ML19305C606
| ML19305C606 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/27/1980 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19305C605 | List: |
| References | |
| PROC-800327, NUDOCS 8003310141 | |
| Download: ML19305C606 (400) | |
Text
{{#Wiki_filter:__ . O .. E'.- O . ELLCEO@U,RE 2 4 i I, i SPECIAL TEST NO. 1
, NATLRAL CIRCULATION TEST l i
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SQNP SPECIAL TEST 1 Page 1 of 1 Rev. 1 NATURAL CIRCULATION TEST Table of Contents
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; Natural Circulation Test I t-i Special Operator Instruction 2 I
1.0 OBJECTIVES 3 2.0 PREREQUISITES 3 3.0 PRECAUTIONS 6 4.0 SPECIAL TEST EQUIPMENT 8 5.0 INSTRUCTIONS 9 6.0 ACCEPTANCE CRITERIA 12 DATA SHEETS 13 () ' APPENDIX A - References 17 APPENDIX B - Deficiencies 18 APPENDIX C - Power Measurement Techniques 19 APPENDIX D - Computer Points 30 I APPENDIX E - Safeguard Blocking Procedure 34 APPENDIX F - Technical Specifications Exceptions 45 TABLE 1 Loop Flow and Core AT for Various Power
; Levels and Isolation Configurations 46 O
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l SQNP SPECIAL TEST 1 Page 1 of 1 Rev. 1 O.
' NATURAL CIRCULATION TEST TEST DESCRIPTION i
i The test will be initiated by simultaneously tripping all reactor coolant pumps while at 3% power. The transient response will be i monitored and establishment of natural circulation verified. Core i exit thermocouples will be monitored to determine the core flow distribution. After stable conditions have been established, forced circulation will be reestablished. 9 1 se O O t I i i I l l 1
SQNP SPECIAL TEST 1 Page 1 of 1 Rev. 1 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 Preasurizer Level to 5 10% Indicated or Sudden Unexplained Decrease of 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 to 5 17% or a Sudden Unexplained Decrease of 5% 1/3 Excores 2 10% Any Loop A T > 65*F Tavg > 578*F Core Exit Temperature (Highest) > 610*F
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES. .
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SQNP SPECIAL TEST 1 Page 1 of 10 Rev. 1 O 1.0 OBJECTIVES i 1.1 To demonstrate the capability to remove decay heat by natural cir-culation. 1.2 To verify that the pressurizer pressure and level control systems
, can respond automatically to loss of forced circulation from all ! four reactor coolant pumps and maintain RCS pressure within accept-i able limits during the coastdown transient.
1.3 To verify that steam generator level and feedwater flow can be con-9 trolled under conditions of natural circulation to maintain ade-quate cooling of the reactor coolant system. 1.4 To provide operator training. All operating shifts will perform this test. NOTE: Data acquisition does not need to be repeated for multiple test performances. i 2.0 PREREQUISITES t i 2.1 Low Power Physics Testing has been completed to the extent neces-sary for conduct of this test. ( Date 2.2 Reactor is critical and manually controlled at approximately 3% power with control bank D at ~ 160 steps or as specified by test engineer. (Power determined as indicated in Appendix C). I Date l 2.3 All four reactor coolant pumps are in operation. Date
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2.4 Pressurizer pressure control and level control are in automatic, maintaining RCS pressure at approximately 2235 psig and pressur-izer level at approximately 27 to 28%. Date 2.5 Steam dump valves are in the pressure control mo'de, maintaining steam generator pressur- at approximately 1005 psig. l [) s_- Date l 3 9 e
SQNP SPECIAL TEST 1 Page 2 of 10 Rev. 1 O \/ 2.0 (Continued) 2.6 Steam generator level is being maintained at approximately 33% on the narrow range indicators with auxiliary feedwater. l Date 2.7 RCS temperature (T,yg) is being maintained at approximately 550 F. I Date
' 2.8 Record the following parameters.
NOTE: Data acquisition steps need not be repeated for multiple test performances. N/A sign offs for these steps. 2.8.1 Install recorders to record data at the following locations.
; Recorder No. 1 Connect To: Monitoring Channel No. 1 1-R-1, FP-414B RCS Flow, Loop 1 Channel No. 2 1-R-1, FP-424B RCS Flow, Loop 2 Channel No. 3 1-R-1, FP-434B RCS Flow, Loop 3
() - Channel No. 4 Channel No. 5 1-R-1, FP-444B 1-R-1, PP-455B RCS Flow, Loop 4 Pressurizer Pressure . Channel No. 6 1-R-1, LP-459B Pressurizer Level Recorder No. 2 , Connect To: Monitoring Channel No. 1 1-R-3, PP-514B Steam Gen.#1 Pressure Channel No. 2 1-R-23, LP-501 Steam Gen.#1 Level
- I Channel No. 3 1-R-3, FP-512B Steam Gen.#1 Steam Flow Channel No. 4 1-R-3, PP-524B Steam Gen.#2 Pressure Channel No. 5 1-R-23, LP-502 Steam Gen.#2 Level Channel No. 6 1-R-3, FP-522B Steam Gen.#2 Steam Flow Recorder No. 3 Connect To: Monitoring Channel No. 1 1-R-4, PP-534B Steam Gen.#3 Pressure Channel No. 2 1-R-23, LP-503 Steam Gen.#3 Level Channel No. 3 1-R-4, FP-532B Steam Gen.#3 Steam Flow Channel No. 4 1-R-4, PP-544B Steam Gen.#4 Pressure Channel No. 5 1-R-23,LP-504 Steam Gen.#4 Level Channel No. 6 1-R-4, FP-542B Steam Gen.#4 SteamFlow O 4 e e *e 3 e.
SQNP SPECIAL TEST 1
- Page 3 of 10 j Rev. 1 l
i O/ * (f 2.0 (Continued)
. Recorder No. 4 Connect To: Monitoring ' Channel No. 1 1-R-3, FP-510B Main Feed Flow, SG#1 Channel No. 2 1-R-3, FP-520B Main Feed Flow, SG#2 Channel No. 3 1-R-4, FP-530B Main Feed Flow, SG#3 Channel No. 4 1-R-4, FP-540B Hain Feed Flow, SG#4 NOTE: If auxiliary feedwater is to be used in place of main feedwater, brush recorder #4 should be in-stalled in the auxiliary control room to record data at the following locations.
Recorder No. 4 Connect To: Monitoring Channel No. 1 F-3-163,TP13,1-L-11B Aux.FeedFlow to SG#1 Channel No. 2 F-3-155,TP13,1-L-11A Aux.FeedFlow to SG#2 Channel No. 3 F-3-147,TP12,1-L-11B Aux.FeedFlow to SG#3 Channel No. 4 F-3-170,TP12,1-L-11A Aux.FeedFlow to SG#4
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NOTE: Record the following on each strip chart: 1 l a) Unit number j g b) Date c) Procedure number d) Parameter scale and range - e) Chart speed
- 2) Name of person recording data g) Recorder ID number 2.8.2 Record-on p-computer recorder -
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- a. Flux
- b. Averagewiderangefcold
- c. Average wide , range hot
- d. Average Steam generator pressure
- e. Reactivity l /
l ! 2.9 A steady feed to the steam generators should be set up to mini-mize temperature variation in the RCS. 1 /
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SQNP SPECIAL TEST I Page 4 of 10 Rev. 1 O V 2.0 (Continued) 2.10 Verify the input logic of safety injection on Hi steam line AP has been blocked in accordance with Appendix E.
