ML19323B927

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Special Test Number 9A, Forced Circulation Cooldown.
ML19323B927
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/06/1980
From: Ballentine J, Lagergran W, Maehr S
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19323B910 List:
References
PROC-800506-02, NUDOCS 8005140427
Download: ML19323B927 (50)


Text

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Sc.iuoyah ::uclear v tant DISTRInUTIO:j 8 005140 %

1C Plant Master File

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Superintendent jy_ Assist. ant Superintendent (Oper.)

9 Assistant Superintendent (Maint.)

Ad:ainistrative Supervisor Maintenance Supervisor (M)

_. _ As';istant Maintenance Supervisor (M)

!!aintenance Supervisor (E)

~ Assistant Maintenance Supervisor (E)

SPECIAL TEST NO. 9A 1U Maintenance Supervisor (I)

_j/g_ Results Supervisor FORCED CIRCULATION COOLDOUN __l_flc Operations Supervisor lu Quality Assurance Supervisor lleal th Phys i.cs Supervisor Public Safety Services Supv.

__ Chie f Storekeeper

_ _ Preop Test Program Coordinator

_ ___ Outage Director Chemical Engineer (Results)

Radiochem Laboratory

__ Instrument Shop

_./ C React.or Engineer (Resuits)

Instrinaent Engineer (Maint. I)

Mechanical Engineer (Results)

Sta ff ]ndustrial Engineer (Plt Sys)

Training Center Coordinator

~~- PSO - Chickamauga Engrg Unit - SNP Prepared Hy: U. R. Larvergran Public Safety Services - SNP

/ (.' Shi f t. Engineer's Of fice Revised Dy: S. R. Machr

_ & Unit Control Room QA&A Rep. - SNP Submitted By: j y ,+0 _

Health Physics Laboratary y Su p e rv'i s o r lu Nuclr Document Control Unit, 606 EB-C 1U S upe rin t en dent. , WUNP PORC Review: J - k$p Superintendent, EFNP

\ \ Date Superintendent, BENP h ~ 1U NCB, W9C174C-K A

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Supv., NPHPS ROB, MS Approved By: ,_fhy,te_ g [b RQ NRC-IE:II Super nCendent Power Security ifficer, 620 CST 2-C g Nuclr Materials Coord. - 1410 CUBB-C L.i Manager, OP-QA&A Staff Date Approved:

O_ f (a_h  ! 1 ac Resident NRC Inspector - SNP 1c_ NSRS, 249A HUB-K Technical Support. Center t l S h s i -f Te cd.n ic!*/ PAvec' Rev. No. Date Pevised Pa;1eg Rev No. Date Revised Pages 0 ./ M1

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SPECIAL TEST 9A Page 1 of 1 Rev. 0 FORCED CIRCULATION C00LDOWN Table of Contents Page Special Operator Instruction 1 Test Description 2 1.0 OBJECTIVES 3 2.0 PREREQUISITES 3 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPMENT 9 5.0 INSTRUCTIONS 9 DATA SIIEETS 15 CALCULATION SHEET 17 APPENDIX B - Deficiencies 18 APPENDIX C - Power Measurement Technique 19 l APPENDIX D - AT Correction Determination 30 APPENDIX E - SafeEuard Blocking _ Procedure 33

, APPENDIX F - Technical Specifications Exceptions 46 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 47 l

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SQNP SPECIAL TEST 9A 5

Page 1 of 1 Rev. O SPECIAL OPERATOR INSTRUCTION

  • An o'pei tor initiated safety injection should be performed only for one or more of the following conditions:

Reactor Coolant System Subcooling 5 10 Sudden Unexplained Decrease in Pressurizer Level of 10%

or to an Indicated Level of 5 10%

Sudden Unexplained Decrease in Any S/G Level to 6 76% Wide Range 5 0% Narrow Range Unexplained Pressurizer Pressure Drop 2 200 PSI Containment Pressure Hi - (1.54 psig) Annunciator XA-55-6B Window 6 initiates An operator initiated reactor trip should be performed for any of the following conditions:

Reactor Coolant System Subcooling 5 15 Sudden Unexplained Decrease in Pressurizer Level of 5%

or to an Indicated Level of 5 17%

1/3 Excores 2 10%

Any Loop A T > 65 F Tavn > 578 F Core Fxit Temperature (Highest) > 610 F Any Uncontrolled Rod Movement

  • SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.

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SQNP o

S SPECIAL TEST 9A Page 1 of 1 4

Rev. 0 -

I FORCED CIRCULATION C00LDOWN Test Description This test will generate a correction factor which will be applied to the excore detector outputs in order to compensate for PV downcomer

, shadowing during a cooldown from ~ 550 F to ~ 450 F.

The RCS will initially be ~ 3% power, in forced circulation. p cooldown via steam dumps will be initiated and continue until avg is approximately 450 F.

During the cooldown primary side ca'arimetrics will be performed, movabic detector integral power calculations performed, and excore detector data obtained simultaneously.

4 Power should be maintained as. constant as possible using the results of the primary side calorimetric and integral power calculations.

Data reduction will be on a continuous basis.

Af ter reaching ~ 450 F the plant will be allowet' to heat up and additional data will be obtained.

i Data reduction will average the cooldown and heatup data and generate an excore detector indicated power correction factor as a function of the average cold leg temperature.

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SQNP SPECIAL TEST 9A Page 1 of 12 Rev. 0 1.0 OBJECTIVES Determine an excore detector indicated power correction factor as a function of the average cold leg temperature.

2.0 PREREQUISITES 2.1 The following initial conditions exist:

2.1.1 Reactor power is at approximately 3% RTP.

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2.1.2 Forced circulation on all four loops is established.

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2.1.3 Steam generators are being fed by the auxiliary feed water system. Level is being maintained at approximately 33%.

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2.1.4 Steam gene rators are steaming via the condenser or atmos-pheric steam dumps. (Preferred is to condenser for SG pressure equilization).

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2.1.5 Pressurizer pressure control in automatic and maintaining normal operating pressures.

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2.1.6 RCS temperature is approximately 550 F.

