ML19323B930
| ML19323B930 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/06/1980 |
| From: | Ballentine J, Lagergran W, Maehr S TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19323B910 | List: |
| References | |
| PROC-800506-03, NUDOCS 8005140430 | |
| Download: ML19323B930 (44) | |
Text
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80051 40 Sequoyah Nuclear Plant DISTRIBUTION
_f C_._ Pl a n t Master File Superintendent
_gg/_ Assistant Superintendent (Oper.)
Assistant Superintendent (Maint.)
Administrat.ive Supervisor
_ _ t!aintenance Supervisor (!!)
Assistant Maintenance Supervisor (M) fla i n t ena n ce Supervisor (E)
Assistant ?laintenance Supervisor (E)
SPECIAL TEST No. 9B
_/ b Maintenance Supervisor (I)
_]p__ Results Supervisor EOR 0" MIXING AND C00LDOUN
__lM Operations Supervisor
_/ W Quality Assurance Supervisor HeaJth Physics Supervisor Public Safety Services Supv.
Chie f Storel:eeper Preop Test Program Coordinator Outage Director Chemical En;;ineer (Results)
Radiochem Laboratory Instrument Shop
_jg Reactor Engineer (Results)
Instrument Engineer (Maint. I)
__ Ilechanical Engineer (Results)
_ _ Staff Industrial Engineer (Plt Svs)
Training Center Coordinator PSO - Chici:amauga Engrg Unit - SNP Prepared By:
W. R. Lagergran Public Safety Services - SNP
_/ L Shift Engineer's Office Revised Dy:
S. R. Maehr
_/_ & Unit Control Roou QAEA Rep. - SNP Submitt ed By:
pqvt/
Ilealth Physics Labora tory g Super
_j h Uncli Document Control Unit, 606 EB-C
.sor JJ', Superintendent, WBNP PORC Revieu g--f, -f c Supe ri n t enden t, BFNP Date Superintendent, BENP
_ g NCR, W9C]74C-K
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Supv., NPHPS ROB, MS hl_Q,kintendentn h [ L L (1,,1_(,
Approved By: __
NRC-IE:II Su Power Security Officer, 620 CST 2-C Nuc]r Materials Coord. - 1410 CUBB-C Manager, OP-QASA Staff m
Date Approved: _[_ _h
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_/G Resident NRC Inspector - SNP j g NSRS, 249A HEU-K 3
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Technica] Support Center
._[C _Sish Te ch nic.4/ Act vb c r Rev. No.
D.i t e Revi:;ed Pages Rev. No.
Date Revised Pager, t
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SPECIAL TEST NO. 9B 1
i BORON MIXING AND C00LDOWN 1
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SQNP SPECIAL TEST 9B Page 1 of 1 Rev. 0 BORON HIXING AND C00LDOWN
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Table of Contents Page Special Operator Instructions 1
Test Description 2
1.0 OBJECTIVES 3
2.0 PREREQUISITES 3
3.0 PRECAUTIONS 7
4.0 SPECIAL TEST EQUIPMENT 9
5.0 INSTRUCTIONS 10 6.0 ACCEPTANCE CRITERIA 14 DATA Sl[EET 1 15 APPENDIX A - References 16 APPENDIX B - Deficiencies 17 APPENDIX C - Core Power Determination 18 APPENDIX D - Safeguard Blocking Procedure 27 APPENDIX E - Technical Specifications Exceptions 40 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 41
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SQNP SPECIAL TEST 9B Page 1 of 1 Rev. O
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SPECIAL OPERATOR INSTRUCTION
- An 6perator initiated saf, sty injection should be performed only for one or more of the following cor.ditions:
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 5 76% Wide Range 5 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 Subcooling 5 15 Sudden Unexplained Decrease in Pressurizer Level of 5%
or to an Indicated Level of 5 17%
1/3 Excores 2 10%
Any Loop A T
> 65 F
.Tavg
> 578 F Core Exit Temperature (Highest)
> 610 F Any Uncontrolled Rod Movement
- SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
1 um
SQNP SPECIAL TEST 9B Page 1 of 1 Rev. O TEST DESCRIPTION This test will demonstrate that the Reactor Ce,' ant System (RCS) can be uniformly borated approximately 100 ppm while in natural circula-tion.
Boron samples will be taken continuously frca the RCS (1 and 3) hot legs and the pressurizer to verify concentration uniformity.
