ML19290C661
| ML19290C661 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/15/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19290C651 | List: |
| References | |
| PROC-791215-02, NUDOCS 8001220539 | |
| Download: ML19290C661 (43) | |
Text
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SPECIAL TEST NO. 7 SIMULATED LOSS OF ALL ONSITE AND OFFSITE AC POWER t
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1787 051 .
8'001220 63
j SPECIAI.NO. 7 i ,
12/15/79 4
SIMULATED 10SS OF ALL ONSITE AND OFFSITE AC POWER Table of Contents Pge, 1.0 OBJECTIVES 1 2.0 PREREQUISITES 2 3.0 PRECAUTIONS 5 1+ . 0 SPECIAL TEST EQUIPMDIT 6 5.0 TEST INSTRUCTICNS 'J DATA SHEETS 18 APPEIDIX A - Eeferences 25 APPENDIX B - Deficiencies 26 APPENDIX C - Power Measurement Technique 27 APPENDIX D - Cc=puter Point 37 a
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1787 052
SPECIAL NO. 7 12/15/79 s
SDWLATED LOSS OF ALL ONSITE AND OFFSITE AC FOWER Ta t 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.
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SPECIAL NO. 7
. Page 1 of 19 12/10/79 1.0 OBJECTIVES The objectives of this test are 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 feedwater system in the manual mode. In addition, it will be verified -
that hot standby conditions can be maintained by manual control of the auxiliary feedwater system. It will also be verified that critical plant operations can be performed 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. .
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I787.054 SPECIAL NO. 7
- Page 2 of 19 12/10/79 2.0 PREREQUISITJE 2.1 Reactor is. critical and manually controlled at approximately 1% power with control bank D at 160 steps or as specified by test engineer. (Povstr level determined as indicated in ApJendix C). .
Date 2.2 All four Reactor Coolant Pumps in operation.
Date 2.3 RCS pressure at approximately 2235 psig and temperature at approximately 548 F, and pressurizer level at approximately 26-28%.
Date 2.4 Steam pressure approximately 1005 psig and being maintained by steam dump to the condenser.
Date 1
2.5 Steam generator level being maintained at approximately 33% on the narrow range indicators.
v Date 2.6 One main feedvater pump in service and the other tripped.
s Date 2.7 Auxiliary feedvater system lined up in standby in accordance with SOI 3.2 Date 2.8 At least 190,000 gallons in the Condensate Storage Tanks and available to supply the Auxiliary Feedvater System.
Date .
2.9 Steam generator chemistry in a condition that the absolute minimum steam -
generator blowdown can be maintained during the duration d this test.
(Zero blevdown is possible). ..-= =._. ==.
Date 1787 055
SPECIAL NO. 7
- Page 3 of 19
, 12/10/79 2.0 (Continued) 2.10 Excess letdown is available for service if required during the test.
Date .
2.11 175-V Vita'. Battery Board I energized from 125-V Vital Battery I (E 2 107 closed).
Date
?.12 125-V Vital Battery Board II energized from 125-V Vital Battery II (BG 107 closed).
Date 2.13 125-V Vital Battery Board III energized from 125-V Vital Battery III (B E 107 closed).
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Date I
2.1h 125-V Vital Battery Board IV energized from 123-V Vital Battery IV (B2 107 closed).
Date 2.15 Verify that battery-powered lights are located in areas where operation of equipment is required after nor=al lighting is de-energized. (Opera-tions to supply lights and position them where deisred). -
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Date NOfE: 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-powere.d lights.
2.16 Charging is being maintained with a centrifugal pu=p and in automatic control.
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Date 1787 056 SPECIAL NO. 7 Page 4 of 19
. 12/10/79 2.0 (Continued) 2.17 Connect Brush Recorders to the following test points:
Brush Recorder #1 Connect to: Monitoring:
Channel #1 1-R-1, FP41'+3 ECS Flow - loop 1 -
Channel #2 1-R-1, FF424B RCS Flow - loop 2 Channel #3 1-R-1, FP434B RCS Flow - loop 3 Channel #4 1-R-1, FP444B RCS Flow - loop 4 Channel #5 1-R-1, PP455B Pressurizer Pressure Channel #6 1-R-1, LP459B Pressurizer level Brush Recorder #2 Connect to: Monitoring:
Channel #1 F-3-163, TP 13, 1-L-llB Aux Feed flow to S.G. #1 Channel #2 F-3-155, TP 13, 1-L-llA Aux Feed flow to S.G. '#2 Channel #3 F-3-147 TP 12, 1-L-113 Aux Feed flow to S.G. #3 Channel #4 F-3-170, TP 12, 1-L-llA Aux Feed flow to S.G. #4 2.18 Set the trend recorders and computer trend printer in the Main Control Room to monitor the parameters indicated in Arpendix D.
