ML19323B945

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Special Test Number 5, Natural Circulation at Reduced Pressure.
ML19323B945
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/06/1980
From: Ballentine J, Maehr S
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19323B910 List:
References
PROC-800506-08, NUDOCS 8005140444
Download: ML19323B945 (51)
v • d • e


Text

,

Se<provah Nucicar Plant OL e +

DISTRIDUTION B 005140 i IC Plant !! aster File Superintendent a gg_ Assistant Superintendent. (Oper.)

Assistant Superintendent (Maint.)

,_____ Administrative Supervisor Maintenance Supervisor (II)

Assistant Maintenance Supervisor (M)

Maintenance Supervisor (E)

Assistant ifaintenance Supervisor (E)

SPECIAL TEST NO. 5 l L Maintenance Supervisor (I)

_[(i_ Results Supervisor NATURAL CIRCULATION AT - l U- Opera tions Supervisor REDUCED PRESSURE in Quality Assurance Supervisor Health Physics Supervisor Public Safety Services Supv.

Chie f St orcheeper Preop Test Program Coordinator Outage Director Chemical Engineer (Results)

Radiochem Laboratory Instrument Shop

_/C___ Reactor Engineer (Results)

Instrument Engineer (Maint. I)

_ Mechanical Engineer (Results)

Staff Industrial Engineer (Plt Sys)

Training Center Coordinat.or PSO - Chickamauga Ennrg Unit - SNP Prepared Hy: S. R. Machr Public Safety Services - SNP

_]f._ Shift Engineer's Office Revised By: S. R. Machr

_] A Unit Control Room QASA Rep. - SNP Submitted By: fuQ lleal th Physics Laboratory Super /isor _1g__ Nuclr Document Control Uni t, 606 EB-C lu Superintendent, WBNP PORC Review f/f,fgo Superintendent, BFNP D, ' e Superintendent, BENP

~ltL NEE, W9C174C-K

\ jk I,UN 3

\ Supv.

Approved By: ak Supctintendent kQ NRC-Ib:NPHPSROB,MS II Power Security Officer, 620 CST 2-C Nuclr fla terials Coord. - 1410 CUBB-C

\_) Manager, OP-QA&A Staff IAs le Approved: ko ,c Resident NRC Inspector - SNP ac NSRS, 249A HHB-K Technical Support Center

.-LC_ s hA1 Technic Al Advaor R_e v . No. Date Revised Paqcs Rev. No. Date Revised Page(

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8 SPECIAL TEST NO. 5 NATURAL CIRCULATION AT REDUCED PRESSURE 1

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SPECIAL TEST 5 Page 1 of 1 Rev. 0 -

NATURAI. CIRCULATION AT REDUCED PRESSURE Table of Contents Page Test Description 1 Special Operator Instruction 2 1.0 OBJECTIVES 3 2.0 PREREQUISITES 4 3.0 PRECAUTIONS 7 4.0 SPECIAL TEST EQUIPMENT ()

5.0 INSTRUCTIONS 10 6.0 ACCEPTANCE CRITERIA 14 DATA SIIEETS 15 APPENDIX A - References 20 APPENDIX B - Deficiencies 21 I

APPENDIX C - Power Measurement Technique 22 APPENDIX D - Computer Points 32 APPENDIX E - Safeguard Blocking Procedure 36 APPENDIX F - Technical Specifications Exceptions 47

- TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 48 l

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SPECIAL TEST 5 Page 1 of 1 Rev. O TEST DESCRIPTION The reactor coolant pumps are tripped with the reactor at 3% of rated power.

The reactor coolant system is depressurized by turning off the pressurizer heaters and possibly turning on auxiliary sprays. Reactor power is re-duced to 1.5% per hour after the pumps are tripped to approximate decay heat conditions. Saturation margin is monitored and increased charging and/or steam flow is used to maintain test limits.

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. SQNP SPECIAL TEST 5 Page 1 of 1 Rev. O SPECIAL OPERATOR INSTRUCTION

  • An operator initiated safety injection should be performed only for one or more of the following conditions:

Reactor coolant system subcooling 5 10 Sudden unexplained decrease in pressurizer level of 10%

or to an Indicated Level of 5 10%

Sudden unexplained decrease in any S/G level to 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 i

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 1 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.

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  • SQNP SPECIAL TEST 5 Page 1 of 12 Rev. 0 1.0 OBJECTIVES 1.1 Verify the abilite to maintain natural circulation at reduced RCS pressures.

1.2 Verify the accuracy of the saturation margin indication from the plant computer.

1.3 Provide operational experience at lower saturation margins and the affects of charging and secondary steam flow on the control of the saturation margin.

1.4 To provide operator training, all shif ts will perform this test.

NOTE: Data acquisition does not need to be repeated for multiple test performances.

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SPECIAL TEST 5 Page 2 of 12 Rev. 0 2.0 PREREQUISITES NOTE: This test can be done in conjunction with Test III, Natural Circulation With Loss of Pressurizer Heaters.

2.1 The reactor is critical at ~ 3% power and under manual control with control bank D at ~ 160 steps or as specified by Test Engi-neer. (Power determined as indicated in Appendix C.)

Date 2.2 All four reactor coolant pumps in operation.

Date 2.3 Steam generator level maintained at approximately 33% on the narrow range indicators by the auxiliary feedwater pumps.

