ML19323B915
| ML19323B915 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/06/1980 |
| From: | Zeringue I TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19323B910 | List: |
| References | |
| PROC-800506, NUDOCS 8005140416 | |
| Download: ML19323B915 (41) | |
Text
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- Sequovah Nuclear Plant DI iTRT HUTION 8005140 N j
n 1C Plant v
Master File G' auperintandent j _ Assistant Superintendent (Oper.)
Assistant Superintendent (Maint.)
_ Administrative Supervisor
_ _ ?!aintenance Supervisor (ff)
Assistant Maintenance Supervisor (M)
Maintenance fiupervisor (E)
Assistant Maintenance Supervisor (E)
SPECIAL TEST NO. 8 1U Maintenance Supervisor (I)
_J Q_ Hesul t:. Supervisor ESTABLISd'!ENT OF MATURAL CIRCULATION _.lU, Opera tions Supervisor FRO:t STAGNANT CONDITION 3 1U Quality Assurance Supervisor Health Phynics Supervisor
__ Public Safety Services Supv.
_ _ Chief Storcheeper Preop Test Program Coordinator
__ Out age Di rect < -
Cheuical Engit er (Results)
Radiochem Laboratory
_____ Instrument Shop
_fC _ Reactor Engineer (Results)
Inutrument Engineer (Maint. I)
Dechanical Engineer (Results)
__ St .f f Indust rial Engineer (P] t Sys)
__ Training Center Coordinator Pieparra Dy. I. Zeringue ~- PSO - Chichamauga Engrg Unit - SNP Public Safety Services - S.'.' P H..rised hv: _/d Sh if t Engineer's Of fice S. R. Machr
_fA Unit Control Room 1 QACA Re). - SNP
' da ii t ted By: _ _ d /t'_ g nu g , _ _ llealt.h Physics Laboratory 3npe isnr ni ':uci r Document Control Unit, 606 EB-C POfa: nevicu 10 Superintendent, WUNP Qg _ g. g/fDat /go, C ____ _ _
((_]SuperiatendenL, BFNP M i
/ .____ Superintendent, BENP
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I SPECIAL TEST NO. 8 !
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j ESTABLISlfilENT OF NATURAL CIRCULATIONS FROM STAGNANT CONDITIONS '
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SQNP SPECIAL TEST 8 Page 1 of 1 Rev. 0 ESTABLISIIMENT OF NATURAL CIRCULATIONS FROM STAGNANT CONDITIONS Table of Contents Page Test Description 1 Special Operator Instruction 2 1.0 OBJECTIVES 3 2.0 PREREQUISITES 3 3.0 PRECAUTIONS 6 4.0 SPECIAL TEST EQUIPMENT 8 5.0 INSTRUCTIONS 9 6.0 ACCEPTANCE CRITERIA 13 APPENDIX A - References 14 APPENDIX B - Deficiencies 15 .
APPENDIX C - Power Measurement Technique 16 APPENDIX D - Safeguard Blocking Procedure 26 APPENDIX E - Technical Specifications Exceptions 37 TABLE 1 - Loop Flow and Core AT for Various Power Levels and isolation Configurationr. 38
SQNP SPECIAL TEST 8 Page 1 of 1 Rev. O TEST DESCRIPTION With stagnant (no flow) conditions existing throughout the primary system, core power will be increased to simulate decay heat and steam generators will be utilized to establish a heat sink. Establishment of natural circulation will be verified by observing the response of the core avit thermocouples, hot leg wide range temperature indication, and cold leg wide range temperature indication. Core exit thermocouples will be monitored to access core flow distribution.
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SQNP SPECIAL TEST 8 Page 1 of 1 Rev. 0 SPECIAL OPERATOR INSTRUCTION
- *An operator initiated safety injection should be performed only for one or 1
more of the following conditions:
Reactor Coolant System Subcooling 5 10 j Sudden Unexplained Decrease in Pressurizer Level of 10%
l or to an Indicated Level of 5 10%
l' Sudden Unexplained Decrease in Any S/G Level to 5 76% Wide Range
, 5 0% Narrow Range d
4 Unexplained Pressurizar Pressure Drop 2 200 PSI Contaisunent Pressure Hi - (1.54 psig) Annunciator XA-55-6B Window 6 initiates An operator initiated reactor trip should be performed for any of the following conditions:
)
Reactor Coolant System Subcooling 5 15 Sudden Unexplained Decrease in Pressurizer Level of 5%
or to an Indicated Level of 5 17%
i 1/3 Excores 2 10%
Any Loop A T > 65 F Tavg > 578 F Core Exit Temperature (Highest) > 610"F Any Uncontrolled Rod Movement t
- SI terminat. ion -should he' in accordance with plant EMERGENCY OPERATING PROCEDURES.
