ML19323B919

From kanterella
Jump to navigation Jump to search
Special Test Number 7, Simulated Loss of All Onsite & Offsite AC Power.
ML19323B919
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/06/1980
From: Maehr S
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19323B910 List:
References
PROC-800506-01, NUDOCS 8005140421
Download: ML19323B919 (63)


Text

.

e pequoyah Nuclear Plant DISTRIBUTION B 005140i 3

_I L Plant. Master File

_ Superintendent

_jgf_ An4istant Superintendent (Oper.)

Assi ; tant Superintendent (t!a i nt . )

Adriinis t ra ti ve Supervisor llaint enance Supervi sor (!!)

Assistant flaintenance Supervisor (M) liaintenance Supervisor (E)

Assintant Maintenance Super'.anor (E)

SPECIAL TEST NO. 7 30 Maintenance Supervisor (I)

_/y_ Results Supervisor SIMULATED LOSS OF ALL ONSITE _ Lg Operationn Supervisor AND OFFSITE AC POWER IU Quality Annurance Supervisor Health Physics Supervisor Public Safety Services Supv.

Chief Storcheeper Preop Test Program Coordinator

_ Outage Director Chemical Engineer (Resulta)

Radiochem Laboratory

__ In:;trument Shop

_ /C_ Hea ctor Engi neer (Resulta)

_ _ Instrument Engineer (?!a i n t. . I)

Mechanical Engineer (Henultn)

__ S ta f f Indus tri al Engineer (Plt Sys)

Training Center Coordinator

_ _,PSD - Chickamauga Ennrg Unit - SNP repared ny: S. R. Macht Public Safety Services - SNP

/ C Shift Engineer's Of fice 1;ev i ned By: S. R. Macht _ / (., Unit Control Room

. .4, QANA Rep. - SNP Submitted By / , _ _ lh ua+vu _ _ Heaith Phynics Laboratory

_"f Supedisor _1U Nuc1r Document Control Unit, 606 EH-C IU Superintendent, WB.NP PORC 1:evi ew ( _ _X- (c - SQ __

Superintendent, RFNP Daty N S u p e r i n t.e n d e n t. , BESP

\ i

g d,' O ldbi T-- Supv., NPHPS ROB, MS Approved Hy:

j

\[11.)n Supdrintendent

~ NRC-IE:II Power Security Of ficer, 620 CST 2-C

\ Nucir !!aterials Coord. - 1410 CUDB-C i

( m f I g,

~

lla n a ge r , OP-QAEA Staff Da t.c Approved: Q_ _L 7

2D IC Resident NHC Inspector - SNP i IC NSRS, 24"A HUH-K Technical Support Center

._[C d)3MJ TccA n , c A l Ad v $i t' <~

Uev. No. Date Revised Pagen Rev. No. Date Revised Pagen 1

0

[.f ch M1 -_-

-4 m.

+

w.- w-,e-,. ---.-~~wwy v w --

---% .w wwg--., ,,.w. -----ww-------w- e+pyr -.-e -wy-g.r- *=m-

f 6

t 4

4 i

1 l

P 1

i i

i i

SPECIAL TEST NO. 7 I

SIMULATED LOSS OF ALL ONSITE AND OFFSITE AC P0hTR i

h i

I e

i I

4 4

3

)

4 5

i i

4 i

?

4 1

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

' SQNP s-SPECIAL TEST 7 Page 1 of 1 Rev. O SIMULATED LOSS OF ALL ONSITE AND OFFSITE AC P0hT.R Table of Contents Page Test Descrption 1 Special Operator Instruction 2 1.0 OBJECTIVES 3 2.0 1REREQUISITES 4 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPflENT 10 5.0 TEST INSTRUCTIONS 11

~

6.0 ACCEPTANCE CRITERIA 23 DATA SilEETS 24 APPENDIX A - References 32 APPENDIX B - Deficiencies 33 APPENDIX C - Power ricasurement Technique 34 APPENDIX D - Computer Point 44 APPENDIX E - Safeguard Blocking Procedure 48 APPENDlX F - Technical Specifications Exceptions 59 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 60

' SQNP

  • ~

SPECIAL TEST 7 Page 1 of 1 Rev. O SIMULATED LOSS OF ALL ONSITE AND OFFSITE AC P0h'ER Test Description This test is intended to provide a significant demonstration of reactor operation in the natural circulation mode under the degraded condition of loss of all onsite and offsite AC power. For the purpose of plant and equipment safety, this total blackout condition will be simulated by the selective deenergizing of components and equipment.

1

SQNP SPECIAL TEST 7 Page 1 of 1 Rev. O SPECIAL OPERATOR INSTRUCTION

  • An operator initiated safety injection should be performed only for one or more of the following conditions:

l Reactor Coolant System Subcooling 5 10

{ Sudden Unexplained Decrease in Pressurizer Level of 10%

or to an Indicated Level of 6 10%

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

Heactor Coolant System Subcooling $ 15 Sudden Unexplained Decrease in Pressurizer Level of 5% ,

! or to an Indicated Level of. $ 17%

1/3 Excores 2 10%

Any Loop A T > 65 F i

Tavg > 578 F Core Exit Temperature (Highest) > 610 F

Any Uncontrolled Rod Movement hSI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.

T 2

. _ . . j

SQNP SPECIAL TEST 7 Page 1 of 21 Rev. 0 1.0 OBJECTIVES The objectives of this test are:

1.1 To demonstrate that following a loss of all onsite and offsite power, including the emergency diesel generators, the decay heat can be removed by natural circulation using the auxiliary feed-water system in the manual mode.

l 1.2 It will be verified that hot standby conditions can be maintained by manual control of the auxiliary feedwater system.

1.3 It will also be verified that. critical plant operations can be per-

) formed using emergency lighting, that the 125-volt vital battery

has the ability to supply the 125-volt vital AC and that certain equipment areas do not exceed maximum design temperature.

1.4 To provide operator training, all operating shifts will perform this test.

)

NOTE: Data acquisition does not need to be repeated for multiple test perfornances.

4 1

i

)

l 3

v e w -,ws ,y ,-w p---r- g, y --y-g ,

SQNP 3 -

SPECIAL TEST 7 Page 2 of 21 Rev. 0 2.0 PREREQUISITES 2.1 Reactor is critical and manually controll-d at approximately 1%

power with control bank D at 160 steps or as specified by test engineer. (Power level determined as indicated in Appendix C).

/

2.2 All four Reactor Coolant Pumps in operation.

i t /

2.3 RCS pressure at approximately 2235 psig and temperature at approxi-mately 548 F, and pressurizer level at approximately 26-28%.

/

2.4 Steam pressure approximately 1005 psig and being maintained by steam dump to the condenser.

l

/ I 2.5 Steam generator level being maintained et approximately 33% on the narrow range indicators.

l

/  !

2.6 One main feedwater pump in service and the other tripped.

l

/ .l l

2.7 Auxiliary feedwater system lined up in standby in accordance with SOI 3.2

/ l 2.8 Steam generator chemistry in a condition that the absolute minimum l steam generator blowdown can be maintained during the duration of this test. (Zero blowdown is possible).

