ML19323B944
| ML19323B944 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/06/1980 |
| From: | Ballentine J, Maer S, Saputa E TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19323B910 | List: |
| References | |
| PROC-800506-07, NUDOCS 8005140443 | |
| Download: ML19323B944 (50) | |
Text
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y 8005140 G i I '
Sequoyah % clear Plant DISTRIBUTION
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1C Plant Master File Superintendent
__/ u_ Ass is tan t Superintendent (Oper.)
Asiistant Superintendent (Maint.)
Administrative Supervisor I!aintenance Supervisor (M)
Assistant Maintenance Supervisor (M)
Maintenance Supervisor (E)
Assistant Maintenance S'aperviso'r (E)
SPECIAL TEST NO. 4 __llL_ Maintenan m Supervisor (I)
_[lf_ Results Supervisor EFFECT OF STEAM GENERATOR SECONDARY SIDE SL_ Operations Supervisor ISOLATION ON NATURAL CIRCULATION _10 Qualit7 Assurance Supervisor ifealth Physics Supervisor Public Safety Services Supv.
Chief Storekeeper Preop Test Program Coordinator Outage Director Chemical Engineer (Results)
_ Radiochem Laborat.ory Instrumer.t Shop
_f_C_ Reactor Engineer (Results)
Instrument Engineer (Ma i n t. . I)
Mechanical Engineer (Results)
Staff Industrial Engineer (Plt Sys)
Training Center Coordinator PSO - Chickamauga Engrg Unit - SNP Prepared By: E. Saputa _ Public Safety Services - SNP.
Revised By:
_/f__ShiftEngineer'sOffice S. R. Macht __/_ Q Unit Control Room QA&A Rep. - SNP Submitted By: IIcalth Physics Laboratory
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Sup#cvisor IU Nuclr Document Control Unit, 606 EB-C 1U Superintendent, WBNP PORC Review: f/J,jg0 Superintendent, BFNP Datp q Superintendent, BENP J 1U NEll, W9C174C-K Supv., NPilPS ROB, MS Approved By: gk n k QQ NRC-IE:II Sup rin tendent Power Security Officer, 620 CST 2-C
[g I Nuc1r Materials Coord. - 1410 CUBB-C
!!ana ge r , OP-QASA Sta ff Date Approved.~ d '
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1C Resident NRC Inspector - SNP 1C NSRS, 249A llBR-K Technical Support Center X MrH Techn w Al M yao r Rev. No. Date Revised Pag 2 Rev No. Dat e Rc"ised Pages l b b h _.. ~
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The last page of this instruction is Number
SPECIAL TEST NO. 4 EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATION ON NATURAL CIRCULATION 4 -
SQNP SPECIAL TEST 4 Page 1 of 1 Rev. 0 EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATION ON NATURAL CIRCULATION Table of Contents Page Test Description 1 Special Operator Instruction 2 1.0 OBJECTIVES 3 2.0 PREREQUISITES 4 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPMENT 9 5.0 INSTRUCTIONS 10 6.0 ACCEPTANCE CRITERIA 16 APPENDIX A - References 17 APPENDIX B - Deficiencies 18 APPENDIX C - Power Measurement Technique 19 APPENDIX D - Computer Points 29 APPENDIX E - Safeguard Blocking Procedure 33 i
APPENDIX F - Technical Specifications Exceptions 46 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolatica Configurations 47 l
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SQNP SPECIAL TEST 4 Page 1 of 1 Rev. O TEST DESCRIPTION With natural circulation established at ~ 1% rated thermal power and re-duced reactor coolant temperature, steam generators will be isolated sequentially to determine the effect on natural circulation conditions.
Isolation of up to 2 steam generators will be tested if limitations per-mit. Steam generators will then be sequentially returned to service to verify that natural circulation can be reestablished.
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SQNP SPECIAL TEST 4 Page 1 of 1 Rev. O SPECIAL OPERATOR INSTRUCTION kAn dperator initiated safety injection should be performed only for one or more cf the following conditions:
- Reactor Coolant System Subcooling 5 10 Sudden Unexplained Decrease in Pressurizer Level of 10%
or t.o an Indicated Level of 5 10%
Sudden Unexplained Decrease in Any S/G Level to 5 76% Wide Range 5 0% Narrow Range Unexplained Pressurizer Pressure Drop 2 200 PSI Containment Pressere 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*
2 Sudden Unexplained Decrease in Pressurizer Level of 5%
1 or to an Indicated Level of 5 17%
1/3 Excores 2 10%
Any Loop A T > 65 F Tava > 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 4 Page 1 of 14 Rev. 0 ,
1.0 OlUECTIVES 1.1 Determine the effect of steam generator isolation on natural cir-culation conditions.
1.2 /erify that natural circulation can provide sufficient flow to re-move decay heat af ter partial loss of heat sink.
1.3 Verify that natural circulation can be reestablished in primary loops af ter steam generators are returned to service.
1.4 To provide operator training. All operating shifts will perform this test.
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SQNP SPECIAL TEST 4 Page 2 of 14 Rev. 0 2.0 PREREQUISITES 2.1 Reactor is critical and manually controlled at approximately 1%
power. (Power level determined as indicated in Appendix C).
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2.2 All four reactor coolant pumps in operation.