This test will also demonstrate the capability to cool down the RCS on natural circulation using four steam generators.
Cooldown will proceed until the RCS temperature is approximately 450 F.
Auxiliary sprays will be used to provide boron mixing between the PRZR and RCS. This will also demonstrate depressurization capability.
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SQNP SPECIAL TEST 9B Page 1 of 12 i
Rev. O 1.0 OBJECTIVE The purpose of this test is:
'1.1 To borate and verify boron mixing while in natural circulation (NC).
1.2 To demonstrate the capability to cool down and depressurize on natural circulation.
2.0 PREREQUISITES 2.1 The following initial conditions exist:
2.1.1 Reactor Power is at 2% to 3% RTP.
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2.1.2 Natural circulations has been established.
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2.1.3 Steam generators are being fed by the auxiliary feedwater system.
Level is being maintained at approximately 33%.
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2.1.4 Steam generators are steaming via the condenser or atmos-pheric steam dumps.
(Preferred is to condenser for SG pressure equilibrium).
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2.1.5 Pressurizer heaters are being manually operated to main-tain normal ope.ating pressure.
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2.1.6 RCS average cold leg temperature is approximately 547 F.
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2.1.7 Shutdown banks are fully withdrawn and control banks are above their insertion limit.
Rod control system is in manual. The rod height should be sucn that control bank D ends up at ~ 160 steps after the boration is complete.
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SQNP SPECIAL TEST 9B Page 2 of 12 Rev. 0 2.0 PREREQUISITES (Continued) 2.1.8 PRZR level control is being maintained by manually matching charging to letdown with the level at approximately 55%.
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2.2 The RCS and PRZR baron concentrations are within 20 ppm.
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2.3 The CVCS is in a normal at power make up and letdown configura-tion.
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2.4 Sufficient boric acid is available for borating the RCS approxi-mately 100 ppm.
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2.5 Sufficient water is available to provide makeup for the expected cooldown to 450 F.
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2.6 Prior to performing the cooldown portion of this test set up the following test signals on the indicated recorders;-
NOTE: Exact recorder / channel parameter matching is not necessary.
2.6.1 Recorder No. 1 CHANNEL PARAMETER TEST POINT RACK 1
PRZR Pressure PP/455E R1 2
PRZR Level LP/459B R1 3
LPl HL Temp TP/413E' R2 4
LP2 HL Temp
.TP/423E R2 5
LP3 HL Temp TP/433E R2 6
LP4 HL Temp TP/443E R2 4
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SQNP SPECIAL TEST 9B Page 3 of 12 Rev. 0 2.0 PREREQUISITES (Continued) 2.6.2 Recorder No. 2 CHANNEL PARAMETER TEST POINT RACK 1
LPl CL Temp TP/413F R6 2
LP2 CL Temp TP/423F R6 3
LP3 CL Temp TP/433F R6 4
LP4 CLTemp TP/443F R6 5
LPl Flow FP/414B R1 6
LP2 Flow FP/424B R1 2.6.3 Recorder No. 3 CHANNEL PARAMETER TEST POINT RACK 1
LP3 Flow FP/434B R1 2
LP4 Flow FP/444B R1 3
LP1 SG Level LP/519B R5 4
LP2 SG Level LP/529B R1 5
LP3 SG Level LP/539B R1 6
LP4 SG Level LP/549B R5 2.6.4 Recorder No. 4 CHANNEL PARAMETER TEST POINT RACK 1
LP1 SG Press PP/516B R12 2
LP2 SG Press PP/526B Rll 3
LP3 SG Press PP/536B Rll 4
LP4 SG Press PP/546B R12 2.6.5 Recorder No. 5 CHANNEL PARAMETER TEST POINT RACK 1
Aux Fd Flow to SG #1 TP-13 1-L-11B 2
Aux Fd Flow to SG #2 TP-13 1-L-11A 3
Aux Fd Flow to SG #3 TP-12 1-L-11B 4
Aux Fd Flow to SC #4 TP-12 1-L-11A l
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2.6.6 Record the following parameters on the reactivity computer recorders.
- a. ' Flux T
b.
Average wide. range hot c.
Average wide range cold d.
. Average steam generator level Reactivity e.
5 M
SQNP SPECIAL TEST 9B Page 4 of 12 Rev. 0 2.0 PREREQUISITES (Continued) 2.7 Trend the following parameters on the process computer at 5-minute intervals.