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, SQNP SPECIAL TEST 8 Page 1 of 11 Rev. 0 1.0 OBJECTIVE 1.1 Verify establishment of natural circulation from stagnant (no flow) conditions in the primary system using reactor power to simulate decay heat.
1.2 To provide operator training. All operating shifts will perfome this test.
NOTE: Data acquisition does not need to be repeated for multiple test performances.
2.0 PREPEQUISITES 2.1 Reactor critical in the hot zero power test range with control rods in manual control.
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2.2 All reactor coolant pumps operating.
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2.3 Steam pressure approximately 878 psig (Tavg ~ 531 F) and being maintained by the atmospheric relief valves or by steam dump to the condenser (preferred).
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2.4 Steam generator water level at approximately 33% and being main-tained by auxiliary feedwater system (motor-driven pumps).
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2.5 Control Bank D at approximately 160 steps or as specified by the test engiaeer to permit reactor power increase up to approximately 3% (required control band D position may be determined during the hot zero power test program).
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2.6 Pressurizer level control in manual.
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2.6.1 RCS pressure at approximately 2200 psig and in automatic control . (slowly adjust setpoint to 62.5%) . Pressurizer level at approximately 25%.
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SQNP )
SPECIAL TEST 8 ')
Page 2 of 11 l Rev. O i 2.0 (Continued) 2.6.2 The sensitivity of the NIS to avg has been completed.
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2.7 Record the following parameters.
- 2. 's .1 Obtain thermocouple map at 15-minute intervals.
2.7.2 Set up P-250 to monitor the following parameters at fast as possible.
T
- a. Wide range c ld (all loops)
T
- b. Wide range hot (all loops)
- c. Power range channels
- d. {ntermediaterangechannels
- e. avg (all loops)
- f. AT (all loops)
- g. Loop flow (1 from all 4 loops)
- h. Steam generator level (all 4 loops)
- 1. Steam generator pressure (all 4 loops)
NOTE: Record the following information on each strip chart:
a) Unit number b) Date c) Special rest number d) Scale and range of measured parameter e) Chart speed .
f) Recorder ID number 2.7.3 Record on reactivity computer recorder.
- a. Flux
- b. Average wid: rangefcold
- c. Average wide range hot
- d. Average steam generator pressure
- e. Reactivity 2.7.4 Record on Recorders.
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 4
SQNP SPECIAL TEST 8 Page 3 of 11 Rev. 0 2.0 (Continued)
Recorder #2 Connect to: Monitoring:
Channel #1 1-R-23, LP501 Steam Gen #1 Level Channel #2 1-R-3, FP512B Steam Gen #1 Steam Flow Channel #3 1-R-3, PPS14B Steam Gen #1 Pressure Channel #4 1-R-23, LP502 Steam Gen #2 Level Channel #5 1-R-3, FP522B Steam Gen #2 Steam Flow Channel #6 1-R-3, PP524B Steam Gen #2 Pressure Recorder #3 Connect to: Monitoring:
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:
Channel #1 F-3-163, TP 13, 1-L-11B Aux Feed Flow to SG #1 Channel #2 F-3-155, TP 13, 1-L-11A Aux Feed Flow to SG #2 Channel #3 F-3-147, TP 12, 1-L-11B Aux Feed Flow to cG #3 Channel #4 F-3-170, TP 12, 1-L-11A Aux Feed Flow tr ,G #4
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2.8 Trend 3 incore T/C's as determined by the test engineer on the analog trend recorders on the main control board. .
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2.8.1 Make preparations to print out incore T/C's temperature on paper tape at approximately 5 minute intervals.