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2.3 l'eactor coolant system pressure is being maintained automatically a t approximately 2000 psig (PIC-68-340A setpoint = 37.5%) and average coolant temperature is being maintained at approximately '
515 F.
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2.4 Steam generator pressure is being maintained at approximately 763 psig using steam dumps in automatic under pressure control.
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2.5 Feedwater to the steam generators will be supplied by the auxiliary feedwater system with flow control in auto. Steam generator levels should be maintained at approximately 33% on narrow range indi-cators.
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2.6 Steam generator chemistry is in a condition that the absolute mini-nium steam generator blowdown can be maintained through the test.
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2.7 The 100 psi steamline differential pressure safety injection bist-ables have been blocked through temporary conditions as specified in Appendix E.
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2.8 Verify the automatic actuation of safety injection has been blocked in accordance with_ Appendix E.
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2.9 Verify the input-logic of safety injection on high steam line AP has been blocked in accordance with Appendix E.
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SQNP SPECIAL TEST 4 Page 3 of 14 Rev. 0 2.0 (Continued) 2.10 VerifytgehighsteamflowcoincidentwithlowS/Gpressureor low-low avg input to safety injection has been modified in accordance with Appendix E.
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2.11 Verify the following UHI isolation valves are gagged.
FCV 21 /
FCV 22 /
FCV 23 /
FCV 24 /
2.12 Verify the bistables supplying the low pressure signal to the high steam flow S.I. logic have been recalibrated in accordance with Appendix E.
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NOTE: This allows cooling down to 450 F without getting a reactor trip.
2.13 Brush recorders have been set up to monitor test points at the following locations:
2.13.1 Recorder No. 1 (6 Channel)
Channel Pa rameter Test Point Rack 1 RCS Flow-Loop 1 FP/414B l-R-1 2 RCS Flow-Loop 2 FP/424B l-R-1 3 RCS Flow-Loop 3 FP/434B l-R-1 4 RCS Flow-Loop 4 FP/444B 1-R-1 5 Pressurizer Pressure PP/455B l-R-1 6 Pressurizer Level LP/459B l-R-1 2.13.2 Recorder No. 2 (6 Channel)
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Channel Parameter Test Point Rack SG 1 Pressure 1 PP/416B l-R-3 2 SG 1 Level LP/501 1-R-23 ,
3 SG 1 Steam Flow FP/512B l-R-3 4 SG 2 Pressure PP/426B l-R-3 i 5 SG 2 Level LP/502 1-R-23 6 SG 2 Steam Flow FP/522B l-R-3 l
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- SQNP SPECIAL TEST 4 Page 4 of 14 Rev. 0 2.0 (Continued) 2.13.3 Recorder No. 3 (6 Channel)
Channel Parameter Test Point Rack 1 SG 3 Pressure PP/436B l-R-4 2 SG 3 Level LP/503 1-R-23 3 SG 3 Steam Flow FP/532B l-R-4 4 SG 4 Pressure PP/446B l-R-4 5 SG 4 Level LP/504 1-R-23 6 SG 4 Steam Flow FP/542B 1-R-4 2.13.4 Recorder No. 4 (4 Channel)
Channel Parameter Test Point Rack 1 SG 1 Aux Feed Flow L-3-163, TP 13 1-L-11B 2 SG 2 Aux Feed Flow L-3-155, TP 13 1-L-llA 3 SG 3 Aux Feed Flow L-3-147, TP 12 1-L-llB 4 SG 4 Aux Feed Flow L-3-170, TP 12 1-L-llA
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NOTE: Record the following on all strip charts:
a) Unit No.
b) Date c) Procedure No.
d) Parameter scale and range c) Chart speed f) Name of person recording data g) Recorder I.D. No.
2.14 Record the following parameters on the reactivity computer recorders-
- a. Flux
- b. Average wide range Teold
- c. Average wide range Thot
- d. Average steam generator pressure i
- c. Reactivity l
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SQNP SPECIAL TEST 4 Page 5 of 14 Rev. 0 2.0 (Continued) 2.15 Set up the P-250 computer trend printer to monitor the following parameters at 1-minute intervals, as specified in Appendix D.
- a. Pressurizer pressure
- b. Pressurizer level
- c. Wide range Tcold (all loops)
- d. Wie'e range Thot (all loops)
- e. Steam generator pressure (all loops)
- f. Steam generator level (all loops)
- g. Power range channels
- h. Additional parameters as determined by the test engineer
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2.16 Trend 4 incore thermocouples as determined by the test engineer on the analog trend recorders in the main control room. It is suggested that these thermocouples be the nottest responding thermocouple in each core quadrant.
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2.17 Control Bank D is at'approximately 160 steps or as specified by the test engineer to permit reactor power increase up to approxi-mately 1% (required control bank D position may be determined during the hot zero power test program).
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2.18 Pressurizer 1cvel control is in automatic, maintaining pressur-izer level at approximately 25%.
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2.19 Normal charging and letdown are in service under automatic control.
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2.20 A determination of the sensitivity <f the NIS to changes in cold has been completed. (Special Test 9A.)
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2.21 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 /
7-
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1 SQNP ,
SPECIAL TEST 4 i Page 6 of 14 l Rev. 0 3.0 PRECAUTIONS 3.1 Do not exceed 5*4 rated thermal power at any time while the test is in progress.