Wide range cold legs T0406A T0426A T0446A 70466A Wide range hot legs T0419A T0439A T0459A T0479A Steam Generator Levels LO403A LO423A LO443A L0463A Loop Flow F0400A F0420A F0440A F0460A
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2.8 Special Test 9A has been performed and data is available to correct the excore detectors for T shadowing.
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2.9 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix D.
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2.10 Verify the input logic of safety injection on high steam line AP has been blocked in accordance with Appendix D.
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2.11 Verify tge, high steam flow coincident with lod S/G pressure or low-low avg input to safety injection has been modified in accordance with Appendix D.
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SQNP SPECIAL TEST 9B Page 5 of 12 Rev. 0 2.0 PREREQUISITES (Continued)
.2.12 Verify the following U.H.I. isolation valves are gagged.
FCV-87-21
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FCV-87-22
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FCV-87-23
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FCV-87-24
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2.13 Recalibrate the bistables supplying the low pressure signal to the high steam flow S.I. logic in accordance with Appendix D.
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NOTE: This allows cooling down to 450 F without getting a reactor trip.
2.14 Intermediate and power range high level reactor trip setpoints
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have been set to 7% in accordance with Appendix C and D of SU-8.5.2.
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Power Range
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Intermediate Range
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3.0 PRECAUTIONS, LIMITATIONS, AND ACTIONS 3.1 Do not exceed 5% RTP.
3.2 Abort the test if any of the following temperature limits are exceeded.
3.2.1 610 F for any core outlet temperature.
3.2.2 65 F for any loop AT.
3.2.3 578 F for any loop T average.
3.3 Avoid sudden changes in auxiliary feedwats: riow rate or in steam generator level.
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SQNP SPECIAL TEST 9B Page 6 of 12 Rev. 0 3.0 PRECAUTIONS, LIMITATIONS, AND ACTIONS (Continued) 3.4 Maintain PRZR pressure at approximately 2235 psig.
Care should be taken in pressure control since sprays are through the auxiliary spray flow path.
3.5 During boration use auxiliary spray to provide maximum mixing in the PRZR.
3.6 Caution should be used in maintaining power level below 5% RTP during the cooldown. Flux shadowing of the excore detectors will occur as the temperature in the downcomer of the pressure vessel decreases.
3.7 During the boration hold Teold approximately constant.
3.8 During cooldown maintain control bank D at approximately 160 steps if possible. The excore shadowing correction factor was
-hta'.ned in this configuration.
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 When operating below 525 F, ensure control bank D position re-mains at k 100 steps.
Should this limit be reached during the cooldown, boron concentration will have to be increased.
3.11 Should a reactor trip occur during the conduct of this test at Icast one reactor coolant pump (#2) should be started prior to closing the reactor trip breaker.
3.12 Maintain D bank at 2 100 steps during the conduct of this test.
Should this limit be reached, boron concentration will have to be increased.
3.13 Ensure the differential pressure across the steam. generators remains below 1600 psid.
3.14 Ensure horic acid flow rate is maintained less than 5 gpm to allow the RCS to adequately mix the boron while rods are being withdrawn.
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e SQNP SPECIAL TEST 9B Page 7 of 12 Rev. 0 4.0 SPECIAL TEST EQUIPMENT IDENTIFICATION CALIBRATION INSTRUMENT SPECIFICATION NUMBER VERIFICATION Reactivity Computer Westinghouse and Associated Equipment (4) 6 Recorders Brush 260 or Equivalent 1 Recorder HP 7100B or Equivalent If test instruments are changed during this test, the instrument in-formation must be recorded here and an entry made in the chronological
-log book explaining this change.
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SQNP SPECIAL TEST 9B l
Page 8 of 12 Rev. 0 J
5.0 INSTRUCTIONS 2
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5.1 Boration l
5.1.1 Begin sampling the RCS and PRZR on a ~ 20-minute frequency and record the data on Data Sheet 1.
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5.1.2 Verify that the system is in equilibrium with respect to l
power, RCS temperature, pressure, and boron concentration.
PRZR pressure ~ 2235 + 50 psig S/G pressure ~ 1005 psig RCS - PRZR boron concentration within 20 ppm Successive boron samples within + 10 ppm l
Reactivity is approximately zero and constant i
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5.1.3 Verify that the following parameters are recorded on the reactivity computer recorders: Record all pertinent in-formation on recorders.
a.
1st strip chart recorder
- 1) Reactivity-ii) Flux b.