/ _ _ _ _

2.1.7 Shutdown banks are fully withdrawn and control banks are above their insertion limit. Rod control system is in manual.

Control bank D is at ~ 160 steps or as determined by the test director.

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SQNP SPECIAL TEST 9A Page 2 of 12 Rev. 0 2.0 PREREQUISITES (Continued) 2.1.8 Pressurizer level control in manua. maintaining approxi-mately 55% level.

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2.2 The RCS and pressurizer boron concentrations are within 20 ppm.

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2.3 Sufficient water is available to provide makeup for the expected cooldown to 450 F.

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2.4 Set up the following test signals on brush recorders.

NOTE: Exact recorder / channel / parameter matching is not necessary.

2.4.1 Recorder No. 1 Channel Parameter Test Point Rack 1 Przr Pressure PP/455B R1

? Przr Level LP/459B R1 3 Lp 1 HL Temp TP/413E R2 4 Lp 2 HL Temp TP/423E R2 5 Lp 3 HL Temp TP/433E R2 6 Lp 4 HL Temp TP/443E R2

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2.4.2 Recorder No. 2 Channel Pa ramete r Test Point Rack 1 LP 1 CL Temp TP/413F R6 2 LP 2 CL Temp TP/423F R6 3 LP 3 CL Temp TP/433F R6 4 LP 4 CL Temp TP/443F R6 5 LP 1 Flow FP/414B R1 6 LP 2 Flow FP/424B R1

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SQNP SPECIAL TEST 9A Page 3 of 12 Rev. 0 2.0 PHEREQUISITES (Continued) 2.4.3 Recorder No. 3 Channel Pa rame te r Test Point Rack 1 LP 3 Flow FP/434B R1 5

2 LP 4 Flow FP/444B R1 3 LP 1 SG Level LP/519B R5 4 LP 2 SG Level LP/529B R1 5 LP 3 SG Level LP/539B R1 6 LP 4 SG Level LP/549B R5

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2.4.4 Recorder No. 4 Channel Pa ramete r Test Point Rack 1 LP 1 SG Press PP/516B R12 2 LP 2 SG Press PP/526B Rll 3 LP 3 SG P) PP/536B Rll 4 LP 4 SG Preos PP/546B R12

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2.4.5 Recorder No. 5 Channel Parameter Test Point Rack 1 Aux Fd Flow to SG #1 TP-13 1-L-11B 2 Aux Fd Flow to SG #2 TP-13 1-L-11A 3 Aux Fd Flow to SG #3 TP-12 1-L-11B 4 Au-e Fd Flow to SG #4 TP-12 1-L-11A 2.4.6 Record the following parameters on the reactivity computer recorders.

(a) Flux (b) Average wide rangeTTcold (c) Average wide range hot (d) Average steam generator pressure (c) Reactivity 5

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

SQNP SPECIAL TEST 9A I

Page 4 of 12  ;

Rev. 0 ,

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l 2.0 PREREQUISITES (Continued) i 2.5 Trend the following parameters on the process computer at ~ 5-minute 2

intervals.

Wide range cold legs T0406A T0426A T0446A

T0466A l Wide range hot legs T0419A -

T0439A

!l T0459A l T0479A

, Steam generator levels LO403A 1

LO423A

} LO443A i LO463A l Loop Flow F0400A

F0420A 4 F0440A F0460A 1

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j 2.6 Obtain the wide' range AT correction factors using Appendix D.

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!1 j 2.7 Perform the reference (REF) portion of the primary calorimetric

Appendix C and a M/D trace simultaneously, Appendix C, Part B.

j Use the output of the primary calorimetric to set the M/D Power j- Monitor Program.

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2.8 Verify the automatic actuation of safety injection has been blocked

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in accordance.with Appendix E.

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i 2.9 Verify the input logic of' safety injection on high steam line AP i has been blocked in accordance with Appendix E.

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SQNP SPECIAL TEST 9A Page 5 of 12 Rev. 0 2.0 PREREQUISITES (Continued)

2.10 Verify tge high steam flow coincident with low S/G pressure or low-low avg input to safety injection has been medified in accordance with Appendix E.

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2.11 Verify the following U.11.I. isolation valves are gagged.

l FCV-87-21 /

FCV-87-22 /

FCV-87-23 /

i FCV-87-24 /

i 2.12 Recalibrate the bistables supplying the low pressure signal to the high steam flow S.I. logic in accordance with Appendix E.

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l 2.13 Intermediate and power range high level reactor trip setpoints have been set to 7% in accordance with Appendix C and D of SU-8.5.2.

Power Raage /

Intermediate Range /

4 2.14 CVCS is aligned to supply auto makeup.

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SQNP SPECIAL TEST 9A Page 6 of 12 Rev. 0 3.0 PRECAUTIONS, LIMITATIONS, AND ACTIONS 3.1 Do not exceed 5% RTP. Caution should be used in maintaining the desired power level because of flux shadowing of the excore detec-tors. Don't depend on the excore detectors. Use as many methods as possible to determine actual core power.

3.2 During the cooldown the isothermal temperature coefficient.will be small but may be of either polarity. Care should be taken when changing reactivity using control rods or boron concentration because at some point the temperature cofficient polarity could change.

4 3.3 Maintain control bank D at ~ 160 steps if possible. This same suggested minimum limit will be used during the natural circula-tion test. This height will minimize the effect of rod shadewing of the excore detectors and insure uniformity between forced and natural circulation test.

3.4 When operating below 525 F, ensure control bank D position remains at 2 100 steps. Should this limit be reached during the cooldown boron concentration will have to be increased.

3.5 When testing with the reactor coolant in the low temperature range of 450 F to 500 F, maintain the lithic concentration at 2.0 to 2.2 ppm, the upper part or the specified lithic range.

i This is especially necessary if high boric acid concentrations

(~ 1000 ppm) are also being used.