3.2 Abort test if any of the following temperature limits are exceeded.
3.2.1 Core exit temperature of 610 F 3.2.2 AT as indicated by H- C of 65 F 3.2.3 avg of 578 F for any loop 3.3 Maintain reactor coolant pump seal and thermal barrier differen-
- Lial pressure requirements as specified in S0I-68.2.
3.4 Avoid any sudden changes in feedwater flow or steam generator level.
3.5 Ensure seal flow to each reactor coolant pump is maintained at or s?ightly above 4 gpm during the test.
3.6 T Af ter the reactor coolant pumps are tripped, thg normal avg and AT indications will become unreliable. AT and avg should be calcu-lated by taking the difference and the average of the hot and cold leg temperature indications respectively.
3.7 Do not exceed 1600 psi primary to secondary differential pressure limit.
3.8 Maintain reactor coolant system cold leg temperatures as stable as possible during system transients. This is required to deter-mine changes in core power level on the NIS channels.
3.9 When testing with the reactor coolant in the low temperature range of 450 F to 500 F, maintain the lithic concentration at 2.0 to 2.2 ppm, the upper part of the specified lithic range.
This is especially necessary if high boric acid concentrations
(~ 1000 ppm) are also being used.
3.10 Ensure control bank D position remains at > 100 steps. Should this limit be reached during the cooldown, boron concentration will have to be increased.
3.11 Ensure auxiliary spray is in service prior to tripping the reactor coolant pumps. . Spray flow to the pressurizer can be controlled by adjusting charging flow, closing the normal charging path, or opening the normal spray valves af ter the
-RCP's are tripped. -
3.12 Should a reactor trip occur during the conduct of this test, at least one reactor coolant pump (#2) should be started prior to closing the reactor trip breaker.
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SQNP SPECIAL TEST 4
, , Page 7 of 14 Rev. 0 4.0 Special Test Equipment Identification Calibration l Instrument Specification Number Verificatio'n '
Heactivity Computer Westinghouse Brush 260 Recorders Brush 260 or (3) Equivalent Brush 400 Recorder Brush 400 or (1) Equivalent Recorder (1) HP7100B or Equivalent
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l If test instruments are changed during this test, the instrument information must he recorded here and an entry made in the chronological log book ex - l plaining this change.
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.-)NP SPECIAL TEST 4 Page 8 of 14 Rev. 0 5.0 INSTRUCTIONS 5.1 Start brush recorders, analog trend recorders, reactivity computer and P-250 trend blocks.
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5.1.1 Establish auxiliary spray flow to the pressurizer.
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CAUTION: Following reactor coolant pump trip avg and AT indication will be unreliable.
5.2 Simultaneously trip all reactor coolant pumps. Reduce seal water flow to each pump to approximately 4 gpm.
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5.3 Maintain steam genecator Icvel at approximately 33%.
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NOTE: At initiation of natural circulation the following initial response is expected:
- 1. Wide rangeTThot, increase
- 2. Wide range cold, slight increase or constant
- 3. Core exit thermocouples, increase
- 4. Pressurizer level, increase 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 thermo-couple average temperature is constant
- 3. Wide range hot I core exit thermocouple average tempera tu re (See Table 1) 5.4 Adjust setpoint on steam dump pressure controller PIC-1-33 as needed to maintain cold Icg temperatures at the initial values.
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5.5 Adjust setpoints on atmospheric relief valve pressure contrv11ers for each loop to maintain steam pressure below 1025 psig before isolating any steam generators. This should prevent opening of-main steam safety valves.
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SQNP SPECIAL TEST 4 Page 9 of 14 Rev. 0 5.0 (Continued) 5.5.1 Establish maximum maintainable flow through normal letdown path, and manually increase charging flow to maintain a constant RCS water mass. Start an additional centrifugal charging pump if necessary. (Maintain prcas:*rir.er Icvel
~ constant after equilibrium has been reached er. natural circulation).
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CAUTION: Monitor primary to secondary differential pressure very.
closely during the transient and do not allow it to exceed 1500 psi.
NOTE: Allow the pressurizer level to increase when T is V
increased. (Expected increase is approximate 1y f% per F increase in avg).
5.6 Close MSIV FCV-1-22. Isolate feedwater flow and steam generator blowdown (if in service) for steam generator #3. Carefully con-trol feedwater additions to the remaining steam generators to hold the levels at approximately 33%. It may be necessgry to adjust the steam dump pressure controller setpoint to reduce cold in the un-isolated loops so that the steam generator pressure in the isolated loop remains below the setpoint of the atmospheric relief valve.
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NOTE: During this transient the following responses can be expected.
T
- 1. Wide range F t, increase
- 2. Wide rangeTT c Id for Loop 3, increase
- 3. Wide range cold for other loops, held constant using steam dump
- 4. Core exit thermocouples, increase (See Table 1)
- 5. Pressurizer pressure and level, increase 5.7 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop 3 AT is approximately
- zero.
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5.8 Verify that the calculated value for Tavg for the remaining 3 loops has stabilized. _If Tavg continues to increase and cannot be stabilized the test director should determine whether further' testing can be conducted.