/

2.9 Excess letdown is available for service if required during the test.

/

4

.s- -- .-

SQNP

.. SPECIAL TEST 7 Page 3 of 21 Rev. 0 2.0 PREREQUISITES (Continued) 2.10 125-V Vital Battery Board I energized from 125-V Vital Battery I (DKR 107 closed).

/

2.11 125-V Vita! Battery Board II energized from 125-V Vital Battery II (UKR 107 closed).

/

2.12 125-V Vital Battery Board III energized from 125-V Vital Battery III (BKR 107 closed).

/

2.13 125-V Vital Battery Board IV energized from 125-V Vital

  • Battery IV (BKR 107 closed).

/

2.14 Verify that battery powered lights are located in areas where operation of equipment is required after normal lighting is de-energized. (Operations to supply lights and position them where desired).

/

NOTE: These temporary lights should only be located in areas ,

where operation of equipment would not normally take place in a blackout. Areas which must be operated during a blackout should be supplied with permanent battery powered lights.

2.15 Charging is being maintained with a centrifugal pump and in auto-matic control.

/

l 5

SQNP

,- SPECIAL TEST 7 8

Page 4 of 21 Rev. 0 2.0 PREREQUISITES (Continued) 2.16 Connect Recorders to the following test points:

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 Recorder #2 Connect to: Monitoring 1

( Channel #1 1-R-23, LP501 Steam Gen #1 Level Cha'mel #2 1-R-3, FP512B Steam Gen #1 Steam Flow Ch nel #3 1-R-3, PP514B Steam Gen #1 Pressure Channel #4 1-R-23, LP502 Steam Gen #2 Level Channel #5 1-R-3, FPS 22B Stear Gen #2 Steam Flow Channel #6 1-R-3, PP524B Stes a Gen #2 Pressure Recorder #3 Connect to: Monitoring 1 Channel #1 1-R-23, LP503 Steam Gen #3 Level Channel #2 1-R-4, FP532B Steam Gen #3 Steam Flow Channel #3 1-R-4, PP534B Steam Gen #3 Pressure Channel #4 1-R-23, LP504 Steam Gen #4 Level Channel #5 1-R-4, FP542B Steam Gen #4 Steam Flow Channel #6 1-R-4, PP544B Steam Gen #4 Pressure Recorder #4 Connect to: Monitoring:

1 Channel #1 F-3-163, TP 13, 1-L-11B Aux Feed flow to S.G. #1 Channel #2 F-3-155, TP 13, 1-L-11A Aux Feed flow to S.G. #2 Channel #3 F-3-147, TP 12, 1-L-11B Aux Feed flow to S.G. #3 Channel #4 F-3-170, TP 12, 1-L-11A Aux Feed flow to S.G. #4 2.17 Set the trend recorders and computer trend printer in the Main Control Room to monitor the parameters indicated in Appendix D.

/

2.18 Install p-computer recorder to monitor the following:

a. Flux
b. Average wide-range cold-
c. Average wide-range hot
d. Average steam generator pressure
e. Reactivity

/

6

g. y i.- .%-,. -

4.- .- ,

_9 .

, y m,.-, y --..m,y- 9y +m-

SQNP

. SPECIAL TEST 7 Page 5 of 21 Rev. 0 2.0 PREREQUISITES (Continued) 2.19 Evacuate ccustruction personnel from all unit 1 and unit 2 work areas in the auxiliary and containment buildings.

/

NOTE: This is a safety measure since these work areas will be without lighting for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2.20 Record on the recorder charts the following information:

a. Unit number
b. Date
c. Procedure number
c. Chart speed
f. Time marker interval
g. Recorder ID number
h. Name of individual recording data

/

2.21 Verify the input logic of safety injection on lli Steam Line AP has been blocked in accordance with Appendix E.

/

2.22 Verify the lli s' aam flow coincident with Lo S/G pressure or to Tav input to safety injection has been modified in accordance with Appendix E.

/

2.23 Verify the automatic actuation of safety injection has been blocked in accordance with Appe, dix E.

/

2.24 Verify the following UllI isolation valves are gagged.

FCV 21 /

FCV 22 /

FCV 23 /

FCV 24 /

2.25 Verify the auxiliary boiler is supplying steam seals to the turbine.

/ ___

7

l

  • SQNP SPECIAL TEST 7 Page 6 of 21 Rev. 0 2.0 PREREQUISITES (Continued) 2.26 Intermediate and power range (low setpoint) high 1cvel reactor trip setpoints have been set to 7% in accordance with Appendix C and D of SU-8.5.2.

Power Range /

Intermediate Range /

3.0 PRECAUTIONS 3.1 Maintain reactor coolant pump seal and thermal barrier different-ial 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 Abort the test if any of the following temperature limits are exceeded:

3.3.1 Core exit temperature of 610 F 3.3.2 AT as indicated by h- c of 65 F 3.3.3 avg temperature of 578 F 3.4 When equilibrium is established after the initial transient, avoid any sudden changes in Auxiliary Feedwater flow or in the Steam Generator water level.

3.5 Ensure seal flow to each' Reactor Coolant pump is maintained at or slightly above 6 gpm during the test.

3.6 AftertheReactorCoolantpumpsaretripped,tgenormalT and AT indication will become unreliable. AT and avg should E0 calcu-I lated by taking the difference and the average of the hot and cold Icg temperature indications respectively.

3.7 If the primary system pressure drops to a point where it is obvious that saturation pressure for the existing wide range hot leg or incore T/C temperatures will soon be reached, the pressurizer heaters will have to be energized or charging flow reestablished to increase system pressure.

3.8 NIS channels can be used to determine changes in core power level providing the RCS cold leg temperatures are maintained at approxi-mately the same value that existed before tripping the reactor coolant pumps.

8

SQNP e

SPECIAL TEST 7 Page 7 of 21 Rev. 0 3.0 PRECAUTIONS (Continued) 3.9 The turbine auxiliary feedwater pump room has four temperature i

detectors designed to isolate the steam supply to the turbine if t,he temperature reaches 125 F. If ambient temperature reaches 115 F, start the AC powered exhaust fan to help maintain tempera-ture.

3.10 Should a reactor trip occur during the conduct of this test, at least one reactor coolant pump (#2) should be started prior to closing the reactor trip breaker.

3.11 Maintain D bank at 2 100 steps during the conduct of this test.

! Should this limit be reached, boron concentration will have to be increased.

1 I

l 2

)

i I

i 9

i p --.

y e y , ,- , . , -- ,-r., , - , . - - -

SQNP a

SPECIAL TEST 7 Page 8 of 21 Rev. 0 4.0 Special Test Equipment Identification Calibration Instrument Specification Number Verification Digital Voltmeters Fluke Model I (DVM) (3) 3120A or equivalent Strip Chart Recorder, Brush 260 or equivalent (6-channel) (2)

Room Thermometers (7)

Reactivity Computer Westinghouse Explosimeter Mine Safety Model 1/3 442760 0-100% explosive Recorder (1) IIP 7100B or equivalent If test instruments are changed during this test, the instrument information must be recorded here and an entry made in the chronological log book ex-plaining this change.

10

SQNP SPECIAL TEST 7 Page 9 of 21 Rev. O i

5.0 TEST INSTRUCTIONS NOTE: For the purpose of operator training, the test instruction steps in Section 5.0 may be repeated. The steps should be performed sequentially an3 those steps indicated by a double asterisk (**) should not be repeated.