Date 2.4 Pressurizer pressure and level being maintained automatically at appro::imately 2235 psig and 27% respectively.

Date 2.5 RCS temperature (Tavg) approximately 550 F.

Date 2.6 Low Power Physics Test Program has been completed to the extent necessary for conduct of this test.

Date 2.7 Steam generator pressure at approximately 1000 psig and being maintained by steam dump to the condenser on pressure control.

Date 4

SQNP SPECIAL TEST 5 Page 3 of 12 Rev. 0 2.0 PREREQUISITES (Continued) 2.8 Connect recorders to the following test points:

NOTE: Data acquisition need not be repeated for multiple test performances. N/A signoff for these steps.

Recorder 1 Connect To: Monitoring:

Channel #1 1-R-1, FP414B RCS Flow-Loop 1 Channel #2 1-R-1, FP424B RCS Flow-Loop 2 Channel #3 1-R-1, FP434B RCS Flow-Loop 3 Channel #4 1-R-1, FP444B RCS Flow-Loop 4 Channel #5 1-R-1, PP455B Pressurizer Pressure Channel #6 1-R-1, LP459B Pressurizer Level Recorder 2 Connect To: Monitoring:

Channel #1 1-R-23, LP501 Steam Gen. #1 Level Channel #2 1-R-3, FP512B Steam Gen. #1 Steam Flow Channel #3 1-R-3, PP514B Steam Gen. #1 Pressure Channel #4 1-R-23, LP502 Steam Gen. #2 Level Channtl #5 1-R-3, FPS 22B Steam Gen. #2 Steam Flow Channel #6 1-R-3, PPS24B Steam Gen. #2 Pressure Recorder 3 Connect To: Monitoring:

Channel #1 1-R-23, LP503 Steam Gen. #3 Level Channel #2 1-R-4, FP532B Steam Gen. #3 Steam Flow Channel #3 1-R-4, PP534B Steam Gen. #3 Pressure Channel #4 1-R-23, LP504 Steam Gen. #4 Level Channel #5 1-R-4, FP542B Steam Gen. #4 Steam Flow Channel #6 1-R-4, PP544B Steam Gen. #4 Pressure i

Recorder 4 Connect To: Monitoring:

Channel #1 1-R-18, FP121A RCS Charging Flow Channel #2 1-R-23, FP132 RCS Letdown Flow Channel #3 1-R-5, PP403A Wide Range RCS Pressure Channel #4 1-R-22, TP454 Pressurizer Steam Temp Channel #5 1-R-20, TP453 )

Pressurizer Liquid Temp. '

Recorder #5 Connect To: Monitoring Channel #1 L-3-163. TP13, 1-L-11B Aux Feed Flow to S.G. #1 Channel 02 L-3-155, TP13,_1-L-11A Aux Feed Flow to S.G. #2 Channel #3 L-3-147, TP12, 1-L-11B Aux Feed Flow to S.G. #3 Channel #4 L-3-170, TP12, 1-L-11A Aux Feed Flow to S.G. /;4 5

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SQNP SPECIAL TEST 5 Page 4 of 12 Rev. O ~~

2.0 PREREQUISITES (Continued)

NOTE: Record the following on each recorder chart.

a) Unit #

b) Date c) Procedure #

d) Parameter Scale and Range c) Chart Speed f) Name of person recording data g) Recorder I.D. #

2.9 Record on p-computer recorder a) Flux b) Averagewide-rangefcold c) Average wide-range hot d) Average steam generator pressure c) Reactivity Date 2.10 Set the trend recorders and coeputer trend printer in the main control room to monitor the parameters indicated in Appendix D.

Date NOTE: Data acquisition need not be repeated for multiple test performances. N/A signoffs for these steps.

2.11 Verify the input logic of safety injection on Hi Steam Line AP has been blocked in accordance with Appendix E.

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2.12 Verify the Hi Steam Flow coincident with Lo S/G pressure or Lo Tav input to Safety Injection has been modified in accordance with Appendix E.

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2.13 Verify the automatic actuation of Safety Injection has been blocked in accordance with Appendix E.

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  • SQNP SPECIAL TEST 5 Page 5 of 12 Rev. 0 2.0 (Continued) 2.14 Verify the following UHI isolation valves are gagged:

FCV 87-21 /

FCV 87-22 /

FCV 87-23 ~/

FCV 87-24 /

2.15 Intermediate and power range (low setpoint) high level reactor trip setpoints have been set to 7% in accordance with Appendix C and D of SU-8.5.2.

Power Range /

Intermediate Range /

3.0 PRECAUTIONS 3.1 Maintain reactor coolant pump seal and thermal barrier differen-tial pressure requirements as given in S0I 68.2.

3.2 Do not exceed 5% nuclear power at any time while the test is in progress.

3.3 Abort test if any of the following temperature limits are exceeded:

3.3.1 Core exit temperature of 610 F.

3.3.2 AT as indicated by Tg -T f 65 F.

C 3.3.3 avg Temperature of 578 F.

3.4 When equilibrium has been established after the initial trans-ient, avoid any sudden changes in feedwater flow or in steam generator water level.

3.5 T Af ter the reactor coolant pumps are tripped the gormal avg and AT indications will be come unreliable. AT and avg should be calculated by taking the difference and the average of the hot and cold leg temperature indications respectively.