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SQNP SPECIAL TEST 4 Page 10 of 14 Rev. 0 5.0 (Continued)
T NOTE: Verify avg is stable prior to conducting the next step.
' CAUTION: Monitor primary to secondary pressure very closely during the transient and do not allow it to exceed 1600 psi.
5.9 Close MSIV FCV-1-29. Isolate feedwater flow and steam generator blowdown (if in service) for steam generator #4. Carefully control feedwater additions to the remaining steam generators to hold the levels at approximately 33%. It may be necegsary to adjust the steam dump pressure controller setpoint to reduce cold in the unisolated loops so that the steam generator pressure in the isolated loops re-main below the setpoint of the atmospheric relief valves.
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NOTE: During this transient, the following responses can be expected:
- 1. Wide range Thot, increase
- 2. Wide range Teold for loops 3 and 4, increase
- 3. Wide range Tcold for loops 1 and 2, held constant using steam dump
- 4. Core exit thermocouples, increase 5.10 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop 4 AT is approximately zero.
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5.11 Verify that the calculated value for Tavg for the remaining 2 loops has stabilized. If Tavg continues to increase and cannot be stabilized, the test director should determine whether further testing can be conducted.
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CAUTION: Monitor primary to secondary pressure very closely during the transient and do not allow it to exceed 1600 psi. If )
equilibrium has not been reached within one-half hour pro- I ceed immediately to the next step. I 5.12 Slowly reduce the setpoint on atmospheric relief valve controller PI: l-31A and allow steam generator #4 pressure to reach approxi-mata equilibrium with steam header pressure. Restore feedwater !
slowly to maintain ~ 33% level.
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SQNP SPECIAL TEST 4 Page 11 of 14 Rev. 0 5.0 (Continued) 5.13 Open first FCV-1-150 and then MSIV FCV-1-29 and close atmospheric relief valve PCV-1-30. Carefully control feedwater addition to steam generators 1, 2, and 4 to maintain steam generator Icvels at approxi-mately 33%. -
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NOTE: During the transient, the following responses can be expected.
- 1. Wide range Thot, decreases
- 2. Wide rangeTT c Id for Loop 4, decrease
- 3. Wide rangeT c Id for Loop 3, no change
- 4. Wide range cold for Loops 1 and 2, ancrease by using steam dump 5.14 Allow natural circulation to stabilize. Steady state should be achieved when the calculated loop AT's for loops 1, 2, and 4 are approximately equal.
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5.15 Slowly reduce the setpoint on atmospheric relief valve controller PIC-1-24A and reduce steam dump to condenser, allowing steam gener-ator #3 to. reach approximate equilibrium with steam header pres-sure of 1005 psig. Restore feedwater slowly to maintain ~ 33%
level.
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5.16 Open first FCV-1-149 and then MS1V FCV-1-22 and close atmospheric .
relief valve PCV-1-23.
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NOTE: During the transient the following responses can be expected.
- 1. Wide rangeTThot, decrease
- 2. Wide rangeT C ldfr1 p 3, decrease
- 3. Wide range cold for loops, 1, 2, and 4, Increase using steam dump 5.17 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop AT's are approximately equal.
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5.18 Stop recording' test' data.
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SQNP SPECIAL TEST 4 Page 12 of 14 Rev. 0 5.0 (Continued) 5.19 Insert control bank D until the reactor is in the hot zero power test range.
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CAUTION: Ensure pressurizer spray controllers are at zero out-put prior to starting the first reactor coolant pump.
5.20 Restart all four reactor coolant pumps in accordance with S0I-68.2 starting with #2 then 1, 3, and 4.
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5.21 Return control of the system to operations.
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5.22 Return the bistables supplying the low pressure signal to the high steam flow S.I. logic to their original setpoints in accordance with Appendix E unless the next test to be performed requires this modification to be made. If this is the case, disregard this step, place N/A in the signature line, and initial.
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5.23RestoreghehighsteamflowcoincidentwithlowS/Gpressureor low-low avg input to safety injection in accordance with Appendix E unless the next test to be performed requires this modification to be made. If this is the case, disregard this step, place N/A in the signature line, and initial.
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5.24 Remove the block of the input logic of safety injection on high steam line AP in accordance with Appendix E unless the next test to be performed requires the block to be intalled. If this is the case, disregard this step, place N/A in the signature line, and initial.
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5.25 Remove the block of automatic actuation of sa G '7 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.
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SQNP SPECIAL TEST 4 Page 13 of 14 Rev. 0 5.0 (Continued) 5.26 Remove the gags from the following UHI isolation valves unless the valves are required to be gagged for the next test. If this is the case, disregard this step, place N/A in the signature line, and initial.
FCV 21 /
FCV 22 /
FCV 23 /
FCV 24 /
5.27 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 /
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SQNP SPECIAL TEST 4 Page 14 of 14 Rev. 0 6.0 ACCEPTANCE CRITERIA 6.1 Core exit thermocouple temperature does not exceed 610 degrees Fahrenheit.
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6.2 AT for any-loop does not exceed 65 degrees Fahrenheit.
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6.3 avg for any loop does not exceed 578 degrees Fahrenheit.
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6.4 Sufficient natural circulation could be maintained in active pri-mary loops to maintain stable temperatures following partial loss of heat sink.
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6.5 Natural circulation could be restored to inactive loops when associated steam generators were returned to service.
