTU /hr 5

Total Reactor Power = (#5) { 6 10 BTU /hr 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 i

MWT 7 Reactor Power = (#6) x 0.29307' 8  % Reactor Power = (#7) x 0.02932 i.

Conversion factor for /1 T obtained from scaling document.

Remarks:

I sa Date By:

CO

%J Checked By:

CD -.

SPECIAL NO. 5 Page 8 of 10 12/30/79 APPENDIX C (Continued)

DATA SHEET C.2 E = F A

N

= B y

= C N

= D N

=

N N" i, = B,, = C s

=

D, = z, = F, =

N = 1.00 A ,

, N = ^N =  % =

B B N N i

? N = = BE =

C N b g=hD =

N CE D

=

N N N ~ " "

E N N N =h~ = "E E =

F F N N Definitions: _ _ -.-- ,-

A,B,C,D,E,FN = Normalized integral from sm:: mary map for each N N N N N detector in a normal path in the first pass A,B,C,D' = Normalized integral from swnmary map for each E g E E EFE detector in an emergency path in the :?aond pass N,N' ~ ** #" * ** " # # # ** * """ #

g B C' b' E' F Remarks:

Data By: Date 1787 019

SPECIAL NO. 5 Page 9 of 10 j 12/30/79 APPENDII 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

. (dour center line and four diagonal tilts) the following should be verified:

I .

j K0701-K0765 = 1, For the flow mixing factors I

j K5501 = 0, Indicates the measured core di T is unreliable K0791 = 0.075, Core bypass flow fraction K5010 = 8. Tells thermocouple program how many readings of thermocouples i are required for averaging before calculation is done. This in turn sets the running frequency of the Thermcouple Averaging Program at 1, 2, . . . . I 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 shifts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts:

l Quadrant Addressable Value 1 U1159 2 U1160 3 U1161 4 U1162 5

- .U1151 _ _ _ _ _

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.

1787 020_

] ~ s.~ - - - - - * - - . _ . _. . -. .. . .EC 3 IAL No. 5 ' t, h Page 10 of 10

,3;  ; y; 12/30

'S APPENDIX C E

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SPECIAL NO. 5 Page 1 of 4 12/15/79 APPENDIX D Procedure Por Use Of Computer System

! Por 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 10406A 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

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RCS Loop 4 Cold Leg Tempe'rature T0466A Steam Generator 1 Pressure PO400A Steam Generator 1 Narrow Range Level LO400A Steam Generator 2 Pressure PO420A

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Steam Generator 2 Narrow Range Level LO420A Steam Generator 3 Pressure PO440A 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) 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 1787 022 I

SPECIAL NO. 5 Page 2 of ~4

. 12/15/79 i

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 Cpolumn Point Column Point 1 P0480A 7 T0459A 13 PO420A 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 LO400A 18 LO460A BLOCK 2 ,

Colu=n Point Column Point 1 N0049A 7 T0017A 2 N0050A 3 T0043A 3 N0051A 9 T0059A 4 N0052A 10- L3 Hottest T/C from each core Quadrant 5 T0002A 14- 18 As Required 6 T0013A l

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 ~ ~

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6. Push STOP betton 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. P0480A) on the alphanumeric keyboard

3. Push ADDRESS button

4. Select block number (1 to 6) on keyboard.

5. Push VALUE 1 button

6. Select colu=n number (1 to 18) on keyboard

7. Push VALUE 2 button

8. Push START button 1787 023

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SPECIAL NO. 5 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.

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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.) 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 i following.

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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:

i 1. Push DICTTAL TREND button l 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 moni.tored_on analog trcnd 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 1787 024 e,

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SPECIAL NO. 5 Page 4 of 4 12/15/79 APPENDIX D (Conthued)

To start an analog trend perform the following steps.

1. Push ANALOG TREND function button

2. Select the computer point addre Q 3A) on the alphanu=aric 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 minira2m value of the parameter to be monitored

7. Select range on the keyboard

8. Push VALUE 3 button

9. Pash 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 i

3. Push VALUE 1 button

4. Select output device code number 20 for progra=mers console on keyboard.

5. Push VALUE 2 button

6. Select 1 on keybeard for a short-form map

7. Push VALUE 3 button R. Push START button 1787 025

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