3.6 Ensure the differential pressure across the steam generators remains below 1600 psig.

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SQNP S

SPECIAL TEST 9A Page 7 of 12 Rev. 0 4.0 SPECIAL TEST EQUIPMENT IDENTIFICATION CALIBRATION INSTRUMENT SPECIFICATION IM!BER VERIFICATION Reactivity Computer Westinghouse and Associated Equipment (4) 6-channel recorders Brush 260 or Equivalent (2) DVM's Fluke (1) Recorder HP 71008 or Equivalent If test instruments are changed during this test, the instrument infor-mation must be recorded here and an' entry made in the chronological log book explaining this change.

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J SQNP SPECIAL TEST 9A Page 8 of 12 Rev. O i

5.0 INSTRUCTIONS
NOTE: Perform SI-38, SI-48, and SI-127 periodically during the cooldown, i

i 5.1 Cooldown

NOTE
Depending on rod position and the magnitude and polarity of the isothermal temperature coefficient dilution and/or boration may be required.

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l 5.1.1 Verify that the system is in equilibrium with respect to power, RCS temperature, pressure and boron concentration.

Pressurizer pressure ~ 2235 + 50 psig i S/G pressure ~ 1005 psig

, RCS-PRZR boron concentration within 20 ppm j Successive boron sample concentration within 10 ppm J

Reactivity is approximately zero and constant i

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d 5.1.2 Start the test recorders on slow speed (5mm/ min). Record

on the charts, the date, time, recorder ID, parameters 2

measured, measurement range, test being performed and name

of person recording data.
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5.1.3 Start process computer trend block.

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l 5.1.4 Obtain a thermocouple map and repeat every 10 F during 4

cooldown.

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i 5.1.5 Record excore detector data on Data Sheet 1 and repeat every 10"F. One of the P.R. channels is connected to e

the reactivity computer so, record the Keithley amplifier

output for that particular channel on Data Sheet 1.

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NOTE: Mark out "N- " and write in "KA."

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SQNP SPECIAL TEST 9A Page 9 of 12 Rev. 0 ~~-

5.0 INSTRUCTIONS (Continued) 5.1.6 Initiate the program for obtaining M/D trace data and re-cord on Data Sheet 2. Repeat every 10 F during cooldown.

Use applicable portions of Appendix C.

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5.1.7 _ Initiate the primary side calorimetric and repeat every 10 F.

Use applicable portions of Appendix C.

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5.1.S Initiate a cooldown by slowly increasing the rate of steam dump and proceed to approximately 450 F core inlet tempera-ture. The rate should be approximately 30 F per hour with stabilized plateaus approximately every 10 F during cooldown.

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l NOTE: Reduce RCS pressure during the cooldown to maintain steam generator AP below 1600 psig.

5.1.9 Use the control rods and soluable boron as necessary to maintain core power approximately constant. Core power

, is determined by-the primary side calorimetric and the M/D trace data. Refer to Appendix C, Parts A and B.

NOTE: Control bank D should be maintained at approximately 160

, steps if possib'e.

5.1.10 Upon reaching approximately 450 F terminate the cooldown and allow the RCS to come to an equilibrium condition.

Continue to obtain data.

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5.2 Heatup 5.2.1 Allow the RCS to heatup at the same rate indicated above. '

Obtain the same data at the same temperature plateaus.

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-5.2.2 Upon reaching approximately 550 F terminate the heatup and

. allow the.RCS to come to:an' equilibrium c'ondition.. Aft <r

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i one set of data has been obtained at ~ 550 F the test is over. Attach ALL data to this test.

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SQNP SPECIAL TEST 9A Page 10 of 12 Rev. 0 --

5.0 INSTRUCTIONS (Continued)

.5.2.3 Return the bistables supplying the low pressure signal to the high steam flow S.I. logic to their original setpoints in accordance with Appendix E unless the next test to be performed requires this modification to be made. If this is the case, disregard this step, place N/A in the signa-ture line, and initial.

5.2.4 Restore the high ste9m flow coincident with low S/G pressure or low-low avg input to safety injection in accordance with Appendix E unless the next test to be performed requires this modification to be made. If-this is the case, disregard this step, place N/A in the signature line and initial.

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5.2.5 Remove the block of the input logic of safety injection on high steam line AP in accordance with Appendix E unless the next test to be performed requires the block to be installed. If this is the case, disregard .nis step, place N/A in the signature line, and initial.

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5.2.6 Remove the block of automatic actuation of safety injec-tion in accordance with Appendix E unless the next test to be performed requires the block to be installed. If this is the case, disregard this step, place N/A in the signature line, and initial.

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5.2.7 Remove the gags from the following U.H.I. isolation valves unless the valves are_ required to be' gagged for the next test. If this is the case, disregard this step, place N/A in the signature line, and initial.

FCV-87-21 /

FCV-87-22 /

FCV-87-23 /'

FCV-87-24 /

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SQNP SPECIAL TEST 9A Page 11 of 12 Rev. 0 -

5.0 INSTRUCTIONS (Continued) 5.2.8 Reset the intermediate and power range high level reactor trip setpoints as indicated by the test engineer in accord-ance with Appendix C and D of SU-8.5.2 unless the next test to be performed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial.

Power Rapre /

Intermediate Range /

5.3 Data Reduction NOTE: This reduction must be performed and an excore detector indi-cated power correction factor as a function of temperature determined before proceeding to the NC ccoldown portion of this test.

5.3.1 Use both the cooldown and heatup data. If for some reason the data was not obtained at exactly the required tempera-ture plateaus mark through that temperature and record the actual measurement temperature.

Excore Data: Sum the top and bottom currents for the 3 (Data Sheet 1) channels in service and enter under sum.

The Keithley amp output should be in sum column. Transfer the data to the Calcula-tion Sheet.

M/D Data: Transfer the calculated power level to the (Data Sheet 2) Calculation Sheet.

Primary Calor. : Transfer the power level obtained from the (Appendix C) primary calorimetric to the Calculation Sheet.

Average Power: Using the incore data and primary calori-(Calculation metric data determine the actual core power l Sheet) at each emperature plateau. A straight average should be used unless one method or the other proves unreliable. ,

l Power Normalization: Divide the average power obtained at to REF Average Power each temperature plateau by the aver-(Calculation Sheet) age power obtained at the reference (REF) condition, 550 F. This. factor will in turn be used to correct the i excore outputs. )

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SQNP SPECIAL TEST 9A Page 12 of 12 Rev. O ~

5.0 INSTRUCTIONS (Continued)

Power Corrected: Divide the measured excore detector cur-Excore Currents & rents by the power normalization factor.