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2.11 Verify the Hi steam flow coincident with Lo S/G pressure or Lo i Tav input to safety injection has been modified in accordance with Appendix E.
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2.12 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix E.
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2.13 Verify the following UHI isolation valves are gagged. FCV 87-21 / FCV 87-22 / FCV 87-23 / FCV 87-24 / ( I 2.14 Intermediate and power range (low setpoint) high level reactor
- trip setpoints have been set to 7% in accordar.ce with Appendix C and D of SU-8,5.2. .
4 Power Range / Intermedia,te Range / . i j 3.0 PRECAUTIONS 4 3.1 Do not exceed 5% nuclear power. i 3.2 Abort test if any of the following temperature limits are exceeded: 3.2.1 610 F for any core outlet thermocouple. 3.2.2 65 F for any loop Delta-T. T 3.2.3 578 F for any loop avg. 3.3 Do not exceed primary to secondary differential pressure of 1600 psi. l
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SQNP SPECIAL TEST 1 Page 5 of 10 Rev. 1 3.0 (Continued) t
; 3.4 Avoid rapid changes in steam pressure, steam generator level, and feedwater flow to prevent rapid cooling of the reactor coolant. -l 3.5 Maintain reactor coolant pump seal and thermal barrier differential requirements as given in SOI 68.2.
T 3.6 After the reactor coolant pumps are tripped, th9 normal ava and AT indications will become unreliable. AT and avg should be i calculated by taking the difference and the average of the hot l and cold leg temperatures indications respectively. T 3.7 Maintain cold at the pretrip temperatures by adjusting the steam dump setpoint. 3.8 Should a reactor trip take place during the conduct of this test, restart at least one reactor coolant pump (#2) prior to closing the reactor trip breaker. 3.9 Maintain D bank at 2 100 steps during the conduct of this test. Should this limit be reached boran concentration
, will have to be increased.
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SQNP SPECIAL TEST 1 Page 6 of 10 Rev. 1 0 4.0 SPECIAL TEST EQUIPMENT Calibration Instrument Specification Identification Verification Strip Chart Recorder Brush 260 or equivalent j (4) l l Reactivity Computer Westinghouse Recorder (1) EP 7100B or equivalent i i 4 i If test instruments are changed during this test, the instrument informa-tion must be recorded here and an entry made in the chronological log book explaining this change. O 8 G g
SQNP i SPECIAL TEST 1 i Page 7 of 10 Rev. 1
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l 5.0 INSTRUCTIONS NOTE: Data acquisition steps need not be repeated for multiple test performances. N/A sign offs for these steps. 5.1 Prepare the plant computer to record data as specified in Appendix D. Record the initial steady state values for these points on Data Sheet 5.1.
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5.2 Start the brush recorders in the auxiliary instrument room and start monitoring of data points on the computer trend typewriter.
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CAUTION: Continuously monitor main-steam line pressures and carefully control feedwater addition during the transient to ensure that differential pressure between any two steam lines does not exceed 100 psid. NOTE: Steam generator pressure, level, and flow conditions should be held as close as possible to stable conditions through the duration of the transient. Reactor coolant gystem cold leg j ) temperatures should be maintained within + 5 F of the initial values. NOTE: At the initiation of natural circulation (RCP trip) the following temperature response is expected. a) Wide rangeThot, - increase b) Wide range cold, - slight increase or constant
- l c) d)goreexitthermocouple,-increase avg indication, - unreliable e) Delta-T indications, - unreliable f) Pressurizer level and pressure, - increase 5.3 Simultaneously trip all four reactor coolant pumps in accordance with S0I 68.2.
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5.4 Maintain RCP seal flow at a minimum of 6 gpm to each pump.
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SQNP SPECIAL TEST 1 Page 8 of 10 Rev. 1 O 5.0 (Continued) 5.5 Maintain pressurizer pressure control in automatic and manually i adjust charging flow to match letdown and maintain a constant RCS water mass. i
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NOTE: Pressurizer heaters and auxiliary spray may be controlled manually as needed. 5.6 Carefully control additions of feedwater to the steam generators 4 to maintain levels at approximately 33%. Do not allow steam generator level to drop below 24% on narrow range indicators.
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NOTE: Natural circulation flow will be stable when: T a) AT between wide range hot andTeold is constant. b) AT between wide range cold and core exit T/C average temperature is constant. c) Wide rangeThot ~ core exit T/C average temperature. (See Table 1). () ' 5.7 After steady state conditions have been reached mark each re-corder chart to indicate equilibrium has been reached and e continue recording data. -
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5.8 Insert control bank D as specified by test engineer until the hot zero power test range is reached. - l / CAUTION. Ensure pressurizer spray controller outputs are approxi-mately zero before starting RCP's 1 or 2. 5.9 Af ter reactor coolant pumps have been shutdown for at least 30 minutes, restart the RCP #2 in accordance with SOI 68.2. Con-
- tinue to collect data through the restart.
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5.10 After steady state conditions have been reached, restart reactor coolant pump #1 in accordance with SOI 68.2. Continue to collect I data through the restart.
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SQNP SPECIAL TEST 1 Page 9 of 10 Rev. 1 f% (_) 5, . 0 (Continued) 5.11 After steady state conditions have been reached restart reactor i coolant pump #3 in accordance with SOI 68.2. Continue to col-l lect data through the restart.
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5.12 After steady state conditions have been reached restart reactor coolant pump #4 in accordance with SOI 68.2. Continue to col-lect data through the restart. l-
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! 5.13 Stop the trush recorders in the auxiliary instrument room, and terminate trend recording on the plant computer.
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5.14 Incorporate the brush recorder charts and computer printouts on Data Sheet 5.2.
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5.15 Remove the block of input logic of sefety injection on Hi steam line AP in accordance with Appendix E, unless the next test to be performed requires the block to be installed. If this is the q g case, disregard this step, place N/A it the signature line and initial. -
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5.16 Remove modification to Hi steam flow coincident with Lo S/G pressure or Lo Tav input to safety injection in accordance with - i 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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' 5.17 Remove block of automatic initiation cf safety injection in accord-ance 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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SQNP SPECIAL TEST 1 Page 10 of 10 Rev. 1
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5.0 (Continued) 5.18~ 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 signature line and initial. FCV 87-21 / FCV 87-22 / FCV 87-23 / FCV 87-24 / 5.19 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 sigature line, and initial. Power Range / Intermediate Range / 6.0 ACCEPTANCE CRITERIA O
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6.1 cere exit rec temPeratore dees not e ceed 61o 1. .
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6.2 Delta-T for any loop does not exceed 65*F. l . T 6.3 avg for any loop does not exceed 578'F.
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T 6.4 Delta-T established between wide hot and eold is stable and less than 65*F.