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SQNP SPECIAL TEST 4 Page 1 of 1 Rev. O APPENDIX A References
- 1. FSAR
- 2. Technical Specifications
- 3. Plant Operating Instructions SOI 68.2 E0I 5 e
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SQNP SPECIAL TEST 4
, , Page 1 of 1 Rev. O APPENDIX B Test Deficiencies //
Test Deficiency Recommended Resolution Final Resolution Originator /
Signature Date PORC Review of Final Resolution Date Approval of Final Resolution /
Plant Superintendent Date I
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SQNP SPECIAL TEST 4
, , Page 1 of 10 Rev. O APPENDIX C Procedure for Determining Core Power Level W
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SQNP SPECIAL TEST 4 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 tesL) a) Output used to adjust M/D Power Monitor Program's power conversion constant.
B. M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent power 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 Monitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 5 or 6 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to once every 2 minutes or as necessary to continuously monitor core power.
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SQNP SPECIAL TEST 4
- Page 3 of 10 Rev. O APPENDIX C COME POWER DETERMIMTION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation)
C.1 Use two DVMs and measure the volt. ige at the test points speci-fled for each loop as rapid as po::sible.
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 4
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- 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 nonnalization constants and enter them into the P-250 as follows:
a) Enter a value of 1.0 into the P-250 for the addresses shown in the table below.
b) With all 5 path selector switches set to normal, run a flux trace.
c) With all 5 path selector switches set.to Emergency, run a second flux trace.
d) Determine the detector normalization constants from Data Sheet C.2.
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SQNP SPECIAL TEST 4
. . Page 5 of 10 Rev. O APPENDIX C (Continued)
Core Power Determination PART B: (Continued) e) Enter these detector normalization constants into the P-250 as shown in the table below.
Drive P-250 Address A K0908 B K0909 C K0910 D K0911 E K0912 F K0913
- 3. Verify that the P-250 parameters listed in the following table have the proper value and that the P-250 time and date are cur-rent. Update as required.
Address Value Function Set the Power K0901 1 Normalization Factor Selects the Modified K5525 1 " Flux Map 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
~ Calorimetric Indicated Power (Item B on Data Sheet C.1) to the M/D calculated powar (UO906) times the current value entered in (K0864).
If no value has been entered into (K0864) enter 0.25. l Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906)
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SQNP SPECIAL TEST 4 Page 6 of 10 Rev. O APPENDIX C (Continued)
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(I) 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 10 550 1.245 3.6765 x 10 7 548 1.2s0 3.6862 x 10 546 1.236 3.6959 x 10 7 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 7 540 1.221 3.7254 x 10 I 538 1.217 3.7348 x 10 7 536 1.213 3.7443 x 10 534 1.209 3.7538 x 10 7 532 1.206 3.7633 x 10 7 530 7 1.202 3.7729 x 10
(
These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia.
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SQNP SPECIAL TEST 4
' Page 7 of 10 Rev. 0 APPENDIX C (Continued) ,
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 (1) F 3 Loop AH = (#2) x Cp (from Table C.1) BTU /lbm 4 Loop RCS Flow (from Table C.1) 0 10 lbm/hr 6
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 MVI' 8 % Reactor Power = (#7) x 0.02932 ! %
(1)Ccavercion factor for AT obtained from scaling document.
Remarks:
Date By:
Checked By:
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SQNP SPECIAL TEST 4
- Page 8 of 10 Rev. O APPENDIX C (Continued)
A B N= N= C N N N N A - B =
E E E E E E N3 = 1.00 N E =
B N N N = =
C N N
=
11 9= , =
D N =AN = DE =
E E N N N,=AN = "E E =
F-N F N
Definitions:
A,B,C,D,E,F y N N N N N
= Normalized integral from summary map for each detector in a normal path in the first pass A'
E E,C' E E' E' E
=
Normalized integral from summary map for each detector in an emergency path in the second pass N,N,N,N' g elect r n rm lization factor for each detector C D E ' "F '
Remarks:
Data By: Date 26
SQNP SPECIAL TEST 4 Page 9 of 10 Rev. O APPENDIX C (Continued)
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 fqur 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 quadrantse -
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 indicative of power shifts and dhould be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts:
Quadrant Addressable Value 1 Ull59 2 U1160 3 U1161 4 U1162 5 Ull51 6 Ull52 7 Ull53 8 Ull54 A Short Form Map should he 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.
27
=
SQNP SPECIAL TEST 4 Page'10 of 10' Rev. O APPENDIX C (Continued)
CENTER Lir4E OUARTCR-COHE SYMMETRY Cold Lens v 3 4 N-4 3 m 2,o* t/- -l2
- O O
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5 , 2 14 i
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- 2. 4 3 l /
/ ExconE DET ECToriS o %- gv o t/~ 4 / 2 l IJ~ 4A Csid L egs Of AGONAL QUtsHT ER-COHE $YMMETRY 22b" 315*
s ,
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w , ;
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28 --
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SQNP SPECIAL TEST 4 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.