3.6 Maintain saturation margin greater than 20 degrees Fahrenheit at all times.

3.7 Monitor reactor power closely whenever adjustments to cold are made. Ifaintain cold above 531 F.

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  • SQNP SPECIAL TEST 5 Page 6 of 12 Rev. 0-3.0 (Continued) 3.8 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.

3.9 ?!aintain D bank at k 100 steps during the conduct of this test.

Should this limit be reached, boron concentration will have to be increased.

3.10 When RCS pressure drops below 1970 psig, manually block S. I.

(setpoint at-1870 psig). If not blocked, the reactor will trip when the setpoint is reached.

3.11 When RCS pressure is dropped below 1970 psig, isolation valves for pressurizer PORV's should be closed.

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  • SQNP SPECIAL TEST 5 Page ' of 12 Rev. 0 4.0 SPECIAL TEST EQUIPMENT Calibration Instrument Specification Identification Verification Strip Chart Recorder Brush 260 or equivalent (4)

Reactivity Computer Westinghouse Recorder (1) llP 7100B or Equivalent 1

If test instrumelits are changed during this test, the instrument informa-tion must be recorded here and an entry made in the chronological log book explaining this change.

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SQNP SPECIAL TEST 5 Page 8 of 12 Rev. 0 5.0 TEST INSTRUCTIONS NOTE: Data acquisition need not be expected for multiple test performance. N/A signoffs for these steps.

~5.1 Ensure the pressurizer backup becters 1A.1B, and 1C remain off by moving handswitches 1-flS-68-341A and 341D to the 'Stop' posi-tion and moving 1-llS-68-341H to 'Stop-Pull to Lock'.

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5.2 Record the data indicated on Data Sheet 5.1.

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5.3 Start tlic computer trend printer printing at the fastest interval possible.

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5.4 Shutoff the preriurizer control heater group by moving 1-HS-68-341F to 'Stop'.

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5.5 Record the time, on the data recorder charts in the auxiliary instrument room and then start them at 125mm/ min.

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5.6 Shutdown the reactor coolant pumps in accordance with SOI-68.2 (simultaneously).

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NOTE: At the initiation of natural circulation' the following temperature response is expected.

a) Wide range hot - increase b) Wide rangeTcold - slight increase or-constant c) goreexitthermocouple-increase d) avg indication - unreliable e) Delta-T indication - unreliable f) Pressurizer level and pressure - increase 5.7 Verify natural circulation is established by following the opera-tional guidelines given in Appendix A of E01-5.

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SQNP SPECIAL TEST 5 Page 9 of 12 Rev. 0 5.0 TEST INSTRUCTIONS (Continued)

NOTE: NaturalCirculationwillgestablewhen: T

1) AT between wide range T hot and cold is constant.
2) AT between wide range cold and core exit thermocouple average temperature is constant.
3) Wide range hot E core exit thermocouple average temperature.

(See Table 1) 5.7.1 Assume manual control of charging flow and match charg-ing to letdown to maintain a constant RCS water mass.

(Ifold pressurizer level ~ constant after equilibrium is reached on natural circulation).

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5.8 Once equilibrium has been established adjust trend printer print-out intervals as specified by the test director.

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NOTE: A slow cooling of the pressurizer will begin at this point and a corresponding decrease in RCS pressure.

5.9 Record the highest T/C temperature indicated on the T/C maps, the lowest of the four pressurizer pressure protection channels, and the saturation margin indicated on the analog trend recorder on data sheet 5.3 at periodic intervals during the depressurization.

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NOTE: If desired, the depressurization rate can be increased by using auxiliary spray. Once the RCS pressure drops below 1700 psig, the pressure reading for Data Sheet 5.3 should be taken from the RCS wide range pressure indicators.

CAUTION: Safety injection must be manually blocked when RCS pressure drops below 1970 psig. (To prevent a reactor trip).*

  • 5.10 Af ter the RCP trips, begin slowly reducing reactor' power to approximately 1.5% and maintain this power level for the duration of the test. (Reduce power at a rate of ~ 1.5% per hour).

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5.10.1 Whe.n RCS pressure drops below 1970 psig, close the isola-tion valves for the pressurizer PORV's by placing their respective handswitches in the 'close' position.

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  • SQNP SPECIAL TEST 5 Page 10 of 12 Rev. 0 -

5.0 TEST INSTRUCTIONS (Continued) 5.11 Continue to monitor the core exit T/C temperature to verify natural circulation is maintained as the saturation margin is decreased.

Continue pressure drop until the test director indicates sufficient data has been recorded to verify the accuracy of the saturation margin indicated on the trend recorder. Increase charging and/or steam flow to increase the saturation margin at this time.

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NOTE: Do not allow the saturation margin to decrease below 20 F.

The margiy can be increased by either increasing RCS pressure or reducing cold. Charging must be increased to maintain pressurizer T

level and pressure when reducing cold. Do not allow pressurizer level to go above 70%.

5.12 Using 1967 ASME steam tables, determine the saturation margin using the pressure and temperature recorded in Data Sheet 5.3 j

' and plot this value along with the saturation margin taken from the analog trend recorder vs time on Data Sheet 5.4.

