ML19323B937
| ML19323B937 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/06/1980 |
| From: | Ballentine J, Maehr S TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19323B910 | List: |
| References | |
| PROC-800506-06, NUDOCS 8005140438 | |
| Download: ML19323B937 (49) | |
Text
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Sequoyah Nuclear Plant DISTRIBUTION
, , 8005140 ', N 1C Plant. Master File Superintendent d IU Assistant Superintendent (Oper.)
Assistant Superintendent. (!!a i n t. . )
Administrative Supcivisor Maintenance Supervisor (M)
Assistant Maintenance Supervisor (?!)
flaintenance Supervisor (E)
Assistant t!aintenance Supervisor (E)
SPECIAL TEST N0. 3 _11L tlaintenance Supervisor (I)
J4(_ Results Supervisor NATURAL CIRCULATION WITil LOSS _/_ll_ operations Supervisor OF PRESSURIZER HEATERS _1U Quality Assurance Supervisor Health Physics Supervisor Public Safety Services Supv.
Chief Storekeeper Preop Tes t. Program Coordina tor Outage Director Chemical Engineer (Results)
Radiochem Laboratory
_ Instrument Shop l C _ Reactor Engineer (Results)
Inst roment Eagineer (Pf a i n t . I)
Mechanical Engineer (Results)
Staff Industrial Engineer (Plt Svs)
Trainin>; Center Coordinator PSO - Chickurmura Engrg Unit - SNP Piep:ir,d Dy. S. R. Machr Public Sa fety Services - SNP
/( Shift Engineer's Office 1:eviwd Dy: S. R. Mnehr f_C_. Uni t Control Room QASA Rep. - SNP Sul.aitted By _ F _J MW llea lt h i hysics Laboratory Supervisor 1U Nuclr Document Control Unit, 606 EB-C 1U Superintendent, WBNP PORC ieview t(3 $D I
___ _ Superintendent, BFNP h' Dat A . Sucerintendent, BCNP M
\ b s 10 NEH, W9C174C-K
\ \ I' 1' Supv., NPliPS ROB, MS Approved By: (Q2Supdintendent fj(QM)dg? NRC-IE:II
.' \ Power Security Officer, 620 CST 2-C
\\ \ Nuclr flaterials Coord. ~ 1410 CUDU-C l
<g Mana ge r, OP-QASA S t.a f f Date Approved: _ _ h3 _)[_h 1 -' IC _ Residet NRC Inspector - SNP
_ IC _ NSRS, 249A HBR-K Technical Support Center
_}_.C__ jdd i1 Te c h n i c .; / Ad v Nte Rev. No. Date Revised Pages. Rev. No. Date Revised Pace 0
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SPECIAL TEST NO. 3 i
2 NATURAL CIRCULATION WITH LOSS OF PRESSURIZER HEATERS
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SQNP SPECIAL TEST 3
. o Page 1 of 1 Rev. O NATUILtL CIRCULATION WITil LOSS OF PRESSURIZER 1[ EATERS Table of Contents Page Test Description 1 Special Operator Instruction 2 l'. 0 OBJECTIVES 3 2.0 PREREQUISITES 4 3.0 PRECAUTIONS 7 4.0 SPECIAL TEST EQUIPMENT 8 5.0 TEST INSTRUC1 IONS 9 6.0 ACCEPTANCE CRITERIt. 13 DATA SilEETS 14 APPENDIX A - References 18 APPENDIX B - Deficiencies 19 APPENDIX.C - Power Measurement Technique 20 '
APPENDIX D - Computer Pcints 30 APPENDIX E - Safeguard Blocking Procedure 34 APPENDIX F - Technical Specifications Exceptions 45 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 46 l
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SQNP SPECIAL TEST 3
. o Page 1 of 1 Rev. 0
, NATURAL CIRCULATION WITH LOSS OF PRESSURIZER HEATERS TEST DESCRIPTION The test will be -Initiated by tripping pressurizer heaters and reactor cool-ant pumps. Establishment of natural circulation will be verified and core exit thermocouples monitored to determine the core flow distribution. System pressure will be monitored to determine the rate of depressurization and,
- prior to reaching saturation, control of the saturation margin will be veri-
. fled through the use of primary system charging flow and secondary system steam flow.