& Keithley Amp This in effect corrects all data for Output fluctuations on core power. The resulting currents then will only be a function of the cold leg temperature.

Excore Current: Divide the power corrected excore cur-

?!ultiplier as a rents obtained at each temperature Function of Cold plateau into the excore current ob-Leg Temperature: tained at the REF condition. NOTE: the

, factors should increase as Tcdecreases.

Plot the correction factors as a function of T for each detector. The plots will be uEed in the natural circulation cool-down phase of this test.

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SQNP ,

SPECIAL TEST 9A Page 1 of 1 Rev. 0 .

DATA SHEET 1 EXCORE DATA SHEET Map No. Shutdown Bank Position: A B C D E Date Control Bank Position: A B C D E Power _

RCCA Position N-41 N-42 N-43 N-44 Time / Temp Top _ Bottom Sum Top Bottom Sum Top Bottom Sum Top Bottom Sum

/550

/540

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" /530

/520

/510

/500

/490

/480

/470

/460

/450 Cocunent:

Data Taken By: / Reviewed by: /

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SQNP .

, SPECIAL TEST 9A Page 1 of 1 DATA SIEET 2 Rev. 0 -

LOW POWER MOVABLE DETECTOR FLUX HAP DATA Initial Final RCC Bank /RCCA Positions (steps) il3P No.: RCS T ( F): SDA SDB SDC SDD Date: IR-35 (amps): _

CA CB CC CD Unit: IR-36 (amps): RCCA ( )

Controlling RCCA/RCC Bank:

Calculated Control RCCA

. Time Power P-250 RCC Bank of Detector - Core Location Detector - Range Level UO906 Posi. tion RECORD A B C D E F A B C D E F 550 540 3, 530 520 510 500

.490 480

470 460 450 Detector A B C D E F Remarks:

Detector Voltage Recorder Pot.

-Data Taken By: Data Checked By:

  • SQNP SPECIAL TEST 9A Page 1 of 1 Rev. O CALCULATION SHEET APPR0XIMATE AVERAGE COLD LEG TEMPERATURES ( F)

REF.

Item # Parameters 550 540 530 520 510 500 490 480 470 460 450 Movable Detector 1 (% RTP)

Primary Calorimetric 2 (% RTP)

Average Power 3 (% RTP)

Power Normalization 4 to REF condition 1.00 Excore Currents N-5 and N-Keithley Amp N-Output KA Power Corrected N-3 Excore Currents N-6 Keithly Amp N-Output KA N- 1.00 Corrections

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7 N- 1.00 Factors N- 1.00 KA 1.00 Remarks:

Calculated by:

Reviewed by:

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  • SQNP

, SPECIAL TEST 9A Page 1 of 1 Rev. O APPENDIX B Test Deficiencies #

Test Deficiency j

Recommended Resolution 1

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1 Final Resolution Originator /

Signature Date PORC Review of Final Resolution Date Approval of Final Resolution /

Plant Superintendent Date 18

SQNP SPECIAL TEST 9A Page 1 of 11 Rev. 0 -

APPENDIX C Outline I. Core Power Determination l

A. Primary Side Calorimetric (Forced Circulation Only)

, 1. Reference (~ 550 F) Calorimetric (Defore NC test) i ~

a) Output used to adjust M/D Power Monitor Program's power conversion constant.

2. Non-reference Temperature Calorimetric (Cooldown) a) Output used at every temperature plateau as a continuous core power monitoring scheme.

b) Output is used in conjunction with the ouput of the M/D Power Monitor Program to assign a best estimate core power at each temperature plateau. The powers are used to nor-malize the excore detector outputs which in turn are plotted as a function of che core inlet temperature.

B. M/D Power Monitor Program

1. Power Conversion Constant Adjustment.

a) The output of the REF primary calorimetric will give a percent power output; this output must be input to the M/D Power-Monitor Program so tnat 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.

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SQNP o-SPECIAL TEST 9A-Page 2 of 11

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Rev. 0 APPENDIX C i

l 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 AT; multiply that AT by the specific heat and i

the Westinghouse best estimate flow rate of the core average

  • i temperature (Table C-1). (Special Test No. 9 uses wide range AT 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 and on the Calculation Sheet.

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SQNP

, SPECIAL TEST 9A Page 3 of 11 Rev. O APPENDIX C 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 10 L-5 B 10 L-11 C 10 E-5 D 10 E-11 E 6 J-8 F 8 P-9 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 i in the table below. j 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 nonnalization constants into the P-250 as shown in the table below. l 21

SQNP SPECIAL TEST 9A Page 4 of 11 Rev. O APPENDIX'C Core Power Determination PART B: (Continued)

Drive P-250 Address A KO908 B K0909 C K0910 __

D K0911 E K0912 .

F K0913

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 Set the power normalization K0901 1 factor Selects the modified " Flux K5525 1 Map Print" program K0900 0 Initiated Pass Number Calibration Constant for K0864 Variable (1) for M/D Power Monitor (1) Variable: The value entered is a ratio of the Primary Calorimetric Indicated Power (Item 8 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 f/8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906)

4. For power determination, obtain a partia] 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 po'wer determination is required.

N9TE: The calculated power (UO906) is printed after each pass and may be trended by the P-250 if desired. The individual detec-tor normalized integrals are also printed.

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  • SQNP SPECIAL TEST 9A Page 5 of 11 Rev. O APPENDIX C 3 PRIMARY SIDE CALORIMETRIC l

DATA SifEET C.1 Loop 1

  1. 1 #2 #3 #4 #5 #6 #7 #8 Approx. IIL CL AT L P L PFlow LoopRxPwr RCS Temp #2-#3 #4+c.f.(2) #5xCp(3) #gx#7 F R2/TP-41(()

Volts F R6/TP-41((

Volts F f4) a F F Btu /lb 10 lb/hr 10 Btu /hr 550(REF) 540 530 520 5_10 500_

'. 490 3

480 470 460 450 460 i

470 480 490 500 I 510 520 530 ,

540 l

550 l j

., i From appropriate scaling document.