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NOTE: Step 5.12 can be conducted concurrent with the depressuri-zation.

5.13 Increase the saturation margin back to above 50 F and stop the brush recorders and trend printers. Attach copies of the print-outs and charts to Data Sheet 5.2.

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5.13.1 When RCS pressure is increased above 1970 psig, open the isolation valves fo'r the pressurizer PORV's.

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5.14 An evaluation of the accuracy of the saturation meter should be done at this time to determine the necessity of reprogramming the computer. The computer trend should indicate a saturation margin within 3% of the margin det' ermined from the steam tables.

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5.15 Increase RCS_ pressure back to 2235 by selectively energizing the pressurizer backup heaters. ,

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5.16 Insert control bank D until the reactor is 'in the hot zero power test range.

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  • SQNP SPECIAL TEST 5 Page 11 of 12 Rev. 0 -

5.0 TEST INSTRIICTIONS (Continued)

Caution: Ensure pressurizer spray controllers are at zero output prior to starting the first reactor coolant pump.

5.17 Restart all four reactor coolant pumps in accordance with SOI 68.2 beginning with 2, 1, 3 and then 4.

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5.18 Return pressurize'r level to approximately 27% and return RCS pressure and level control to automatic.

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NOTE: Conditions can now be established for the conduct of the next test.

5.19 Remove the block of input logic of Safety Injection on Hi Steam Line AP in accardance with Appendix E 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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5.20 Remove modification to Hi Steam Flow coincident with Lo S/G pressure or to Tav input to Safety Injection in accordance with Appendix E, unless the next test to be performed requires the modification to be made. If this is the case, disregard this step, place N/A in signature line and initial.

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5.21 Remove block of automatic initiation of Safety Injection in c

ac'ordance with Appendix E, unless the next test to be performed requires the modification to be made. If this is the case, dis-regard this step, place N/A in the signature line and initial.

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5.22 Remove the gag from the following UHI isolation valves unless the next test to be performed requires the valves to be gagged.

If this is the case, disregard this step, place N/A in the signature line and initial.

. FCV 87-21 /

FCV 87-22 /

FCV 87-23 /

FCV 87-24 /

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, SQNP SPECIAL TEST 5 Page 12 of 12 Rev. 0 5.0 TEST INSTRUCTIONS (Continued) 5.23 Reset the intermediate and power range high level reactor trip setpoints as indicated by the test director in accordance with Appendix C and D of SU-8,5.2 unless the next test to be per-formed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, ar.d initial.

Power Range /

Intermediate Range /

6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperatures does not exceed 610 F.

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6.2 Delta-T for any loop does not exceed 65 F.

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6.3 avg for any loop does not exceed 578 F.

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6.4 Natural circulation can be established and maintained at reduced low RCS pressure.

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6.5 The plant computer calculated saturation margin is in agreement with margins determined using recorded plant parameters within

+ 3%.

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-a SQNP SPECIAL TEST 5 Page 1 of 3 Rev. O ~

DATA SHEET 5.1 Initial Conditions Unit- Time Date Pressurizer Pressure PR-68-340 PSiS Pressurizer Level f LR-68-339 Red Pen  %

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  1. 1 Hot leg temp TR-68-1 o F

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  1. 1 Cold leg temp TR-68-18 o F
  1. 2 Hot leg temp TR-68-1 F
  1. 2 Cold Icg temp TR-68-18 o F

, #3 Hot leg temp 1

TR-68-43 o F

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! #3 Cold leg temp

! TR-68-60 a i F

//4 Hot leg temp j TR-68-43 o F

  1. 4 Cold leg temp i TR-68-60 o F

S.G. #1 Level (narrow range)

LI-3-42 S.G. #2 Level (narrow range)

LI-3-55 i 'a' I

S.G. - #3 Level (narrow range)

LI-3-97  %

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' S.G. #4 Level (narrow range) '

LI-3-110 i  %

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' . Recorded By Date- 1 i

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DATA SlfEET 5.1 Unit - Time Date S.G. #1 Level (wide range)

LR-3-43 Pen 1  %

S.G. #2 Level (wide range)

LR-3-43 Pen 2  %

l S.G. #3 Level (wide range)

LR-3-98 Pen 1  %

S.G. #4 Level (.2de range)

LR-3-98 Pe- 2  %

S.G. #1 Pressure PI-1-2A psig S.G. #2 Pressure PI-1-9A psig S.G. #3 Pressure PI-1-20A psig' S.G. #4 Pressere PI-1-27A psig S.G. #1 Feedwater flow FI-3-35A gym S.G. #2 Feedwater flow F1-3-48A gpm S.G. #3 Feedwater flow FI-3-90A gpm

- S.G. #4 Feedwater flow FI-3-103A gpm S.G. #1 Steam flow FI-1-3A lbs/hr S.G. #2 Steam flow.

  • FI-1-10A lbs/hr

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Recorded By Date 4

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DATA SIIEET 5.1 Unit Time Date S.G. #3 Steam flow FI-1-21A lbs/hr S.G. #4 Steam flow FI-1-28A lbs/hr Loop f/1 T-average o

TI-68-2E F Lo:p #2 T-average o

TI-68-25E F Loop #3 T-average o

TI-68-44E F Loop #4 T-average TI-68-67E ,F Loop #1 A T g TI-68-2D F Loop #2 A T TI-68-25D F Loop #3 A T TI-68-44D F Loop #4 A T TI-68-67D F (0-100% = 0-55 F A T)

NIS Channel N-41  %

NIS Channel N-42 1?