    • 5.1 Close the following dampers on El 669 in the Auxiliary Building.

1-31C-1105 /

1-31C-1109 /

1-31C-1150 /

1-31C-1148 /

NOTE: These dampers and the following coolers will be shutdown to allow monitoring the air temperatures in the area of the turbine driven auxiliary feedwater pump room under blackout

conditions.
    • 5.2 Adjust the thermostats on the General Vent Coolers LC and 2C on El 669 to their highest settings. (Note their present setpoint).

0-TIC-313-610 As Found Dial Setting 2-TIC-313-611 As Found Dial Setting id5.2.1 Shutdown the main control room air conditioning and place a <

room thermometer on the operators' desk to monitor control room air temperature.

/

5.3 Position AUO's in the following positions in the plant to be avail-able to operate vital equipment.

a) Auxiliary Feedwater Level Control Valves LCV-3-172, 173, 174, q and 175.

b) Turbine driven Auxiliary Feedwater pump.

c) Power relief control valves PCV-1-5, 1-23, 1-12,-and 1-30.

/

5.4 Clear the control and auxiliary building of all non-essential personnel and announce over the Public Address System that a blackout test will be beginning shortly.

/

11

SQNP SPECIAL TEST 7 Page 10 of 21 Rev. 0 5.0 TEST INSTRUCTIONS (Continued) 5.5 Manually adjust PIC-68-340B and PIC-68-340D to zero % output (closes pressurizer spray valves) and leave the controllers in manual control.

/

5.6 Ensure the pressurizer backup heaters lA,1B, and IC will remain off by moving handswitches 1-ilS-68-341A and 341D to the "stop" position and moving 1-HS-68-341H to "stop pull to lock".

/

5.7 Ensure Auxiliary Feedwater motor driven pumps 1A-A and IB-B will not start on the simulated blackout by moving switches 1-HS-3-118A and 1-HS-3-128A on 1-M-4 to the "stop" position

/

5.8 Move switch 1-HS-30-217 to "stop" to shut off the AC auxiliary feedwater turbine pump room exhaust fan. Verify switch 1-HS-30-214 4

in in " Auto". (Both located in Turbine driven Aux. Feed pump room).

/

5.9 Just prior to initiating RCP trips, reduce charging flow to the minimum required to maintain seal injection flow. (FCV-62-89 should be fully closed).

/

5.10 Isolate RCS letdown by closing the following valves from their respective handswitches on 1-M-6.

1-FCV-62-69 /

q 1-FCV-62-70 /

1-FCV-62-72 /

1-FCV-62-73 /

1-FCV-62-74 / ,

    • 5.11 Record the data indicated on Data Sheet 5.1.

l

/ l

~12

SQNP SPECIAL TEST 7 Page 11 of 21 Rev. 0 4

5.0 TEST INSTRUCTIONS (Continued)

    • 5.11.1 Start the Computer Trend printer printing at 1-minute inter-vals.

/

    • 5.12 Record the time, date and initial the charts on the data recorders in the Auxiliary Instrument Room.

/

    • 5.13 open 6.9KV ACB located on 6.9KV Common Board A that feeds the Auxiliary Building Lighting Bus A.

I

/

k*5.14 Open 6.9KV ACB located on 6.9 K Common Board B that feeds the Auxiliary Building Lighting Bus B.

/

5.15 Start all four reactor coolant pump oil lift pumps from 1-HS-68-84A, 85A, 86A, and 87A on 1-M-5.

/

NOTE: The following step should be conducted immediately before initi-4 ating the trips.

1 5.16 Isolate the contro) air supply to the air accumulator for the ,

i

, following turbine drive.n Auxiliary Feedwater pump level control valves.

i 1-LCV-3-172 /

1 i 1-LCV-3-173 /

1-LCV-3-174 /

1-LCV-3-175 /

i 5.17 As quickly as possible shutdown the following equipment. As many people as possible should be utilized to complete this step so that a close approximation to a blackout can be simu-lated.

NOTE: Zero Time =

Check ua) Trip pressurizer heater group 1D from 1-llS-68-341F on 1-M-4 13 k,

y. ..m. _ - . .

7 __7 , ._ g

SQNP SPECIAL TEST 7 Page 12 of 21 Rev. 0 5.0 TEST INSTRUCTIONS (Continued) b) Trip all four reactor coolant pumps from 1-HS-68-8A, 31A, 50A, 73A c) Close main steam isolation valves from 1-HS-1-4, 11, 22, 29 on 1-H-4 d) Trip the main feed pump presently in operation from either 1-HS-46-9A (Pump A) or 1-!!S-46-36A (Pump B)

NOTE: The next steps will remove the 125V Vital Battery chargers from service which places the entire 125VDC Vital load on the 125V Vital batteries.

    • e) Open the breaker on 125V Vital Battery Board I from ine No. I 125V Vital Battery charg er. (BKR 225)
    • f) Open the brea :er on 125V Vital Battery Board Il frou the No. II 125V Vital Battery charger. (BKR 225)
    • g) Open the breaker on 125V Vital Battery Board III from the No. III 125V Vital Battery charger. (BKR 225)
    • h) Open the breaker on 125V Vital Battery Board li from the No. IV 125V Vital .

Battery charger. (BKR 225) h*i) Open 480-V standby Lighting Cabinet NO.

4 breaker, located on 480-V Shutdown Board 1A2-A, Breaker 9C.

    • J) Open 480-V Standby Lighting Cabinet No.

1 breaker located on 480-V Shutdown Board 2A2-A, Breaker 9C.

'Ak) Open 480-V Standby Lighting Cabinet No.

2 breaker located on 480-V Shutdown Board IB1-B, Breaker 8D.

l

'A1) Open 480-V Standby Lighting Cabinet No.

3 breaker located on 480-V Shutdown Board 2B1-B, Breaker 8D.

NOTE: At this point the normal lighting in the Control Building and the Auxiliary Building has been deenergized and the emergency lighting is energized from the 125-VDC Vital Battery.

14

  • SQNP SPECIAL TEST 7 Page 13 of 21 Rev. 0 5.0 TEST INSTRUCTIONS (Continued)

>*m) Open 480-vac input breaker on Vital Inverter 1-I.

    • n) Open 480-vac input breaker on Vital Inverter 1-11.
    • o) Open 480-vac input breaker on Vital Inverter 1-III.
    • p) Open 480-vac input breaker on Vital Inverter 1-IV.
    • q) Open 480-vac input breaker on Vital Inverter 2-1.
    • r) Open 480-vac input breaker on Vital Inverter 2-II.
    • s) Open 480-v input breaker on Vital Inverter 2-III.
    • t) Open 480-v input breaker on Vital Inverter 2-IV. -- --
    • u) Turn vital battery room I exhaust fan off.
    • v) Turn vital battery room II exhaust fan .

off.

l A*w) Turn vital battery room II exhuast fan off.

    • x) Turn vital battery room IV exhaust fan l off.