(3)From Appendix D.

Remarks:

g)mCgfrom fromTable TableC-1 C-1 1

Data by: /

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SQNP SPECIAL TEST 9A Page 6 of 11 Rev. O APPENDIX C PRIMARY SIDE CALORIMETRIC DATA SHEET C.1 Loop 2

  1. 9 #10 #11 #12 #13 //14 #15 #16 Approx. HL CL AT LoopFlow LoopRxPwr LoopAJ)

RCS Temp R2/TP-42{r) R6/TP-42]'}

  1. 10-#11 #12+c.f.(2) #13xCp f4) #g4x#15 E Volts F Volts F F F Btu /lb 10 lb/hr 10 Btu /hr 550(REF) 540 530 520 510 l 500 490 480 4_7_0 460 '

450 460 470 480 490 500 510 520 530 540 550 Remarks.

Data by: /

C;iccked by: /

24

  • SQNP SPECIAL TEST 9A Page 7 of 11 Rev. O APPENDIX C.

PRIMARY SIDE CALORIMETRIC DATA SIIEET C.1 Loop 3

  1. 17 #18 #19 #20 #21 #22 #23 #24 A Pprox. IIL CL AT L pO LoopFlow LoopRxPwr RCS Temp #18-#19 #20+c.f.(2) #21xCp(g) #g3x#24 R2/TP-43(() R6/TP-43(() f4)

F Volts F Volts F F F Btu /lb 10 lb/hr 10 Btu /hr 550(REF) 540 530 520 510 500 490 480 470 460 450 460 470 480

/

_90 E 'o 5io 520 530 540 550 Remarks:

Data by: /

Checked by: /

25

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SQNP.

  • SPECIAL TEST 9A Page 8 of 11 Rev. 0 --

APPENDIX C PRIMARY SIDE CALORIMETRIC t

DATA SIEET C.1 Loop 4

  1. 25 #26 #27 #28 #29 #30 #31 #32 Approx. liL CL AT LPO L PFlow LoopRxPwr RCS Temp #26-#27 #28+c.f.(2) #29xCp(lh #g0x#31

, F R2/TP-44((}

Volts F R6/TP-44((

Volts F F f4)

F Btu /lb 10 lb/hr 10 Btu /hr 550(REF) 540 530 520 510 500 490

$_80 470 460 450 460 l

470 480 490 500 i

510 ~

520 5~30 540 j 550 1

Remarks:

Data by: /

Checked by: /

'26 f -

,-~--,,- , , - __, - , - ., -.e. e

  • SQNP SPECIAL TEST 9A Page 9 of 11 Rev. O APPENDIX C PRIMARY SIDE SLORIMETRIC DATA SIIEET C.1 Total
  1. 33 #34 #35 #36 Approx. Total Reactor Power Reactor Power  % Reactor Power RCS Temp. #8+g16+#24+#32 #34 x 0.29307 #35 x 0.02932 F 10 Bru/hr MWt  %

550(REF) 540 530

520 5_1_0 500 490 480 470 460 450 460 470 480 490 500 510 520 530 540 550 Remarks:

Data by: /

Checked by: /

i s

27

+

  • SQNP SPECIAL TEST 9A Page 10 of- 11 Rev. O APPENDIX C PRIMARY SIDE CALORIMETRIC Table C-1 Temp. Cp(1) S F Btu /lb. F #m/hr 560 1.270 3.6239 x 10 7 550(REF) 1.246 3.6765 x 10 7 540 1.221 3.7254 v.10 7 530 1.202 3.7729 x 10 520 1.183 3.8179 x 10 7 510 1.168 3.8621 x 10 7 3.9044 x 10 7 1

500 1,152 490 1.140 3.9436 x 10 7 480 1.127 3.9837.x 10 7 470 1.117 4.0215 x 10 7 460 1.107 4.0589 x 10 7 450 1.098 4.0949 x 10 7 440 1.089 4.1294 x 10 7

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

28

SQNP

  • SPECIAL TEST 9A Page 11 of 11 Rev. 0 APPENDIX C A B C E * =

N= N= N N= N N A E

  • E E E E E E N3 = 1.00 N

B

  • ^
  • D
  • N N N B C= C N N A N N N = CE =

D=DN D N

E N N A

Ng = = *EE =

N N Definitions:

A,B,C,D' 'y

= Normalized integral from summary map Z,r each N N N N' N detector in a normal path in the first 1 ass A'N' E E E' E,E' E E

= Normalized integral from summary map for each detector in an emergency path 2.n the second pass tiA' "B' 'C' D' E' F

= Detector normalization factor for each detector Remarks:

Data By: Date 29

SQNP

  • SPECIAL TEST 9A Page 1 of 3 Rev. 0 -

APPENDIX D WIDE RANGE AT CORRECTION D.1 Use two DVM's and measure the voltage at the test points specified for each loop as rapidly as possible.

D.2 Use the appropriate scaling to convert the DV voltages to F.

D.3 The correction factor (c.f.) determined in item 5 is used on Data Sheet C.1 to correct the calculated wide range AT for the AT across the core gener-I ated by the Reactor Coolant Pumps.