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SQNP SPECIAL TEST 3 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:
Reactor Coolant System Subcooling 5 10 Sudden Unexplained Decrease in Pressurizer Level of 10%
or to an Indicated Level of 5 10%
Sudden Unexplained Decrease in Any S/G Level to 6 76% Wide Range 6 0% Narrow Range Unexplained Pressurizer Pressure Drop 2 200 PSI Containment Pressure Hi - (1.54 psig) Annunciator XA-55-6B Window 6 initiates An operator initiated reactor trip should be performed for any of the following conditions:
Reactor Coolant System Subcocling 5 15 Sudden Unexplained Decrease in Pressurizer Level of 5%
or to an Indicated Level of 6 17%
1/3 Excores 2'10%
Any Loop A T > 65 F Tavt, > 578 F Core Exit Temperature (Highest) > 610 F Any Uncontrolled Rod Movement hSI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
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SQNP
- SPECIAL TEST 3
. o Page 1 of 11 Rev. 0 1.0 OBJECTIVES 1.1 Verify natural circulation conditions can be established in all loops once the RCP's are tripped.
1.2 Verify the ability to maintain natural circulation and saturation margin with the loss of the pressurizer heaters.
1.3 Determine RCS d pressurization rate after the RCP's and pressur-izer heaters are tripped.
1.4 Verify saturation margin can be controlled through the use of
., primary charging flow and secondary steam flow.
- 1.5 To provide operator training, all shifts will perform this test.
, NOTE: Data acquisition does not need to be repeated for multiple test.
4 performances.
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SQNP SPECIAL TEST 3
, , Page 2 of 11 Rev. 0 2.0 PREREQUISITIES 2.1 The reactor is critical at ~ 3% power and under manual control with control bank D at 160 steps or as specified by test engineer.
(Power level determined as indicated in Appendix C.)
~~
Date 2.2 All four reactor coolant pumps in operation.
Date 2.3 Steam generator level maintained at approximately 33% on the narrow range indicators by the auxiliary feedwater system Date 2.4 Pressurizer pressure being maintained at approximately 2235 psig automatically by pressurizer heaters and spray and pressurizer levei at approximately 26-28%.
Date 2.5 RCS temperature (Tavg) approximately 550 F.
Date 2.6 Low Power Physics Test program has been completed to the extent necessary for conduct of this test.
Date 2.7 Steam generator pressure at approximately 1000 psig and being maintained by steam dump to the condenser on pressure control.
(or power-operated relief valves).
Date 4
SQNP SPECIAL TEST 3 Page ? of 11 Rev. L 2.0 PREREQUISITES (Continued) 2.8 Connect recorders to the following test points:
NOTE: Data acquisition steps need not be repeated for multiple test perforcancer,. N/A sign offs for these steps.
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 t-R-1, PP455B Pressurizer Pressure Channel #6 1-R-1, LP459B Pressurizer Level Recorder 2 Connect To: Monitoring:
Channel #1 1-R-23, LP510 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, PPS24B Steam Gen. #2 Pressure Recorder 3 Csnnect To: Monitoring:
Channel #1 1-R-23, LP503 Steam Gen. #3 Level Cnannel #2 1-R-4, FP532B Steam Gen. #3 Steat 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, PP544B Steam Gen. #4 Pressure thannel #6 1-R-4, FP542B Steam Gen. #4 Steam Flow Recorder 4 Connect To: Monitoring:
Channel #1 1-R-18, FP121A RCS Charging Flow Channel #2 1-R-23, FP132 RCS Letdown Flow-Channel #3 1-R-5, PP403A Wide range RCS Press Channel #4 1-R-22, TP454 Press Steam Temp-Channel #5 1-R-20, TP453 Press Liquid Temp Recorder 5 Connect To: Monitoring Channel #1 L-3-163, TP13, 1-L-11B Aux Feed Flos to SG#1 Channel #2 L-3-155, TP13, 1-L-11A Aux Feed F]ow to SG#2 Channt. f3 L-3-147, TP12, 1-L-11B Aux Feed tiow to SG#3 Channel #4 I-3-170, TP12, 1-L-11A Aux Feed flow to SG#4 5
SQNP SPECIAL TEST 3 Page 4 of 11 Rev. 0 2.0 (Continued)
NOTE: Record the following on each strip chart:
a) Unit number b) Date c) Procedure number d) Parameter scale and range e) Chart speed f) Name of data recorder g) Recorder ID number 2.9 Set up the P-250 computer trend printer to monitor the parameters
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indicated in Appendix D.
/
2.10 Record on the p-computer recorder,
- a. Flux
- b. Average wide rangeTTc Id
- c. Average wide range hot
- d. Average steam generator pressure
- c. Reactivity
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2.11 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix E.