)

NOTE: At this point in time the 125-v Vital Battery is supply-ing all the 120-v Vital AC load as well as the Emergency  ;

Lighting. l l

y) Begin monitoring and recording the parameters indicated on Data Sheet 5.2, sheets 2 through 4, at the intervals ,

indicated. l NOTE:

Monitor reactor power closely and make any adjugtments necessary to maintain approximately 1% power, c for each leg should be m.iintained at approximately the pretrip temperature.

15

  • SQNP SPECIAL TEST 7 Page 14 of 21 Rev. 0 5.0 TEST INSTRUCTIONS (Continued) 1 5.18 Verify the steam-driven Auxiliary Feedwater pump has started and flow established to each steam generator.

/

NOTE: The Auxiliary Feedwater level control valves LCV-3-172,173, 174, 175 will open shortly after the Aux Feed pump starts but will fail close in 4 or 5 minutes as the accumulators run out of air. Preparations must be made to operate these valves by hand when this happens.

5.19 Operators should be dispatched to take manual control of the Auxiliary feedwater level control valves, and main steam power operated relief valves.

/

5.20 Move the following handswitches to the "t' lose" position to simu-late loss of control to the main steam power operated relief

valves.

1-HS-1-6 /

l-US-1-13 /

1-HS-1-24 ,

1-HS-1-31 /

5.21 After the simulated blackout has taken place the operational guidelines in Appendix A of EDI-5 should be followed to verify natural circulation has'been established.

/

5.22 Record the time that full manual control of the Auxiliary Feed-water level control valves takes place.

Time 1-LCV-3-172 1-LCV-3-173 1-LCV-3-174 1-LCV-3-175

/

16 l

1 l

SQNP SPECIAL TEST 7 l

Page 15 of 21 Rev. O l

5.0 TEST INSTRUCTIONS (Continued) l 5.23 Bring the steam generator 1cvels back to normal operating level .

(approximately 33%) and manually adjust atmospheric dump and

, auxiliary feedwater flow to maintain the pretrip cold leg tempera-I ture. (Ectablish a steady feedwater flow. Do not stop and start flow to control the level.)

/

5.24 When equilibrium conditions have been established for each steam generator, make notes on Data Sheet 5.2 of the time and continue recording data.

/

5.25 Maintain steam generator level at approximately 33% and reactor power at 1% for a two-hour period from the time of the simulated i blackout.

/

NOTE: The pressurizer water level is not expected to rise above 70%, however, if it should, put excess letdown into ser-vice to reduce the RCS water volume. Maintain letdown until level reaches 50%. (Note letdown established on Data Sheet 5.2).

! 5.26 At the end of the 2-hour period, manually adjust the Main Steam p0RV pressure controllers PIC-1-6A, -13A, -24A, and -31A to ,

appro:timately the output corresponding to the percentage each valve in open as indicated by the valve position indicator on the valve.

/

5.27 Adjust the setpoint dial on the pressure controllers to 1000 psig (83.3% on dial) and individually return the power-operated relief valves to ' auto' control by putting first the valve handswitch in

' auto' and then the corresponding controller.

CAUTION: Let each steam generator come to equilibrium before putting the next power relief valve in Auto.

1-HS-1-6 and PIC-1-6A /

l 1-HS-1-13 and PIC-1-13A /

1-HS-1-24 and PIC-1-24A /

1-US-1-31 and PIC-1-31A /

l 17 E

.SQNP

.SPECIAL TEST 7 Page 16 of 21 Rev. 0 5,. 0 TEST INSTRUCTIONS (Continued) 5.28 Individually return the control air supply to the Auxiliary Feed-water level control valves and adjust the flow controllers to ob-tain approximately the equilibrium flow indicated before the air was returned.

1-LCV-3-172 /

1-LCV-3-173 /

1-LCV-3-174 /~

1-LCV-3-175 /

5.29 Return the Auxiliary Feedwatet- level controllers to ' auto' and verify automatic control is resumed.

/

5.30 Return pressurizer spray controllers PIC-68-340B and PIC-68-340D to ' Auto'. (Spray will not be available until the reactor coolant pumps are restarted).

/

5.31 If the RCS pressure is below 2210 psig, allow one of the hand-switches for the pressurizer backup heaters to return to P-Auto.

The heater should energize and increase RCS pressure. Control RCS pressure by energizing or deenergizing the backup heaters. ,

/

5.32 Manually adjust.the output of PIC-68-340A to 40% output and ener-gize the pressurizer control heater group 1D. Return PIC-68-340A to ' Auto.' ,

/

5.33 Insert Control bank D until the reactor is in the hot zero power 1 test range.  !

l

/  :

NOTE: The following steps return normal power to the vital instruments. The steps must be followed in sequence.

    • 5.34 close 480vac input breaker on Vital Inverter 1-I.

~ ./_

j **5.35 Close 480vac _ input breaker on Vital Invert-v -2

_ /

s. .

18'

.a

=

M *

  • e

, SQNP SPECIAL TEST 17 Page 17 of 21 Rev. 0 5.0 TEST INSTRUCTIONS (Continued)

    • 5.36 Close 480vac inpt. breaker on Vital Inverter 1-III.

/

    • 5.37 Close 480vac input breaker on Vital Inverter 1-IV.

/

    • 5.38 Close 480vac input breaker on Vital Inverter 2-I.

/

$'*5.39 Close 480-vac input breaker on Vital Inverter 2-II.

/

lh5.40 Close 48-vac input breaker on Vital Inverter 2-III.

/

    • 5.41 Close 480-vac input breaker on Vital Inverter 2-IV.

/

    • S.42 Close 6.9-kV ACB located on 6.9-kV Common Board A that feeds the Auxiliary Building Lighting Bus A.

/

    • 5.43 Close 6.9-kV ACB located on 6.9-kV Common Board B that feeds the -

Auxiliary Building Lighting Bus B.

/

    • 5.44 Close 480-V Standby Lighting Cabinet No. 4 breaker, located on 480-V Shutdown Board 1A2-A, breaker 9C.

/

    • 5*.45 Close 480-V Standby Lighting Cabinet No. 1 breaker, located on 480-V Shutdown Board 2A2-A, Breaker 9C.

/

    • 5.46 Close 480-V Standby Lighting Cabinet No. 2 breaker, located on 480-V Shutdown Board IB1-B, Breaker SD.

/

    • 5.47 Close 480-V Standby Lighting Cabinet No. 3 breaker, lo : ate 6 on 480-V Shutdown Board 2B1-B, Breaker 8D.

+

j.

19

-,-q

SQNP SPECIAL TEST 7

  • Page 18 of 21 Rev. 0 5.0 TEST INSTRUCTIONS (Continued)
    • 5.48 Close the breaker on 125V Vital Battery Board I from the No. I 125V Vital Battery Charger. (BKR 225)

/

'*5.49 Close the breaker on 125V Vital Battery Board II from the No. II 125V Vital Battery Charger. (BKR 225)

/

N*5.50 Close the breaker on 125V Vital Battery Board III from the No.

III 125V Vital Battery Charger. (BKR 225)

/

  • '5.51 Close the breaker on 125V Vital Battery Board IV from the No. IV 125V Vital Battery Charger. (BKR 225)

/

NOTE: At this time the 125 vdc Vital Battery, 120 vac Vital Instrument Power, and the Plant Emergency Lighting System are normal.