J 1

1 i

i l

1 1

30

SQNP

  • SPECIAL TEST 9A Page 2 of 3 Rev. O APPENDIX D WIDE RANGE AT CORRECTION LOOP 1 Item Pa rameter Location Reading Parameter

_ _No . Rack / Test Point Volts F Loop 1 1 Ilot '.c,g R2/TP-413E (b Loop 1 2 Cold Leg R6/TP-413F (1)

Loop 1 3 W.R. AT Item 1-Item 2 Loop 1 4 N.R. AT R2/TP-411G (

W.R. AT 5 CorrectionFactor Item 4-Item 3 c.f.=

LOOP 2 Loop 2 1 llot Leg R2/TP-423E (I Loop 2 2 Cold Leg R6/TP-423F (1)

Loop 2 3 W.R. AT Item 1-Item 2 Loop 2 4 N.R. AT R6/TP-421G (1)

W.R. AT 5 CorrectionFactor Item 4-Item 3 c.f.=

( ) Scaling Document.

l 31

SQNP SPECIAL TEST 9A Page 3 of 3 Rev. O APPENDIX D WIDE RANGE AT CORRECTION

  • LOOP 3 Item Parameter Location Reading Parameter i No. Rack / Test Point Volts F Loop 3 1 Hot Leg (y)

R2/TP-433E Loop 3 2 Cold Leg R6/TP-433F (1)

Loop 3 3 W.R. AT Item 1-Item 2 Loop 3 4 N.R. AT (y)

R10/TP-431G W.R. AT 5 CorrectionFactor Item 4-Item 3 c.f.=

LOOP 4 Loop 4 1 Hot Leg R2/TP-443E (}

Loop 4 2 Cold Leg R6/TP-443F (1)

Loop 4 3 W.R. AT Item 1-Item 2 Loop 4 4 N.R. AT R13/TP-441G (1)

W.R. AT 5 CorrectionFactor Item 4-Item 3 c.f.=

( } Scaling Document.

l

, I 32 w w --*9

SQNP

' SPECIAL TEST 9A Page 1 of 13 Rev. 0 APPENDIX E Safeguard Blocking Procedure The 'first step blocks automatic initiation of a safety injection. The safety injection alarm, manual S.I handswitch, and the reactor trip portion of the protection logic will remain in operation. If conditions exist that would normally initiate a safety injection; (1) the safety injection alarm will initiate telling the operator that the condition exists and what the problem is. (2) a reactor trip will take place automatically. (3) a safety injection can be initiated manually from the switch in the control room if conditions warrant.

1. Install temporary jumpers and temporary alteration control tags to logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.

NOTE: These jumpers will be specially made for this purpose and installed by an instrument mechanic.

R-47 Panel Performed by: /

Verified by: /

R-50 Panel Performed by: /

Verified by: /

Procedure for blocking automatic actuation of a safecy injection on high steamline Delta-P. This block will prevent a reactor trip from occuring during the natural circulation tests from high AP caused by degraded test conditions. (This block will also defeat all AP S.I. alarms.)

2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, 73, 76 are all clear prior to starting blocking procedure.
3. Move test trip switch PS-515A in 1-R-7 to the trip position and verify the amber light above the switch comes on.

Performed by: /

~

Verified by: /

CAUTION: In the next step, and all following steps in which a voltage is being applied to the indicated terminals, ensure the applied voltage is of the same polarity as the terminals. This check should be.done for every step that a voltage' source is applied.

Failure to apply the correct polarity will ground the rack power supply. (This problem can be avoided if only the hot wire from the voltage source in the rack is applied to the first terminal indicated in each step [the lower numbered terminal]. The 33

SQNP

. SPECIAL TEST 9A Page 2 of 13 Rev. 0 -

APPENDIX E ground will already be made up through the trip switch). The wire on the rack side of the terminal block must be lifted and taped for the terminal point where the jumper wire is connected.

The TACF tag will be attached to the bistable switch and the TACF must note the jumper and the lifted wire.

NOTE: Orange "out of service" stickers should be placed on all status /

alarm windows as the 120V source is connected.

4. Lift and tape the wire on the rack side of terminal L-9 in the rear of
  • 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 and verify 1-XX-55-6B/25 is clear.

Performed by: /

Verified by: /

5. Move test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

6. Lift and tape the wir on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/27 is clear.

Performed by: /

Verified by: /

i

7. Move test trip switch PS-516C in 1-R-12 to the trip position and verify j the amber light above the switch comes on. '

l Performed by: /

Verified by: /

8. Lift and tape the wire'on the rack side of terminal L-5 in the rear of 1-R-12. Apply 120-VAC cource to terminals L-5 and L-6 and verify 1-XX-55-6B/73 is clear. .

Performed by: /

Verified by: / .

34 -

L

SQNP

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SPECIAL TEST 9A Page 3 of 13 Rev. 0 -

APPENDIX E

9. Move test trip switch PS-516D in 1-R-12 to the trip position and verify

~the amber light above the switch comes on.

Performed by: /

Verified by: /

10. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-12. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/76.

Performed by: /

Verified by: /

11. Move test trip switch PS-525B in 1-R-8 to trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

12. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-8. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/28 is clear.

Performed by: /

Verified by: /

13. Move test trip switch PS-525A in 1-R-8 to the trip position and verify the amber light above the switch comes-on.

Performed by: /

Verified by: /

14. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-8 and verify that XX-55-6B/26 is clear.

Performed by: /

Verified by: -

/

l t .

35

- =

g ,

SQNP SPECIAL TEST 9A Page 4 of 13 Itev. O APPENDIX E

15. Move test trip switch PS-526D in 1-R-11 to the' trip position and verify

-the amber light above the switch comes on.

Performed by: /

Verified by: /

16. Lift and tape the wire on .the rack side of terminal L-7 in the rear of 1-R-11. Apply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-11 and verify that XX-55-6B/51 is clear.

Performed by: /

Verified by: /

17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

18. ' Lift and tape the wire on the rack side of terminal L-5 in the rear of 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is clear.

Performed by: /

Verified by: /

Temporary Mgdificat. ion to High Steam Flow Coincident with Low S.G. Pressure or Low-Low avg Safety Injection

19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be cleared.

Performed by: /

~

Verified by: /

NOTE: If the alarms will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected.

36

,7 4.-

SQNP

, SPECIAL TEST 9A Page 5 of 13 Rev. O APPENDIX E

20. Move test trip switch TS412D in R-2 to the trip position and verify

'the amber light above the switch comes on.

Performed by: /

Verified by: /

21. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.

Performed by: /

Verified by: /

22. Move test trip switch TS-422D in R-6 to the trip position and verify the amber light above the switch comes on.

Performed by: / _

Verified by: /

23. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.

Performed by: /

Verified by: /

24. Move test trip switch TS432D in R-10 to the trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

25. Lift and tape the wire on the rack side of terminal M-3 in.the rear of 1-R-10. Apply a 120-VAC source to terminals M-3 and M-4 in R-10 and verify XA-55-6A/30 will clear.