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6.5 Delta-T established between wide range cold and core exit T/C average temperature is stable and less than 65"F. i i
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SQNP
- SPECIAL TEST 1 6 Page 1 of 3 i, Rev. 1
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DATA SHEET 5.1 INITIAL CONDITIONS Unit Date Time Pressurizer Pressure psig PR-68-340 Pressurizer Level % LR-68-339 RCS Loop 1 Hot Leg Temperature F TR-68-1 RCS Loop 1 Cold Leg Temperature F TR-68-18 RCS Loop 2 Hot Leg Temperature F TR-68-1 RCS Loop 2 Cold Leg Temperature F TR-68-18 RCS Loop 3 Hot Leg Temperature F TR-68-43 - RCS Loop 3 Cold Leg Temperature F
. TR-68-60 RCS Loop 4 Hot Leg Temperature F I TR-68-43 1 RCS Loop 4 Cold Leg Temperature F TR-68-60 Steam Generator 1 Level (NR) %
(LI-3-42) Steam Generator 2 Level (NR) %
.(LI-3-97)
. Steam Generator 3 Level (NR) %
(LI-3-110) Steam Generator 4 Level (NR) %
.(LI-3-110) n
() Recorded by / ! 13 g a e
SQNP SPECIAL TEST 1 Page 2 of 3 Rev. 1 0 ~ DATA SHEET 5.1 INITIAL CONDITIONS Unit Date Time Steam Generator 1 Level (WR) % LR-3-43 Pen 1 I Steam Generator 2 Level (WR) % LR-3-43 Pen 2 Steam Generator 3 Level (WR) % LR-3-98 Pen 1 Steam Generator 4 Level (WR) % LR-3-98 Pen 2 Steam Generator 1 Pressure psig PI-1-2A Steam Generator 2 Pressure P818 PI-1-9A Steam Generator 3 Pressure P818 - PI-1-20A -
; Steam Generator 4 Pressure . psig PI-1-27A Steam Generator 1 Feedwater Flow gpm (FI-3-35A)
Steam Generator 2 Feedwater Flow spm (FI-3-48A) Stet- Generator 3 Feedwater Flow gpm (FI-3-?0A) Steam Generator 4 Feedwater Flow gpm (FI-3-103A) Steam Generator 1 Steam Flow lbs/hr (FI-1-3A) Steam Generator 2 Steam Flow lbs/hr (FI-1-10A) () Recorded by / 14 eme -
SQNP SPECIAL TEST 1 Page 3 of 3 Rev. I F '\ DATA SHEET 5.1
, INITIAL CONDITIONS Unit Date Time Steam Generator 3 Steam Flow lbs/hr (FI-1-21A)
Steam Generator 4 Steam Flow lbs/hr i (FI-1-28A) Loop 1 Tavg F (TI-68-2E) Loop 2 Tavg F (TI-68-25E) Loop 3 Tavg F (TI-68-44E) Loop 4 Tavg F (TI-68-67E) 1 Loop 1 AT - F (TI-68-2D) Loop 2 AT F (TI-68-25D) . l Loop 3 AT F (TI-68-44D) Loop 4 AT F (TI-68-67D) NIS Channel N-41 % 1 NIS Channel N-42 _ l NIS Channel N-43 % NIS Channel N-44 % I Recorded by / e l (m) Checked by / 15 i 1
SQNP SPECIAL TEST 1 Page 1 of 1
.; Rev. 1 0, - DATA SEET 5.2 i-
. Attach copies of the computer trend printout and brush recorder charts to this page.
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SQNP SPECIAL TEST 1 Page 1 of 1 Rev. 1 0 .
- APPENDIX A h
References i
- 1. FSAR
- 2. Technical Specifications 1 3. Plant Operating Instructions E0I-5 j SOI-68.2 1
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SQNP
-! SPECIAL TEST 1
. Page 1 of 1 i Rev. I h
k APPENDIX B i I Test Deficiencies #
-i Test Deficiency i
Reconnended Resolution
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l Final Resolution 6 1 l l t Originator / I Signature Date . PORC Review of Final Resolution Date Approval of Final Resolution / Plant Superintendent Date O 18 i l
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SQNP
' SPECIAL TEST 1 Page 1 of 11 Rev. 1 U
APPENDIX C i 6 I Procedure for Determining Core Power Level l l I 3 . J e 9 l l t l O 19 e T'
SQNP l SPECIAL TEST 1 Page 2 of 11 Rev. 1 APPENDIX C Outline i
! I. Core Power Determination 3
A. Primary Side Calorimetric (Forced Circulation Only) i
- 1. Reference (~ 550 F) Calorimetric (Before NC test)
I a) Output used to adjust M/D Power Monitor Program's power conversion constant. B. M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent
; power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.
- 2. Power Monitoring p/
a) The M/D Power Monitor Program will calculate the integral s 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. 20
SQNP i SPECIAL TEST 1
- Page 3 of 11
! Rev. I ti '( APPENDIX C f, 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. O
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SQNP SPECIAL TEST 1 Page 4 of 11 Rev. 1 ) l O APPENDIX C I. 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-: 1 C 10 E. 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 fol' lows:
a) Enter a value of 1.0 into the P-250 for the addresses *
.I shown in the table below, b) With all 5 path selector switches set to normal, run a flux trace.
c) With all 5 path selector switches set to Emergency, run a second flux trace.
! d) Determine the detector normalization constants from Data Sheet C.2.
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SQNP SPECIAL TEST 1 Page 5 of 11 Rev. 1 k.) APPENDIX C
, CORE POWER DETERMINATION 1
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-j g rent. Update as required.
Address Value Function Set the Power K0901 'l Normalization Factor Selects the Modified K5525 1 " Flux Map Print" Programs - I K0900 0 Initiated Pass Number Calibration Constant for K0864 Variable (I) M/D Power Monitor (1) Variable: The value entered is a ratio of the Primary Calorimetric Indicated Power (Item B on Data Sheet C.1) to the M/D calculated power (UO906) times the current value entered in (K0864). If no value has been entered into (K0864) enter 0.25. Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906) e
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SONP SPECIAL TEST 1 Page 6 of 11 Rev. 1 O APPENDIX C CORE POWER DETERMINATION 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 (U0906) is printed af ter each pass
, and may be trended by the P-250 if desired. The individ-ual detector normalized integrals and axial offsets are l ; also printed.
- 5. The M/D Power Monitor printout should be attached to this pro-cedure.
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SQNP SPECIAL TEST 1 i Page 7 of 11
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. APPENDIX C l
PART C: Using Thermocouples i 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 lines and four diagonal tilts) the following L
should be verified: K0701-K0765 = 1, For the flow mixing factors K5501 = 0, Indicates the measured core AT is unreliable i K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the run-ning frequency of the Thermocouple Averaging Program at 1, 2, . . . . X 8 seconds or 64 seconds for us. The thermocouple programs breaks the core down into eight quand-l k rants--four centerline and four diagonal quandrants (see Figure C-1). Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot. - The quadrant tilts are in.dicative of power shifts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts: l Quadrant Addressable Value i 1 U1159 2 U1160 3 U1161 4 U1162 5 U1151 6 U1152 7 U1153 8 U1154 A Short Form Map should be run periodically or upon request from the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for ob-taining thermocouple maps. r~s The frend output and Short Form Maps should be attached to this (_) procedure at the end of the test. 25 q r m o e-
SQNP SPECIAL TEST 1 Page 8 of 11 Rev. 1 APPENDIX C TABLE C-1 Temp Cp(I) s
'F BTU /lbm F lbm/hr 7
556 1.260 3.6448 x 10 7 i 554 1.255 3.6553 x 10 7 552 1.250 3.6659 x 10 3.6765 x 10 7 550 1.245 7 548 1.240 3.6862 x 10 7 ' 546 1.236 3.6959 x 10 7
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544 1.231 3.7057 x 10 O 542 1.226 3.7155 x 10 7 7 3.7254 x 10 a 540 1.221 7 538 '1.217 3.7348 x 10 536 - 1.213 3.7443 x 10 7 - 7 534 1.209 3.7538 x 10 7 532 1.206 3.7633 x 10 7 530 1.202 3.7729 x 10 (I)These values are from the 1967 ASME Steam Tables. Values are for a pres-sure of 2250 psia. O 26
SQNP
. SPECIAL TEST 1 Page 9 of 11 i Rev. 1 (m) APPENDIX C f
FIGURE C.1 i CENTER LINE QUARTER-CORE SYMMETRY t Cdd Logs i 3
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N-43 m ,,g N.42 O O ll l { \
, 3 j , 2 l 4
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<so e y,a,p -
N 5'? ( -) . . P. I 4 s I/ ( ) ExConE DETECTORS OvfvO #~#4 N-f/ 2 .