5.52 Individually move handswitches 1-HS-3-118A and 1-HS-3-128A to

' auto' position. When these switches are returned to Auto, the motor-driven Auxiliary Feedpumps will start so a close watch should be maintained to verify proper automatic level control.

/

    • 5.53 Turn off the data recorders and note the time on the charts.

/

CAUTION: Prior to starting RCP 1 and/or 2 ensure pressurizer spray valves are closed.

5.54 Restart reactor coolant pumps in accordance with SOI 68.2 starting with RCP 2, 1, 3 and then 4.

/

5.55 Return the pressurizer level to approximately 26*4 and return control to auto.

/

5.56 Re-establish normal letdown and charging in accordance with SOI 62.1B.

/

20

SQNP

. SPECIAL TEST 7 Page 19 of 21 Rev. 0 5.0 TEST INSTRUCTIONS (Continued) 5.57 Open MSIV warmup bypass valves. Control them to maintain stable heatup and pressure conditions in the main steam pipjng. Do not exceed main steam piping heatup rate of 200 F/hr.

/

NOTE: Tempe are can be monitored on computer log points T2300 i2301, T2302, and T2303.

5.58 When steam pressure across the MSIV's is less than 25 psi, with ifs-1-4A, 11A, 22A, and 29A in close positions, reset main steam isolation valves by momentarily placing control switch MS-1-4A in the reset position.

/

5.59 Open the following MSIV's:

FCV-1-4 /

FCV-1-11 /

FCV-1-22 /

FCV-1-29 /

    • 5.60 Return the following dampers on El 669 in the auxiliary building to their original positions:

, 1-31C-1105 /

1-31C-1109 /

1-31C-1150 /

1-31C-1148 /

    • 5.61 Return the thermostats on General Vent Coolers 1C and 2C to their original setpoints.

/

    • 5.62 Return main control room air conditioning to normal.

/

    • 5.63 Turn vital battery room I exhaust fan on.

/

    • 5.64 Turn vital battery room II exhaust fan on.

_ /

21

. SQNP SPECIAL TEST 7 Page-20 of 21 Rev. 0

. 5.0 TEST INSTRUCTIONS (Continued)

    • 5.65 Turn vital battery room III exhaust fan on.

/

    • 5.66 Turn vital battery room IV exhaust fan on.

/

4 5.67 Remove the block of the input logic of safety injection on Hi 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 this step, place N/A in signature line and initial.

/

5.68 Remove modification to Hi steam flow coincident with Lo S/G pressure or Lo Tav safety injection input 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.

~

/

\

5.69 Remove block of automatic actuation of safety injectien ~n accord-ance with Appendix E unless the next test to be performed requires this lockout. If this is the case, disregard this step, place N/A in the signature line and initial. .

/

5.70 Remove the gag from the following UHI isolation valves unless the valves are required to be gagged in 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 /

5.71 Reset the intermediate and power range high level reactor trip set-points as indicated by the test director in accordance 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 Range -/ -

Intermediate Range /

22 1

SQNP SPECIAL TEST 7 Page 21 of 21 Rev. 0 6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperature did not exceed 610 F.

_, /

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

/

6.3 -Tavg for any loop did not exceed 578 F.

/

6.4 Natural circulation can be established and maintained with the

- degraded condition of a simulated loss of offsite and onsite power.

/

6.5 Emergency lighting in the plant is sufficient to operate critical equipment in the loss of all normal lighting.

/

6.6 Ilot standby conditions can be maincained for a 2-hour. period with critical equipment operating off of vital battery power.

/

6.7 Manual operation of auxiliary feedwater valves and main steam power reliefs can be coordinate < by the unit operator to main-tain stable plant conditions.

/

6.8 Auxiliary feedwater turbine driven pump room temperature did not exceed 115 F.

/

23 i

~n

  • SQNP SPECIAL TEST 7 Page 1 of 4 Rev. O DATA SIIEET 5.1 Initial Conditions Date Time Unit Pressurizer Pressure PR-68-340 psig Pressurizer Level LR-68-339 Red Pen  %
  1. l Ifot leg temp g TR-68-1 F
  1. 1 Cold leg temp g

in-6A-18 F

//2 Ilot leg temp g

TR-68-1 F

  1. 2 Cold leg temp g

TR-68-18 F

  1. 3 llot leg temp g

TR-68-43 F

  1. 3 Cold leg temp g

TR-68-60 F .

(!4 ffot leg temp TR-68-43 F

//4 Cold leg temp TR-68-60 F S.G. //l Level (narrow range)

LI-3-42  %

S.G. #2 Level (narrow range)

LI-3-55  %

S.G. //3 Level (narrow range)

LI-3-97  %

S.G. #4 Level (narrow range)

LI-3-110  %

Data By /

24

SQNP SPECIAL TEST 7 Page 2 of 4 Rev. O DATA Sl[EET 5.1 Date Time Unit S.G. #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. /14 Level (wide range)

LR-3-98 Pen 2  %

S.G. #1 Pressure PI-1-2A psig  ;

S.G. #2 Pressure PI-1-9A psig S.C. #3 Pressure PI-1-20A psig S.G. #4 Pressure 1 PI-1-27A psig ,

l Attach computer printout of Incore Thermocouple Temperature Map. Refer to Appendi:< D for the procedure for printing out this map. .]

S.G. #1 Feedwater flow FI-3-35A lbs/hr S.G. !!2 Feedwater flow

'T-3-48A lbs/hr S.G. #3 Feedwater flow FI-3-90A lbs/hr S.G. #4 Feedwater flow FI-3-103A lbs/hr l

S.G. #1 Steam flow l FI-1-3A lbs/hr S.G. #2 Steam flow FI-1-10A lbs/hr Data By: /

25

SQNP

. SPECIAL TEST 7 Page 3 of 4 Rev. O DATA SHEET 5.1 Date Time Unit S.G. //3 Steam flow FI-1-21A lbs/hr S.G. ij4 Steam flow FI-1-28A lbs/hr Loop !!1 T-average o TI-68-2E F Loop //2 T-average o TI-68-25E F Loop /!3 T-average o TI-68-44E F Loop /!4 T-average o TI-68-67E F Loop //1 AT TI-68-2D  %

Loop //2 AT TI-68-25D  %

Loop (/3 AT TI-68-44D  %

Loop /!4 AT TI-68-67D  %

(0-52 F = 0-100%)

NIS Channel N-41  %

NIS Channel N-42  %

i NIS Channel N-43  %

NIS Channel N-44  %

Temperature reading in Turbine-driven Auxiliary g Feedwater Pump Room F Data By /

26

SQNP SPECIAL TEST 7 Page 4 of 4 Rev. O DATA SIIEET 5.1 Date Time Unit Temp rature reading outside turbine-driven Auxil- g iary Feedwater Pump Room (Elevation 669) F Main control room temperature F Remarks:

Data By: /

Reviewed By: /

l 1

l l

l l

27

, SQNP SPECIAL TEST 7 Page 1 of 4 Rev. O DATA SHEET 5.2 Attach the computer printout from the following parameters. Refer to Appendix D for the computer log points and setup procedure.