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C 2.19 Install /)-computerrecordertomonitorthefollowing:
- a. Flux
- b. Avarage wide-range T
- c. Average wide-range (eold
- d. AveragesteamgeneraEoEpressure
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2.20 Evacuate construction personnel from all unit 1 and unit,2 work areas in the auxiliary and containment buildings.
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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 />.
2.21 Record en the recorder charts the following information:
- a. Unit number
- b. Date
- c. Procedure number ., ,
- e. Chart speed
- ~
- f. Time marker interval
- g. Recorder ID number
- h. Name of individual recording data _ _ _ _ _ .
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2.22 Block auto actuation of safety injection on Hi Steam Line406 P.
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SPECIAL NO. T
- Pqe 5 of l9
, 12/10/79 3.0 PRECAUTIONS 1
3.1 Maintain reactor coolant pump seal and tt9rmal barrier differential pressure requirements as given in SOI 68 2.
3.2 Do not exceed 5% nuclear power at any time while the test is in -
progress.
3.3 Do not exceed any of the following temperature limits:
3 3.1 Core exit temperature of 610 F 3.3.2 sd T as indicated by T h - T, of 65 F 3.3.3 T avg t emperature f 578 F 3.k When equilibrium is established afte the initial transient, avoid any sudden changes in Auxiliary Feedvater 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 When the Reactor Coolant pumps are first tripped, Steam Generator water level vill first shrink (due to flow coastdown) and then swell
, (as natural circulation reaches equilibrium). When complete manual .
control of auxiliary feedvater is begun, do not reduce feedvater flow below h0 gpm to each steam generator during the swell. (Until nor=al leve'l is established).
3.7 After the Reactor Coolant pumps are tripped, the normal T and 2$ T indication will become unreliable. d T and T shouldSecalculatedby E
taking the difference and the average of the h8IEand cold leg temperature indications respectively. .
3.8 If the primary system pressure drops to a point where it is obvious that saturation pressure for the existing vide range hot leg or incere T/C temperatures vill soon be reached, the pressurizer heaters vill have to be energized or charging flow reestablished to increase system pressure.
3.9 NIS channels can be used to determine changes in core power level providing the RCS cold leg temperatures are maintained at approximately the same value that existed before tripping the reactor coolant pumps.
3.10 The turbine auxiliary feedvater pump room has four temperature detectors designed to isolate the steam supply to the turbine if the tenperature reaches 125 F. If ambient _ t_emperature reaches 115 F, start the AC-powered exhaust fan to help maintaid" temperature.
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L787 058
SPECIAL NO. 7 Page 6 of 19
- 4.0 Scecial Test Equirment 12/10/79 Identification Calibration Seecification Number Verification Instrument Digital Voltmeters Fluke model
. (DVM)(3) 3120A or equivalent
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Strip Chart Recorder, Brush 260 or equivalent' *
(6-channel) (2)
Room Thermometers (7)
Reactivity Computer Westinghouse Hydrogen Meter
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s If test instruments are changed during this test, the instrument infor=ation must be recorded here and an entry de in the chronological log book explaining _
this change.
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787 059 O' 9 M
SPECIAL NO. 7 Page 7 of 19 12/10/79 5.0 TEST INSTRUCTIONS 5.1 Close the following dampers on El 669 in the Auxiliary Building.
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1-31C-1105 1-31C-1109 /
1-31C-1150 /
l-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 Coclers 1C and 2C on El 669 to their highest settings. (Note their present setpoint).
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5.2.'1 Shutdown the main control room air conditioning and place a
- room thermometer on the operators' desk to monitor control room air temperature.
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- 5.3 Position AUO's in the following positions in the plant to be available to operate vital equipment.
a) Auxiliary Feedwater Level Control Valves LCV-3-172,173,174, and ~
175.
b) Turbine driven Auxiliary Feedwater pump.
c) Power relief control valves PCV-1-5,1-23,1-12, and 1-30.
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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.
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1787-060
bt't.A.1A1. nU. /
. Page 8 of 19 12/10/79 5.0 (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.
f -
5.6 Ensure the pressurizer backup heaters lA,1B, and 1C will remain of f by moving handswitches 1-HS-68-341A and 341D to the "stop" position and moving 1-HS-68-341H to "stop-pull to lock".
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5.7 Ensure Auxiliary Feedwater motor driven pumps lA-A and 1B-B will not start on the simulated blackout by moving switches 1-HS-3-ll8A and 1-HS-3-128A on 1-M-4 to the "stop" position.
