ML19290C656

Natural Circulation W/Loss of Pressurizer Heaters, Special Test 3

ML19290C656
Person / Time
Site:	Sequoyah
Issue date:	12/14/1979
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19290C651	List: ML19290C650 ML19290C652 ML19290C653 ML19290C656 ML19290C658 ML19290C659 ML19290C660 ML19290C661 ML19290C662 ML19290C663 ML19290C664
References
PROC-791214-03, NUDOCS 8001220487
Download: ML19290C656 (31)

Text

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SPECIAL NO. 3 12/14/79 NATURAL CIRCULATION WITH LOSS OF PRESSURIZER HEATERS Table of Contents

.Page, 1.0 OBJECTIVES 2

2.0 PREREQUISITES 3

3.0 PRECAUTIONS 5

4.0 SPECIAL TEST EQUIPMENT 6

5.0 INSTRUCTIONS 7

6.0 ACCEPTANCE CRITERIA 9

DATA SHEETS 10 APPENDIX A - References 14 APPENDIX B - Deficiencies APPENDIX C - Power Measurement Technique APPENDIX D - Computer Points

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NATURAL CIRCULATION WITH LOSS OF PRESSURIZER HEATERS TEST DESCRIPTION The test will be initiated by tripping pressurizer heaters and reactor coolant pumps. Establish =ent of natural circulation will be verified and core exit thermocouples monitored to determine the core flow distribution.

System pressure will be monitored to determine the rate of depressurization and, prior to reaching saturation, control of the saturation margin will be verified through the use of primary system charging flow and secondary system steam flow.

1785 296.

SPECIAL NO. 3 Page 1 of 8 1.0 OBJECTIVES 1.1 Verify natural circulation conditions can be established in all loops once the RCP's are tripped.

1.2 Verify the ability to maintain natural circulation and saturation margin with the loss of the pressurizer heaters.

1.3 Determine RCS'depressurization rate after the RCP's and pressurizer heaters are tripped.

1.4 Verify saturation margin can be controlled through the use of primary charging flow and secondary steam flow.

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SPECIAL NO. 3 Page 2 of 8 12/15/79 2.0 PREREQUISITIES 2.1 The reactor is critical at ~ 3% power and under manual control with control bank D at-160 steps or as specified by test engineer.

(Power level determined as indicated in Appendix C.)

Date 2.2 All four reactor coolant pumps in operation.

Date 2.3 Steam generator level maintained at approximately 33% on the narrow range indicators by the main feedwater system (or auxiliary feedwater).

Date 2.4 Pressurizer pressure being maintained at approximately 2235 psig automatically by pressurizer heaters and spray and pressurizer level at approximately 26-28%.

Date 2.5 RCS temperature (Tavg) approximately 550 F.

_ _ nn.- -

Date - -

.n 2.6 Low Power Physics Test program has been completed to the extent 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.

(or power-operated relief valves).

Date 1785 298 E

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SPECIAL NO. 3 Page 3 of 8 12/15/79 2.0 PREREQUISITES (Continued) 2.8 Connect brush recorders to the following test points:

Brush Recorder 1 Connect To:

Monitoring:

Channel #1 1-R-1, FP414B RCS Flow-Loop 1 Channel #2 1-R-1, FP424B RCS Flow-Loop 2 Channel #3 1-R-1, FP434B RCS Flow-Loop 3 Channel #4 1-R-1, FP444B RCS Flow-Loop 4 Channel #5 1-R-1, PP455B Pressurizer Pressure Channel #6 1-R-1, LP459B Pressurizer Level Brush Recorder 2 Connect To:

Monitoring:

Channel #1 1-R-3, FP510B Main Feed Flow, SG#1 Channel #2 1-R-3, FP512B Steam Gen. #1, Steam Flow Channel #3 1-R-3, PP514B Steam Gen. Il Pressure Channel #4 1-R-3, FPS 20B Main Feed Flow, SG#2 Channel #5 1-R-3, FPS 22B Steam Gen. #2 Steam Flow Channel #6 1-R-3, PPS24B Steam Gen. #2 Pressure Brush Recorder 3 Connect To:

Monitoring:

Channel #1 1-R-4, FPS 30B Main Feed Flow SG#3 Channel #2 1-R-4, FPS 32B Steam Gen. #3 Steam Flow Channel #3 1-R-4, PP534B Steam Gen. #3 Pressure Channel #4 1-R-4, FP540B Main Feed Flow, SG#4 Channel #5 1-R-4, PP544B Steam Gen. #4 Pressure Channel #6 1-R-4, FP542B Steam Gen. #4 Steam Flow Brush Recorder 4 Connect To:

Monitoring:

'~ ChYnnel #1~ ~ ~

9 M ',7P121A RCS Charging Flow Channel #2 1-R-23, FP132 RCS Letdown Flow Channel #3 1-R-5, PP403A Wide range Press Press Channel #4 1-R-22, TP454 Press Steam Temp Channel #5 1-R-20, TP453 Press Liquid Temp 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 data recorder g) Recorder ID number 2.9 Set up the P-250 computer trend printer to monitor the parameters indicated in Appendix D.

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SPECIAL NO. 3 Page 4 of 8 12/15/79 3.0 PRECAUTIONS 3.1 Maintain reactor coolant pump seal and thermal barrier differential pressure requirements as given in SOI 68.2.

3.2 Do not exceed 5% nuclear power at any time while the test is in progress.

3.3 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 f65%.

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3.3.3 Tavg Temperature of 578 F.

3.4 When equilibrium has been established af ter the initial transient, avoid any sudden changes in feedwater flow or in steam generator water level.

3.5 After the reactor coolant pumps are tripped the normal Tavg and

d. T indications will be come unreliable.

A T and Tavg should be calculated by taking t'.ie difference and the average of the hot and cold leg temperature indications respectively.

3.6 Maintainsaturationmargingreaterthan10degreeshahrenheitatall

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times.

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

(Through the use of steam generator pressure control).

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SPECIAL TEST NO. 3 Page 5 of 8 12/15/79 14. 0 Special Test Ecuipment Identification Calibration Instrument Specification Number Verification Strip Chart Recorder Brush 260 or equivalert (4)

Reactivity Computer Westinghouse

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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. 1785 301 S

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SPECIAL NO. J Page 6 of 8 12/15/79 5.0 TEST INSTRUCTIONS 5.1 Ensure the pressurizer backup heaters LA, IB, and 1C will remain off by moving handsvitches 1-HS-68-341A and 341D to 'Stop' position and moving 1-HS-68-341H to 'Stop-Pull to Lock'.

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5.2 Record the data indicated on Data Sheet 5.1.

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5.3 Start the computer trend printer printing as faat as possible.

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5.4 Shut off the pressurizer control heater group by moving 1-HS-68-341F to 'Stop'.

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5.5 Record the time, on the data recorder charts in the auxiliary instrument room and then start them at 125 mm/ min.

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CAUTION: Continuously monitor main steamline pressure and carefully control feed-water addition during the transient to ensure the differential pressure between any two steam lines does not exceed 100 psid. This would ini-tiate a safety injection. Should this occur,: refer to AOI-19.

(Feed-water 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).

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NOTE: At the initiation of natural circulation the following temperature response is expected.

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a) Wide range T

- increase hat b) Wide range T

- slight decrease or constant c) CoreexittheEbNeouple increase d) T indication unreliable e) DelEa-T indication unreliable f) Pressurizar level increase 5.7 Verify natural circulation is established by following the operational guidelines given in E0I-5, Appendix A.

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NOTE: Natural circulation will be stable when:

1) J1 T between wide range T and T a constant hot eold

2) di T between wide range T and core exit thermocouple average eold temperature is constant

3) Wide range T 0: c re exit thermocouple average temperature hat 5.7.1 Assume manual control of charging flow and match charging to letdown to maintain a constant RCS water volume.