Pressurizer pressure Pressurizer Level RCS Loop 1 Hot Leg Temp RCS Loop 2 Hot Leg Temp RCS Loop 3 llot Leg Temp RCS Loop 4 Hot Leg Temp RCS Loop 1 Cold Leg Temp RCS Loop 2 Cold Leg Temp RCS Loop 3 Cold Leg Temp RCS Loop 4 Cold Leg Temp Steam Generator 1 Pressure Steam Generator 1 Narrow Range Level Steam Generator 2 Pressure Steam Generator 2 Narrow Range Level Steam Generator 3 Pressure Steam Generator 3 Narrow Range Level Steam Generator 4 Pressure.

Steam Generator 4 Narrow Range Level Power Range Channel 1 Power Range Channel 2 Power Range Channel 3 Power Range Channel 4 Incore Thermocouples #1 through #5 (upper head)

NOTE: The preceding parameters should be printed every 1 minute until equilib-rium conditions are reached. At this time the interval can be changed as required.

The data points on page 3 of this data sheet aill have to be recorded by hand at the indicated intervals using a DVll.

Print out core T/C maps as required.

1 l

l 28

SQNP e

SPECIAL TEST 7 Page 2 of 4 Rev. O DATA SIIEET 5.2 Record the following temperatures at the indicated intervals.

Time Auxiliary

  • Ele.669 Outside Main Control After Trip F.P. Room F.P. Room Room 15 mins.

30 mins.

45 mins.

60 mins.

75 mins.

90 mins.

105 mins. __

120 mins.

'If ambient temperature reaches 115 F, start the AC powered exhaust fan.

Data By: /

I 29

l ad

- tB i

VrV wI cP -

a l vt 0 s 2 n 7 1I T

S4 l E ad Tf tB o i I L VrI A30 wI I cP -

PC e . a l NE gv vt QP ae 0 s SSPR 2 n 1 I l

ad tE i

VrI wI cP -

r a l e vt w 0 s o 2 n P 1 I t

n l e ad m t E u i r VrI t

s w-c l' 1 n a I ) vt e 0 s l g 2 n a a 1 I t t 2 i l V o 5 V l V c aI T a t t E v u p

iD E VB H 0 t S 2 u vt 1 O 5t A 2 a T d y 1 B A n r D a e t I y t lI r a aI e B t t ( iD _ /

t VB a _

B vt 5t l 2 a a 1B t

i V

lI V aI

- t 5 iD 2 VE 1

vt 5t 2 a 1B l

aI t

iD VB vt 5t 2 a 1B

) y T b

(

y 0 a

. . . . . . . . . n n n t s l B n n n n n n n n n i i i a l n e i i i i i i i i i m m m D ao t g m m m m m m m m m ii an 0 0 0 tt ii 0 0 0 0 0 0 0 0 0 0 1 2 i i d w 1 2 3 4 5 6 7 8 9 1 1 1 nd eo '

I n ml + + + + + + + + + + + +

o ml C I o T T T T T T T T T T T T F

g o

y r

e f t o

- t e a El B a V

  • c 7 lI ,S a I I

T t m S4 io E Vo '

Tf R o V p L - m A40 5 e I 2 T PC e . 1 NE gv QP ae SSPR y

r e f t o t e a %l BI a I

  • c 1I
a. 1 1S t m i o V o R

l V p e - m v 5 e e 2 T L 1 1

2 1

s e .

r n u o t

a y s 2 r r n e e f a 5 p t o f m t e T e a %l t E T B a s E I 'Sc u il m l I $ a S o a H h o t m x A R i o e T V o A y R n D r V p r .

e - m u t 5 e t t 2 T a 1 )

B 2 1

1 l

a  %

t 2 i (

V 8

V

- e 5 l 2 y a / /

1 r c e f s t o t e f a %l o B a l I

  • c  %

a I9S I

0 5

t m io s Vo e R h V p c

- m a 5 e o 2 T r 1 p -

p a

I -

I f

n n n n n n I y -

s n n n n n n i i i b -

n i i i i i i i i i m m m o m m m m m m m m m  :  : d _

li 0 0 0 N s y e at 0 0 0 0 0 0 0 0 0 0 1 2 O k b w -

ii td 1 2 3 4 5 6 7 8 9 1 1 1 I r e -

+ T a a i -

i n + + + + + + + + + + + U m t v no A e a e T

IC T T T T T T T T T T T C R D R -

t ' _

w

  • SQNP SPECIAL TEST 7 Page 1 of 1 Rev. 0 APPENDIX A References
1. FSAR
2. Technical Specifications
3. Plant Operating Instructions SOI 3.2 SOI 68.2 E01 5 SOI 62.1B 32

SQNP SPECIAL TEST 7 Page 1 of 1 Rev. O APPENDIX B Test Deficiencies //

Test Deficiency 1

Recommended Resolution Final Resolution Originator /

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

Plant Superintendent Date 33

  • SQNP SPECIaL TEST 7 Page 1 of 10 Rev. O APPENDIX C Procedure for Determining Core Power Level e

e 34 1

L..

  • SQNP SPECIAL TEST 7 Page 2 of 10 Rev. O APPENDIX C Outline I. Core Power Detennination 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 con-version constant.

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 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.

i e

4 35

~~

a SQNP SPECIAL TEST 7 Page 3 of 10 Rev. O APPENDIX C CORE POWER DETERMINATION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation)

C.1 Use two DVMs and measure the voltage at the test points speci-fied for each loop as rapid as possible.

C.2 Calculate the AT; multiply that AT by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (Tchle 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.

l l

f 36 l

, SQNP SPECIAL TEST 7 Page 4 of 10 Rev. O APPENDIX C Core Power Determination PART B: !!/D Power tionitor 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 i upon low power physics testing results and previous special l testing experience.

l 2. Determine the detector normalization constants and enter them into the P-250 as follows:

a) Enter a value of 1.0 into the P-250 for the addresses shown in the table below.

b) With all 5 path selector switches set to normal, run a flux trace.

c) With all 5 path selector switches set to Emergency, run a second flux trace.

d) Determine the detector normalization constants from Data Sheet C.2.

37 l

l

SQNP SPECIAL TEST 7 Page 5 of 10 Rev. 0 4

APPENDIX C Core Power Determination PART B: (Continued) e) Enter these detector normalization constants into the P-250 as shown in the table below.

Drive P-250 Address A K0908 B K0909 C K0910 D K0911 E K0912 F K0913

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 cur-rent. Update as required.

Address Value Function .

Set the Power ,

K0901 1 Normalization Factor l iclects the Modified K5525 1 'Ilux Map Print" programs K0900 0 Initiated Pass Number Calibration Constant for K0864 Variable (l) M/D Power Monitor (1) Variable: The value entered is a ratio of the Primary Calori- j metric Indicated Power (Item B on Data Sheet C.1) '

to the M/D calculatea power (UO906) times the cur-rent value entered in (K0864). If no value has been I entered into (K0864) enter 0.25.

Item #8 l Data Sheet C.1 New (K0864) = Current (K0864) x (UO906) l 1

38 l

o

  • SQNP SPECIAL TEST 7 Page 6 of 10 Rev. O APPENDIX C PART B: (Continued)
4. For power determination, obtain a partial core flux map as per TI-53. The M/D's need not be withdrawn between passes, and passes may be repeated as often as a power determination is re-quired.