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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-ES-30-214 is in " Auto". (Both located in Turbine driven Aux. Feed pump room).
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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).
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5.10 Isolate RCS letdown by closing 1-FCV-62-69, 70, 72, 73, and 74 from their respective handsvitches on 1-M-6.
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5.11 Close charging line stop valve 1-FCV-62-85 (or 1-FCV-62-86) once charging flow is stopped.
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5.11.1 Record the data indicated on Data Sheet 5.1.
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5.11.2 Start the Computer Trend printer printing at 1-minute intervals.
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-w-f787 061
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SPECIAL NO. 7
. Page 9 of 19 12/10/79
- 5.0 ,'(Continued) -
5.12 Record the time, date and initial the charts on the data recorders in the Auxiliary Instrumant Room,
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5.13 Open 6.9KV ACB located on 6.9KV Common Board A that feeds the Auxiliary Building Lighting Bus A.
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5.14 Open 6.9KV ACB located on 6.9 K Common Board B that feeds the Auxiliary Building Lighting Bus B.
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. 5.15 Start all four reactor coolant pump oil lif t pumps from 1-HS-68-84A, 85A, 86A, and 87A on 1-M-5.
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NOTE: The following step should be conducted immediately before initiating the trips.
5.16 Isolate the control air supply to the air accumulator for the following turbine driven Auxiliary Feedwater pump level control valves.
1-LCV-3-172 /
l-LCV-3-173 /
, 1-LCV-3-174 /
1-LCV-3-175 ,
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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 simulated.
NOTE: Zero Time = ,/
Check V a) Trip pressurizar heater group 1D from 1-ES-68-341F on 1-M-4 b) Trip all four reactor coolant pumps from 1-RS-68-8A, 31A, 50A, 73A c) Close main steam isolation valves from 1-HS-1-4,11, 22, 29 on 1-M-4 d) Trip the main feed pump presently in operation from either 1-HS-46-9A (Pu=p A) or 1-HS-46-36A (Pump B)
_,_ 1787 062
SPECIAL NO. 7 Page 10 of 19
- 12/10/79
[ 5.0 5.17 (Continued)
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 the No. I 125V Vital Battery charger. (BKR 225) f) Open the breaker on 125V Vital Battery Board II _,
from 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 IV from the No. IV 125V Vital Battery charger. (BKR 225) 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 1reaker located on 480-V Shutdown Board 2A2-A, Breaker 9C.
k) Open 480-V Standby Lighting Cabinet No. 2 breaker
' located on 480-V Shutdown Board 1B1-B, Breaker 8D.
- 1) 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.
m) Open 480-vac input breaker on Vital Inverter 1-I.
n) Open 480-vac input breaker on Vital Inverter 1-II.
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-I.
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.
w) Turn vital battery room II exhuast fan off.
x) Turn vital battery room IV exhaust fan off.
1787 063
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SPECIAL NO. 7
. Page 11 of 19
,' 12/10/T9 50 5 17 (Continued)
NOTE: At this point in time the 125-v Vital Battery is supplying all the 120-V vital AC load as well as th? Emergency Lighting.
y) Begin monitoring and recording the parameters indicated on Data Sheet 5.2 at the intervals indicated.
NorE: Monitor reactor power closely and make any adjustments necessary to maintain approximately 1% power. T for each leg should be maintained at approximately t$e pretrip temperature.
5 18 Verify the steam-driven Auxiliary Feedvater pu=p has started and flow established to each steam generator.
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NOTE: The Auxiliary Feedvater level control valves LCV-3-172, 173, 174, 175 vill open shortly after the Aux Feed pu=p starts but vill fail close in k or 5 minutes as the accumulators run out of air. Preparations =ust be made to operate these valves by hand when this happens.
. 5 19 Operators should be dispatched to take manual control of the Auxiliary Feedvater level control valves, and main steam power operated relief valves.
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5 20 Move handsvitches 1-ES-1-6, 13, 2h, and 31 to the "Close" position to simulate loss of control to the main steam power operated relief valves.
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5.21 After the simulated blackout has taken place the operational guidelines in E0I-5, Appendix A, should be followed to verify natural circulation has been established.
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5.22 Record the time that full manual control of the Auxiliary Feedvater ~
level control valves takes place.
Time 1-LCV-3-172 1-LCV-3-173 1-LCV-3-17h 1-LCV-3-175
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1787 064
SPECIAL NO. 7
, Page 12 of 19 12/10/79 5.0 (Continued) 5 23 Bring the steam generator levels back to normal operating level (approximately 33%) and manually adjust atmospheric dump and auxiliary feedvater flow to maintain the pretrip cold leg temperature. (Establish a steady feedvater flow. Do not stop and start flow to control the level.)