/
2.12 Verify the input logic of safety injection on high steam line AP has been blocked in accordance with Appendix E.
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2.13 VerifytgehighsteamflowcoincidentwithLowS/Gpressureor Low-Low avg input to safety injection has been modified in accordance with Appendix E.
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2.14 Verify the following UHI isolation valves are gagged. 1 FCV .87-21 /
FCV 22 /
FCV 23 /
FCV 24 /
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SQNP SPECIAL TEST 3 Page 5 of 11 Rev. 0 2.0 (Continued) 2.25 Intermediate and power range (low setpoint) high level reactor' trip setpoints have been set to 7% in accortance with Appendix C and D of SU-8.5.2.
Power Range __ /
Intermediate Range /
J 3.0 PRECAUTIONS j 3.1 Maintain reactor coolant pump seal and thermal barrier dif feren-tial 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 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 T 3 -T f 65 F.
C 3.3.3 avg Temperature of 578 F.
3.4 When equilibrium has been established after tripping the RCP's, l avoid any sudden changes in feedwater flow or in steam generator '
water level.
i 3.5 After the reactor coolant pumps are tripped the 9ormal Tavg and l
j AT indications will be come unreliable. AT and avg should be cal-culated by taking the difference nd the average of the hot and cold leg temperature indications respectively.
3.6 Maintain saturation margin greater than 20 degrees Fahrenhei' at all times.
3.7 Monitor reactor gower closely whenever adjustments toTcold are s made. Maintain cold above 531 F.
3.8 When RCS pressure drops below 1970 psig, manually block S.I. (set-point at 1870 psig). -If not blocked, the reactor will trip when the setpoint is reached.
3.9 When RCS pressure is dropped belov 1970 psig, isolation valves for the pressurizer PORV's should be closed.
3.10 Should a reactor trip take place during the conduct of this test at least one reactor coolant pump (#2) should be restarted prior to . closing the reactor trip breaker.
3.11 Maintain D bank'at 1 100 steps during the conduct of this test.
j Should this limit be reached boron concentration will have to be l increased.
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SQNP SPECIAL TEST 3 Page 6 of 11 Rev. 0
.4.0 SPECIAL TEST EQUIPPIENT Calibration Instrument Specification Identification Verification Strip Chart Recorder Brush 260 or equivalent (4)
Reactivity Computer Westinghouse 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.
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SQNP SPECIAL TEST 3 Page 7 of 11 Rev. 0 5.0 TEST INSTRUCTIONS NOTE: Data acquisition steps need not be repeated for multiple test pe rfo rmances . N/A signoffs for these steps.
5.1 Ensure the pressurizer backup' heaters IA,1B, and 1C will remain off by moving handswitches 1-HS-68-341A and 341D to 'Stop' posi-tion and moving 1-HS-68-341H to 'Stop-Pull to Lock'.
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5.2 Record the data indicated on Data Sheet 5.1.
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5.3 Start the computer trend printer printing as fast as possible.
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5.4 Shut off the pressurizer control heater group by moving 1-HS-68-341F to 'Stop'.
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5.5 Record the time, on the data recorder charts in the auxiliary instru-ment room and then start them at 125 mm/ min.
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5.6 Shutdown the reactor coolant pumps in accordance with SOI 68.2 (Simultaneously).
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NOTE: At the initiation of natural circulation the following tempera-ture response is expected.
T a) Wide range hot - increase b) Wide range Tcold - slight increase or constant c) goreexitthermocouple-increase d) cyg indication - unreliable-e) Delta-7 indication - unreliable f) Pressurizer level - increase 1
5.7 Verify natural circulation is established by following the opera-tional guidelines given in Appendix A of E0I-5.
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SQNP SPECIAL TEST 3 Page 8 of 11 Rev. 0 5.0 (Continued)
NOTE: Natural circulation will be stable when:
T
- 1) AT between wide range T hot andT cold is constant
- 2) AT between wide range cold and core exit _ thermocouple average temperature is constant
- 3) Wide range hot a core exit thermocouple average tempera-l Lure (See Table 1) 5.7.1 Assume manual control of charging flow and match charging to letdown to maintain a constant RCS water mass. (i.e.
maintain pressurizer level ~ constant af ter equilibrium has been reached on natural cir;ulation.)
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5.8 Once equilibrium has been established adjust trend printer inter-vals as specified by the test director.
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NOTE: The following steps will allow the pressurizer to cool and slowly decrease system pressure. The purpose is to determine the time that saturation margin can be maintained without the use of pres-nurizer heaters and then verify the margin can be reestablished through charging or secondary steam flow. Reactor power level will be reduced to simulate an actual shutdown situation with residual heat.