Performed by: /

Verified by: /

L i

e 37

SQNP

, SPECIAL TEST 9A Page 6 of 13 Rev. O APPENDIX E

26. Move test trip switch TS-442D in R-13 to th,e trip position and verify "the amber light above the switch comes on.

Performed by: /

Verified by: /

27. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 in R-13 and verify XA-55-6A/30 will clear.

Performed by: /

Verified by: /

NOTE: The avg inputs to the high steam flow S.I and steam dump interlock are now blocked, '..e next steps will trip the steam flow inputs to the high steam flow Safety Injection signal so that an S.I. signal will be initiated on low steam generator pressure alone (600 psig). (This would result in a reactor trip, an S.I. alarm, but no S.I.

initiation).

28. Move test trip switch FS512B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/2 come on.

Performed by: /

Verified by: /

29. Move test trip switch FS522B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/9 come on.

Performed by: /

Verified by: /

NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal.

l l

l l

l 38 ,

\

._j

(_ -

SQNP SPECIAL TEST 9A Page 7 of 13 Rev. 0 -

APPENDIX E

30. Apply Temporary Alteration Control Tags forms to all the above test trip switches to ensure that they remain in the trip position.

Damage to the bistable could occur if the switch is moved back to the normal position. Record the temporary alteration numbers below:

RACK TEST SWITtil TEMP ALT. NO.

R-7 PSS15F /

R-7 PS515B /

R-12 PS516C /

R-12 PS516D /

R-8 PS525B /

R-8 PS525A /

R-11 PS526D /  !

R-11 RS526C /

P-2 TS412D /

R-6 TS422D /

R-10 TS432D /

R-13 TS442D /

R-3 FS512B /

R-3 FS522B /

The following step reduces thy setpoint of the S/G pressure input to S.I.

to trip at 350 psig allowing avg to be reduced to 450 F.

31. Recalibrate the following bistables to the indicated setpoints and attach Temporary Alteration Control Tags.

Panel Bistable Setpoint R-12 PS-1-5A (PB516A) 350 psig Decreasing (21.66 MA Loop Current)

Performed by: /

Verified by: /

R-11 PS-1-12A (PB526A) 350 psig Decreasing (21.66 MA Loop Current) j Performed by: / i Verified by: /

i

-l i

t

-39 L_ _

SQNP

. SPECIAL TEST 9A Page 8 of 13 Rev. O ~~

APPENDIX E R-11 PS-1-23A (PB536A) 350 psig Decreasing (21.66 MA Loop Current)

Performed by: /

Verified by: , /

R-12 PS-1-3GA (PB546A) 350 psig Decreasing (21.66 IM Loop Current)

Performed by
/

Verified by: /

NOTE: When calibrating bistables, approach the setpoint very slowly to reduce the effect of the lead / lag module in the loop.

j Calibrate one loop at a time and have all loop bistables tripped while calibrating. The same individuals may only calibrate 2 of these instruments. The remaining 2 instru-ments must be calibrated by 2 other individuals.

To return the steamline Delta-P S.I. to normal condition, the following steps should be followed, t

NOTE: The orange "out of service" stickers should be removed from the alarm / status window as each bistable is put back in service.

32. Remove the 120-VAC source from L-5 and L-6 in 1-R-11. Reterminate wire on L-5.

?

Performed by: /

Verified by: /

33. Move test trip switch PS-526C in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/50 are clear.

Performed by: /~

Verified by: /

34. Remove the:120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire on L-7. .

Performed by: /

Verified by: /

t 40'

,m v T'"

SQNP SPECIAL TEST 9A Page 9 of 13 Rev. O APPENDIX E

35. Move test trip switch PS-526D in 1-R-11 to the normal position and

' verify the amber light above the switch and 1-XX-55-6B/51 are clear.

Performed by: /

Verified by: /

36. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.

l Performed by: /

l Verified by: /

i

37. Move test trip switch PS-525A in 1-R-8 to the normal position and verify the amber light and 1-XX-55-6B/26 are clear.

Performed by: /

1 Verified by: /

38. Remove the 120-VAC source from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.

i Performed by: /

Verified by: /

39. Move test trip switch PS-525B in 1-R-8 to the normal position and verify the amber light above the switch and 1-XX-5-6B/28 are clear. I i

Performed by: /

Verified by: /

I i

40. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. -Retermi-nate wire on L-7.

Performed by: /

Verified by: / l l

41. Move test trip switch PS-516D in 1-R-12 to the normal position and verify the amber light. above the switch and 1-XX-55-6B/76 are cicar.

Performed by: /

Verified.by: '/

41 . l L -.

SQNP

. SPECIAL TEST 9A Page 10 of 13 Rev. 0 -

APPENDIX E

42. Remove the 120-VAC source from terminals L-5 and L-6 in 1-R-12. Retermi-

'nate wire on L-5.

Performed by: /

Verified by: /

43. Move test trip switch PS-516C in 1-R-12 to the normal position and verify the amber light above the switch and 1-XX-55-6B/73 are clear.

Performed by: /

Verified by: /

44. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi-nate wire on L-7.

Performed by: /

Verified by: /

45. Move test trip switch PS-515B in 1-R-7 to the normal position and verify the amber light and 1-XX-55-6B/27 are clear.

Performed by: /

Verified by: /

46. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.

Performed by: /

Verified by: /

47.  !!ove test trip switch PS-515A to the normal position and verify the -

amber light above the switch and 1-XX-55-6B/25 are clear.

Performed by: /

Verified by: /

NOTE: At this point the steamline Delta-P safety i,njection is in a normal operating mode.

To retur9 the high steain flow coincident .eith low steam generator pressure or low-low avg to normal, perform the following steps.

42

SQNP SPECIAL TEST 9A Page 11 of 13 Rev. 0 -

APPENDIX E

48.  ?!ove test trip switch FS522B in R-3 to the normal position and verify

'the amber light goes out and XA-55-6B/9 will clear.