2nd strip chart recorder i) Average Th wide range j
li) Average Tc wide range
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5.1.4 Energize PRZR heaters and initiate auxiliary sprays. Try to energize all heaters.
Ideally auxiliary sprays should operate continuously to provide. for maximum mixing in the pressurizer. Transfer charging paths.between normal and auxiliary sprays as necessary to provide for optimum pres-sure control and boron concentration'equilization between the RCS and PRZR.
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5.1.5 Initiate boration at approximately 500 pcm/hr via the borate mode.
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SQNP SPECIAL TEST 9B Page 9 of 12 Rev. 0 5.0 INSTRUCTIONS (Continued) 5.1.6 As the boration proceeds withdraw the controlling banks as necessary to maintain flux approximately constant and re-activity approximately zero.
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NOTE: Observe and T. They should remain approximately C
h constant gg,)
5.1.7 Terminate boration after s 100 ppm increase in RCS baron concentration at the end of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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5.1.8 Continue sampling until the boron concentration stabilizes and the system is again in equilibrium, as defined above.
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f 5.2 Cooldown NOTE: Perform SI-38, SI-48, and SI-127, periodically during the cooldown.
5.2.1 Verify that the CVCS will provide auto makeup.
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NOTE: Depending on rod position and the magnitude and polarity of the isothermal temperature coefficient dilution and/or boration may be required.
5.2.2 Verify that'the system is in equilibrium with respect to power, RCS temperature, pressure and boron concentration.
PRZR pressure 2235 + 50 psig S/G pressure ~ 1005 psig RCS - PRZR boron concentration within 20 ppm Successive boron samples within' 10 ppm Reactivity is approximately zero and constant
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7 SQNP SPECIAL TEST 9B Page 10 of 12 Rev. 0 5.0 INSTRUCTIONS (Continued) 5.2.3. Start the test recorders on slow speed (Smm/ min). Record on the charts the date, time, recorder ID, parameters mea-sured, incasurement range, charts speed, test being performed and name of person recording data.
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5.2.4 Start process computer trend block.
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5.2.5 Obtain a thermocouple map and repeat every 10 F during cooldown.
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5.2.6 Before cooldown is initiated read the following statement.
Cooldown should be initiated as slow as possible to prevent possible adverse steam generator water i
level fluctions.
When the unit operator feels comfortable with the SG 1evels the cooldown rate may be increased.
l 5.2.7 Initiate the cooldown by slowly increasing the rate of steam dump and proceed to approximately 450 F core inlet temperature.
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NOTE: Allow RCS pressure to decrease with the cooldown to maintain steam generator 6P less than 1600 psid. Pressure can be controlled using auxiliary spray and pressurizer heaters.
5.2.8 Use.the control' rods as necessary to maintain core power approximately constant. Refer to Appendix C for power indication.
Control bank D should be maintained at ap-proximately 160 steps if possible.
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. CAUTION: As the cold leg. temperatures decrease the excore detectors-will not be dependable because of neutron shadowing.
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SQNP SPECIAL TEST 9B Page 11 of 12 Rev. 0 5.0 INSTRUCTIOFS (Continued) 5.2.9 Upon reaching approximately 450 F terminate the cooldown.
The test is completed; turn off the recorders and terminate the trend blocks. Attach strip chart, recorder traces, and P-250 output to this test.
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5.2.10 Insert control rods until the reactor is subcritical.
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Caution:
Ensure the pressurizer spray valves are closed prior to starting the reactor coolant pumps.
5.2.11 Restart all four reactor coolant pumps in accordance with S0168.2 starting with RCP //2,1, 3 and then 4.
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5.2.12 Allow primary system to heat up to ~ 547 F.
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5.2.13 Return the bistables supplying the low pressure signal to the high steam flow S. I. logic to their original setpoints in accordance with Appendix D 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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5.2.14 Restore the high stegm flow coincident with low S/G pressure or low-low avg input to safety injection in accordance with Appendix D 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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SQNP SPECIAL TEST 9B Page 12 of 12 Rev. 0 5.0 INSTRUCTIONS (Continued) 5.2.15 Remove the block of the input logic of safety injection on high steam line AP in accordance with Appendix D un-less the next test to be performed requires the block to be installed.
If this is the case, disregard this step, place N/A in the signature line, and initial.
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5.2.16 Remove the block of automatic actuation of safety injec-tion in accordance with Appendix D unless the next test to be performed requires the block to be installed.