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2.9 Verify the input logic of safety injection on Hi steam line AP has been blocked in accordance with Appendix D.
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2.10 Verify the Hi steam flow coincident with Lo S/G or Lo Tas input to safety injection has been modified in accordance with Appendix D.
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2.11 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix D.
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SQNP SPECIAL TEST 8 Page 4 of 11 Rev. 0 2.0 (Continued) 2.12 Verify the following UHI isolation valves are gagged.
FCV 87-21 /
FCV 87-22 /
FCV 87-23 /
FCV 87-24 /
2.13 Intermediate and power range (low setpoint) high level 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, LIMITATIONS, AND ACTIONS 3.1 Do not exceed 5% rated thermal power.
3.2 Abort the test-if any of the following temperature limits are exceeded:
3.2.1 610 F for any core outlet thermocouples 3.2.2 65 F for any loop Delta-T o T '
3.2.3 578 F for any loop avg 3.3 Avoid sudden changes in steam pressure.
3.4 Avoid sudden changes in auxiliary feedwater. l 3.5 Maintain pressurizer pressure at a aout 2200 psig.
3.6 Onset of natural circulation may be accompanied by a power in-crease due to the introduction of cooler water into the core. l 3.7 During natural circulation, reactor coolant loop transit time l is on the order of 3 to 5 minutes. )
3.8 Maintain constant steam generators pressure throughout test except where specifically stated otherwise.
1 3.9 M:_ntain steam generator water level constant at ~ 33%. !
l 3.10 .Do not maintain no-flow conditions in the primary system for more than 30 minutes.
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o SQNP SPECIAL TEST 8 Page 5 of 11 Rev. 0 3.0 (Continued) 3.11 Reactor coolant pumps should not be restarted for 30 minutes after pump trip unless required by this instruction or unless safety con-cerns necessitate the re-establishment of forced circulation.
3.12 Do not increase flux at a rate faster than .25 DPM (~ 60 pcm) in order to minimize RCS pressure surges.
3.13 As reactor power is increased to 3%, a pressuriner pressure and level surge is expected. If the pressure surge cannot be controlled below the PORV setpoint using auxiliary spray, the reactor should be manually tripped.
3.14 Should a reactor trip occur during the conduct of this test at least one reactor coolant pwnp (#2) should be started prior to closing the reactor trip breaker.
3.15 Maintain D bank at 2100 steps during the conduct of this procedure.
Should this limit be reached, boron concentration will have to be increased.
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SQNP SPECIAL TEST 8 Page 6 of 11 Rev. 0 4.0 SPECIAL TEST EQUIPMENT Identification Calibration Instrument Specification Number Veri fica tion Reactivity Computer Westinghouse Recorder (4) Brush or Equivalent Recorder (1) HP 7100 B or Equivalent I
If test instruments are changed during this test, the instrument informa-tion must be recorded here and an entry made in the chronological log book explaining this enange.
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SQNP SPECIAL TEST 8 Page 7 of 11 Rev. 0 5.0 INSTRUCTIONS CAUTION: If primary system temperatures are within 10 F of the limits specified in step 3.2:
a) Insert control bank ' until reactor power is in the hot zero power test range.
b) Verify pressurizer spray vais. sed c) Start loop 2 reactor coolant pump.
d) Establish stability: pressurizer level and pressure, steam generator level and pressure, and primary system temperature, e) Return pressurizer icvel control to automatic.
f) Start the remaining reactor coolant pumps one at a time.
5.1 Start recorders, P-250 trend block, and T/C printout.
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CAUTION: Following reactor coolant pump trip Tave and Delta-T indication will be unreliable.
5.2 Trip reactor coolant pumps 1, 3, and 4 and allow flow in these loops to coast down for two minutes and then trip RCP 2.
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5.3 Stabilize steam generator water level at approximately 33%.
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5.4 Close main steam dump valves to condenser.
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5.5 Close auxiliary feedwater syste a level control valves.
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l 5.5.1 Reduce seal injection flow to the reactor coolant pumps to approximately 4 gpm.
/ l 5.5.2 Initiate auxiliary spray to the pressurizer just prior to beginning withdrawal of control bank D in the next step.
Be prepared to isolate the normal charging path in order to get full flow to the spray nozzle.