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- Cold Legs l
1 s Of AGONAL QUARTER. CORE SYMMETRY l . m' a,s s ,
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SQNP SPECIAL TEST 1. Page 10 of 11 Rev. 1 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 Test Point 1 Loop A T - Inservice (at test point) Volts 2 Loop A T = (#1) x II) F 3 Loop A H = (#2) x Cp (from Table C.1) BTU /lbe 6 Loop RCS Flow (from Table C.1) 4 10 lbs/hr 6 5 Loop Reactor Power = (#3) x (#4) 10 BTU /hr 6 Total Reactor Power = (#5) 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307 !WT
. 8 % Reactor Power = (#7) x 0.02932 %
( Conversion factor for AT obtained from scaling document. Remarks: Date By: Checked By: e e
SQNP
- JPECIAL TEST 1 , Page 11 of 11 Rev. 1
.~. L,'i APPENDIX C DATA SHEET C.2 l A l N= BN* N* N* N= FN* l
- AE= BE* E* E E= FE*
N = 1.00 A N B=AN_
= Ak =
B N N NC* N N N =AN = NCCE = II D N N D N E=
= DE =
E N N
' E N l = EE =
q ) F=A{ I I N N Definitions: A,B' N N N, DN ' N, FN = No'rmalized integral from summary map for each detector in a normal path in the first
, pass -
I A,B,C'U, E g E E e, F E
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= Normalized integral from summary map for each detector in an emergency path in the second pass N,N,N,N,N,N A B C D g p = Detector normalization factor for each de-tector
. Remarks:
Data By: Date Checked By: Date ("'N, V 29 T
SQNP SPECIAL TEST 1 Page 1 of 4 Rev. I APPENDIX D c3 Li Procedure For Use Of Computer System For Data Collection The following parameters will be monitored during this test using the plant computer system. Parameter Computer Point Pressurizer Pressure P0480A Pressurizer Level LO480A t 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 I k RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressure P0400A - l - 1 t Steam Generator 1 Narrow Range Leve LO400A Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level LO420A Steam Generator 3 Pressure PO440A Steam Generator 3 Narrow Range Level LO440A Steam Generator 4 Pressure P0460A Steam Generator 4 Narrow Range Level LO460A Power Range Channel 1 (Quadrant 4) N0049A Power Range Channel 2 (Quadrant 2) N0050A Power Range Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A
) Incore Thermocouples T0001A through T0065A 30
?
SQNP SPECIAL TEST 1 Page 2 of 4 Rev. 1 O \' / , APPENDIX D The computer trend typewriter will be used to monitor the following com-puter points. (Additional points may be added as required by the test director). j BLOCK 1 i l Column Point Column Point Column Point I
; 1 P0480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 PO400A 17 PO460A 6 T0426A 12 LO400A 18 LO460A BLOCK 2 i 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
(^J'
\ 5 T0002A 14-18 As Required 6 T0013A -
To initially clear each data block. perform the following step for each block to be used.
- 1. Push DIGITAL TREND button
- l 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 2 button
- 6. Push STOP button l
Repeat the above 6 steps for each data block to be used. ] NOTE: A Block Trend Error message will occur if the data block is ini-tially clear. J l l l l l 31
SQNP SPECIAL TEST 1 Page 3 of 4 Rev. 1
'-[ APPENDIX D h
j 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 .
l 2. Select the point address (i.e. PO480A) on the I alphanumeric keyboard l 3. Push ADDRESS button
- 4. Select block number (1 to 6) on keyboard.
j 5. Push VALUE 1 button
- 6. Select column number (1 to 18) on keyboard
- 7. Push VALUE 2 button
- 8. Push START button Once the blocks are set up they can be initiated by performing the follow-ing steps for each block.
- 1. Push DIGITAL TREND butr.on.
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button l 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 I 4. Select new interval number (0 = 30 sec. ,1 = 1 min. ,
2 = 2 min., etc) on keyboard
- 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select C on keyboard
- 5. Push VALUE 3 button
- 6. Push STOP button p
32 i I I 4
4 SQNP ! SPECIAL TEST 1 Page 4 of 4 li Rev. 1 APPENTIX D i
! In addition to the data recorded on the trend typewriter, the following i 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). After selecting the per to be used to record a value, ensure that it is l cleared by performing the following steps.
- 1. Push ANALOG TREND function button
- 2. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
- 4. Push STOP button To start an analog trend perform the following steps.
- 1. Pesh ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on 'he alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select per number (1 to 12) on keyboard
- 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the minimum value of the parameter to be monitored -
- 7. Select range on the keyboard
- 8. Push VALUE 3 button
- 9. Push START button Repeat these steps until all of the desired analog points are being recorded.
- Prior to initiation of the transient, an i as required thereafter, incore i thermocouple maps will be recorded at the programmers console in the computer room. To initiate an incore T/C 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 map
- 3. Push VALUE 1 button
- 4. Select output device code number 20 (on keyboard)
- 5. Push VALUE 2 button
- 6. Select 1 on keyboard for short form map
- 7. Push VALUE 3 button
- 8. Push START button
,r3
,s 33 1
SQNP SPECIAL TEST 1 Page 1 of 11 Rev. 1 APPENDIX E i 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 l
, injection alarm will initiate telling the operator that the condition exists and what the problem is. (2) a reactor trip will take place auto-matica11y. (3) a safety injection can be initiated manually from the g
switch in the control room if conditions warrant.
- 1. Install temporary jumpers and temporary alteration control tags to 1cgic 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: /
p)
. 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 tes,ts from high AP caused by degraded test conditions. (This block will also defeat all AP SI alarms).
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, -
t 73, 76 are all clear prior to starting blocking procedure.
- 3. Hove test trip switch PS-515A in 1-R-7 to the trip position and verify the a.aber 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 l the voltage source in the rack is applied to the first terminal l indicated in each step [the lower numbered terminal]. The 3 (V 34 g .-
SQNP SPECIAL TEST 1 Page 2 of 11 Rev. 1 APPENDIX E ground will already be made up through the trip switch). The wire on the rack side of the terminal block must be lifted and
! taped for the terminal point where the jumper wire is connected The TACF tag will be attached to the bistable switch and the i TACF must note the jumper and the lif ted wire.
- h. NOTE: Orange "Out of Service" stickers should be placed on all l status / alarm windows as the 120V source is connected.
t l 4. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-7 and verify 1-XX-55-6B/25 is clear. Performed by: / Verified by: /
- 5. Hove test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
, Performed by: /
I Verified by: /
- 6. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear.