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5 2h when equilibrium conditions have been established for each steam generator, make notes on Data Sheet 5.2 of the time and continue recording data.
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5.25 Maintain steam generator level at approximately 33% and reactor power at 1% for a two-hour period from the time of the si=ulated blackout.
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NOTE: The pressurizer water level is not expected to rise above 80%,
however, if it should, put excess letdown into service to reduce the RCS vater volu=e. 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 i pressure controller PIC-1-6A, -13A, -24A, and -31A to approximately the output corresponding to the percentase each valve is open as indicated by the valve position indicator on the valve.
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5.27 Adjust the setpoint dial on the pressure controllers to 1000 psig (83.3% on dial) and individually return the power-operated relier valves
, to ' auto' control by putting first the valve handsvitch in ' auto' and i then the corresponding controller.
CAUTION: Iet each steam generator come to equilibrium before putting the next power relief valve in Auto.
1-HS-1-6 and PIC-1-6A /
1 uS-1-13 and PIC-1-13A /
1-HS-1-24 and PIC-1-2kA /
1-RS-1-31 and PIC-1-31A /
5.28 Individually return the control air supply to the Auxiliary Feedvater level control valves and adjust the flow controllers to obtain approximately the equilibrium flow indicated before the air was returned.
1-LCV-3.172 /
1-LCV-3-173 /
1-LCV-3-17h /
1-LCV-3-175 / e c
,787 i 0o3
SPECIAL NO. 7
. Page 13 of 19
. 12/10/79 5.0 (Continued) 5.29 Return the Auxiliary Feedwater level controllers to ' auto' and verify automatic control is resumed.
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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) .
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5.31 If the RCS pressure is below 2210 psig, allow one of the handsvitches 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.
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5.32 Manually adjust the output of PIC-68-340A to 40% output and energize the pressurizer control heater group 1D. Return PIC-68-340A to ' Auto.'
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5.33 Insert Control bank D until the reactor is in the hot zero power test range.
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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.
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5.35 Close 480vac input breaker on Vital Inverter 1-II.
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5.36 Close 480vac input breaker on Vital Inverter 1-III.
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5.37 Close 480vac input breakar on Vital Inverter 1-IV.
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5.38 Close 480vac input breaker on Vital Inverter 2-I.
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1787 066
SPECIAL NO. 7
. Page 14 of 19
, 12/10/79 5.0 (Continued) 5.39 Close 480-vac input breaker on Vital Inverter 2-II.
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5.40 Close 48-vac input breaker on Vital Inverter 2-III.
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5.41 Close 480-vac input breaker on Vital Inverter 2-IV.
f 5.42 close 6.9-kV ACB located on 6.9-kV Comtea Board A that feeds the Auxiliary Building Lighting Bus A.
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5.43 Close 6.9-kV ACB located on 6.9-kV Common Board B that feeds the Auxiliary Building Lighting Bus B.
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5.44 Close 480-V Standby Lighting Cabinet No. 4 breaker, located on 480-V Shutdown Board 1A2-A, breaker 9C.
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5.45 Close 480-V Standby Lighting Cabinet No.1 breaker, located on 480-V Shutdown Board 2A2-A, Breaker 9C.
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t 5.46 Close 480-V Standby Lighting Cabinet No. 2 breaker, located on 480-V
, Shutdown Board 131-B, Breaker 8D.
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5.47 Close 480-V Standby Lighting Cabinet No. 3 breaker, located on 480-V Shutdown Board 2B1-B, Breaker 8D-
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5.48 Close the breaker on 125V Vital Battery Board I from the No. I 125V Vital Battery Charger. (BKR 225) ,
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5.49 Close the breaker on 125V Vital Battery Board II from the No. II 125V Vital Battery Charger. (BKR 225)
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5.50 Close the breaker on 125V Vital Battery Board III from the No. III 125V Vital Battery Charger. (BKR 225)
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5.51 Close the breaker on 125V Vital Battery Board IV from the No. IV 125V Vital Battery Charger. (BKR 225) 1 1787 067
SPECIAL NO. 7 Page 15 of 19 12/10/79
'5 . 0 (Continued)
NOTE: At this time the 125 vde Vital Battery, 120 vac Vital Instrument Power, and the Plant Emergency Lighting System are normal.