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SQNP SPECIAL TEST 8 Page 8 of 11 Rev. 0 E
5.0 (Continued)
NOTE: Some control over the auxiliary spray flow can be obtained by opening the normal pressurizer spray valves from PIC-68-340B and PIC-68-340D and allowing the auxiliary spray flow to bypass the spray nozzle and directly enter the reactor coolant loop. By posit.'.oning these valves
- the flow rate to the nozzle can be increased or decreased.
i.e. Opening the valves will decrease the spray and closing the valves will increase it.
Increased spray flow can also be obtained by in-creasing charging flow with FIC-62-93.
NOTE: During control bank withdrawal continuously monitor increase in: a) reactivity computer flux level, b) NIS indicated power level, and core exit thermo-couple temperature (e:pect delayed response).
5,6 Approximately 5 minutes after auxiliary feedwater system level control valve closure open main steam dump valves to condenser as needed, place auxiliary feedwater level control valves in automatic, and begin control bank D withdrawal, as requested by the test engineer, until reactor power is at ~ 3%.
I NOTE: Flux level should not be increased faster than .25 D.P.M.
(~ 60 pcm).
5.7 Record control bank D position: steps
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CA " ION: Oncet of natural circulation may be accompanied by a power increase. Control bank D may be inserted to rednce the mag-nitude of the increase. Immediately following power transient, return control bank D to the position recorded in step 5.7.
CAUTION: Reduction in T may result in a nonconservative, false NISpowerlevel1Ndication. Do not withdraw control bank D beyond the position recorded in step 5.7 unless requested by test engineer 10
- SQNP SPECIAL TEST 8 Page 9 of 11 Rev. 0 5.0 (Continued)
NOTE: At initiation of natural circulation the following initial response is expected.
- 1) Reactivity computer flux level increase
- 2) NIS power lgvel indication increase
- 3) Wide rang T hot increase (See Table 1)
- 4) Wide range cold slight increase or stable
- 5) Core exit thermocouples a) Increase if T/C temp. + (~ 17 F) < initial cold b) Decrease if T/C temp. + (~ 17 F) > initial cold CAUTION: Primary coolant system may be held in a stagnant condition (no flow) for a maximum of 30 minutes. If the NTR m pri-mary system temperature instrumentation doe not indicate that natural circulation has started within 25 minutes after RCP trip, insert control bank D until reactor power is in the hot zero power test range, and restart reactor coolant pumps as previously described.
5.8 Verify that natural circulation has started (increase in hot leg temperatures) prior to increasing power above 1%. If no indica-tion of natural circulation is observed, reduce steam generator pressure 50 psig or until natural circula1ation is initiated. 1 Rate of pressure decrease should be accomplished at a controlled I rate as requested by the test engineer. Utilize auxiliary feed as necessary to maintain staam generator level constant.
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1 NOTE: Natural circulation fl'ow will be stable when:
a) AT between wide range T and T is constant.
eold b) AT between wide range Tg[d nd core exit T/C average temperature 1s constant.
7 c) Uide range hot ~ core exit T/C average temperature.
5.9 When natural circulation flow h4s establishedT s1 wly regulate secondary side steam flow to s'.owly increase cold to ~ 547"F.
During natural circulation locp transient time is long (3 to 5 minutes).
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L.10 flaintain natural circulation under the established conditions for approximately 15 minutes.
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5.11 Stop recording test data, i
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y SQNP SPECIAL TEST 8 Page 10 of 11 Rev. 0 5.0 (Continued) 5.12 Insert' control bank D until the reactor is in the hot zero power test range.
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Caution: Ensure pressurizer spray valves are closed prior to starting reactor coolant pumps.
5.13 Restart reactor coolant pumps one at a time as previously de-scribed starting with RCP 2, 1, 3, and then 4.
4 l 5.13 Attach all strip charts, trend data, and T/C maps to this test procedure.
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5.15 Return pressurizer level control to automatic.
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5.16 Remove the block of input logic of safety injection on Hi steam AP in accordance with Appendix D, unless the next test to be per-formed requires the block to be installed. If this is the case, disregard this step, place N/A in the signature line and initial.