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SPECIAL NO. 3 Page 7 of 8 12/15/79 5.0 (Continued) 5.8 Once equilibrium has been established adjust trend printer intervals as specified by the test director.

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NOTE:

The following steps will allow the pressurizer to cool and slowly decrease system pressure.

The purpose is to determine the time that saturation margin can be maintained without the use of pressurizer heaters and then verify the margin can be reestablished through charging or secondary steam flow. Reactor power level will be reduced to simulate an actual shutdown situation with residual heat.

5.9 The primary system pressure will now be monitored to determine the rate of depressurization.

The saturation margin should be monitored closely on the trend recorder and steam dump or RCS charging flow increased in accordance with AOI-18 when the saturation margin appraches 10 F or as specified by test engineer.

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5.10 Approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> af ter RCP trips, reduce reactor power to approximately 1.5% and maintain this power level for the duration of the test.

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CAUTION:

If RCS pressure is dropped below 1500' psig, ' gag' UHI valves ~to prevent an inadvertent UHI actuation.

5.11 Once it is determined by the test director that sufficient data has been recorded to satisfy the requirements of this test or saturation margin approaches 10 F, increase saturation margin above 50 F through the use of charging flow and/or steam dump.

above 80%.

Do not allow pressurizer level to go

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NOTE:

Margin will increase by either increasing RCS pressure or reducing T ld' 5.12 Once saturation margin is above 50 F or pressurizer level reaches 80%,

reactivate the pressurizer backup heaters selectively to increase RCS pressure back to 2235 psig.

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5.13 Stop the brush recorders and trend printers and attach the printouts and charts to Data Sheet 5.2.

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5.14 Manually adjust PIC-68-340A to 40% output and energize the control heater group by moving 1-HS-68-341F to 'on'.

Return PIC-68-340A to ' Auto'.

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NOTE:

Maintain RCS pressure at approximately 2235 by using Auxiliary Spray in accordance with SOI 68.3C if necessary.

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SPECIAL No. 3 Page 8 of 8 12/15/79 5.0 (Continued) 5.15 Insert control bank D until the reactor is in the hot zero power test range.

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CAUTION:

Ensure pressurizer spray controller are at zero output prior to starting the first reactor coolant pumps.

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

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5.17 Return the pressurizer heater,s to automatic control by moving 1-HS-68-341A,

-341D, and -341H to the ' Auto' position.

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5.18 Return pressurizer level to approximately 26-28%.

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NOTE:

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

6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperatures did 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,y for any loop does not exceed 578 F.

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6.4 RCS saturation margin can be controlled through the use of charging and secondary steam flow.

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6.5 Natural circulation can be established and maintained without the use of the pressurizer heaters.

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Onit SPECIAL No. 3 Date Page 1 of 3 Time 12/15/79 DATA SHEET 5.1 Initial Conditions Pressurizer Pressure PR-68-340 psig Pressurizer Level LR-68-339 Red Pen I

1. 1 dot 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-68-43 F

1. 3 Cold leg temp o

TR-68-60 F

1. 4 Hot leg temp o

TR-68-43 F

1. 4 Cold leg temp o

TR-68-60 F

S.G. #1 Level (narrow range)

LI-3-42.,,_

S.G. #2 Level (narrow range)

LI-3-55 S.G. #3 7a,el (narrow range)

LI-3-E/

S.G. #4 Level (narrow range)

LI-3-110 S.C. #1 Level (wide range)

LR-3-43 Pen 1 S.G. #2 Level (wide range)

LR-3-43 Pen 2 S.G. #3 Level (wide range)

LR-3-98 Pen 1 S.G. #4 Level (wide range) j tn-LR-3-98 Pen 2 JV)

/ Data Recorded By

Unit SPECIAL NO. 3 Date Page 2 of 3 Time 12/15/79 DATA SHEET 5.1 (Continued)