0.52 Individually move handswitches 1-HS-3-118A and 1-ES-3-128A to ' auto" position. When these switches are returned to Auto, the motor-driven Auxiliary Feedpu=ps will start so a close watch should be maintained to verify proper automatic level control.
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5.53 Turn off the data recorders and note the time on the charts.
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i CAUTION: Prior to starting RCP 1 and/or 2 ensure pressurizer spray valves are closed.
5.54 Lestart reactor coolant pumps in accordance with SOI 68.2.
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5.55 Return the pressurizer level to the setpcint level indicated on LR-68-339.
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5.56 Re-establish nor=al letdown and charging in accordance with SOI 62.1B.
i e
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5.57 Open MSIV war =up 'oypass valves while controlling them to maintain stable heatup pressure conditions in the staam generators and not exceeding main steam piping heatup rate of 200 F/hr.
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NOTE:
Temperature can be monitored on computer leg points T2300, T2301, T2302, and T2303.
5.58 When steam pressure across the MSIV's is less than 25 psi. with HS-1-4A, llA, 22A, and 29A in close positions, reset main steam isolation valves by momentarily placing control switch MS-1-4A in the resen position.
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5.59 Open MSIV's FCV-1-4, 11, 22, and 29. .
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5.60. Return the following dampers on El 669 in the auxiliary building to their original positions:
1-31C-1105 /
l-31C-1109 /
l-31C-1150 /
J-31C-1148 1787 068
SPECIAL NO. 7
- Page 16 of 17 12/10/79 5.0 (Continued) 5.61 Return the thermostats on General Vent Coders 1C and 2C to their original setpoints.
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5.62 Return main control room air conditioning to normal.
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5.63 Turn vital battery room I exhaust fan on.
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5.64 Turn vital battery room II exhaust fan on.
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5.65 Turn vital battery room III exhaust fan on.
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5.66 Turn vital battery room IV exhaust fan on.
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i 5.67 Remove the block of auto actuation of safety injection on H1 steam lir.e a P 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.
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8 1787 069
SPECIAL NO. 7 Page 17 of 17 12/10/79 6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C te=perature did not exceed 610 F.
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6.2 Delta-T for any loop did not exceed 65 F.
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6.3 Tavg for any loop did not exceed 578 F.
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6.4 Natural circulation can be established and maintained with the degraded condition of a simulated loss of offsite and onsite power.
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6.5 Emergency lighting in the plant is sufficient to operate critical equipment in the loss of all normal lighting.
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6.6 Hot standby conditions can be maintained for a 2-hour period with critical equipment operating off of vital battery power.
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(. 7 Manual operation of auxiliary feedwater valves and main steam power reliefs can be coordinated by the unit operator to maintain stable plant conditions.
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1787 070
Date SPECIAL NO. 7
- T.ime Page 1 of 3 Unit 12/10/79 DATA SHEET 5.1 Initial Conditions Pressurizer Pressure PR-68-340 psig Pressurizer Level LR-68-339 Red Pen %
1
- 1 Hot leg temp o TR-68-1 F
- 1 Cold leg temp o TR-68-18 _, F
- 2 Hot leg temp o TR-68-1 F
- 2 Cold leg temp o TR-68-18 F
- 3 Hot leg temp o TR-68-43 F
- 3 Cold leg temp o TR-68-60 F
- 4 Hot leg temp -
o TR-68-43 F
- 4 Cold leg temp o TR-68-60 F S.G. #1 Level (narrow range)
LI-3-42 %
S.G. #2 Level (narrow range)
LI-3-55 %
S.G. #3 Level (narrow range)
LI-3-97 %
S.G. #4 Level (narrow range)
- LI-3-110 %
S.C. #1 Level (wide range) -
LR-3-43 Pen 1 %
S.G. #2 Level (wide range)
LR-3-43 Pen 2 %
S.C. #3 Level (wide range)
LR-3-98 Pen 1 , %
S.G. #4 Level (wide range)
LR-3-98 Pen 2 %
Data by: /
1787 071
SPECIAL NO. 7 Page 2 of 3 12/14/79 DATA SHEET 5.1 (Continued)
S.G. #1 Pressure PI-1-2A psig S.G. #2 Pressure PI-1-9A psig S.G. #3 Pressure PI-1-20A psig S.G. #4 Pressure PI-1-27A __psig Attach computer printout of Incore Thermocouple Temperature Map. Refer to Appendix D for the procedure for printing out this map.