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5.17 Remove modification to Hi steam flow coincident with Lo S/G pressure or lo Tav input to safety injection in accordance with Appendix D, unless the next test to be performed requires the modification to be made. If this is the case, disregard this-step, place N/A in the signature line and initial.
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5.18 Remove block of automatic initiation of safety injection in accordance with Appendix D, unless the next test to be per-fonned requires the modification to be made. If this is the case, ' disregard this step, place N/A in the signature line and initial.
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- SQNP SPECIAL TEST 8 Page 11 of 11 Rev. 0 5.0 (Continued) 5.19 Remove the gag from the following UHI isolation valves unless the next test to be performed requires the valves to be gagged. 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 /
5.20 Reset the intermediate and power range high level reactor trip setpoints 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 /
6.0 ACCEPTANCE CRITERIA 6.1 Delta-T established between wide range T hot andT cold is stable and-less than 65"F.
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6.2 Delta-T established between wide range cold and core exit T/C average temperature is stable and less than 65 F.
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SQNP SPECIAL TEST 8-Page 1 of 1 Rev. O APPENDIX A References
- 1. FSAR
- 2. Technical Specifications I
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SQNP SPECIAL TEST 8 Page 1 of 1 Rev. O {
APPENDIX B Test Deficiencies #
Test Deficiency
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Reccmmended Resolution '
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Final Resolution 1 Originatcr /
. Signature Date PORC Review of Final Resolution Date Approval of Final Resolution /
Plant Superintendent Date i
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SQNP SPECIAL TEST 8 Page 1 of 10 i
Rev. O
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APPENDIX C 1
Procedure for Determining Core Power Level 1
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- SQNP SPECIAL TEST 8 Page 2 of 10 Rev. O APPENDIX C 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.
1 B. M/D Power Monitor Program i
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent p wer output; this output must be input to the M/D Power-Monitor Program so that the program output will be in per-cent power and equal to the primary calorimetric output.
- 2. Power Mouitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 5 or 6 detectors. After the i output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to once every 2 minutes ,
, or as necessary to continuously monitor core power.
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. o SQNP
'SPECIAL TEST 8 Page 3 of 10 Rev. O APPENDIX C CORE POWER DETERMINATION PART A: Primary side eclorimetric - Data Sheet C.1 (Forced Circulation)
C.1 Use two DVMs and measure the voltage at the test points speci-fled 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 (Table C-1). (Special Test No. 9 uses wide range AT so a correction factor is required to compensate for pump heating, refer to Appendix D of ST-9A).
C.3 Sum the loop heat rates and convert to a percent reactor power.
The output is used in Part B.
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. SQNP SPECIAL TEST 8 Page 4 of 10 Rev. O APPENDIX C (Continued)
Core Power Determination PART B: M/D Power Monitor Program
- 1. Set up the movable detector system for a 1 pass partial core flux map as per TI-53. Select flux thimbles as per the table below for the flux map.
Drive 10-Path Position Core Location A 10 L-5 B 10 L-11 C 10 E-5 D 10 E-11 E 6 J-8 F 8 P-9 These positions may be altered by the test engineer, based upon low power physics testing results and previous special testing experience.
- 2. Determine the detector normalization constants and enter them into the P-250 as follows:
a) Enter a value of 1.0 into the P-250 for the addresses shown in the tabic 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, 19
SQNP SPECIAL TEST 8 Page 5 of 10
-Rev. O APPENDIX C Core Power Determination PART B: (Continued) c) 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 i K0901 1 Normalization Factor ~I Selects the Modified K5525 1 " Flux Hap Print" Programs K0900 0 Initiated Pass Number Calibration Constant for K0864 Variable (1) M/D Power Monitor (1) Variable: The value entered is a ratio of the Primary Calori-metric Indicated Power (Item B on Data Sheet C.1) to the M/D calculated power (UO906" times the current value entered in (K0864). If no value has been entered into (K0864) enter 0.25.
Item #8 Data Sheet C.1 New (K0864) = Current (K08f4) x (UO906) l 1
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SQNP SPECIAL TEST 8 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 required.