NOTE: The calculated power (UO906) is printed after each pass and may be trended by the P-250 if desired. The individ-ual detector normalized integrals are also printed.

TABLE C-1 Temp Cp(I) m F BTU /lbm F lbm/hr 556 1.260 3.6448 x 10 554 1.255 3.6553 x 10 1

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 10 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 7 540 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 10 532 1.206 3.7633 x 10 7 530 1.202 3.7729 x 10 I

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

39

SQNP SPECIAL TEST 7 Page 7 of 10 Rev. 0 -

APPENDIX C Data Sheet C.1 Date Time Unit Power Tavg F Loop 1 Loop 2 Loop 3 Loop 4 Item # Calculation Procedure Units R2/TP-411J R6/TP-421J R10/RP-431J R13/RP-441J l Loop AT - Inservice (at test point) Volts 2 Loop AT = (#1) x F Loop All = (#2) x Cp

~

_ (from Table C.1) BTU /lbm 6

4 Loop RCS Flow (from Table C.1) 10 1bm/hr g 5 Loop Reactor Power = (#3) x (#4) 6 10 BTU /hr 6 Total Reactor Power = (#5) 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307  ?!WT _

8  % Reactor Power = (#7) x 0.02932  %

(1) Conversion factor for AT obtained from scaling document.

Remarks:

Date By: _

Checked By:

. SQNP SPECIAL TEST 7 Page 8 of 10 Rev. O APPENDIX C by= By = C y

_D y = E y= Fy

A = Bg = C E E E E E N3 = 1.00 NA Ng =h#

= AE B

=

N N fl =

C" C J N A

N =N = CE =

D D

N N A

N = N = DE =

E ,*, E

. N A

N = N = "E E =

F~N r N.

Definitions:

A,B,C,D,E,F y g g N N N

"' i

  • I"' I
  1. 0* 8""*'9 ""E ' #

each detector ?8#in a normal path in the first pass ,

A' E,D' = Normalized integral from sununary map for E E' E E' E each detector in an emergency path in the second pass N,N,N' g D' E'

""'"C' # " "'1I* 'I " ' ' # ' # "# '

  • 3 C F detector Remarks:

Data By: Date 41

SQNP SPECIAL TEST 7 Page 9 of 10

-Rev. O APPENDIX C Part C: Using Thermocouples The incore thermocouples can le 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 AT is unreliable K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the run-ning frequency of the Thermcouple Averaging Pro-gram 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).

i 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 q addressable values are the quadrant tilts:

Quadrant Addressable Value 1 U1159 2 Ull60 3 U1161 4 U1162 5 Ull51 6 Ull52 7 Ull53 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 thermo-couple maps.

The trend output and Short Form Maps should be attached to this procedure at the end of the test.

42

, SQNP SPECIAL~ TEST 7 Page 10 of 10 Rev. 0 4

APPENDIX C O

i CENTER.Lif4E QUARTER-CORE SYP/ METRY 1

Cdd Le.as e 3 4 1 N-43 m 2,o m

  • u J2 O O
  • J D I 1 2 ,I

}

,o. ,

180 - :' J '-i lsu: :

m 6.*1:

(

2,  ! 4 3 s1 I E XCO F1 E

( t j

OETECTC:.5 S

, O L ' 90 v b *U*AA i*

d~$/ 2 l Cs!d - L eas V

t i

l CIAGONAL-OutsP.TER CORE SY!.1 METRY i

3 225 315 s ,

S r g g'

I '

4 7

\%

g h=

i 135 45' l

i Fau<e c-t _] l 43

_m e ( -w- w + --

  • - .
  • y

- SQNP SPECIAL Test 7 Page 1 of 4 Rev. O APPENDIX D Procedure For Use Of Computer System For Data Collection The following parameters will be monitored during this test using tFa plant computer systc.a.

Parameter Computer Point Pressurizer Pressure P0480A 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 1 LO400A Steam Generator 2 Pressure PO420A Steam Generator 2 Narrow Range Level 1 LO420A Steam Generator 3 Pressure PO440A Steam Generator 3 Narrow Range Level 1 LO440A Steam Generator 4 Pressure PO460A Steam Generator 4 Narrow Range Level 1 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 NOTE: One power range channel will be connected to the reactivity computer and will be unavailable for trend.

44

SQNP SPECIAL TEST 7 Page 2 of 4 Rev. O APPENDIX D The computer trend typewriter will be used to monitor the following com-puter points. (Additional points may be added as required by the test director).

BLOCK 1 Column Point Column Point Column Point 1 P0480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO423A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO443A 5 T0439A 11 PO400A 17 PO460A 6 T0426A 12 LO403A 18 LO463A BLOCK 2 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A 4 N0052A 10-18 As Required 5 T0002A 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) ou keyboard
3. Push VALUE 1 button
4. Select 0 on keyboard
5. Push VALUE 2 button
6. Push STOP button Hepeat the above 6 steps for each data block to be used.

NOTE: A Block Trend Error message will occur if the data block is ini-tially clear.

W 45 L

SQNP SPECIAL TEST 7 Page 3 of 4 Rev. O APPENDIX D To set up the data blocks, perform the following series of steps for each point to be monitored.

1. Push the DIGITAL TREND button
2. Select the point address (i.e. PO480A) on the alphanumeric keyboard
3. Push ADDRESS button
4. Select block number (1 to 6) on keyboard.
5. Push VALUE 1 button
6. Select column number (1 to 18) on keyboard
7. Push VALUE 2 button b Push START button Once the blocks are set up they can be initiated by performing the follow-ing steps for each block.
1. Push DIGITAL TREND button.
2. Select block number (1 to 6) on keyboard
3. Push WLUE 1 button
4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 = 2 minute, et- . "he 30-second interval is recommended for the duration of the test transient
5. Push VALUE 3 button
6. Push START button If it in 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 the trend typewriter, the following points will be monitored on analog trend recorded.

T0056A (Core exit temp).

Others as needed (Recommend pressurizer pressure, steam generator level (WR) and steam generator pressure).

46

+

  • SQNP SPECIAL TEST 7 Page 4 of 4 Rev. O APPENDIX D After selecting the per to be used to record a value, ensure that it is cleared by performing the following steps.

L. Push ANALOG TREND function button

2. Select per number (1 to 1.) on keyboard
3. Push VALUE 1 button
4. Push STOP 'mtton To start an analog trend perfonn 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 kevboard S. 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, per- .

i form the following steps.

1. Push IN-CORE T/C MAP function button

! 2. Select 25 on keyboard for short-form current map

3. Push VALUE 1 button

. 4. Select output device code number 20 for programmers 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 bu. ton l

4 47 .

- _ . . , , _ _ _ _ _ w_ _ ,_ y ,

9 - -

, SQNP SPECIAL TEST 7 Page 1 of 11 Rev. O 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 por-tion of the protection logic will remain in operation. If conditions exist that would normally initiate a safety injection; (1) the safety injection alarm wili initiate telling the operator that the condition exists and what the problem is. (2) a reactor trip will take place auto-matica11y. (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 car.ls A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.

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

R-47 Panel ?erformed by: /

Verified by: /

R-50 Panel Performed by: /

Verified by: /

Procedure for blocking automatic actuation of a safety 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 cor.d ition s . (This block will also defeat all AP SI alarms).