S.G. #1 Pressure PI-1-2A psig S.G. #2 Pressure PI-1-9A psig S.G. #3 Pressure PI-1-20A psig S.G. #4 Pressure PI-1-27A psig S.G. #1 Feedwater flow FI-3-35A gpm S.G. #2 Feedwater flow FI-3-48A gpm S.G. #3 Feedwater flow FI-3-90A gpm S.G. #4 Feedwater flow FI-3-103A gpm S.G. #1 Steam flow FI-1-3A lbs/hr S.G. #2 Steam flow FI-1-10A lbs/hr S.G. #3 Steam flow

. FI-1 -21A.,_

lbs/hr S.G. #4 Steam flow FI-1 -28A lbs/hr Loop #1 T-average TI-68-2E F

Loop #2 T-average TI-68-25E F

Loop #3 T-average TI-68-44E F

Loop #4 T-average TI-68-67E

,F

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Data Recorded By 1785 306

. Unit SPECIAL NO. 3 Date Page 3 of 3 Time 12/15/79 DATA SHEET 5.1 (Continued)

Loop #1 T TI-68-2D F

Loop #2 T TI-68-25D F

Loop #3 T TI-68-44D F

Loop #4 T TI-68-67D F

(0-100% 55 F T)

NIS Channel N-41 i

NIS Channel N-42 NIS Channel N-43 NIS Channel N-44 NOTE: Attach Computer Printout of Incore Thermocouple Temperature Map.

Refer to Appendix D for the procedure fo'r printing out of this map.

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SPECIAL NO. 3 DATA SHEET 5.2 Page 1 of 1 12/15/79 DATA SHEET 5.2 Attach copies of the computer trend printout and the brush recorder charts to this page.

From the above data, starting after equilibrium has been reached, calculate the depressurization rate and the pressurizer cooldown rate (liquid temp) and record below.

Depressurization Race psig/hr.

Pressurizer Cooldown Rate F/hr.

Calculated by

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Reviewed by

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I NOTE: A plot of the RCS depressurization rate vs time can be made from the attached data if desired.

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SPECIAL NO. 3 Page 1 of 1 12/15/79 APPENDIX A References 1.

FSAR 2.

Technical Specifications 3.

Plant Operation Instructions: SOI 68.2, 68.3 E0I 5 AOI 18

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unic Yorm Date Appendix B 2/6/79 Page of Rev.

Page of Test Deficiencies #

Test Deficiency Recom. ended Resolution

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Finni Resolution Originator.

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Signature Date PORC Review of Final Resolution Date 1785 310 Approval of Final Resolution

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Plant Superintendent Date I L.

SPECIAL NO. 3 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 9hb.

SPECIAL NO. 3 Page 2 of 10 12/30/79 APPENDIX 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 1. 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 every 2 minutes or as necessary to continuously monitor core power. .-..n - n,., - - 785 312.

SPECIAL NO. 3 Page 3 of 10 12/30/79 APPENDIX C CORE POWER DETERMLNATION 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 6 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 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. 7 }fhh. ~ y..

SPECIAL NO. 3 Page 4 of 10 12/30/79 l APPENDIX 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 thi=bles as per the table below for the flux map. Drive 10-Path Petition Core Location A B C D E F These positions raty 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'a'115-path selector" switches set to Emergency c 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 }fhh F K0913 -

SPECIAL NO. 3 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 F-250 time and date are current. Update as required. Address Value Functie-K0901 1 Set the power normalization factor Selects the modified K5525 1 " Flux Map Print" programs K0900 0 Initiated Pass Number 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 (K0864) = Current (K0864) x (UO906) 4. Por 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 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. =., --~-- ~~ ~ 1785 315 _20_