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(1} A F BTU /lbm F lbm/hr 7
556 1.260 3.6448 x 10 7
554 1.255 3.6553 x 10 7
552 1.250 3.6659 x 10 7
550 1.245 3.~765 x 10 7
548 1.240 3.6862 x 10 7
546 1.236 3.6959 x 10 7
544 1.231 3.7057 x 10 542 1.226 3.7155 x 10 7
540 1.221 3.7254 x 10 7
538 1.217 3.7348 x 10 536 1.213 3.7443 x 10 7
534 1.209 3.7538 x 10 7
532 1.206 3.7633 x 10 7
530 1.202 3.7729 x 10 (1)These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia.
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SQNP '
SPECIAL TEST 8 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 (I) F 3 Loop AH = (#2) x Cp (from Table.C.1) BTU /lbm 6
4 Loop RCS Flow (from Table C.1) 10 1bm/hr 0
5 Loop Reactor Power = (#3) x (#4) 10 BTU /hr N
6 Total Reactor Power = (#5) 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307 iMT S % Reactor Power = (#7) x 0.02932 %
(1) Conversion factor for AT obtained from scaling document.
Remarks:
Date By:
Checked By:
SQNP SPECIAL TEST 8 Page 8 of 10 Rev. O APPENDIX C C
- AN* N= N N" N N*
A = B D
- E E E= E E E N = 1.00 3
A N g=A N = AE =
N N B
N = ^N = 'BE =
C'N C N
A N N = N = CE =
Dy N
ti E
N N
N Ny 'E =
N N Definitions:
A'B' N N N,D' N N' N
= Normalized integral from summary map for each detector in a normal path in the .
first pass
^E' E' E,D' E E' E
= Normalized integral from summary map for each detector in an emergency path in the second pass Ng , N , N ' e ector normalizadon factor for each de-B C "D' "E' F tector Remarks:
Data By: Date 23
SQNP SPECIAL TEST 8 Page 9 of 10 Rev. O APPENDIX C Part C: Using Thermocouples The incore thermocouples can be used as an indication of both core flow distribution and power shifts during natural circulation.
Prior to running a thermocouple map or trending the eight quadrant tilts (four center line and four diagonal tilts) the following should be verified:
K0701-K0765 = 1, For the flow mixing factors K5501 = 0, Indicates the measured core 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 a t 1, 2, .. . X 8 seconds or 64 seconds for us.
The thermcouple programs breaks the core down into eight quadrants--
four centerline and four diagonal quadrants (see Figure C-1).
Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot.
The quadrant tilts are inditative of power shif ts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts:
guadrant Addressable Value 1 Ull59 2 U1160 3 Ull61 4 U1162 5 U1151 6 U1152 7 U1153 8 U1154 A Short Form Map should be run periodically or upon request from-the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for obtaining thermocouple maps.
The trend output and Short Form Maps should be attached to this procedure at the end of the test.
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.SQNP SPECIAL TEST 8 Page 10 of 10 ,
Rev. 0 R
APPENDIX C ,
4 i CENTER Lif4E QUARn CR COftE $YPAMETRY Cdd Leas 3 4 N-43 m ,,g m N- -!2 O O l
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SQNP SPECIAL TEST 8 Page 1 of 11 Rev. O APPENDIX D 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 will initiate telling the operator that the condition exists and what the problem is. (2) a reactor trip will take place auto-matically. (3) a safety injection can be initiated manually from the switch in the control room if conditions warrant.
- 1. Install temporary jumpers and temporary alteration control tags to logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.
NOTE: These jumpers will be specially made for this purpose and installed by an instrument mechanic.
R-47 Panel Performed by: /
Verified by: /
R-50 Panel Performed by: /
Verified by: /
Procedure for blocking automatic actuation of a 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 conditions. (This block will also defeat all AP SI alarms).
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51,.
73, 76 are all clear prior to starting blocking procedure.
- 3. Move test trip switch PS-515A in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
CAUTION: In the next step, and all.following steps in which a voltage is being applied to the indicated terminals, ensure the applied voltage is of the same polarity as the terminals. This check should be done for every step that a voltage source is applied.