S.G. #1 Feedwater flow FI-3-35A lba/hr S.G. #2 Feedwater flow FI-3-4&A lbs/hr S.G. #3 Feedwater flow
. FI-3-90A lbs/hr S.G. #4 Feedwater flow FI-3-103A lbs/hr S.G. #1 Steam flow FI-1-3A lbs/hr S.G. #2 Steam flow FI-1-10A lbs/hr S.G. #3 Steam flow FI-1-21A lbs/hr S.G. #4 Steam flow FI-1-28A lbs/hr Loop #1 T-average TI-68-2E F Loop #2 T-average TI-68-25E F Loop #3 T-average TI-68-44E ,F Loop #4 T-average ,
TI-68-67E F Data by: /
1787 072
SPECIAL NO. 7 Page 3 of 3 12/10/79 DATA SHEET 5.1 (Continued)
I Loop #1 T TI-68-2D %
Loop #2 T TI-68-25D %
Loop #3 T TI-68-44D %
Loop #4 T TI-68-67D %
(0-52 F = 0-100%)
NIS Channel N-41 %
NIS Channel N-42 %
NIS Channel N-43 %
NIS Channel N-44 %
i Temperature reading in Turbine-driven Auxiliary Feedwater g I Pump Room F Temperature reading outside turbine-driven Auxiliary Feedwater g Pump Room (Elevation 669) F Main control room temperature F Remarks:
Data by: /
Reviewed by: /
1787 073
- 2. _ . . . . . . . _ . . _ . . . . . .
' Date SPECIAL NO. 7 Time Page 1 of 3 Unit 12/10/79 I
- 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 Hot 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 Wide Range Level Steam Generator 1 Narrow Range Level 1 Steam Generator 1 Narrow Range Level 2 Steam Generator 1 Narrow Range Level 3 Steam Generator 2 Pressure Steam Generator 2 Wide Range Level Steam Generator 2 Narrow Range Level 1 Steam Generator 2 Narrow Range Level 2 Steam Generator 2 Narrow Range Level 3 Steam Generator 3 Pressure Steam Generator 3 Wide Range Level Steam Generator 3 Narrow Range Level 1 Steam Generator 3 Narrow Range Level 2 ,
Steam Generator 3 Narrow Range Level 3 Steam Generator 4 Pressure Steam Generator 4 Wide Range Level Steam Generator 4 Narrow Range Level 1 Steam Generator 4 Narrow Range Level 2 Steam Generator 4 Narrow Range Level 3 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 hould be printed every 1 minute until equilibrium conditions are reached. At this time the interval can be changed to 2 or 3 minutes between data prints. .
The data points on page 3 of this data sheet will have to be recorded by hand at the indicated intervals using a DVM.
At 15-minute intervals from time = 0, print out a core thermocouple map as outlined in Appendix D.
17L87 074
._ . _- w -- .._ _._._ ___ _ _ __.. .. . . _ _
- SPECIAL NO. 7 i * . Page 2 of 3
- 12/10/79 DATA SHEET 5.2 (Continued)
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-pcwered exhaust fan.
Data by: /
-22_ 1787 075
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. SPECIAL NO-
. 7 -- ---
Page 1 of 1 12/10/79 APPENDIX A References
- 1. FSAR
- 2. Technical Specifications
- 3. Plant Operating Instructions SOI 3.2 SOI 68.2 E0I 5 I
8 1787 078
,;_, '~~ ; . . .
Appendix B 2/6/79 Page_ of Rev.
Page of Test Deficiencies #
Test Deficiency Recommended Resolution i
Final Resolution Originator .
/
Signature Date PORC Review of Final Resolution 1787 079 Date Approval of Final Resolution /
Plant Superintendent Date e
SPECIAL NO. 7 Page 1 of 10
- 12/30/79
' APPENDIX C A
i i
i Punchlist:
- 1. Part C - Thermocouples
- 2. Part B - Address in P-250 for:
- a. Priority scan option selection
- b. Power calibration constant
- c. Calculated power e
1787 080
~. ....__ .
SPECIAL NO. T
- Page 2 of 10
. 12/30/79 APPENDIX C (Continued)
Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)
- 1. Reference ( " 550 F) Calorimetric (Before NC test) a) Output used to adjust M/D Power Monitor Program's power conversion constant.
B. M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a % power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.
- 2. Power Monitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 5 or 6 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it vill be j
rerun up to once every 2 minutes or as necessary to continuously
- monitor core power.
9
-9 e
1787 081 SPECIAL No. 7 Page 3 of 10 12/30/79 APPENDIX C CORE POWER DETERMINATION
,PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation)
C.1 Use two DVMs and measure the voltage at the test points specified for each loop as rapid as possible.
C.2 Calculate the A T; multiply that 4 T by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (Table C-1). (Special Test No. 9 uses vide range A T so a correction factor is required to compensate for pump heating, refer to Appendix D of ST-9A).