S.9 The primary system pressure will row be monitored to' determine the rate of depressurization. The saturation margin should be monitored closely on the trend recorder and steam dump or RCS charging flow increased in accordance with AOI-18 when the satu-ration margin appraches 20 F or as specified by test engineer.
Caution: Low pressure S.I. should be blocked as pressure drops below 1970 psig to prevent tripping the reactor.
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5.10 After.the RCP trips, begin slowly reducing reactor power to approximately 1.5% and maintain this power level for the dura-tion of the test. (Reduce power at a rate of ~ 1.5% per hour).
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5.10.1 When RCS pressure drops below 1970 psig, close the isola-tion valves for the pressurizer PORV's by placing their respective handswitches in the 'close' position.
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SQNP SPECIAL TEST 3 Page 9 of 11 Rev. 0 5.0 (Continued) 5.11 Once it is determined by the test director that sufficient data has been recorded to satisfy the requirements of this test or saturation margin approaches 20 F, increase saturation margin i
above 50 F through the use of charging flow and/or steam dump.
Do not allow pressurizer level to go above 70%.
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NOTE: Margin yill increase by either increasing RCS pressure or re-j ducing cold. Charging must be 1 creased to maintain pressurizer level ar.d pressure when reducing9cold.
5.11.1 When RCS pressure is increased above 1970 psig, open the isolation valves for the pressurizer PORV's.
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5.12 Once saturation margin is above 50 F or pressurizer level reaches 70%, reactivate the pressurizer backup heaters selectively to increase RCS pressure back to 2235 psig.
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5.13 Stop the recorders and trend printers and attach the printouts and charts to Data Sheet 5.2.
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5.14 Manually adjust PIC-68-3.40A to 40% output and energize the control heater group by moving 1-HS-68-341F to 'On'. Return PIC-68-340A to ' Auto'.
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NOTE: Maintain RCS pressure at approximately 2235 by using Auxiliary Spray in accordance with SOI 68.3C if necessary.
5.15 Insert control bank D until the reactor is in the hot zero power test range.
/
CAUTION: Ensure pressurizer spray controller are at zero output prior to starting the first reactor coolant pumps.
5.16 Restart all four ' reactor coolant pumps in accordance with SOI-68.2 starting _with RCP #2, 1, 3 and then 4.
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SQNP SPECIAL TEST 3 Page 10 of 11 Rev. 0 5.0 (Continued 5.17 Return the pressurizer heaters to automatic control by moving 1-IIS-68-341A, -341D, and -34111 to the ' Auto' position.
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5.18 Return pressurizer level to approximately 26-28% and then return control to auto.
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5.19 RectoreghehighsteamflowcoincidentwithLowS/Gpressureor Low-Low avg input to safety injection in accordance uith Appendix E unless the next test to be performed requires this modification to be made. If this is the case, disregard this step, place N/A in the signature line, and initial.
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5.20 Remove the block of the input logic of safety injection on high steam Iine AP in accordance with Appendix E unless the next test to be performed requires the block to be installed. If this is the case, disreg,ard this step, place N/A in the signature line, and initial.
/
5.21 Rcmove the block of automatic actuation of safety injection in accordance with Appendix E unless the next test to be performed .
requires the block to be. installed. If this is the case, disre-gard this step, place N/A in the signature line, and initial.
/
5.22 Remove the gags from the following Ulil 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 21 /
FCV 22 /
FCV 23 /
FCV 24 /
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k 9 SQNP 9 SPECIAL TEST 3 4 Page 11 of 11 Rev. 0 5.0 (Continued) 1 5.23 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 per-formed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial.
Power Range /
Intermediate Range /
NOTE: Conditions can now be established for the conduct of the next test.
$ 6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperatures did not exceed 610 F.
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6.2 Delta-T for any loop does not exceed 65 F.
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4 6.3 T avg for anv loop does not exceed 578 F.
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6.4 RCS saturation margin can be controlled through the use of charging and secondary steam flow.
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, 6.5 Natural circulation can be established and maintained without the u:;e of the pressurizer heaters.