Performed'by: / Verified by: / , 1
- 7. Hove test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 8. Lift and tape the wire on the rack side of terminal L-5 in the rear of 1-R-7. Apply 120-VAC source to terminals L-5 and L-6 in the rear of 1-R-12 and verify 1-XX-55-6B/73 is clear.
Performed by: / Verified by: /
~
Ll , 35 g ~ .
SQNP
' SPECIAL TEST 1 Page 3 of 11 Rev. 1 N
APPENDIX E
'f.
. 9. Hove test trip switch PS-516D in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 10. Lif t and tape the wire on the rack side of terminal L-7 in the rear of i 1-R-12. Apply 120-VAC source to terminals L-7 and L-8 in the rear of i 1-R-12 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 Dy: / Verified by: / t f- 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
; (3,j 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. Lift and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.
Performed by: / Verified by: /
- 15. Hove 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: / 36
. - - .-~
SQNP SPECIAL TEST I l Page 4 of 11 Rev. 1 0 APPENDIX E e
- 16. I.ift and tape the wire on the rack side of terminal L-7 in the rear of l l-R-II. Apply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-il and verify that XX-55-6B/51 is clear.
Performed by: / Verified by: /
- 17. Hove test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 18. Lift and tape the wire on the rack side of terminal I.-5 in the rear or 1-R-il. 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 9H dification to liigh Steam Flow Coincident with Low S.G. Prensure (, or Low-Low avg Safety Injection
- 19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be cleared.
Performed'by: / Verified by: / , NOTE: If the alarms will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected.
- 20. Hove test trip switch TS412D in R-2 to the trip position and verify the amber light above the switrh comes on.
Performed by: / Verified by: /
- 21. Lift and tape the wire on the rack side of terminal H-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will cicar.
/
Performed by: Verified by: / , _ _ 37
SQNP SPECIAL TEST 1 Page 5 of 11 Rev. 1 ( ,) 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.
j Performed by: / l Verified by: / i 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 l the amber light above the switch comes on.
t Performed by: /
! Verified by: /
l 25. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-H-10. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
. Performed by: /- ,
Verified by:
/
- 26. Move test trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
- Performed by: /
Verified by: /
- 27. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: / NOTE: TheTavg inputs to the high steam flow S.I and steam dump l 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 n pressure alone (600 psig). (This would result in a reactor (j trip, an S. I. alarm, but no S. I. initiation.) 38 3.
SQNP
, SPECIAL TEST 1 Page 6 of 11 Rev. 1 / 1 k sl APPENDIX E t
- 28. Nove test trip switch FSS12B in R-3 to the trip position and verify
, the amber light and annunciator XA-55-6B/2 come on.
Performed by: / Verified by: /
. 29. Move test trip switch FSS22B in R-3 to the trip position and verify the j amber light and annunciator XA-55-6B/ come on.
Performed by: / Verified by: / NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal.
- 30. Apply Temporary Alteration Control 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:
t,R-7 RACK TEST SWITCH TEMP ALT. NO. PSS15A / R-7 PSS15B / R-12 PSS16C / R-12 'PSS16D / R-8 PS525B / I R-8 PSS25A / R-11 PS526D / R-11 RS526C / R-2 TS412D /
; R-6 TS422D /
R-10 TS432D / R-13 TS442D / i R-3 FSS12B / R-3 FS522B / 1 l
.To return the steamline Delta-P S.I. to normal condition, the following steps should be followed. )
,~
\_,A 39 l
e +
SQNP SPECIAL TEST 1 Page 7 of 11 Rev. 1 7-) A) APPENDIX E i NOTE: The orange "Out of Service" stickers should be removed from the alarm / status window as each bistable is put back in service. j 31. Remove the 120-VAC source from L-5 and L-6 in 1-R-11. Reterminate wire on L-5. j 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.
Performed by: / Verified by: /
- 33. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire i on L-7.
Performed by: / Verified by: / () l
- 34. Move test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/51 are -clear.
Perhormed.by: -/ Verified by: / 1 35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9. I Performed by: / Verified by: /
- 36. Nove 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'from L-7 and L-8 in 1-R-8. Reterminate wire
, on L-7. Performed by: / l j() Verified by: / 40 _g .- +-- .. . . .
SQRP SPECIAL TEST 1 Page 8 of 11 Rev. 1 s
- (V') APPENDIX E
- 38. Hove test trip switch PS-525B in 1-R-8 to the normal position and verify i 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. Hove 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-c ,
nate wire on L-5. ( ,3') i Performed by: / Verified by: /~
- 42. Move test trip switch PS-516C'in 1-R-12 to the normal position and verify the amber light above the switch and 1-XX-55-6B/73 are clear.
Performed by: / Verified by: /
- 43. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi-
- nate wire on L-7.
Performed by: / Verified by: / 1
..44. 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: /
\
Q 41 E
SQNP SPECIAL TEST 1 Page 9 of 11 Rev. 1 L/ APPENDIX E
- 45. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Ret e rmi-nate wire on L-9.
Performed by: / Verified by: /
- 46. Move 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. Toreturntgehighsteamflowcoincidentwithlowsteamgeneratorpressure or low-low avg to normal, perform the following steps.
- 47. Move test trip switch FSS22B in R-3 to the normal position and verify the amber light goes out and XA-55-6B/9 will clear.
j g Performed by: /
/
Verified by:
- 48. Hove 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.
Performed by: / - Verified by: /
- 49. 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: /
- 50. Hove 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: / (,, Q,Y 42 l -
SQNP
- SPECIAL TEST 1 Page 10 of 11 Rev. 1
' APPENDIX E
- 51. Remove the 120-VAC source from terminals M-3 and M-4 in R-10. Retermi-
? nate wire on M-3.
1 Performed by: / Verified by: /
- 52. Hove test trip switch TS432D in R-10 to the normal position and verify j the amber light goes out and XA-55-6A/30 will clear.
Performed by: / Verified by: /
- 53. Remove the 120-VAC source from terminals M-3 and !!-4 in R-6. Retermi-nate wire on M-3.
Performed by: / Verified by: /
- 54. Hove 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.
l I Performed by: / Verified by: /~
- 55. Remove the 120-VAC source fro'm terminals M-3 and M-4 in R-2. Retermi-nate wire on M-3.
I Performed by: / Verified by: /
- 56. Move 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: /
<m
( ) v 43
SQNP SPECIAL TEST 1 Page 11 of 11 Rev. I m APPENDIX E
. 57. Remove the Temporary Alteration Tage on the following test trip switches:
I RACK TEST SWITCH TEMP ALT. NO. 1 i R-7 PSS15A / R-7 PS515B / j R-12 PSS16C / R-12 PSS16D / R-8 PS525B / R-8 PS525A / R-11 PSS26D / R-11 RS526C / I R-2 TS412D / l R-6 TS422D / R-10 TS432D / t R-13 TS442D / R-3 FS512B / R-3 FS522B /
- 58. Remove the jumpers and the Temporary Alteration Tags from logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50. . .
I R-47 Panel Performed by: / e 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. k L] 44 _, ,,_ - . . - - . - - -r-
SQNP SPECIAL TEST 1 Page 1 of 1 Rev. 1 APPENDIX F Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. 8 d E e :s
- Po e8
- u d .a g c Ie % 0 E E o Oem 2E8 8 ?