NIS Channel N-43  %

NIS Channel N-44  %

NOTE: Attach Computer Printout of Incore Thermocouple Temperature Map.

Refer to Appendix. A for the procedure for printing out of this map.

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Recorded By Date

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' SQNP SPECIAL TEST 5 Page 1 of 1 Rev, 0 1

DATA SHEET 5.3 i Unit' Time Date 9

Lowest of PI-68-340, 334A, 323A or 322A (PI-68-66A if below Highest Incore Computer Saturation 4

1700 psig) T/C Margin on Trend Time = 0

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  • SQNP SPECIAL TEST 5 Page 1 of 1 Rev. 0 4 DATA SIIEET 5.4 l

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(To be plotted on graph paper and attachel) i I

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APPENDIX A References

1. FSAR
2. Technical Specifications
3. Plant Operating Instructions E0i-5 S01-68.2 4

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- SQNP SPECIAL TEST 5 Page 1 of 1 Rev. O APPENDIX B Test Deficiencies #

Test Deficiency Recornmended Resolution Final Resolution Originator

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Signature Date PORC Review of Final Resolution Date Approval of Final Resolution

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Plant Superintendent Date 21

  • SQNP i-SPECIAL TEST 5 Page 1 of 10 Rev. O "'

APPEhTIX C Procedure for Determining Core Power Level i

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APPENDIX C Outline I. Core Por Determination A. Primary Side Calorimetric (Forced Circulation Only)

1. Reference (~ 550 F) Calorimetric (Before NC test) 3 a) Output used to adjust M/D Power Monitor Proaram'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 4

power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.

2. Power Monitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 5 or 6 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to once every 2 minutes or as necessary to continuously monitor core power.

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, SQNP SPECIAL TEST 5 Page 3 of 10 Rev. O APPENDIX C CORE POWER DETERMINATION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation)

C.1 Use two DVMs and measure the voltage at the test points speci-fied for each loop as rapid as possible.

C.2 Calculate the AT; multiply that AT by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (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 5 Page 4 of 10 Rev. O APPENDIX C 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 b2 altered by the test engineer, based upon low power physics testing results and previous special testing experience.

2. Determine the detector normalization constants and en'.er them into the P-250 as follows:

a) Enter a value of 1.0 into the P-250 for the a dresses 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) D:termine the detector normalization constants from Data Sheet C.2.

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  • SQNP SPECIAL TEST 5 Page 5 of 10 Rev. 0 -

APPENDIX C 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 K0901 1 Set the power normalization factor Selects the modified " Flux Map K5525 1 Print" programs K0900 0 Initiated Pass Number Calibration Constant for M/D Power

_ K0864 Variable (I) 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 power (UO906) times the current value enter'ed in (K0864). If no value has been entered into (K0864) enter 0.25.

New (K0864) = Current (K0864) x Item #8 Data Sheet C.1-26

  • SQNP SPECIAL TEST 5 Page 6 of 10 Rev. 0 -

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 556 1.260 3.6448 x 10 1

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 7 546 1.236 3.6959 x 10 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 7 540 'l.221 3.7254 x 10 7

. 538 1.217 3.7348 x 10 7 536 1.213 3.7443 x 10 7 534 1.209 3.7538 x 10 7 532 1.206- 3.7633 x 10 7 530 1.202 3.7729 x 10

( ~

These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia.

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SQNP SPECIAL TEST S Page 7 of 10 Rev. O APPENDIX C ,

Data Sheet C.1 .

Date Time Unit Power Tavg F Loop 1 Loop 2 Loop 3 Loop 4

. Item # Calculation Procedure Units R2/TP-411J R6/TP-421J R10/RP-431J R13/RP-441J l Loop AT - Inservice ' (at tes t point) 7olts 2 Loop AT = (#1') x (1) F 3 Loop Alf = (#2) x Cp (from Table C.1) BTU /lbm 6

4 Loop RCS Flow (from Table C.li 10 1bm/hr 6

5 Loop Reactor Power - (#3) x (#4) 10 BTU /hr E$ Total Reactor Power = (#5) 6 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307 MWT 8  % Reactor Power.= (#7) x 0.02932  %

(1) Conversion factor for AT obtained from scaling document.

Remarks:

Date By:

Checked By:

' SQNP SPECIAL TEST 5 Page 8 of 10 Rev. O APPENDIX C DATA SIEET C.2 4

A B N N* N N= E N N A g= B E= CE= D E= E E E*

NA = 1.00 II

  • B N N tl g =

N N N =A N =

N CE =

D D N N N = E =

E= _

N N N y=A = TE =

N N Definitions:

A,B,C'U' N N N N N'

= Normalized integral from summary map for each N

detector in.a normal path in the first pass A'U,C'U,E,F E E E E E E.