If this is the case, disregard this step, place N/A in the signature line, and initial.
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5.2.17 Remove the gags from the following U.H.I. 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-87-21
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FCV-87-22
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FCV-87-23
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FCV-87-24
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5.2.18 Reset the intermediate and power range high level reactor trip setpoints as indicated by the test engineer in accord-ance with Appendix C and D of SU-8.5.2 unlessL the next test to be performed requires this adjustment.
If this is the case, disregard this step, place N/A in the signadure line, and initial.
Power Range
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Intermediate Range
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6.0_EACCEPTANCE CRITERIA
' he RCS can be borated and the boron uniformly mixed in natural 6.1 T
circulation.
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6.2 The RCS can be cooled.down to approximately 450 F on natural circulation.
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SQNP i
SPECIAL TEST 9B l
Page 1 of 1 i
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DATA SIIEET 1 Time (tlin)
Boron Concentration (PPM) 0 20 i
40 60 80 I
100 i
120 1
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SQNP SPECIAL TEST 9B l
Page 1 of 1 l
Rev. 0 APPENDIX A References 1.
FSAR 2.
Technical Specifications e
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SQNP SPECIAL TEST 9B Page 1 of 1 Rev. 0 APPENDIX B Test Decificiencies #
Test Deficiency Recommended Resolution Final Resolution Originator
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Signature D' ate PORC Review of Final Resolution Date Approval of Final Resoltuion
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Plant Superintendent Date 17
SQNP SPECIAL TEST 9B Page 1 of 9 Rev. O APPENDIX C Procedure for Determining Core Power Level i) l l
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SQNP SPECIAL TEST 9B Page 2 of 9 Rev. O APPEhDIX C Outline I.
Core Power Determination A.
Excore detector output correction factor plots.
1.
The-plots obtained in Special Test 9A should be used to correct the excore detector outputs for changes in the core inlet tem-peratures.
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 acen 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 9B Page 3 of 9 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 hT; multiply that WT by the specific heat and I
the k'estinghouse best estimate flow cate of the core average temperature (Table C-1).
(Special Test No. 9 uses wide range WT so a correction factor is required to compensate for pump I
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 9B Page 4 of 9 Rev. O APPENDIX C Core Power Determination PART B: M/D Power Monitor Program L.
Set up the movable detector system for a 1 pass partial core flux map as per TI-53.
Select flux thimbles as per the table below for the flux map.
Drive 10-Path Position Core Location A
10 L-5 B
10 L-11 C
10 E-5 D
10 E-11 E
6 J-8 F
8 P-9 These positions may be altered by the test engineer, based upon low power physics testing results and previous special testing experience.
2.
Determine the detector normalization constants and enter them into the P-250 as follows:
a) Enter a value of 1.0 into the P-250 for the addresses shown in the table below.
b) With all 3 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 9B Page 5 of 9 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 indivi-dual detector normalized integrals are also printed.
TABLE C-1 Temp Cp(1) m F
BTU /lbm F lbm/hr 7
556 1.260 3.6448 x 10 7
554 1.255 3.6553 x 10 7
552 1.250 3.6659 x 10 7
550 1.245 3.6765 x 10 7
548 1.240 3.6862 x 10 346 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 3.734h x 10 7
536 1 213 3.7443 x 10 7
534 1.209 3.7,538 x 10 7
532 1.206 3.7633 x 10 530 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,9B Page 6 of 9 Rev. 0 APPENDIX C Data Sheet C.1 Date Time Unit
_ Power Tavg F
Loop 1 Loop 2 Loop 3 Loop 4 Itea #
Calculation Procedure Units R2/TP-411J R6/TP-421J R10/RP-431J R13/RP-441J 1
Loop AT - Inservice (at test point)
Volts Loop AT = (#1) x-(1) 2 F
3 Loop AH = (#2) x Cp (from Table C.1)
BTU /lbm 6
4 Loop RCS Flow (from Table C.1) 10 1bm/hr 6
j 5
Loop Reactor Power = (#3) x (#4) 10 BTU /hr Total Reactor Power = (#5) 6 6
Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7
Reactor Power = (#6) x 0.29307 WI N
x_
x 8
% Reactor Power = (#7) x 0.02932
( ) Conversion factor for AT obtained from scaling document.