Performed by: _ _ _ /

Verified by: /

1

49. Move test trip switch FSS12B in R-3 to the normal position and verify the amber light goes out and XA-55-6B/2 will clear.

Performed by: /

Verified by: /

50. Remove the 120-VAC source from terminals M-3 and 11-4 in R-13. Retermi-nate wire on M-3.

Performed by: /

Verified by: /

51. Move test trip switch TS442D in R-13 to the normal position and verify the amber light goes out and XA-55-6A/30 will clear.

Performed by: /

Verified by: /

52. Remove the 120-VAC source from terminals M-3 and M-4 in R-10. Retermi-nate wire on M-3.

Performed by: /

Verified by: /

53. Hove test trip switch TS432D in R-10 to the normal position and verify the amber light goes out and XA-55-6A/30 will clear.

Performed by: / _

Verified by: /

54. Remove the 120-VAC source from terminals M-3 and M-4 in R-6. Retarmi-nate wire on M .3.

Performed by: , /

Verified by: /

43 i

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  • SQNP

" . SPECIAL TEST 9A Page 12 of 13 Rev. 0 -

APPENDIX E

55. Move test trip switch TS442D in R-6 to the normal position and verify

'the amber light goes out and XA-55-6A/30 will clear.

Performed by: /

Verified by: _ /

56. Remove the 120-VAC source from terminals M-3 and M-4 in R-2. Retermi-nate wire on M-3.

Performed by: /

Verified by: /

57. Move test trip switch TS412D ia R-2 to the trip position and verify the amber light comes on and XA-55-6A/30 will clear.

Performed by: /

Verified by: /

58. Remove the Temporary Alteration Tage on the following test trip switches:

RACK TEST SWITC11 TEMP ALT. NO.

R-7 PS515A /

R-7 PS515B /

R-12 PSS16C /

R-12 PSS16D /

R-8 PS525B /

R-8 PS525A /

i R-11 PSS26D /

R-11 RSS26C /

R-2 TS412D /

R-6 TS422D /

R-10 TS432D /

R-13 TS442D .

/

R-3 'S512B F /

R-3 FSS22B /

44 L

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, ,, SPECIAL TEST 9A Page 13 of 13 Rev. 0 -

APPENDIX E

59. Remove the jumpers and the Temporary Alteration Tags from logic cards

'A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.

! R-47 Panel Performed by: /

Verified by: /

] R-50 Panel Performed by: /

Verified by: /

The following step should be carried out to return the calibration of the S/G low pressure S.I. bistables to normal.

60. The following bistables should be returned to their normal setpoints indicated on the calibration card for the particular bistable. (30.0 + .2MA)

Remove the temporary alteration control tags after the recalibration.

NOTE: These calibrations require 2 IM's per calibration. The same individuals may only calibrate 2 of the instruments. The other instruments must be calibrated by other individuals.

Panel Bistable Performed By/ Verified By R-12 PS-1-5A (PB516A) /

/

R-11 PS-1-12A (PB526A) / l

/

R-11 PS-1-23A (PB536A) /

/

~

R-12 PS-1-30A (PB546A) /

/

NOTE: All reactor safeguard systems modified for the special startup tests are back in a normal configuration at jthis time.

45

SQNP

, o SPECIAL TEST 9A l Page 1 of 1 Rev. O APPENDIX F Technical Specifications Exceptions The t'able below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests.

o a .ae Mew E%*

u e bnB a 9 88*$8!

"4at:

8e ss 33*""5 o 8e B%aaae n*w .5 a Ot: a3aS e B mo o $ .d*

YYYYYMo E e n UUNW%% y8

$E$$$$M$

m a a m m o m w o o N m TECIINICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment III Pressure SI (3.3.2.1) X X X X X X X X X X Safety Limits (2.1.1) X X X X X X X X X Ol%T (3.3.1) Inoperable because of low flow X X X X X X X X X OTAT (3.3.1) Inoperable because of low flow X X X X X X X X X Minimum temperature (3.1.1.4) X X X X Moderator temperature coefficient (3.1.1.3) X X X X Steamline AP SI (3.3.2.1) bypassed X X X X X X X X X X liigh Steamflow coincident 91 w/ low steamline pressure or low-low avg SI Reset flow to 07,and ' avg blocked X X X X X X X X X X Reset low steamline pressure X X X Low pressurizer pressure SI (3.3.2.1) X X X X X X X X X X SG level low AFW start reset.(3.3.2.1) X X Pressurizer (3.4.4) X X X UlII (3.5.1.2) X X X X X X X X X X AFW (3.7.1.2) X X Diesel Gens. (3.8.1.1) X X A.C. Electrical Boards (3.8.2.1) X X

Batteries (3.8.2.3) X X RCS Flowrate (3.2.3) X X X X X X X X i Control Rod Insertion Limits (3.1.3.6) X X X X X X X Reactor Coolant Loops Normal Operation (3.4.1.2) X X X X X X X X 46 I L___________________-__ _ _ -

SQNP

, . . SPECIAL TEST 9A Page 1 of 1 Rev. O TABLE 1 Loop Flow and Core AT for Various Power Levels and Isolation Configurations (Computer Estimates)

No. of Loops Operating (Nat. Circ.)

Power Level 4 3 2 1

.5% L= 3.7 L= 3.6 L= 4.1 L= 5.2 AT = 10.3 AT = 12.5 AT = 16.4 AT = 26

.75% L= 3.7 L= 4.1 "L = 4.7 L= 5.9 AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 1% L= 4.1 L= 4.5 L= 5.2 L= 6.5 AT = 16.3 AT = 19.8 AT = 26 AT = 41 1.5% L= 4.7 L= 5.2 L= 5.9 L= 7.5 AT = 21.4 AT = 26 AT = 34 AT = 54 2% L= 5.2 L= 5.7 L= 6.5 L= 8.2 AT = 26 AT = 31.4 AT = 41 AT = 65.4 2.5% L= 5.6 L= 6.2 L= 7.1 L= 8.9 AT = 30.1 AT = 36.5 AT = 47.1 AT = 75.9 3% L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE: L is % of 97,000 gpm flow through operable loop.

AT = Loop AT in F.

47