Pa rameter Computer Point Pressurizer Pressure PO480A Pressurizer Level LO480A RCS Loop 1 Hot Leg Temperature T0419A RCS Loop 1 Cold Leg Temperature T0406A RCS Loop 2 Hot Leg Temperature T0439A RCS Loop 2 Cold Leg Temperature T0426A RCS Loop 3 Hot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Hot Leg Temperature T0479A RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressure PO400A Steam Generator 1 Narrow Range Level LO400A Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level LO420A Steam Generator 3 Pressure PO440A Steam Generator 3 Narrow Range Level LO440A 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 29
SQNP SPECIAL TEST 4 Page 2 of 4 Rev. O APPENDIX D (Continued)
The computer trend typewriter will be used to monitor the following computer points. (Additional points may be added as required by the test director).
BLOCK 1 Column Point Column Point Column Point 1 PO480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 PO400A 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 Ilottest T/C from each core Quadrant-5 T0002A 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 fer each data block to be used.
NOTE: A Block Trend Error message will occur if the data block is ini-tially clear.
30
SQNP SPECIAL TEST 4 Page 3 of 4 Rev. O APPENDIX D (Continued)
To set up the data blocks, perform the following series of steps O r 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 Lice the blocks are set up they can be initiated by performing the follow-ing steps for each block.
- 1. Pust LIGITAL 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 TEFND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select C on keyboard
- 5. Push VALUE 3 button
- 6. Push STOP button In addition to the data recorded on the trend typewriter, the following points.will be monitored on analog trend recorded.
T0056A (Core exit temp).
Others as needed (Recommend pressurizer pressure, steam generator level (WR) and steam generator pressure).
31- -- --
SQNP SPECIAL TEST 4
- *' Page 4 of 4 Rev. O APPENDIX D (Continued)
After selecting the per to be used to record a value, ensure that it is cleared by performing the following steps.
- 1. Push ANALOG TREND function button
- 2. Select per number (1 to 12) on 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
- 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the minimum value of the. parameter to be monitored
- 7. Select range on the keyboard
- 8. Push VALUE 3 button
- 9. Push START button Repeat these steps until all of the desired analog points are being recorded.
Prior to initiation of the transient, and required thereafter, incore thermo-couple maps will be recorded at the programmers console in the computer room.
To initiate an incore thermocouple map at that location, perform the following steps.
- 1. Push IN-CORE T/C MAP function button
- 2. Select 25 on keyboard for short-form current map
- 3. Push VALUE 1 button
- 4. Select output device code number 20 for programmers !
console on keyboard.
- 5. Push VALUE 2 button .
- 6. Select 1 on keyboard for a short-form map i
- 7. Push VALUE 3 button l
- 8. Push START button 4
32
=~
V
SQNP SPECIAL TEST 4 Page 1 of 13 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 portion of the protection logic will remain in operation. If conditions exist that would normally initiate a safety injection; (1) the safety injection alarm will initiate telling the operator that the condition exists and what the problem is. (2) a reactor trip will take place automatically. (3) a safety injection can be initiated manually from the switch in the control room if conditions warrant.
- 1. Install temporcry jumpers and temporary alteration control tags to logic cards A216, test point 1, to the logic g.ound 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 stnamline Delta-P. This block will prevent a reactor trip from occuring during the natural circulation tests from high AP caused by degraded test conditions.
(This block will also defeat all AP S.I. alarms.)
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, 73, 76 are all clear prior to starting blocking procedure.
- 3. 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 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 tenninal indicated in each step [the lower numbered terminal]. The 33
SQNP SPECIAL TEST 4
- Page 2 of 13 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 will be attached to the histable 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. Appiy a 120-VAC sotirce to terminals L-9 and L-10 and verify 1-XX-55-6B/25 is clear.
Performed by: /
Verified by: /
- 5. ?!ove 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. Lif t 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 and verify 1-XX-55-6B/27 is clear.
Performed by: /
Verified by: /
- 7. flove test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 8. Lift and tape the wire on the' rack side of terminal L-5 in the rear of 1-R-12. Apply 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/73 is clear.
Performed by: /
Verified by: /
34
SQNP SPECIAL TEST 4 Page 3 of 13 Rev. O APPENDIX E
- 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 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 svitch comes on.
Performed by: /
Verified by: _ /
- 12. Lift and tape the wire on the rack side of terminal L-7 in the rear o f 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. Hove 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: /
l
- 14. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 in the rear of l 1-R-8 and verify that XX-55-6B/26 is clear.
Performed by: /
Verified by: /
35
SQNP SPECIAL TEST 4 Page 4 of 13
- Rev. O APPENDIX E
- 15. Move test trip switch PS-526D in 1-R-11 to the trip-position and verify
'the amber light above the switch comes on.
Performed by: /
Verified by: /
- 16. 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. 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: /
3
- 18. Lift and tape the wire on the rack side of terminal L-5 in the rear of 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is clear.
Performed by: /
i 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 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 th problem corrected.
36
~. -
~.,1
SQNP SPECIAL TEST 4 Page 5 of 13 Rev. O APPENDIX E
- 20. Move test trip switch TS412D in R-2 to the trip position and verify
'the amber light above the switch comes on.
Performed by: /
Verified by: /
^
- 21. Lift and tape the wire on the rack side of terminal M-3 in the rear
- of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
f Performed by: /
Verified by: /
- 22. Move test trip switch TS-422D in F-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.
I 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 in R-10 and verify XA-55-6A/30 will clear.