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SQNP SPECIAL TEST 3 o
Page 1 of 3 Rev. O DATA SIIEET 5.1 Initial Conditions Unit Date Time Pressurizer Pressure PR-68-340 Psig Pressurizer Level LR-68-339 Red Pen %
ill llot leg terup o
TR-68-1 F
- 1 Cold leg temp o TR-68-18 F
- 2 Ilot leg temp o TR-68-1 F
- 2 Cold leg temp o TR-68-18 F
- 3 Ilot leg temp o TR-68-43 F
- 3 Cold leg temp o TR-68-60 F
- 4 liot leg temp o, TR-68-43 1
- 4 Cold leg temp o TR-68-60 F S.G. #1 Level (narrow range)
LI-3-42 %
S.G. #2 Level-(narrow range)
LI-3-55 %
S.G. #3 Level (narrow range)
LI-3-97 %
S.G. #4 Level (narrow range)
LI-3-110 %
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Recorded By Date 14
SQNP SPECIAL TEST 3 Page 2 of 3 Rev. O DATA SHEET 5.1 (Continued)
Unit Date Time S.G. (11 Level (wide range)
LR-3-43 Pen 1 %
S.G. #2 Level (wide range) -
LR-3-43 Pen 2 %-
S.G. #3 Level (wide range)
LR-3-98 Pen 1 %
S.G. //4 Level (wide range)
LR-3-98 Pen 2 %
S.G. #1 Pressure PI-1-2A Psig 1
S.G. i/2 Pressure PI-1-9A psig
- S.G. //3 Pressure PI-1-20A psig S.G. #4 Pressure PI-1-27A psig S.G. ill Feedwater flow 4
FI-3-35A gpm S.G. !/2 Feedwater flow FI-3-48A gpm S.G. il3 Feedwater flow FI-3-90A gpm S.G. #4 Feedwater flow F1-3-103A gpm S.G. //l 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 j
Recorded By Date 15
SQNP SPECIAL TEST 3
, .. Page 3 of 3 Rev. O DATA SHEET 5.1 (Continued)
Unit Date Time S.G. #4 Steam flow FI-1-28A lbs/hr Loop #1 T-average TI-68-2E o F
Loop //2 T-average o
TI-68-25E F Loop //3 T-average TI-68-44E o F
Loop #4 T-average TI-68-67E o F
Loop ill AT TI-68-2D o F
Loop #2 AT TI-68-25D o F
Loop #3 AT TI-68-44D o F
Loop //4 AT TI-68-67D op (0-100% = 0-55 F AT)
NIS Channel N-41 %
NIS Channel N-42 %
NIS Channel N-43 %
NIS Channel N-44 %
NOTE: Attach Computer Printout of Incore Thermocouple Temperature Map.
Refer to Appendix D for the procedure for printing out of this map.
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Recorded By Date 16-l 1
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SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 0
-DATA SHEET 5.2 Attach copies of the computer trend printout and the brush recorder charts to this page.
From the above data, starting after equilibrium has been reached, calculate the depressurization rate and the pressurizer cooldown rate (liquid temp) and record below.
psig/hr.
Depressurization Rate Pressurizer Cooldown Rate F/hr.
Calculated by /
Reviewed by /
NOTE: A plot of the RCS depressurization rate vs time can be made from the attached data if desired.
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SQNP SPECIAL TEST 3 Page 1 of 1 Rev. O APlEhTIX A References
- 1. FSAR
- 2. Technical Specifications
- 3. Plant Operating Instructions: SOI 68.2, 68.3 E0I 5 AOI 18 18
SQNP SPECIAL TEST 3 Page 1 of 1 Rev. O APPENDIX B Test Deficiencies //
Test Deficiency Reconur. ended Resolution Final Resolution Originator /
Signature Date PORC Revicu of Final Resolution Date Approval of Final Resolution /
Plant Superintendent Date 19 )
SQNP SPECIAL TEST 3 Page 1 of 10 Rev. 0 APPENDIX C Procedure for Determining Core Power Level i
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SQNP SPECIAL TEST 3 Page 2 of 10 Rev. O 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 Powar 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 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 RZF primary calorimetric it will be rerun up to once every 2 minutes ,
or as uccessary to continuously monitor core power.
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SQNP SPECIAL TEST 3 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 (Tablo 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 3 Page 4 of 10
'Rev. O APPENDIX C (Continued)
Core Power Determination PART B: ?!/D Power Monitor Program
- 1. Set up the movabic 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 nay be altered by the test engineer, based upon low power physics testing results and previous special testing experience.
- 2. Determine the detector normalization constants and enter them '
into the P-250 as follows:
a) Enter a value of 1.0 into the P-250 for the addresses shown in the table below.
b) With all 5 path selector switches set to normal, run a flux trace.
c) With all 5 path selector suitches set to Emergency, run a second flux trace.
d) Determine the detector normalization constants from Data Sheet C.2.
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SQNP SPECIAL TEST 3 Page 5 of 10 Rev. O APPENDIX C (Continued)
Core Power Determination l
PART B: (Continued) c) Enter these detector normalization constants into the P-250 as sitown in the table below.