Normalize <1 integral from summary map for each detector in an emergency path in the second pass N,N' g B C, ND '- E'

Detector normalization factor for each detector-F Remarks:

Data By: Date 29 i

e

  • SQNP SPECIAL-TEST 5 Page 9 of 10 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 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 runn-ing frequency of the Thermcouple Averaging Program at 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 d'rectly correlated with the excore detectors but quadrant 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 U1159 2 -Ull60 3 Ull61 4 U1162 5 Ull51 6- Ull52 7 U1153 E Ull54 i A Short Form Mcp should be run periodically or upon request from l the test engineer as an indication of core flow distribution. It  !

should be p,ut on the Utility Typewriter if possible. The P-250  ;

Operator's Console Reference Manual provides instructions for ob-t'ining. thermocouple maps.

The trend output and Short Form Maps should be attached to this procedure at.the end of the test.

L30-

  • SQNP SPECIAL TEST 5 Page-10:of 10 Rev. O APPENDIX C CENTEH.LINE OUARTER-COHE SY?AMETRY C dd 1.oa V

3 4 N-4 3 m 2,n* N- .l2 O O-

. a ], , 3

\

,s

)

id lhi iy e sre

( )

E 4 3 I/

(

  • EXCORE DET ECTCriS O w if v C ff. } l g l ll* AA' Csid Laa: v l

Of AGONAL QUARTER CORE SYMMETRY 225* 315 s ,

b w

s, 8 6

, ,,s, 7

e

's s- a-Fiquic C-f 31

.~:  :-

' SQNP SPECIAL TEST 5 Page 1 of 4 Rev. O APPENDIX D Procedure For Use Of Computer Cystem For Data Collection The following parameters will be monitored during this test using the plant ccmputer system.

Parameter Computer Point Pressurizer Pressure P0480A 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 PO460A 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 IO065A 32

, SQNP SPECIAL TEST 5 Page 2 of 4 Rev. O APPENDIX D 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 'P0480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO'e20A 3 T0419A 9 T0479A 15 P0s'.0A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 PO400A 17 P0460A 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 Hottest 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.

i 1. Push DIGITAL TREND button

2. Select block number (1 to 6) on keyboard 1 3. Push VALUE 1 button
4. Sciect 0 on keyboard
5. Push VALUE 2 button
6. Push STOP button Repeat the above 6 steps.for each data block to be used.

i i

NOTE: A Block Trend Error message will occur if the data block is initially clear.

To set up the data blocks, perform the following series of steps for each point to be monitored.

i

1. Push the DIGITAL TREND button
2. Select the point address (i.e. P0480A) on the alphanumeric keyboard
3. Push ADDRESS button -
4. Select block number (1 to 6) on keyboatd.

'5. Push VALUE 1 button

6. Select column number (1 to 18).on keyboard
7. Push VALUE 2 button

' 8. Push START button 33

ESQNP SPECIAL TEST 5 Page 3 of 4 Rev. O APPENDIX D

Once the blocks are set up they can be initiated by performing _the follow-ing steps for each block.
1. Push DIGITAL TREND button.
2. Select block number (1 to 6) on keyboard
3. Push VALUE 1 button
4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 = 2 minute, etc.) The 30-second interval is recommended for the duration of the test transient
5. Push VALUE 3 button
6. Push START button If it is necessary to change the trend interval of a block or trend, perform -

the following.

1. Push DIGITAL TREND button
2. Select block number (1 to 6) on keyboard
3. Push VALUE 1 button
4. Select new interval number (0 = 30 sec., 1 = 1 min.,

2 = 2 min., etc) on keyboard

5. Push VALUE 3 button
6. Push START button To stop trending or block perform the following:
1. Push DIGITAL TREhD 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).

Af ter 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. S. elect per number (1 to 12) on keyboard
3. Push VALUE 1 button
4. Push STOP button -'

34 w e 4

  • SQNP SPECIAL TEST 5 Page 4 of 4 Rev. O APPENDIX D To start an analog trend perform the following steps.
1. Push ANALOG TREND func .on 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 re-corded.

Prior to initiation of the transient, and as 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
7. Push VALUE 3 button
8. Push START button

/

4 35

I

  • SQNP SPECIAL TEST 5 Page 1 of 11 Rev. 0-APPENDIX E Safeguard' Blocking Procedure The first step blocks automatic initiation of a safety injection. The safety injection alarm, manual S.I handswitch, and the reactor trip por- '

tion of the protection logic will-remain in operation. If conditions exist that would normally initiate a safety injection; (1) the safety injection alarm will initiate telling the . operator that the condition exists and what the problem is. (2) a reactor trip will take place auto-matically. (3) a safety injection can be initiated manually from the switch in the control room if conditions warrant.

1. Install temporary jumpers and temporary alteration control tags to logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.

NOTE: These jumpers will be specially made for this purpose and installed by an instrument mechanic.

R-47 Panel Performed by: /

Verified by: /

R-50 Panel Performed by: /

Verified by: /

Procedure for blocking automatic actuation of a safety injection on high steamline Delta-P. This block will prevent a reactor trip from occuring during the natural circulation tests from high AP caused by degraded test conditions. (This block will also defeat all AP S1 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 36 l

. ., SQNP SPECIAL TEST 5 Page 2 of 11

, Rev. 0 i

l APPENDIX E i

i 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 l The TACF tag will be attached to the bistable switch and the TACF must note the jumper and the lif ted wire.

NOTE: - Orange "Out of Service" stickers should be placed on all l status / alarm windows as the 120V source is connected.