Performed by: /
Verified by: /
A
'37
.., - .+ _ _
t
SQNP SPECIAL TEST 4
'
- Page 6 of 13 Rev. O APPENDIX E
- 26. Ilove 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 11-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals 11-3 and 11-4 in R-13 and verify XA-55-6A/30 will clear.
Performed by: /
Verified by: /
NOTE: The avg inputs to the high steam flow S.I and steam dump interlock are now blocked. 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).
- 28. flove 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/9 come on.
Performed by: /
Verified by: /
NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal.
38 k .
SQNP SPECIAL TEST 4
'
- Page 7 of 13 Rev. O APPENDIX E
- 30. Apply Temporary Alteration Control Tags forms to all the above test
' trip switches to ensure that they remain in the trip position.
Damage to the histable could occur if the switch is moved back to the normal position. Record the temporary alteration numbers below:
RACK TEST SWITCII TEt!P ALT. NO.
R-7 PSS15A /
R-7 PS515B /
R-12 PS516C /
R-12 PSS16D /
R-8 PS525B /
R-8 PS525A /
R-11 PSS26D /
R-11 RS526C /
R-2 TS412D /
R-6 TS422D /
R-10 TS432D /
R-13 TS442D /
R-3 FSS12B /
R-3 FS522B /
The following step reduces thg setpoint of the S/G pressure input to S.I.
to trip at 350 psig allowing avg to be reduced to 450 F.
- 31. Recalibrate the following bistables to the indicated setpoints and attach Temporary Alteration Control Tags.
Panel Eistable Setpoint R-12 PS-1-5A (PB516A) 350 psig Decreasing (21.66 f1A Loop current)
Performed by: /
Verified by: /
R-11 PS-1-12A (PB526A) 350 psig Decreasing l
.(21.66 ?!A Loop Current)
)
Performed by: / I
\
Verified by: /
39 t.
SQNP SPECIAL TEST 4 Page 8 of 13 Rev. O APPENDlX E R-11 lS -33A (PB536A) 350 psig Decreasing (21.66 MA Loop Current)
Performed by: /
Verified by: /
R-12 PS-1-30A (PB546A) 350 psig Decreasing (21.66 MA Loop Current)
Performed by: /
Verified by: /
NOTE: When calibrating histables, approach the setpoint very slowly 3 to reduce the effect of the lead / lag module in the loop.
/ \ Calibrate one loop at a time and have all loop bistables tripped while calibrating. The same individuals may only calibrate 2 of these instruments. The remaining 2 instru-ments must be calibrated by 2 other inrlividuals.
To return the steamline Delta-P S.I. to norinal condition, the following steps should be followed.
NOTE The orange "out of service" stickers should be removed from the alarm / status window as each bistable is put back in service
- 32. Remove the 120-VAC source from L-5 and L-6 in 1-R-11. 'Reterminate wire on L-5.
Performed by: /
Verified by: /
- 33. Hove test trip switch PS-526C in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/50 are clear.
Performed by: /
Verified by: /
- 34. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire on L-7.
Performed by: /
. Verified by: /
40
SQNP SPECIAL TEST 4 Page 9 of 13 Rev. O APPENDIX E
- 35. ?!ove test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/51 are clear.
Performed by: /
Verified by: /
- 36. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.
Performed by: /
Verified by: /
- 37. t!ove test trip switch PS-525A in 1-R-8 to the normal position and verify the amber light end 1-XX-55-6B/26 are clear.
Performed by: /
Verified by: /
- 38. Remove the 120-VAC source from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.
Performed by: /
Verified by: /
- 39. 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: /
- 40. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. Retermi-nate wire on L-7.
Performed by: /
Verified by: /
- 41. flove test trip switch PS-516D in 1-R-12 to the normal position and verify the amber light. above the switch and 1-XX-55-6D/76 are clear.
Performed by: /
Verified by: /
41
SQNP SPECIAL TEST 4
'
- Page 10 of 13 Rev. O APPENDIX E
- 42. Remove the 120-VAC source from terminals L-5 and L-6 in 1-R-12. Retermi-nate wire on L-5.
Performed by: /
Verified by: /
- 43. 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: /
Verified by: /
- 44. Remove the 120-VAC source from terminals L-7 cud L-8 in 1-R-7. Retermi-nate wire on L-7.
Performed by: /
Verified by: /
- 45. Move test trip switch PS-515B in 1-R-7 to the normal position and verify the amber light and 1-XX-55-6B/27 are clear.
Performed by: /
Verified by: /
- 46. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.
Performed by: /-
Verified by: /
- 47. Move test trip switch PS-515A to the normal position ed 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 returg the high steam flow coincident with low steam generator pressure or low-low avg to normal, perform the following steps.
42
SQNP SPECIAL TEST 4
, , , Page 11 of 13 Rev. O APPENDIX E 48, flove 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: /
- 49. flove test trip switch FS512B in R-3 to the normal position and verify the amber light. goes out and XA-55-6B/2 will clear.
Performed by: /
Verified by: /
- 50. Remove the 120-VAC source from terminals t!-3 and ?!-4 in R-13. Retermi-nate wire on !!-3.
Performed by: /
Verified by: /
- 51. Flove test trip switch TS442D in R-13 to the normal position and verify ~
the amber light goes out and XA-55-6A/30 will clear.