SPECIAL NO. 3 Page 6 of 10 12/30/79 APPENDIX C (Continued) TABLE C-1 femp Cp( ) m F BTU /lbm F lbm/hr 7 556 1.260 3.6448 x 10 7 554 1.255 3.6553 x 10 7 552 1.250 3.6659 x 10 7 550 14245 3.6765 x 10 548 1.240 3.6862 x 10 7 546 1.236 3.6959 x 10 7 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 540 1.221 3.7254 x 10 7 538 ~ 1.217 ~ 3'.7348 x 10 ' 7 536 1.213 3.7443 x 10 534 1.209 3.7538 x 10 7 532 ,1.206 3.7633 x 10 ~ 530 --- -- -1720 ?" 3.7729 x 10 (1)These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia. 1785 516 _ m e

SPECIAL NO. 3 Page 7 of 10 12/30/79 . APPENDIX C (Continued) Data Sheet Col i o Date Time Unic Power Tavg F + l 1 Item # Calculation Procedure Units Loop 1 Loop 2 Loop 3 Loop 4 test point) Volts R2/TP-4113 R6/TP-421J R10/RP-431J R13/RP-441J 1 Loop A T - Inservice (at i 2 Loop ti T - (#1) x (1 F 3 Loop /1 H = (#2) x Cp (from Table C.1) BTU /lba 6 4 Loop RCS Flow (from Table C.1) 10 1bm/hr 6 5 Loop Reactor Power - (#3) x (#t) 10 BTU /hr 1+ Loop 2+ Loop 3+ Loop l4 Total Reactor Power = (#5) 0 10 BTU /hr 6 Loop 4 7 Reactor Power = (#6) x 0.29307 MWT 8 % Reactor Power = (#7) x 0.02932 ( } Conversion factor for /1 T obtained from scaling document. Remarks: v k N hhateBy: (,Ghecked By:

SPECIAL NO. 3 Page 8 of 10 12/30/79 APPENDIX C (Continued) DATA SHEET C.2 A B N N g= D = = ~ = F N N N" A B z s g= D, = E, = F, = = N = 1.00 A As N = = B B N y B "C BE = = = N s ^ NC N = _N CE = = n D N N N DE = = = E 5 s N =b NE gE = = F F N N Definitions:_ A,B,C,D' No m lized integral from su= mary map for each w 'y N N N N' N detector in a normal path in the first pass A,B' E. D ' E' E g E E Normalized integral from summary map for each = detector in an emergency path in the second pass N,N' ~ B C' D' E' F Remarks: Data By: Date 1785 318 _23 e

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SPECIAL NO. 3 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 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 46 T is unreliable K0791 = 0.075, Core bypass flow fraction K5010 - 8, Tells thermocoGple 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: Quadrant Addressable Value 1 U1159 2 U1160 3 U1161 4 U1162 5 U1151 ~~ ~ ~~ U W 2 6 - ' ' ' ~ ~- 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. _ 1785 319

SIECIAL NO. 3

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SPECIAL NO. 3 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 Pressure PO400A Steam Generator 1 Narrow Range Level LO400A Steam Genera 3or 2 Pressure _

PO420A - 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 1785 321 6

t SPECIAL NO. 3 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 Column Point Column Point Column Point 1 PO480A 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 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A 4 N0052A 10-13 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 to 6) on keyboard 3. Push VALUE 1 button 4. Select 0 onJyboard. 5. Push D E~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 colu=n number (1 to 18) on keyboard 7. Push VALUE 2 button 8. Push START button 1785 322.

SPECIAL NO. 3 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 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 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 button 6. Push STOP button In addition to the data recorded on th'e trend typewriter, the fo11 ewing points will be monicoredj n analog _ trend raqqrded, - ~.- - ~ 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 i785 323

SPECIAL NO. 3 Page 4 of 4 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 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 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 Select 25 on keyboard for short-fom current map 3. Push VALUE 1 button 4. Select output device code number 20 for programers console on keyboard. 5. Push VALUE 2 button 6. Select 1 on keyboard for a short-form map 7. Push VALUE 3 button 8. Push START button = - 1786 324 .}}