~
Drive P-250 Address i
A K0908 B K0909 C K0910 D K09 '_1 I
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 Vatue Function Set the Power K0901 1 Normalization Factor Selects the Modified K5525 1 " Flux Map Print" programs K0900 0 Initiated Pass Ntunber j Calibration Constant for K0864 - Vzriable(1) M/D Power Monitor
( Variabic: The value entered is a ratio of the Primary i
Calorimetric Indicated Power (Item B on Data
- Sheet C.1) to the M/D calculated power (UO906) 1 times the current value entered in (K0864).
If no value has been entered into (K0864) enter i 0.25.
j Item (18 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906)
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SQNP SPECIAL TEST 3 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( m F BTU /lbm F lbm/hr 556 1.260 3.6448 x 10 554 1.255 3.6553 x 10 7 552 1.250. 3.6659 x 10 7 550 1.245 3.6765 x 10 548 1.240 3.6862 x ?q 7 546 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 10 536 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 3 ,
. Page 7 of 10 Rev. 0 APPENDIX C Data Sheet C.1 Date Time Unit Power Tavg F l
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 - In'ervice (at test point) Volts op 2 Loop AT = (#1) x (1) 3 Loop AH ='(#2) x Cp (from Table C.1) BTU /lbm 6
4 Loop RCS Flow (from Table C.1) 10 1bm/hr 6
g 5 Loop Reactor Power = (#3) x (#4) 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 MWT 8 % Reactor Power = (#7) x 0.02932 % N_
(1) Conversion factor for AT obtained from scaling document.
Remarks:
Date By:
Checked By:
SQNP SPECIAL TEST 3 Page 8 of 10 Rev. 0
-APPENDIX C (Continued)
DATA SIEET C.2 Ag = B y= Cy = Dy = Eg = Fg =
A E= !lE* D - E E= E E E N = 1.00 A
N = NA AE =
N=AIIN B N N N = N A
NB gE
Cd C N
N =AN = CE =
D~ D N N N,=A-r.
N = DE
=
N 'N A
N. = N = EE =
5;a Y N
Definitions:
AN ' "N , Cg , Dg , EN ' N
= Normalized integral from suma:ary niap for each detector in a normal path in the first pass A,D,C' g g
=
NomaHzed intggral from smary map for E e' ' E' E.
each detector in an emergency path in the second pass flg , Ng , N C' D' "E' "F
= Detector normalization factor for each de-tector Remarks:
Data By: Date 27
r ,
SQNP SPECIAL TEST 3 Page 9 of 10 Rev. O APPENDIX C (Continued)
Part 0: Using Thermocouples The incore thermocouples can be used as an indication of both core flow distribution and power shif ts during natural circulatf or.
Prior to running a thermocouple map or trending the eight qu,drant 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 to eight quadrants--
four centerline and four diagonal quadrants ( e Figure C-1).
Quadrants 1-4 can be directly correlated with the excore detectors -
but quadrants 5-8 cannot.
The quadrant tilts are indicative of power shifts and should be trended at approximately a 2-minute frequency. The following ,
addressable values are the quadrant til.ts:
guadran t Addressable Value 1 U1159 2 U1160 3 U1161 4 U1162 5 U1151 o U1152 .
7 U1153 {
8 U1154 1 1
A Short Form Map should be run periodically or upon r uluest from the test engineer as an~ indication of core flow distribution. It should be put on the Utility Typewriter if possibic. The P-250 Operator's Console Reference !!anual provides instructions for obtaining thermocouple maps.
The trend output and Short Form Maps should be attached to this l procedure at the end of the test.
~28 1
~ ~
m- _
SQNP SPECIAL TEST 3 Page 10 of 10 Rev. O APPENDIX C (Cont.inued)
CENTER.Lif4E QUARTER.COf tE SYMMETRY Co!) Leas u 3 4 N-43 m ,,o o
tt- .l.?
t O i *O I
\
r 0 1 2 4 fF4 s o' 4$f[p;
/J.* /..otr "
v I
- 2. a 3 1I
/ E X CO f t E OETEcToas H-41 o vevvl &, !I* AA Cs!d lin.: v i
oi Aco\ t cumiEn ccHE SYF.M1ETRY 2: 5" ais' s ,
N 5
y A.
7
/ \
,/ -
4 ~\g 135 45 l
?t s us c 0\
29 i - _
SQNP SPECIAL TEST 3 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 the plant computer system.