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T 8 9d . . . U 6 U00 001 3
> E UUUUU* O
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5
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2 0 33 33" Wn OBY$gl 8 c 8 O e ,S e e a b 3 e e e U TECHNICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment HI Pressure SI (3.3.2.1) X X X X X X X X X X Safety Limits (2.1.1) X X X X X X X X X OPAT (3.3.1) Inoperable because of low flow X X X X X X X X OTAT (3.3.1) Inoperable because of low flow 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) bypassed X X X X X X X X X X High Steamflow coincident 91 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 l 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 l UHI (3.5.1.2) X X X X X X X X X X j AFW (3.7.1.2) X X
- Diesel Gens. (3.8.1.1) X X l A.C. Electrical Boards (3.8.2.1) X X l Battdries (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 (O) 45
SQNP SPECIAL TEST 1 Page 1 of 1 Rev. 1 O TABLE 1 Loop Flow and Core AT for Various Power Levels and Isolation Configurations , (Computer Estimates)
! I .
I No. of Loops Operating (Nat. Circ.) Power Level 4 3 2 1 N W
.5% L= 3.7 L= 3.6 "L = 4.1 L= 5.2 i AT = 10.3 AT = 12.5 AT = 16.4 AT = 26 N N
.75% L= 3.7 L= 4.1 L= 4.7 L= 5.9 AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 N N 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 t 2% L= 5.2 L= 5.7 L= 6.5 L= 8.2 AT = 26 AT = 31.4 AT = 41 AT = 65.4 N N ' 2.5% L= 5.6 L= 6.2 L= 7.1 L= 8.9 AT = 30.1 AT = 36.5 AT = 47.1 AT = 75.9 3% L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE: L is % of 97,000 gpm flow through operable loop. AT = Loop AT in 'F. C) v 46 l l l
m ~ Jwa _ L. - -m_ - - ea - u _, _ _ ,,_. - -- - - - _ - -_ - - - - --- O I SPECIAL TEST NO. 2 NATURAL CIRCULAT?)N WITH SIMULATED LOSS OF OFFSITE AC POWER O - j i
+
e 4 0 Oe ,
- - - - - - _ ___ _ -w
SQNP SPECIAL TEST 2
- Page 1 of 1
- Rev. 1 i
. NATURAL CIRCULATION WITH SIMULATED LOSS OF OFFSITE AC POWER Table of Contents P.agg I
Test Description 1 Special Operator Instruction 2 1 1.0 OBJECTIVES 3 2.0 PREREQUISITES 4 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPMENT 9 5.0 INSTRUCTIONS 10 6.0 ACCEPTANCE CRITERIA 16 DATA SHEETS 7 APPENDIX A - References 21 APPENDIX B - Deficiencies 22 APPENDIX C - Power Measurement Technique 23
, APPENDIX D - Computer Points 34 ,
APPENDIX E - Vital Equipment List 38 APPENDIX F - Safeguard Blocking Procedure 41 APPENDIX G - Technical Specifications Exceptions 52 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 53 l O g a. - . .m+ . +
- _ ._ _ ._ -4 -__
SQNP i SPECIAL TEST 2 j Page 1 of 1 Rev. 1 ( TEST DESCRIPTION This test is intended to provide a significant demonstration of reactor operation in the natural circulation mode under the degraded condition of loss of offsite AC power. The initial conditions for this test shall be as follows:
- a. The reactor shall be at approximately 1% power. (Simulating reactor decay heat at hot standby following power operation).
- b. All four reactor coolant pumps operating.
- c. Auxiliary Feedwater System in service operating on offsite power.
- d. Pressurizer Heaters in service controlling pressure.
l e. Primary System at normal operating temperature and pressure. This test will be conducted by simultaneously tripping all four reactor coolant pumps and initiating a blackout on the unit 1 6.9-kV shutdown boards which will result in a loss of motor-driven auxiliary feedwater pumps end pressurizer heaters. After the appropriate time delay, the O. diesel generators will energize the 6.9-kV shutdown boards and the motor-driven auxiliary feedwater pumps and pressurizer heaters will be reener- - gized. The establishment of natural circulation will be verified. - , O I
. . . . . . . . '........ .l- -
SQNP SPECIAL TEST 2 Page 1 of 1 Rev. 1 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 Window 6 Initiates An operator initiated reactor trip should be performed for any of the fol-lowing conditions: Reactor Ccolant System Subcooling 5 15' O 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
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
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SQNP SPECIAL TEST 2 Page 1 of 14 Rev. 1 . O
, 1.0 OBJECTIVES 1.1 The objectives of this test are to demonstrate that following a loss of offsite AC power, natural circulation cooling can be established and maintained while being powered from the emer-i gency diesel generators. In addition it will be verified that after offsite power is restored, the emergency loads can be transferred to offsite power and the diesel generators restored to standby status.
1.2 To provide operator training. All operating shifts will perform i this test. NOTE: Data acquisition'does not need to be repeated for multiple test performances.
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SQNP SPECIAL TEST 2 Page 2 of 14 Rev. 1 1.0 PREREQUISITES 2.1 Reactor is critical and manually controlled at approximately 1% power with control bank D at 160 steps or as specified by test engineer. (Power determined as indicated in Appendix C).
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2.2 All four reactor coolant pumps in operation.
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I 2.3 RCS pressuge at approximately 2235 psig and temperature of approxi-mately 548 F, and pressurizer level E 27-28%.
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2.4 Pressurizer pressure and level control system in automatic.
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2.5 Auxiliary Feedwater System in service and operating on offsite power in accordence with System Operating Instruction SOI 3.2A and B. p g O 2.6 Steam pressure approximately 1005 psig and being maintained by steam dump to the condenser.
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2.7 Steam generator level being maintained at approximately 33% on
- the narrow range indicators and under automatic control.
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2.8 Steam generator chemistry in a condition such that the absolute minimum steam generator blowdown can be maintained during conduct
. of this test. (Zero blowdown if possible).
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2.9 Excess letdown is available for service if required during the test. l /- l l 2.10 6.9-kV Shutdown Board 1A-A energized from 6900V unit board.
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SQNP
- SPECIAL TEST 2 Page 3 of 14 Rev. 1 0 2.0 (Continued) 2.11 6.9-kV Shutdown Board 1B-B energized from 6900V unit board.
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! 2.12 Diesel generators lA-A and IB-B in standby status. I
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2.13 Control and auxiliary building service air compressors C and D in service powered from the auxiliary building common board.
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2.14 Unit 1 turbine turning gear oil pump on the emergency DC supply.
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2.15 Waste Gas compressor B in service. (Powered from unit 2 Rx Vent Board 2A-A).
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s 2.16 Close/ Verify 1-FCV-1-17 by placing 1-HS-1-17A into manual and close g) position. (1-HS-1-17A located on panel 1-M-4).
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1 NOTE: The preceding step will isolate steam feed to the auxiliary feedwater turbine. This is necessary so that verification can be made that natural circulation can be established on emergency (diesel generator) power. The ability to go on natural circula-
- tion with the turbine-driven AFWP will be verified during the conduct of Special Test No. 7.
2.17 Record the following parameters. NOTE: Data acquisition steps need not be repeated for multiple test parameters. N/A sign offs for these steps. 1 2.17.1 Record on p-computer recorder.