C.3 Sum the loop beat rates and convert to a percent reactor power. The output is used in Part 3.
0 1787 082
SPECIAI NO. 7 Page / of 10 12/30/79
.' APPENDIZ C (Continued)
Core Power Determination PART B: M/D Power Monitor Program
- 1. Set up the movable detector system for a 1 pass partial core flux map as per TI-53. Select flux thimbles as per the table below for the flux map.
Drive 10-Path Position Core Location i A B
s C
- D E
F
' These positions may be altered by the test engineer, based upon low-power physics testing results and previous special tias :ing 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.
e) Enter these detector notmalization 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 1767 083
, , SPECIAL NO. 7
. Page 5 of 10
. 12/30/79 APPENDIX C (Continued)
Core Power Determination PART B: (Continued) 3 Verify that the P-250 parameters listed in the followin6 table have the proper value and that the P-250 time and date are current.
Update as required.
Address Value Function K0901 1 Set the power normalization raetor Selects the modified K5525 1 " Flux Man Print" proarams K0900 0 Initiated Pass Number Calibration Constant for M/D K086h Variable Power Monitor Varfable: The value entered is a ratio of the Primary Calorimetric Indicated Power (Ite s B on Dcta Sheet C.1) to the M/D calculated power ('J0906) times the current value entered in (K0864). If ni value has been entered into (K086h) enter 0.25
~ Item #8 Data Sheet C.1 New (K086h) = Current (K0864) x (UO906) i I h. For power determination, obtain a partial core flux =ap as per TI-53 The M/D's need not be withdrawn between passes, and passes may be repeated as often as a power determination is required.
NOIE: The calculated power (UO906) is printed after each pass and may be trended by the P-250 if desired. The individual detector normalized integrals are also printed.
1787 084
SPECIAL NO. 7
. Page 6 of10 12/30/79
, APPENDIX C (Continued)
TABLE C-1 Temp Cp( m F BTU /lbm F lbm/hr 556 1.260 3.6448 x 10 7 i
- 554 1.255 3.6553 x 10 7 552 1.250 3.6659 x 10
! 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 10 542 1.226 3.7155 x 10 540 1.221 3.7254 x 10 7 538 1.217 3.7348 x 10 7 3.7443 x 10 7 536 1.213 534 1.209 3.7538 x 10 7 532 1.206 3.7633 x 10 7 530 1.202 3.7729 x 10
( )These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia.
. 1787 085
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u F t cL o f c T T H c a P r l S a e+ o r a ( k \ C e R r t o C [ / / R R 1 o c t l t a c p p p p p ap c e a o o o o o t o a R f c o o o o oo e I l L L L TL R % n o :
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SPECIAL NO. 7
- Page 8 of 10 12/30/79
. APPENDIX C (Continued)
A = B = = D = E = F N N C
N N N N" A
E
= B E
= C E
Dg
g= F E"
NA = 1.00 A
N = N = Ab =
B B N N N " "
C" N N N " ~
8 D"D N N N ~ ~ "
E
, E
[ N N Np =b = EE =
I I N N Definitions:
q',B'N N' N' N' N
= Normalized integral from summary map for each detector in a normal path in the first pass A,B,C' ~ #*" ** '8## # """#U "I # **"
E E E E' E' E detector in an emergency path in the second pass N,N' = ee r n rma iza n actor for each detector A B C' D' E' "F Remarks:
1787 087 Data By: Date
SPECIAL NO. 7
. P ge 9 of l0
. 12/30/79 l APPENDIX C (Continued)
Part C: Using Thermocouples The incore ther=occuples can be used as an indication of both core flow distribution and power shifts during natural circulation.
Prl.or to running a ther=occuple map or trending the eight quadrant tilts (fo u center line and four diagonal tilts) the following should be verified:
K0701-K0765 = For the flow mixing factors K5501 = 0, Indicates the measured core /L T is unreliable K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocoup?.es are required for averaging before calculation is done. This in turn sets the running frequency of the Ther= couple Averaging Program at 1, 2, . . . . X 8 seconds or 6k seconds for us.
The thermcouple programs breaks the core down into eight quadrants--four centerline and four diagonal quadrants (see Figure C-1). Quadrants 1-k can be directly correlated with the excore detectors but quadrants 5-8 cannot.
The quadrant tilts are indicative of power shifts and should be trended at approximately a 2-minute frequency. The following addressable values are the t quadrant tilts:
Quadrant Addressable Value 1 Ull59 2 Ull60 3 Ull61 h U1162 5 U1151 6 U1152 7 U1153 8 Ull5h A Short Form Fhp should be run periodically or upon request from the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 operator's Console Reference Manual provides instructions for obtaining thermocouple maps.