4. Lift and tape the wire on the rack side of terminal L-9 in the rear of

. 1-R-7. Apply a 120-VAC source to terminals L-9 and L-11 in the rear of 1-R-7 and verify 1-XX-55-6B/25 is clear.

Performed by: /

Verified by: /

J i

5. Move test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

6. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. . Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear.

Performed by: /

Verified by: /

i

7. Move test trip switch PS-516C in 1-R-12 to the trip position and verify the amber-light above the switch comes on.

4 Performed by: /

_ Verified by: /.

8. Lift and tape the wire on the rack side of terminal L-5 in the rear of 1-R-7. . Apply 120-VAC source to terminals L-5 and L-6 in the rear of 1-R-12 and verify 1-XX-55-6B/73 is clear.

- Per 3rmed by: /-

-Verified by: /

f A

f 4

37 x ,

- -

  • SQNP SPECIAL TEST 5 Page 3 of 11 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. Lif t and t. ape the wire on the rack side of terminal L-7 in the rear of 1-R-12. Apply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-12 and verify 1-XX-55-6B/76.

Performed by: /

Verified by: /

11.  ?!ove test trip switch PS-525B in 1-R-8 to trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

12. Lif t and tape the wire on the rack side of terminal L-7 in the rear of '

i 1-R-8. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/28 is clear.

, Performed by: /

Verified by: /

13.  !!ove test trip switch PS-525A in 1-R-8 to the trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

-14. Lif t and tape the wire on the rack side of terminal L-9 in the rear of I-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.

Performed by: /

4 Verified by: /

l

15. Flove test trip switch PS-526D in 1-R-11 to the trip p ,ition and verify.

the amber light above the switch comes on.

Performed by: _ /

Verified by: /

l 38 -

l 1

1

  • SQNP SPECIAL TEST 5 Page 4 of 11 Rev. O APPENDIX E

, 16. Lift 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: /

I

17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify 2

the amber light above the switch comes on.

1 Performed tj: /

Verified by: /

18. Lif t and tape the wire on the rack side of terminal L-5 in the rear or 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is clear.

, Performed by: /

1 Verified by: /

Temporary Mgdification to High Steam Flow Coincident with Low S.G. Pressure' or Low-Low avg Safety. Injection I 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 m'odifica-tion as a reactor trip may result. The input bistables should be checked ar.d the source of the problem corrected.

- 20. Move test trip switch TS412D in R-2 to the trip position and verify the amber lightLabove the switch comes on.

Performed by: /

Verified by: /

21. Lif t and tape the wire on.the rack side of terminal M-3 in the rear of-1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verifyr

~XA-55-6A/30 will clear.

Performed by: -/-

--Verified by: /

,39 .

-w-- twn p "

, , SQNP SPECIAL TEST 5 Page 5 of 11 Rev. 0 APPENDIX E

22. Move test trip switch TS-422D in R-6 to the trip position and verify

-the amber light above the switch comes on.

Performed by: /

Verified by: /

! 23. Lift and tape the wire on the rack side of terminal M-3 in the rear of

, 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify l- XA-55-6A/30 will clear.

Performed by: /

Verified by: /

24. Move test trip switch TS432D in R-10 to the trip position and verify the amber light above the switch comes on.

Performed by: /

Verified by: /

25. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-10. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.

Performed by: /

j Verified by: /

t

26. Nove test trip switch TS-442D in R-13 to th- trip position and verify

, the amber light above the switch comes on.

Performed by: /

Verified by: /

i 27. Lif t and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a'120-VAC source to. terminals M-3 and M-4 and verify XA-55-6A/30 will clear.

Performed by: /

Verified by: /

NOTE: The avg inputs to the high ster.m 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 au 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.)

40 y o-. -

e '

  • SQNP SPECIAL TEST 5 Page 6 of 11 Rev. O APPENDIX E
28. Hove test trip switch FS512B in R-3 to the trip position and verify

'the amber light and annunciator XA-55-6B/2 come on.

i Performed by: /

Verified by: /

29. Move test trip switch FS522B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/ come on.

i Performed by: /

Verified by: /

NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal.

30. Apply Temporary Alteration Control Tags forms to all the above test trip swit.ches 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 SWITCll TEMP ALT. NO.

R-7 PS515A /

R-7 PSS15B /

R-12 PS516C /

R-12 PS516D /

R-8 PS525B /

R-8 PS525A /

R-11. PSS26D /-

R-11 RS526C /

1 R-2 TS412D /

R-6 TS422D /

R-10 TS432D /

R-13 TS442D /

R-3 :FS512B /  !

l R-3 FS522B /

To return the steamline Delta-P S.I. to normal condition, the following steps-should'be followed.  ;

1 I

41.  !

\

l

  • , . SQNP SPECIAL TEST 5 Page 7 of 11 Rev. O APPENDIX E NOTE: The orange "Out of Service" stickers should be removed from the alarm / status window as each bistable is put back in service.
31. Remove the 120-VAC source from L-5 and L-6 in 1-R-11. Reterminate wire on L-5.

Performed by: /

Verified by: /

32. 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.

e Performed by: /

Verified by: /

33. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire on L-7.

Performed by: /

Verified by: /

34.  ?!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: /

35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.