Parameter Computer Point Pressurizer Pressure P0480A Pressurizer Level LO480A RCS Loop 1 Ilot 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 flot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Hot Leg femperature T0479A RCS Loop 4 Cold Leg Temperature T046'4 Steam Generator 1 Pressure P0400A Steam Generator 1 Narrow Range Level LO400A Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level LO420A Steam Generatoc 3 Pressure PO440A l
Steam Generator 3 Narrow Range Level LO440A l
Steam Generator 4 Pressure P0460A Steam Generator 4 Narrow Range Level LO460A Power Range Channel 1 (Quadrant 4) N0049A Power-Range Channel 2 (Quadrant 2) N0050A Power Range Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A Incore Thermocouples T0001A through T0065A~
30 j
O
- SQNP SPECIAL TEST 3 Page 2 of 4 Rev. O APPENDIX D (Continued)
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 Poin_t Column Point Column Point 1 PO480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 P0440A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 P0400A 17 PO460A' 6 T0426A 12 LO400A 18 LO460A BLOCK 2 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A 4 .N0052A 10-13 T0002A Hottest T/C from each core Quadrant 5 14-18 As Required 6 T0013A To initially clear each data block perform the following step for each block to be used.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select 0 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 ini-tially cit:;.
i
)
31.
.~ " '
- ' SQNP SPECIAL TEST 3 Page 3 of 4 Rev. O APPENDIX D (Continued)
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
- 8. Push START button 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 C. Push STOP button 32
. . SQNP SPECIAL TEST 3 Page 4 of 4 Rev. O APPENDIX D (Continued)
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).
Af ter selecting the per to be used to record a value, e".sure that it is cleared by performing the following steps.
I
- 1. Push AEALOG TREND function button 4
- 2. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
- 4. Push STOP button 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 i 5. Push VALUE 1 button
- 6. Select per position on keyboard. Thi. is the minimum value of the parameter to be monitored
-7. Select cange 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 as required thereafter, incore thermocouple maps will be recorded at the programmers console in the computer room. To in!, ite an incore thermocouple map at that location, perform the follow ag 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 z l 33 m _ _ - mm -
n ww
~.
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- SQNP SPECIAL TEST 3 i Page I 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 will initiate telling the operator that the condition exists and what the proolem 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 LP 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 proceuure.
- 3. Hove 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 'nplied 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 34
-~
.,-,o
, . , SQNP SPECIAL TEST 3 Page 2 of 11 Rev. O APPENDIX E
~
ground will already be made up through the trip switch). The wire on the rack side of the terminal block must be lifted and taped for the terminal point where the jumper wire is connected
- The TACF tag vill be attached to the bistable switch and the TACF must note the jumper and the lif ted wire.
NOTE: Orange "Out of Service" stickers should be placed on all status / alarm windows as the 120Y 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: __ /
I Verified by: /
l 5. Hove 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 4
1-R-12 and verify 1-XX-55-6B/73 is clear.
Performed by: /
Verified by: /
l 35 -
.w.. .+.
l
.m.
,,,,,w.-- ,., , - - , , , ,.v..,
' '
- SQNP SPECIAL TEST 3 Page .3 of 11 Rev. O APPENDIX E
- 9. flove test trip switch PS-516D in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 10. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-12. Apply 120-VAC source to terminals L-7 and L-8-in the rear of 1-R-12 and verify 1-XX-55-6B/76.
Performed by: /
Verified by: /
- 11. ?!ove 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. ?!ove 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: /
- 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.
Pe rformed by: /
Verified by: /
1 -
36- - -
, , , SQNP SPECIAL TEST 3 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. Hove 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: /
l Temporary flgdification to Ifigh 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. Move test trip switch TS412D in R-2 to the trip position and verify
- the amber light above the switch comes on.
Performed by: /
Verified by: /
- 21. Lif t and tape the wire on the rack side of terminal M-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify-
.XA-55-6A/30 will clear.
Performed by: /
Verified by: /
i 37
]
- SQNP SPECIAL TEST 3 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 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. 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-55-6A/30 will clear.
Performed by: /
Verified by: /
NOTE: The avg inputs to the high steam flow S.I and steam dump interlock are now blocked. 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.)
38
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- SQNP SPECIAL TEST 3 Page 6 of 11 Rev. O APPENDIX E
- 28. ?!ove 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. flove 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.
- 30. Apply Temporary Alteration Control fags 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 bm: to the normal position. Record the temporary alteration numbers lelow:
RACK TEST SWITCII TEf!P ALT. NO.