Remarks:
Date By:
Checked By:
N
SQNP r
SPECIAL TEST 9B Page 7 of 9 Rev. 0 APPENDIX C DATA SHEET C.2 t
A,7 =
11N N=
D F
N*
N N*
A D =
C =
D =
E E
E E
E=
F =
E l
N3 = 1.00 g=h NA N
=
AE
=
0 N
N A
N N = N
=
BE
=
l C
g-C N
N N
I
=
E
=
D D
DN N
=fN ND N
=
=
g E
N N
A NE N
N
=
EE
=
Y = f~
1 y
N N
i Definitions:
]
A, II y
N' N'
N' N, FN.=
Normalized integral from summary map - for each q
detector in a normal path in the first pass A'U,C' E
E E
E' E, FE Normalized integral from summary map for each
=
detector in an emergency path in the second pass N, N, N ' "D' "E, Np g_
g_C Detector normalization factor for each detector
=
Remarks:
3 Data By:
Date 24 n
g
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SQNP SPECIAL TEST 9B Page 8 of 9 Rev. 0 APPENDIX C PART C: Using Thermocouples The incore thermocouples can be used as an indication of both core flow distribution and power shifts during natural circulation.
Prior to running a thermocouple map or trending the eight quadrant tilts (four center line and four diagonal tilts) the following should be verified:
K0701-K0765 = 1, For the flow mixing factors K5501 = 0, Indicates the measured core WT 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 runn-ing frequency of the Thermcouple Averaging Program a t 1, 2, X 8 seconds or 64 seconds for us.
The thermcouple programs breaks the core down into eight quadrants--
four centerline and four diagonal quadrants (see Figure C-1).
Quad-rants 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 tilts:
Quadrant Addressable Value 1
Ull59 2
Ull60 3
Ull61 4
U1162 5
U1151 6
Ull52 7
Ull53 8
U1154 A Short Form Map should be run periodically or upon request from the test engineer as an indication of core flow distribution.
It should be put on the Utility Typewriter if pass'ible. The P-250 Operator's - Console Reference Manual provides instructions for ob-taining thermocouple maps.
The trend output and Short Form Maps should be attached to this procedure at the end of the test.
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SQNP SPECIAL TEST 9B Page 9 of 9 Rev. O APPENDIX C CEf4TER tJf4E OUARTER CORE SYMtAETRY Cold Leas e
3 4
M-0 3 A 270* O I!~
O.
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EXCORE DETECTORS ovavo W-41 2
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OI AGON AL QUART ER-CORE SYMMETRY 226" 315 N
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6 SQNP SPECIAL TEST 9B Page 1 of 13 Rev. O APPENDIX D Safeguard Blocking Procedure The first step blocks automatic initiation of a safety injection.
The safety injection alarm, manual S.I handswitch, and the reactor trip 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 temporary jumpers and temporary alteration control tags to logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.
NOTE: These jumpers will be specially made for this purpose and installed by an instrument mechanic.
R-47 Panel Performed by:
/
Verified by:
/
R-50 Panel Performed by:
/
Verified by:
/
Procedure for blocking automatic actuation of a safety injection on high steamline Delta-P.
This block will prevent a reactor trip from occuring during the natural circulation tests from high AP caused by degraded test conditions.
(This block will also defeat all AP 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.
Move test trip switch PS-515A in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by:
/
Verified by:
/
CAUTION:
In the next step, and all following steps in which a voltage is being applied to the indicated terminals, ensure the applied voltage is of the same polarity as the terminals. This check should be done for every step that a voltage' source is applied.
Failure to apply the correct polarity will ground the rack power supply.
(This problem can be avoided if only the hot wire from the voltage source in the rack is applied to the first terminal _
indicated in each step [the lower numbered terminal). The 27
SQNP SPECIAL TEST 9B Page 2 of 13 Rev. 0 APPENDIX D 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 bistable switch and the TACF must note the jumper and the lifted wire.
NOTE Orange "out of service" stickers should be placed on all status /
alarm windows as the 120V source is connected.
4.
Lift 79d 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 and verify 1-XX-55-6B/25 is clear.
Performed by:
/
Verified by:
/
5.
Move test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by:
/
Verified by:
/
6.
Lift and tape the wire on the rack side of terminal L-7 in the rear o f 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.
Move tec+. 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:
28
SQNP SPECIAL IFc'. 9B Page '
13 Rev. O APPENDIX D 9.
Move test trip switch PS-516D in 1-R-12 to the trip position and
.fy
'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.
Move test trip switch PS-525B in 1-R-8 to trip position and verify the amber light above the switch comes on.