Performed by: /
Verified by: /
- 52. Remove the 120-VAC source from terminals 11-3 and 11-4 in R-10. Retermi-nate wire on fl-3.
Performed by: /
Verified by: /
- 53. !!ove test trip switch TS432D in R 0 to the normal position and verify the amber light goes out and XA-55 oA/30 will clear.
Performed by: /
Verified by: /
- 54. Remove the 120-VAC source from terminals !!-3 and if-4 in R-6. Retermi-nate wire on !!-3.
Performed by: /
Verified by: /
43
SQNP SPECIAL TEST 4
, , , Page 12 of 13 Rev. O APPENDIX E
- 55. 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: /
Verified by: /
- 56. Remove the 120-VAC source from terminals 11-3 and M-4 in R-2. Retermi-nate wire on ?!-3.
Performed by: /
Verified by: /
- 57. ?!ove 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.
Performed by: /
Verified by: /
- 58. Remove the Temporary Alteration Tage on the following test trip switches:
RACK TEST SWITCl! TEFIP ALT. NO.
R-7 PSS15A /
R-7 PS515B /
R-12 PSS16C /
R-12 PSS16D /
R-8 PS525B /
R-8 PS525A /
R-11 PS526D /
R-11 RSS26C /
R-2 TS412D /
R-6 TS422D /
R-10 TS432D /
R-13 TS442D /
R-3 FS512B /
. R-3 FS522B /
44 9
- SQNP SPECIAL TEST 4
' ' ' Page 13 of 13 Rev. O APPENDIX E
- 59. Remove the jumpers and the Temporary Alteration Tags from logic c rds A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.
R-47 Panel Performed by: /
Verified by: /
R-50 Panel Performed by: /
Verified by: , /
The following step should be carried out to return the calibration of the S/G low pressure S.I. bistables to normal.
60 The following bistables should be returned to their normal setpoints indicated on the calibration card for the particular bistable. (30.0 + .2MA)
Remove the temporary alteration control tags af ter the recalibration.
NOTE: These calibrations reo tre 2 IM's per calibration. The same individuals may only (alibrate 2 of the instruments. The other instruments must be calibrated by other individuals.
Panel Bistable Performed By/ Verified By R-12 PS-1-5A (PB516A) /
/
R-11 PS-1-12A (PB526A) /
/
R-11 PS-1-23A (PB536A) /
/
~
R-12 PS-1-30A (PB546A) /
/
NOTE: All reactor safeguard systems modified for the special startup tests are back in a normal configuration at this time.
45
SQNP SPECIAL TEST 4
, , Page 1 of 1 Rev. O APPENDIX F Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily hypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests.
E 5 be E
$U$3 p g S S$*M N$ o 0 d"4833
% t AB*~*3 e 8 8 8%oaJe e e
.n U
b .n U
.h .n U s & B B to e a 0 U dt1%1S8 ee ?
bo aaNit Fo 8 8 o
u 3"mu .ENA 0 o N a$om$ ca m TECilNICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment III Pressure SI_(3.3.2.1) X X X X X X X X X X Safety Limits (2.1.1) X X X X X X X X X OPAT (3.3.1) Inoperable because of low flow X X X X X X X X X ifi'AT (3.3.1FInoperable because of low flow X X X X X X X X X tlinimum temperature (3.1.1.4)
~ X X X X i!oIlerator 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 High Steamflow coincident 91 w/ low steamline pressure or low-low gvg SI
- Reset flow to 07,and ' avg blocked X X X X XX X X X X Reset low steamline pressure X X X Low pressurizer prennure 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.' X X X UllI (3.5.1.2) X X X X X X X X X X AFW (3.7.1.2) X X Diesel Gens. (3.8.1.1) X X A.C. Electrical Boards (3.8.2.1) X X Batteries (3.8.2.3) X X RCS Elowrate (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 Flow Normal Operation (3.4.1.2) X X X X X X X X 46 u
SQNP SPECIAL TEST 4
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- Page 1 of 1 Rev. O TABLE 1 Loop Flow and Core AT for Various Power Levels and Isolation Configurations (Computer Estimates)
I No. of Loops Operating (Nat. Circ.)
Power Level 4 3 2 1
.5% L= 3.7 L= 3.6 L= 4.1 L= 5.2 AT = 10.3 AT = 12.5 AT = 16.4 AT = 26
.75% L= 3.7 L= 4.1 L= 4.7 L= 5.9 AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 1% L= 4.1 "L = 4.5 L= 5.2 L= 6.5 AT = 16.3 AT = 19.8 AT = 26 AT = 41 1.5% L= 4.7 L= 5.2 L= 5.9 L= 7.5 AT = 21.4 AT = 26 AT = 34 AT = 54 2% L= 5.2 L= 5.7 L= 6.5 L= 8.2 l AT = 26 AT = 31.4 AT = 41 AT = 65.4 l
2.5% L= 5.6 L= 6.2 L= 7.1 L= 8.9
_ AT = 30.1 AT = 36.5 AT = 47.1 AT = 75.9 3% L= 5.9 L= 6.5 L= 7.5 "L = 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE: L is % of 97,000 gpm flow through operable loop.
AT = Loop AT in F.
47