The trend output and Short Foca Maps should be attached to this procedure at the end of the test.
178L7 088
- ~ ~
, -SPECIAI 20. 7
,,,k,'.
.i . ,
Page 10 of 10 ; . p;Q{I9 i
[
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{N!,M't. 12/30 : .
I pig dP APPEDIX C -
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1787 089
~
~ . . . , ,, ,, u m m r - * . . * * ~ -
SPECIAL NO. 7
, Page 1 of 4
. 12/14/79 8
APPENDIX D Procedure For Use Of Computer System For Data Collection The following parameters will be monitored during this test using the plant computer system.
Parameter Computer Point Pressurizer Pressure PO480A Pressurizer Level LO480A RCS Loop 1 Hot Leg Temperature T0419A RCS Loop 1 Cold Leg Te=perature 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 P0400A Steam Generator 1 Wide Range Level LO403A Steam Generator 1 Narrow Range Level 1 LO400A Steam Generator 1 Narrow Range Level 2 LO401A Steam Generator 1 Narrow Range Level 3 LO402A Steam Generator 2 Pressure P0420A Steam Generator 2 Wide Range Level LO423A .
Steam Generator 2 Narrow Range Level 1 LO420A Steam Generator 2 Narrow Range Level 2 LO421A Steam Generator 2 Narrow Range Level 3 LO422A Steam Generator 3 Pressure PO440A Steam Generator 3 Wide Range Level LO443A Steam Generator 3 Narrow Range Level 1 LO440A Steam Generator 3 Narrow Range Level 2 LO441A Steam Generator 3 Narrow Range Level 3 LO442A Steam Generator 4 Pressure PO460A Steam Generator 4 Wide Range Level LO463A Steam Generator 4 Narrow Range Level 1 LO460A Steam Generator 4 Narrow Range Level 2 LO461A .
Steam Generator 4 Narrow Range Level 3 LO462A Power Range Channel 1 (Quadrant 4) N0049A Power Range Channel 2 (Quadrant 2) N0050A Power Range Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A Incore Thermocouples T0001A through T0065A 1787 090
. SPECIAL NO. 7
- Page 2 of 4
. 12/10/79 i , APPENDIX D (Continued) i The computer trend typewriter will be used to monitor the following computer points.
(Additional points may be added as required by the test director).
, BLOCK 1 Column Point Colu=n Point Colum_n 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 Colu=n Point Colu=n Point 1 N0049A 7 TOOL 7A 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) on keyboard
- 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 2 button
- 6. Push STOP button Repeat the above 6 steps for each data block to be used.
NOTE: A Block Trend Error message will occur if the data block is initially clear.
To set up the data blocks, perform the following series of steps for each point to be monitored.
- 1. Push the DIGITAL TREND button
- 2. Select the point address (i.e. PO480A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select block number (1 to 6) on keyboard.
- 5. Push VALUE 1 button '
- 6. Select column nuaber (1 to 18) on keyboard
- 7. Push VALUE 2 button .
- 8. Push START button ,
}fhf 9-
~
l SPECIAL NO. 7 l Page 3 of 4
, e, 12/10/79
- APPENDIX D (Continued)
Once the blocks are set up they can be initiated by performing the following steps for each block.
- 1. Push DIGITAL TREND button.
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 = 2 minute, etc.) The 30-second interval is recommended for the duration of the test transient
- 5. Push VALUE 3 button
- 6. Push START button If it is necessary to change the trend interval of a block or trend, perform the following.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select new interval number (0 = 30 sec., 1 = 1 min.,
2 = 2 min., etc) on keyboard
- 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
. 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select C on keyboard
- 5. Push VALUE 3 button
- 6. Push STOP button In addition to the data recorded on 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).
After selecting the per to be used to record a value, ensure that it is, cleared by performing the following steps.
- 1. Push ANALOG TREND function button
- 2. Select per number (1 to 12) on keybccrd -
- 3. Push VALUE 1 button
- 4. Push STOP button
i - SPECIAL NO. 7
- ' a Page 4 of 4
. 12/10/79
$* APPENDIX D (Continued)
To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select per number (1 to 12) on keyboard 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-mir.ute intervals thereafter, incore thermocouple maps will be recorded at the progrm=mera console in the computer room.
To initiate an incore thermocouple map at that location, perform the following steps.
- 1. Push IN-CORE T/C MAP function button
- 2. Select 25 on keyboard for short-form current map
- 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 button 6
40-1787 093