Performed by:
/
Verified by:
/
12.
Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-8.
Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/28 is clear.
Performed by:
/
Verified by:
/
13.
Move test trip switch PS-525A in 1-R-8 to the trip position and verify the amber light above the switch comes on.
Performed by:
/
Verified by:
/
14.
Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8.
Appiy 120-VAC source to terminals L-9 and L-10 in the rear of.
1-R-8 and verify that XX-55-6B/26 is clear.
Performed by:
/
Verified by:
/
29
SQNP SPECIAL TEST 9B Page 4 of 13 Rev. O APPENDIX D 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 i
of 1-R-11 and verify that XY-55-6B/51 is clear.
Performed by:
/
Verified by:
/
17.
Move test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by:
/
Verified by:
/
18.
Lift and tape the wire on the rack side of terminal L-5 in the rear 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:
/
Verified by:
/
Temporary Ugdification 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:
/
If thie alarms will not clear, do not. proceed with this modifica-NOTE:
tion as a reactor trip may result. The input bistables should be checked and the source of the-problem corrected.
30
SQNP SPECIAL TEST 9B Page 5 of 13 Rev. 0 APPENDIX D 20.
Move test trip switch TS412D in R-2 to the trip position and verify j
the amber light above the switch comes on.
4 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 H-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by:
/
3 Verified by:
/
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:
/
i 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 in R-10 and verify XA-55-6A/30 will clear.
Performed by:
/
Verified by:
/-
1 I
.31
SQNP SPECIAL TEST 9B Page 6 of 13 Rev. O APPENDIX D 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 o f 1-R-13.
Apply a 120-VAC source to terminals M-3 and M-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.
Move test trip switch FS512B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/2 come on.
Performed by:
/
Verified by:
/
29.
Move test trip switch FSS22B 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.
32 1
SQNP SPECIAL TEST 9B Page 7 of 13 Rev. O APPENDIX D 30.
Apply Temporary Alteration Control Tags forms to all the above test
' trip switches to ensure that they remain in the trip position.
Damage to the bistable could occur if the switch is moved back to the normal position. Record the temporary alteration numbers below:
RACK TEST SWITClf TEMP ALT. NO.
R-7 PS515A
/
R-7 PSS15B
/
R-12 PS516C
/
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 FSS22B
/
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 histables to the indicated setpoints and attach Temporary Alteration Control Tags.
Panel Distable Setpoint R-12 PS-1-5A (PB516A) 350 psig Decreasing (21.661Uk Loop Current)
Performed by:
/
Verified by:
/
R-11 PS-1-12A (PB526A) 350 psig Decreasing (21.66 MA Loop Current)
~
Performed by:
/
Verified by:
/
33
SQNP SPECIAL TEST 9B Page 8 of 13 Rev. O APPENDIX D R-11 PS-1-23A (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 bistables, approach the setpoint very slowly 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 individuals.
To return the steamline Delta-P S.I. to normal 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.
Move test trip switch PS-526C in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/50 are clear.
Performed by:
/
Verified by:
/
34.
Remove the 120-VAC source from L-7 and L-8 in 1-h-11.
Reterminate wi.re on L-7.
Performed by:
/
Verified by:
/
34
SQNP SPECIAL TEST 9B Page 9 of 13 Rev. O APPENDIX D 35.
Move test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-Yl-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.
Ilove 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:
/
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.
Move 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-55-6B/76'are clear.
Performed by:
/
Verified by:
/
35 i
SQNP SPECIAL TEST 9B Page 10 of 13 Rev. O APPENDlX D 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.
!!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:
/
- 44. 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:
/
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.
!!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 retury the high steam flow coincident with low steam generator pressure or low-low avg to normal, perform the following steps.
36
SQNP SPECIAL TEST 9B Page 11 of 13 Rev. O
~
\\
APPENDIX D 48.
Mc-test trip switch FS522B in R-3 to the normal position and verify
't!
amber light goes out and XA-55-6B/9 will clear.
Performed by:
/
Verified by:
/
i 49.
Move 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 M-3 and M-4 in R-13.
Retermi-nate wire on M-3.
Performed by:
/
Verified by:
/
51.
Move test trip switch TS442D in R-13 to the normal position and verify the amber light goes out and XA-55-6A/30 will clear.
Performed by:
/
Verified by:
/
{
52.
Remove the 120-VAC source from terminals M-3 and M-4 in R-10.