2. Veri -tatus lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, 73, 7/ are all clear prior to starting blocking procedure.
3.  !! ave 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 poiarity 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 48

  • SQNP SPECIAL TEST 7 Page 2 of 11 Rev. O APPENDIX E 1

l ground will already be made up through the trip switch). The l 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 lif ted wire, i

NOTE: Orange "Out of Service" stickers should be placed on all j status / alarm windows as the 120V source is connected.

4. Lif t 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 in the rear of
l-R-7 and verify 1-XX-55-6B/25 is cicar.

Performed by: /

Verified by: /

i

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

Performed by: /

t Verified by: ___ /

4 1 6. Lif t and tape the wire on the rack side of terminal L-7 in the rear of I l-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of I

i 1-R-7 and verify 1-XX-55-6B/27 is clear.

]

Performed b'y: /

Verified by: /

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

Performed by: /

Verified by: /

8. Lift and tape the wire.on the rack side of terminal L-5 in the rear of
1-R-7. Apply 120-VAC source to terminals L-5 and L-6 in the rear of 1-R-12 and verify 1-XX-55-6B/73 is clear.

Performed by: /

Verified by: /

49

,y ,, y. ,..Wk -a w

. SQNP SPECIAL TEST 7 Page 3 of 11 Rev. O APPENDIX E

9. liove 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. Lift 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 in the rear of 1-R-12 and verify 1-XX-55-6B/76.

i l Performed by: /

Verified by: /

11.  !! ave 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 cicar.

Performed by: /

Verified by: /

13. flove 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. Lift 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 and verify that XX-55-6B/26 is clear.

Performed by: /

Verified by: /

i

15.  ?!ove 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: /

l 50 l

  • SQNP SPECIAL TEST 7 Page 4 of 11 Rev. O APPENDIX E
16. Lif t 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.  ?!ove 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. Lif t and tape the wire on the rack side of terminal L-5 in the rear or 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 ?! 9 dification to liigh 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.

20.  ?!ove 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. Lif t and tape the wire on the rack side of terminal F1-3 in the rear of 1-R-2. Apply a 120-VAC source -to terminals 11-3 and 11-4 and verify XA-55-6A/30 will clear.

Performed by: /

Verified by: /.

51

/

SQNP SPECIAL TEST 7 Page 5 of 11 Rev. O APPENDIX E

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. Lif t 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 and verify XA-55-6A/30 will clear.

Performed by: /

Verified by: / -

26. Move test t rip switch TS-442D in R '3 to the 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 and verify XA-;5-6A/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. The 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.)

52

  • SQNP SPECIAL TEST 7 Page 6 of 11 Rev. O APPENDIX E
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. Hove test trip switch FS522B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/ come on.

Performed by: /

Verified by: /

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

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 SWITCH TEMP ALT. NO.

R-7 PS515A /

R-7 PS515B /

R-12 PSS16C /

R-12 PS516D /

R-8 PS525B /

R-8 PS525A /

R-11 PS526D /

R-11 RS526C /

R-2 TS'+12D /

R-6 TS422D /

R-10 TS432D /

R-13 TS442D /

R-3 FS512B /

H-3 FS522B f To return the steamline Delta-P S.I. to normal condition, the following steps should be followed.

l 53

-* SQNP SPECIAL TEST 7 Page 7 of 11 Rev. O APPENDIX E NOTE: The orange "Out of Service" stickers should be removed from the alarm / status window as each bistable is put back in service.

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

Performed by: /

Verified by: /

32.  !!ove 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: /

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

Performed by: /

Verified by: /

34. }!ove 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: /

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

Performed by: /

Verified by: /

36.  ?!ove 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: /

Verified by: /

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

Performed by: /

Verified by: /

54

~<.y wr- . rwg

  • SQNP

=

SPECIAL TEST 7 Page 8 of 11 Rev. O APPENDIX E

38.  !!ove 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.

Performed by: / _

Verified by: /

39. 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: /

40. 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 clear.

Performed by: /

Verified by: /

41. 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: /

42. 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: /

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

Performed by: /

Verified by: /

44. Move test trip switch PS-515B in 1-R-7 to the normal position and verify j the amber light and 1-XX-55-6B/27 are clear. l 4

Performed by: /

Verified by: /

l 55 '

l l

l l

a

, SQMP SPECIAL TEST 7 Page 9 of 11 Rev. O APPENDIX E

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

I Performed by: /

Verified by: /

46. t!ove test trip switch PS-515A to the normal p rition 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 injection is in a normal operating mode.

Toreturntgehighsteamflowcoincidentwithlowsteamgeneratorpressut_

or low-low avg to normal, perform the following steps.

47. Move 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: / .

48.  ?!ove test trip switch FS512B 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: /

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

Performed by: /

Verified by: /

50. 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: /

56

o SQNP SPECIAL TEST 7 Page 10 of 11

' Rev. 0 1

APPENDIX E E

51. Remove the 120-VAC source from terminals M-3 and M-4 in R-10. Re termi-nate wire on M-3.

Performed by: /

Verified by: /

52. Move test trip switch TS4.' D in R-10 to the non-cl position and verify the amber light goes out aad XA-55-6A/30 will clear.

Performed by: /

Verified by: /

53. Remove the 120-VAC source from terminals M-3 and M-4 in R-6. Retermi-nate wire en M-3.

Performed by: /

Verified by: /

54. 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: / .

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

Performed by: /

Verified 5 3: /

56. Move test trip switch TS412D in R-2 to tLe trip position and verify the amber light comes on ar.a XA-55-6A/30 will clear.

Performed by: /

Verified by: /

57

  • ' SQNP SPECIAL TEST 7 Page 11 of 11

) Rev. O APPENDIX E

57. Remove the Temporary Alteration Tags on the following test trip switches:

RACK TEST SWITCII TEMP ALT. NO.

R-7 PS515A /

R-7 PS515B /

R-12 PSS16C /

R-12 PSS16D /

R-8 PS525B /

R-8 PS525A / _

R-11 PS526D /

R-11 RS526C /

R-2 TS4123 /

R-6 TS422D /

R-10 TS432D /

R-13 TS442D /

R-3 FSS12B /

R-3 FS522B /

58. 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 Perfr-mod by: / I Verified by: /

R-50 Panel Performed by: /

Verified by: /

NOTE: All reactor safeguard systems modified for the special startup tests are back in a normal configuration at this time. i 58

o ' ** SQNP g SPECIAL TEST 7 Page 1 of 1 Rev. O APPENDIX F Technical Specifications Exceptions The table 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.

E B

a B!3

  • 8e8 o u he e e Nkt8 9 9 8 3&a tee e3 yeDaet "

t 8 a . . . t 8 o EdEEEE $ 3 E a ts u a a " "'

3 E

-% ~ ~ ~ Eti" E R EE2u Bn335%ag? e aa n8 e 3 e a a 6s M ee TECilNICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment HI 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 OPAT (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 High Steamtlow coincident 91 v/ low steamline pressure or low-low gvg SI Reset flow to 0% and avg blocked X X X X X X X X X X Heset 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 UHI (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 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 59

SQNP SPECIAL TEST 7 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.

60

. '