Failure to apply the correct polarity will ground the rack power supply. (This problem can be avoided if only the hot wire from the voltage source in the rack is applied to the first terminal indicated in each step [the lower numbered terminal] . The 26
SQNP SPECIAL TEST 8 Page 2 of 11 Rev. O APPENDIX D ground will already be made up through the trip switch). The wire on the rack side of the terminal block must be lif ted and taped for the terminal point where the jumper wire is connected The TACF tag will be attached to the bistable switch and the TACF must note the jumper and the lifted wire.
NOTE: Orange "Out of Service" stickers should be placed on all status / alarm windows as the 120V source is connected.
- 4. Lift and tape the wire on the rack side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of.
1-R-7 and verify 1-XX-55-6B/25 is clear.
Performed by: /
Verified by: /
- 5. Move test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 6. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear. .
Performed 'by: /
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. Lif t 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: /
27
SQNP SPECIAL TEST 8 Page 3 of 11 Rev. O APPENDIX D
- 9. ?!ove 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.
Performed by: /
Verified by: , /
- 11. Flove 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. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-8. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/28 is clear.
Performed by: / .
Verified by: /
- 13. 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. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.
Performed by: /
Verified by: /
- 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: /
28
SQNP SPECIAL TEST 8 Page 6 of 11 Rev. O APPENDIX D
- 16. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-11. 'pply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-11 and verify that XX-55-6B/51 is clear.
Performed by: /
Verified by: /
- 17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 18. Lift and tape the wire on the rack side of terminal L-5 in the rear 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 Mgdification to High Steam Flow Coincident with Low S.G. Pressure or Low-Low avg Safety Injection
- 19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be cicared. .
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.
l
- 20. Move test trip switch TS412D in R-2 to the trip position and verify the amber light above the swltch comes on.
Performed by: /
Verified by: /_
I
- 21. -Lift and tape the wire on the rack side of' terminal M-3 in the rear of l 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: /-
Verified by: /
29
SQNP SPECIAL TEST 8 Page 5 of 11 Rev. O APPENDIX D
- 22. Hove test trip switch TS-422D in R-6 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 23. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: /
Verified by: /
- 24. Move test trip switch TS432D in R-10 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 25. Lif t 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 trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 27. Lif t 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-55-6A/30 will clear.
Performed by: /
Verified by: /
T 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.)
30
SQNP SPECIAL TEST 8 Page 6 of 11 Rev. O APPENDIX D
- 28. Move test trip switch FSS12B 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 4 logic required to get a Safety Injection Signal.
i
- 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:
i RACK TEST SWITCH TEMPALT.N}.
R-7 PSS15A /
J R-7 PS515B /
j R-12 PSS16C /
R-12 PS516D /
1
- R-8 PSS25B /
R-8 PS525A /
R-11 PSS26D /
R-11 RS526C /
R-2 TS412D / i R-6 TS422D , /
R-10 TS/32D / l R-13 TS452D /
i R-3 FS512B /
R-3 FS522B /
i
' To return the steamline Delta-P S.I. to normal condition, the following steps
_should be followed.
l 31 r.
- - - -~ , - . --
SQNP SPECIAL TEST 8 Page 7 of 11 Rev. 0 APPENDIX D NOTE: The orange "Out of Service" stickers snould 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. Move test trip switch PS-526C in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/50 are clear.
Performed by: /
Verified by: /
- 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. Move test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/51 are clear.
Performed by: /
Verified by: /
- 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. Hove test trip switch PS-525A in 1 R-8 to the nonnal 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: /
32 i
SQMP SPECIAL TEST 8 Page 8 of 11 Rev. O APPENDIX D a
2
- 38. flove 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.'
2 i
9 Performed by: /
1 Verified by: /
1 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: /
i Verified by: /
i 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.
t 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: /
4 Verified by: / .
i
~
- 42. Hove 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: /
I Verified by: /
- 43. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi i nate wire on L-7.
Performed by: /
Verified by: /
i
- 44. -flove test trip switch PS-515B in 1-R-7 to the normal position and verify
, the amber light and 1-XX-55-6B/27 are clear.
Performed by: /
Verified by: /
1" 33
. . - q. ,
SQNP SPECIAL TEST 8 Page 9 of 11 Rev. 0 4
i APPENDIX D I
- 45. Re ave the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.