Performed by: /

Verified by: /

36. Ilo": 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: /

37. Remove the 120-VAC source f rom L-7 and L-8 in 1-R-8. Reterminate wire on L-7.

I formed by: /

Verified by: /

42

' ' ' SQNP SPECIAL TEST 5 Page 8 of 11 Rev. O APPENDIX E

38. Ifove test trip switch PS-525B in 1-R-8 to the normal position and verify the amber light above the switch and 1-XX-5-6B/28 are clear.

Performed by: /

Verified by: /

39. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. Retermi-nate wire on L.7.

Performed by: /

Verified by: /

40. Move test trip switch PS-516D in 1-R-12 to the normal position and verify the amber light above the switch and 1-XX-55-6B/76 are clear.

Performed by: /

Verified by: /

41. Remove the 120-VAC source from terminals L-5 and L-6 in 1-R-12. Retermi-nate wire on L-5.

Performed _by: /

Verified by: /

42. t!ove test trip switch PS-516C in 1-R-12 to the normal position and verify the amber light above the switch and 1-XX-55-6B/73 are clear.

Performed by: /

Verified by: /

43. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi-nate wire on L-7. 4 Performed by: /

Verified by: /

44. Hove 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: / l 1

43

  • SQNP SPECIAL TEST 5 Page 9 of 11 Re". O APPENDIX E
45. Remove t he 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.

Performed by: /

Verified by: /

, 46. flove 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.

i To return the high steam flow coincident with low steam generator pressure or low-low

  • avg to normal, perform the following steps.
47. 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: /

48. tfove test trip. switch FSS12B in R-3 to the normal position and verify the amber light goes out and XA-55-6B/2 will clear.

Perfonned by: /

Verified by: /

49. Remove the 120-VAC source from terminals 11-3 and 11-4 in R-13. Retermi-nate wire on ?!-3.

Performed by: /

Verified by: /

50.  ?!ove test trip switch TS442D.in R-13 to the normal position and verify the amber light goes out and XA-55-6A/30 will cicar. ~

Performed by: /-

Verified by: /

44

  • *
  • SQNP SPECIAL TEST 5 Page 10 of 11 Rev. O APPENDIX E
51. Remove the 120-VAC source from terminals 11-3 and 11-4 in R-10. Retermi-

^nate wire on 11-3.

Performed by: /

Verified by: /

52. ?! ave test trip switch TS432D in R-10 to the normal position and verify the amber light goes out and XA-55-6A/30 will clear.

Performed by: /

Verified by: /

53. Remove the 120-VAC source from terminals 11-3 and 11-4 is. R-6. Retermi-nate wire on F1-3.

Performed by: /

Verified by: /

54. Flove test trip switch TS442D in R-6 to the normal position and verify the amber light goes out. and XA-55-6A/30 will clear.

Performed by: /

Verified by: /

55. Remove the 120-VAC source f rom terminals 11-3 and 11-4 in R-2. Retermi-nate wire on F1-3.

Performed by: /

Verified by: /

56. flove test trip switch TS412D in R-2 to the trip position and verify the amber light comes on and XA-55-6A/30 will cicar.

Performed by: /

Verified by: /

t 45

  • SQNP SPECIAL TEST 5 Page 11 of 11 Rev. O APPENDIX E
57. Remove the Temporary Alteration Tags on the following test trip

'avitches:

RACK TEST SWITCH TEMP ALT. NO.

R-7 PS515A /

R-7 PSS15B /

< R-12 PSS16C /

R-12 PSS16D /

R-8 PS525B /

R-8 PS525A /

R-11 PS526D /

R-11 RS526C /

R-2 TS412D /

R-6 TS422D /

R-10 TS432D /

R-13 TS442D /

R-3 FS512B /

R-3 FS522B /

53. Remove the jumpers and the Temporary Alteration Tags from logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.

R-47 Panel Performed by: /

Verified by: /

R-50 Panel Performed by: /

~

Verified by: /

NOTE: All reactor safeguard systems modified for the special startup tests are back in a normal configuration at this time.

46

a

,, , SQNP SPECIAL TES5 5 Page 1 of 1 Rev. O APPENDIX F 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 thin and all other special tests.

~

8 d 5!

1: n3

  • 8e8 n bo e o c #et 89 9 8 3& a28e e3

%e 'P a e t " t 8 9 .$ . . .

fO U Ed EE EE B 3 E C8uuu* "' n 'n

-% ~~ ~ F is t " is 2 EE E To a * ? c 3nBBBk8hB B aaaaaeaeea 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 Saf ety 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 Moderator temperature coefficient (3.1.1.3) X X X X Steamline AP SI (3.3.2.1) hypassed X X X X X X X X X X liigh Steamflow coincidentgl w/ low steamline pressure or low-low avg SI Reset flow to 0% and ^ avg blocked X X X-X X X X X X X Reset 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 level low AFW start reset (3.3.2.1) X X Pressurizer (3.4.4) X X X UHI (3.5.1.2) X X X X X X X X X X AEW (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 Loops Normal Operation (3.4.1.2) X'X X X 'X X X X 47

  • SQNP SPECIAL TEST 5 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 i

(Nat. Circ.)

Power Level 4 3 2 1

.5% L= 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 c- 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 'T A = 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

- W NOTE: L is % of 97,000 gpm flow through operabic loop.

AT = Loop AT in F.

48 1

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