5 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 TS412D /
~
R-6 TS422D /
R-10 TS432D /
R-13 TS442D /
H-3 FS512B' /-
R-3 FSS22B / _
To return the steamline Delta-P S.I. to normal condition, the following steps should be followed.
39 u e.
e~ - c#r 5
. n r.
e , , _ , __. g , -,.-
n-n,
- *
- SQNP SPECIAL TEST 3 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 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. Move test trip switch PS-525A in 1-R-8 to the normal position and verify the amber light and 1-XX-55-6B/26 are clear.
Performed by: /
Verified by: / l l
- 37. Remove the 120- GC source from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.
l Performed by: /
Verified by: /
l
'~ _ 40. _
, l
..y
, . . . SQNP SPECIAL TEST 3 Page 8 of 11 Rev. O APPENDIX E
- 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.
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, t!ove 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. ?!ove 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 terminals L-7 and L-8 in 1-R-7. Retermi-nate wire on L-7.
Performed by: /
Verified by: /
- 44. Ifove 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: /
41 m_._
. = m.-.
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- SQNP SPECIAL TEST 3 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.
Perforn.ed by: /
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.
Performed by: /
Verified by: /
NOTE: At this point the steamline Delta-P safety injection is in a normal operating mode.
To return tige high steam flow coincident with low steam generator pressure or low-low avg to normal, perform the following steps.
- 47. ffove 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 FS5;2B in R-3 to the normal position and verify the amber light goes ut and XA-55-6B/2 will clear.
Performed by: /
Verified by: /
- 49. Remove the 120-VAC source from terminals !!-3 and t!-4 in R-13. Retermi-nate wire on M-3.
Performed by: /
Verified by: /
- 50. t!ove 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: /
42
- *
- 51. Remove the 120-VAC source from terminals ?!-3 and tf-4 in R-10. Retermi-nate wire on H-3.
Performed by: /
Verified by: /
- 52. ?!ove test trip switch TS432D in R-10 to the normal position and verify the amber light goes out and XA-55-6A/30 will clesr.
Performed by: / '
Verified by: /
- 53. Remove the 120-VAC source from terminals ?!-3 and 11-4 in R-6. Retermi-nate wire on 11-3.
Performed by: /
Verified by: /
- 54. Ilove 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 11-3 and 11-4 in R-2. Retermi-na te wire on 11-3.
Performed by: /
Verified by: /
- 56. flove test trip switch TS412D in R-2 to the trip position and verify the amber light comes on and XA-55-6A/30 will clear.
l Performed by: / i Verified by: -/
. 1 G
43 i
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E
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- SQNP SPECIAL G r 3 Page 11 of 11 hev. O APPENDIX E
- 57. Remove the Temporary Alteration Tags on the following test trip
' switches:
RACK TEST SWITCif TEMP ALT. NO.
R-7 PSS15A /
R-7 PSS15B /
R-12 PSS16C /
R-12 PSS16D /
R-8 PS525B /
R-8 PSS25A /
R-11 PS526D /
- R-11 RS526C /
R-2 TS412D /
R-6 TS422D /
R-10 TS432D /
R-13 TS442D /
R-3 FS512B /
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: /
h"TE: All reactor safeguard systems modified for the special startup tests are back in a normal configuration at this time.
l
~
l ,
l l t 1 l 44
, .. k SQNP SPECIAL TEST 3 Page 1 of 1 Rev. O APPENDIX l' 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.
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u d O d d d v O O aan am 15 Hm w w m TECflNICAL 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 flinimum temperature (3.1.1.4) X X X X
?!oderator temperature coef ficient (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 Steamilow coincidentgl w/ low steamline pressure or low-low avg SI Reset ilow to 0% and avg blocked X X X X X X X X X X Reset low steamline pressure X X X I.ow gessurizer 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 llHI (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 El ect.rical Boa rds (3.8.2.1) X X Batteries (3.8.2.3) X X RCS Flowrate (3.2.3) X X X X X XX X
. Control Rod Insertion Limits (3.1.3.6)
X X X X X X X Reactor Cooland Loops Normal Operation (3.4.1.2) X X X X X X X X 45 l
eo> SQNP SPECIAL TEST 3 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= 37- 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 1.57, L= 4.7 L= 5.2 "L = 5.9 L= 7.5 AT = 21.4 AT = 26 3T = 34 AT = 54 2% L= 5.2 L= 5.7 L= 6.5 L= 8.2 ar = 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 ST = 36.5 AT = 47.1 AT = 75.9 l l
3% L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 i 1
NOTE: L is % of 97,000 gpu flow through operable loop.
AT = Loop AT in F.
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