Performed by: /
i Verified by: /
} 46. ?!ove test trip switch PS-515A to the normal position and verify the amber light above the switch and 1-XX-55-6B/25 are clear.
t i
Performed by: /
Verified by: /
! NOTE: At this point the steamline Delta-P safety injection is in a normal operating mode.
. To return the high steam flow coincident with low steam generator pressure or low-low ' avg to normal, perform the following steps. '
l
- 47. flove test trip switch FS522B in R-3 to the normal position and verify the amber light goes out and XA-55-6B/s will clear.
t Performed by: /
Verified by: / -
1
~
- 48. flove test trip switch FS512B in R-3 to the normal position and verify l the amber light goes out and XA-55-6B/2 will clear.
Performed by: /
Verified by: /
- 49. ~ Remove the 120-VAC source from terminals ?!-3 and !!-4 in R-13. Retermi-nate wire on fl-3.
Performed by: /
, Verified by: /
- 50. flove test trip switch TS442D in R-13 to the normal pocition and verify the amber light goes out and XA-55-6A/30 will clear.
Performed by: /
Verified by: /
34
SQNP SPECIAL TEST 8.
Page 10 of 11 Rev. O APPENDIX D
- 51. Remove the 120-VAC source from terminals !!-3 and 11-4 in R-10. Retermi-
- nate wire on M-3.
Performed by: /
Verified by: /
j 52. Ifove test trip switch TS432D in R-10 to the normal position and verify the amber light goes out and XA-55-6A/30 will clear.
! Performed by: /
l Verified by: /
l
- 53. Remove the 120-VAC source from terminals M-3 and ?!-4 in R-6. Retermi-nate wire on M-3.
j Performed by: /
Verified by: /
- 54. Flove 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: /
d Verified by: /
- 55. Remove the 120-VAC source from terminals M-3 and t!-4 in R-2. Retermi-nate wire on 11-3.
Performed by: /
Verified by: /
- 56. Ilove test trip switch TS412D in R-2 to the trip position and verify I the amber light comes on and XA-55-6A/30 will clear.
Performed by: /
Verified by: / l
- 1 f
- ~35 l l
- ~ . .. _ . - J
a **
- SQNP SPECIAL TEST 8 Page 11 of 11 Rev. O APPENDIX D
- 57. Remove the Temporary Alteration Tags on the following test trip switches:
RACK TEST SWITCH TEMP ALT. No.
R-7 PSS15A /
R-7 PSS15B /
R-12 PSS16C /
R-12 PSS16D /
R-8 PS525B /
R-8 PS525A /
R-11 PS526D /
R-11 RS526C /
R-2 TS412D /
R-6 TS422D /
R-10 TS432D /
R-13 TS442D /
R-3 F8512B /
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 Performed by: /
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.
36
. .. o SQNP SPECIAL TEST 8 Page 1 of 1 Rev. O APPENDIX E Technical Specifications Exceptions The table below identilles 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.
0 n ne eao *E1 u 8 tUS1c e s 88"A 88 6 e
- d " 4 8 1 3 5 'a AB*~*3 o 8 8 8%JJ Ju e w
.h t .b .h .h e o o oo o MB S w o o E .ti
-u -- a c s c :s:
22
$n333%8a2%3g? c E 2 asanae18aa TECilNICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B I l
Containment III Pressure SI (3.3.2.1) X X X X X X X X X X .
Safety Limits (2.1.1) X X X X X X X X X Ol%T ( 3. 3.1 ) Inoperable because of low flow X X X X X X X X X OTAT (3.3.1) Inoperable because of low flow X X X X X X X X X flinimum temperature (3.1 1.4) X X X X ,
?!oderator temocrature coeiticient (3.1.1.3) X X X X Steamline AP SI (3.3.2.1) bypassed X X X X X X X X X X liigh Steamflow coincident 91 w/ low steamline pressure or low-low avg SI I Reset flow to 0% and ' avg blocked X X X X X X X X X X Reset low steamline pressure X X X I Low pressurizer pressure S1 (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 Ulil (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 1
j ljatteries (3.8.2.3) X X l 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 37 L
.o .. %
SQNP SPECIAL TEST 8 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 Er = 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 Nr = 34 AT = 54 W W W 2% W' 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.
38