Retermi-nate wire on M-3.
Performed by:
/
Verified by:
/
- 53. Move test trip switch TS432D in R-10 to the normal position and verify the amber light goes out and XA-55-6A/30 will clear.
4 Performed by:
/
Verified by:
/
- 54. Remove the 120-VAC source from terminals M-3 and M-4 in R-6.
Retermi-nate wire on M,3.
Performed by:
/
Verified by:
/
37
SQNP SPECIAL TEST 9B Page 12 of 13 Rev. 0 APPENDIX D 55.
Move test trip switch TS442D in R-6 to the normal position and verify the amber light goes out and XA-55-6A/30 will clear.
Performed by:
/
Verified by:
/
56.
Remove the 120-VAC source from terminals M-3 and M-4 in R-2.
Retermi-nate wire on M-3.
' Performed by:
/
Verified by:
/
57.
Nove 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 SWITCH TEMP ALT. NO.
R-7 PSS15A
/
R-7 PS515B
/
R-12 PS516C
/
R-12 PS516D
/
R-8 PSS25B
/
R-8 PSS25A
/
R-11 PSS26D.
/
R-11 RSS26C
/
R-2 TS412D
/
R-6 TS422D
/
R-10 TS432D
/
R-13.
TS442D
/
R-3 FSS12B
/
R-3 FS522B
/
38
SQNP SPECIAL TEST 9B Page 13 of 13 Rev. O APPENDIX D 59.
Remove the jumpers and the Temporary Alteration Tags from logic cards l
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:
/
t 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 after the recalibration.
NOTE: These calibrations require 2 IM's per calibration. The same individuals may only calibrate 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.
l 1
9 39
SQNP SPECIAL TEST 9B Page 1 of 1 Rev. O APPENDIX E Technical Specifications Exceptions The t'able below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests.
e 2
e Me %t 8
n tU3?n 9
e 88"388 8
e a"
8t3 3
9 A3*~*3 8
8 o
8taJ de 8
o w
dDddd8 M
B S
O O O O O H
,j Q Q H % H H H C
% C Z
c3 O d d d ar4 O d C
a 4
O t8%tt"33 8
8
=a a a n 6m m m m
TECIINICAL 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 OTAT (3.3.1) Inoperable because of low flow X X X X X X X X
X.
Minimum temperature (3.1.1.4)
X X
X X
!!oderator temperature coefficient (3.1.1.3)
X X
X X
Steamline AP SI (3.3.2.1) bypassed X X X X X X X X X
X liigh Steamflow coincidentgl w/ low steamline pressure or low-low 9vgSI Reset flow to 0% and avg blocked X X X X X X X X X
X
!!ese t low steamline pressure X
X X
, Low pressurizer pressure SI (3.3.2.1)
X X.X X X X X X X
X SG 1evel low AFW start reset (3.3.2.1)
X X
Pressurizer (3.4.4)
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 Flowrate (3.2.3)
X X X X X X X X
Control Rod Insertion Limits (3.1.3.6)
X X X X X X X Reactor Coolant Loops Normal Operation (3.4.1.2)
X X X X X X X X
40
SQNP SPECIAL TEST 9B Page 1 of 1 Rev. O TABLE 1 Loop Flow and Core AT for Various Power Levels and Isolation Configurations (Computer Estimates)
No. of Loops Operating (Nat. Circ.)
Power Level 4
3 2
1
.5%
L=
3.7 L=
3.6 L=
4.1 L=
5.2 AT = 10.3 AT = 12.5 AT = 16.4 AT = 26
.75%
L=
3.7 L=
4.1 L=
4.7 L=
5.9 AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 1%
L=
4.1 L=
4.5 L=
5.2 L=
6.5 AT = 16.3 AT = 19.8 AT = 26 AT = 41 1.5%
L=
4.7 L=
5.2 L=
5.9 L=
7.5 AT = 21.4 AT = 26 AT = 34 AT = 54 2%
L=
5.2 L=
5.7 L=
6.5 L=
8.2 AT = 26 AT = 31.4 AT = 41 AT = 65.4 2.5%
L=
5.6 L=
6.2 L=
7.1 L=
8.9 AT = 30.1 AT = 36.5 AT = 47.1 AT = 75.9 3%
L=
5.9 L=
6.5 L=
7.5 L=
9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE:
L is % of 97,000 glm flow through operable loop.
AT = Loop AT in F.
41
.