- a. Flux
- 3. Average wide range T eo)d ~
c_ Average wide range T d: Average steam generaIf pressure
- e. Reactivity
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G V 5 4
.m.,..... .%. ,e* * - ** ** en -
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SQNP SPECIAL TEST 2 Page 4 of 14 Rev. I t ~.," 2.0 (Continued)
! 2.17.2 Connect recorders to the following test points:
I 5 Recorder No. 1 Test Point Location Monitoring Channel No. 1 1-R-1, FP414B RCS Flow - Loop 1 Channel No. 2 1-R-1, FP424B RCS Flow - Laop 2 Channel No. 3 1-R-1, FP434B RCS Flow - Loop 3 Channel No. 4 1-R-1, FP444B RCS Flow - Loop 4 Channel No. 5 1-R-1, FP455B Pressurizer Pressure Channel No. 6 1-R-1, LP459B Pressurizer Level Recorder No. 2 Test Point Location Monitoring Channel No. I 1-R-3, PP-514B Steam Gen #1 Pressure Channel No. 2 1-R-23, LP-501 Steam Gen #1 Level Channel No. 3 1-R-3, FP-512B Steam Gen #1 Steam Flow , Channel No. 4 1-R-3, PP-524B Steam Gen #2 Pressure Channel No. 5 1-R-23, LP-502 Steam Gen #2 Level Channel No. 6 1-R-3, FP-522B Steam Gen #2 Steam Flow Recorder No. 3 Test Point Location Monitoring i Channel No. I 1-R-4, PP-534B Steam Gen #3 Pressure Channel No. 2 1-R-23, LP-503 Steam Gen #3 Level (;
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Channel No. 3 1-R-4, FP-532B Steam Gen #3 Steam Flow
. Channel No. 4 1-R-4, PP-544B Steam Gen #4 Pressure Channel No. 5 1-R-23, LP-504 Steam Gen #4 Level Channel No. 6 1-R-4, FP-542B Steam Gen #4 Steam Flow Recorder No. 4 Test Point Location Monitoring Channel No. 1 L-3-163,TP13,1-L-llB Aux. Feed Flow to SG#1 -
Channel No. 2 L-3-155,TP13,1-L-11A Aux. Feed Flow to SG#2 Channel No. 3 L-3-147,TP12,1-L-llB Aux. Feed Flow to SG#3 Channel No. 4 F-3-170,TP12,1-L-llA Aux. Feed Flow to SG#4
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2.17.3 Record on the recorder charts the following information:
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- a. Unit number
- b. Date
- c. Procedure number
- d. Scale and range of parameters recorded
- e. Chart speed
- f. Time matter interval
- g. Recorder I.D. No.
- h. Name of individual record.ng data i NOTE: Ensure recorders are powered from vital AC.
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SQNP SPECIAL TEST 2 ! Page 5 of 14 l Rev. 1 0 , 2.0 (Continued) i 2.17.4 Set the trend recorders and camputer trend printer in the main control room t eonitor the parameters indicated in
, Appendix D.
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i 2.18 Verify the input logic of safety injection on Hi Steam Line AP has been blocked in accordance with Appendix F. l 2.19 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 F. '
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2.20 Verify the automatic initiation of Safety Injection has been blocked in accordance with Appendix F.
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2.21 Verify the following UHI isolation valves are gagged.
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( ,/ FCV 87-21 /
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FCV 87-22 / FCV 87-23 / FCV 87 / 2.22 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 /
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SQNP SPECIAL TEST 2 Page 6 of 14 Rev. 1 O i 30 PRECAUTIONS 3.1 Maintain reactor coolant pump seal and. thermal barrier differen-tial pressure requirements as given in SOI 68.2. (It is recom-mended that component cooling pump C-S be utilized being powered from unit 2 480-V shutdown board 2B2-B and aligned to provide A & B train cooling water for unit 1). 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: i 3.3.1 Core exit temperature of 610 F 3.3.2 AT as indicated by hTc of 65 F T 3.3.3 RCS avg 578 F 3.4 When equilibrium is established after the initial transient, avoid any sudden changes in auxiliary feedwater flow or in steam gener-ator water level. l' 3.5 After the reactor coolant pumps are tripped, the normal Tavg and AT indication will become unreliable. AT should be calculated taking the difference (T - T O averaseerthesetadcB1d18)andTavgcalculatedbytakingthe temPerat re indicatie s. 3.6 Following the blackout and after the diesel generators energize the shutdown boards, the blackout should be reset and Operations personnel should immediately be dispatched to energize or verify energized as necessary the equipment listed in Appendix E. CAUTION: Do not exceed D/G rating.
- 3.7 Maintain pressurizer. level greater than 20%.
3.8 Reactor Coolant Pumps should not be restarted for 30 minutes after pump trip unless safety concerns necessitate the re-establishment of forced circulation. A 3.9 Should a reactor trip take place during the conduct of this test, re tart at least one reactor coolant pump (#2) prior to closing the reactor trip breaker. 3.10 Maintain D bank at 2: 100 steps during the conduct of this pro-cedure. Should this limit be reached, boron concentration will have to be increased. O 8 i
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SQNP SPECIAL TEST 2 Page 7 of 14 Rev. 1 4.0 SPECIAL TEST EQUIPMENT I Calibration Instrument Specification Identification Verification Strip Chart Recorder Brush 260 or equivalent 6-channel (2) Reactivity Computer Westinghouse Recorder (1) HP 7100B or Equivalent f'
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If test instruments are changed during this test, the instrument information must be recorded here and an entry made in the chronological log book ex-plaining this change. i O 9 I l J n
SQNP SPECIAL TEST 2 Page 8 of 14 Rev. 1 I V 5.0 TEST INSTRUCTIONS NOTE: Data acquisition steps need not be repeated for multipic test perfo rmances . N/A sign offs for these steps. 5.1 Clear the unit I control room area of all nonessential personnel.
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5.2 Place / verify 6.9-kV shutdown board 1A-A manual transfer selector switch XS-57-43, located on panel 1-M-1, to the manual position. I
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5.3 Place / verify 6.9-kV Shutdown board IB-B manual transfer selector switch XS-57-70, located on panel 1-M-1, to the manual position.
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5.4 Place / verify D/G 1A-A 43TL test switch located on 6.9-kV shutdown board 1A-A logic relay panel, to the normal position.
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5.5 Place / verify D/G 1B-B 43TL test switch, located on 6.9-kV Shutdown
. Board IB-B logic relay panel to the normal position.
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l 5.6 Place diesel generator 2A-A 43TL switch, located on 6.9-kV shut-down board 2A-A logic relay panel to the test position. l . 5.7 Place diesel generator 2B-B 43TL switch, located on 6.9-kV shutdown board 2B-B logic relay panel to the test position.
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NOTE: This will prevent auto start of diesel generators 2A-A and 2B-B when the blackout signal is initiated on diesel generators IA-A and IB-B. 5.8 Record data indicated on Data Sheet 5.1.
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5.9 Place / verify pressurizer backup heaters 1A-A and IB-B in automatic.
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SQNP SPECIAL TEST 2 Page 9 of 14 Rev. 1 A V
- 5. 0 (Continued) 5.10 Trip pressurizer backup' heaters 1C & ID by hand switches HS-69-341H and HS-68-34'1F respectively. (Stop-Pull to Lock).
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5.11 Start the computer trend printer printing as fast as possible. (See Appendix D).
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5.12 Start the strip chart recorders located in the auxiliary instrument room and auxiliary control room.
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NOTE: The next step will simulate a loss of offsite power. Following RCP trip, the following response is expected: Widerangefcold - alight increase or stable Wide range hot - increase goreexitT/C - increase avg - unreliable AT - unreli,-ble
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(' ') Pressurizer Pressure - increast 5.13 As close to simultaneously as possible perform the following actions. NOTE: Time zero
- a. Trip all 4 reactor coolant pumps ,
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- b. Trip 6.9-kV Shutdown Board 1A-A normal feeder ACB 1718
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- c. Trip 6.9-kV Shutdown Board 1B-B normal feeder ACB 1726
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- d. Place steam dump controls 1-HS-1-103A and 1-HS-1-103B to off and place controllers to manual.
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SQNP SPECIAL TEST 2 Page 10 of 14 Rev. 1 LO 5.0 (Continued) 5.14 Verify diesel generators lA-A and 1B-B started, energized their 6.9-kV shutdown boards and the following equipment sequenced onto the shutdown boards: Component Cooling Water Pumps /
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Auxiliary Feedwater Pumps / Centrifugal Charging Pumps / Pressurizer Heaters / ERCW Pumps /
- Remove non-essential loads.
i i i CAUTION: If either diesel generator fails to start, manually restore
' power to that shutdown board by closing either the normal or alternate feeder supply breaker.
I 5.15 Re-establish normal letdown and transfer control of the pressur-izer heaters to manual control to prevent over pressurizing the pressurizer.
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5.16 Dispatch Operations personnel to reset blackout and re-energize
, equipment required from the list in Appendix E.
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5.17 Begin printing'T/C maps every 15 minutes from time zero. (See - Appendix D).
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NOTE: Monitor reactor power closely and make any. adjustments necessary to maintain approximately 1-percent power. 5.18 Verify the steam generator level returns to normal level (approxi-mately 33%).
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5.19 Verify automatic control o~f auxiliary feedwater flow and power-operated reliefs to maintain a normal operating level and pres-sure in the steam generators (approximately 33% level and 1025 Psig). 12 I -
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SQNP SPECIAL TEST 1 Page 11 of 14 [ Rev. 1
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50 (Continued) NOTE: If automatic control of auxiliary feedwater and power reliefs fail to maintain the normal steam generator level and level, change to manual control of auxiliary feedwater flow control valves and power relief valves. 5.20 Verify natural circulation is established in accordance with the
- operational guideline of Emergency Operating Instrection 5 (Black-out), Appendix A, and maintain steady state conditions for 30 minutes.
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NOTE: Natural circulation flow will be stable when: T
- a. 6T between wide range hot and cold is constant.
i b. 6T between wide range Teold and core exit T/C average temperature is constant. t c. Wide range hot a core exit T/C average temperature. (See Table 1) 5.21 Turn off data recorders and note time on charcs. t ('~)) / x 5.21 Establish ventilation and cooling in the remaining areas- in accord-
.ance with E0I 5, Sections C through G (Subsequent Operation Action).
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5.23 Perform section V " Recovery", steps I through K, of E0I S. *
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. 5.24 Verify steam supply header to the AFWP turbine warm and open FCV l-1-17 by placing handswitch 1-HS-1-17A to the open position, return to P-Auto.
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NOTE: This valve was closed to prevent operation of the AFWP Turbine during a blackout. 4 5.25 Adjust condenser dump controllers to 0% output.
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SQNP SPECIAL TEST 2 Page 12 of 14 Rev. 1 O,
,~# 5.0 (Continued) t 5.26 Place steam dump controls 1-HS-1-103A and 1-HS-1-103B to the
'On' Position.
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5.27 Place steam dump controllers in auto and adjust to maintain approximately 1000 psig steam pressure.
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5.28 Establish the following conditions and verify: 5.28.1 Insert control rod bank D until the reactor is in the hot zero power test range.
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NOTE: Ensure pressurizer spray valves are closed prior j to starting any RCP. t 5.28.2 Restart reactor coolant pumps 2, 1, 3, and 4. (In the indicated sequence). (-, . I
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5.28.3 RCS pressure at agproximately 2235 psig and temperature at - approximately 548 F. - l 5.28.4 Pressurizer pressure and level controls in automatic. ,
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accordance with SOI 3.2A and 3.2B.
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5.28.6 Steam pressure approximately 1000 psig and being maintained by steam dump to the condenser.
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5.28.7 Steam generator level being maintained at approximately 33% on the narrow range indicators and under automatic control.
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SQNP SPECIAL TEST 2 Page 13 of 14 Rev. I p)
.t
'T f 5, . 0 (Continued)
.' 5.28.8 Collect data charts and attach to data sheet 5.2.
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5.29 Remove the black of input logic of safety injection on Hi steam line AP in accordance with Appendix F'uuless 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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5.30 Remove modification to Hi Steam Flow coincident with Lo S/G pres-sure or Lo Tav input to Safety Injection in accordance with Appendix F unless the next test to be performed requires the modification to be made. If this is the case, disregard this step, place N/A in the signature line and initial.
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i 5.31 Remove block of automatic initiation of Safety Inject'an in accord-ance with Appendix F unless the next test to be per' .med requires l the modification to be made. If this is the case .isregard this step, place N/A in the signature line and initial. (~q\ '
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5.32 Remose the gag from the followng UHI isolation valves unless the next test to be performed requires the valves to be gagged. If this is the case, disregard this step, place N/A in the signature line and initial. FCV 87-21 / FCV 87-22 / FCV 87-23 / FCV 87-24 / 5.33 Reset the intermediate and power range high level reactor trip setpoints as indicated by the test director in accordance with Appendix C and D of SU-8.5.2 unless the next test to be per-formed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial. Power Range / Intermediate Range / l l N-) 15 l 1 l __
SQNP SPECIAL TEST 2 Page 14 of 14 Rev. 1 6.0 ACCEPTANCE CRITERIA i j 6.1 Core exit T/C temperature did not exceed 610 F.
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6.2 Delta-T for any loop did not exceed 65 F.
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T 6.3 ava for any loop did not exceed 578 F.
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6.4 Natural circulation was establi.hed and maintained while emergency l loads were powered from the emergency diesel generators.
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6.5 Offsite power was restored and the emergency loads transferred back to offsite power.
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SQNP SPECIAL TEST 2 Page 1 of 3 Rev. 1
, DATA SHEET 5.1 Initial Conditions Pressurizer Pressure l PR-68-340 Psig Pressurizer Level LR-68-339 Red Pen %
#1 Hot leg temp o TR-68-1 F
#1 Cold leg temp o
TR-68-18 F
! #2 Hot leg temp o
6 TR-68-1 F l 1 #2 Cold leg temp
' o TR-68-18 F l
#3 Hot leg temp o
TR-68-43 f
#3 Cold leg temp o
TR-68-60 F
#4 Hot leg temp -
o TR-68-43 F
#4 Cold leg temp ' .
o TR-68-60 F S.G. #1 Level (narrow range) LI-3-42 % S.G. #2 Level (narrow range) LI-3-55 % S.G. #3 Level (narrow range) LI-3-97 % S.G. #4 Level (narrow range) ~ LI-3-110 I S.G. #1 Level (wide range)
- LR-3-63 Pen 1 %
Datt by: / 17 D
SQNP SPECIAL TEST 2 Pr.ge 2 of 3 Rev. 1 O (s DATA SHEET 5.1 S.G. #2 Level (wide range) LR-3-43 Pen 2 , % s S.G. #3 Level (wide range) LR-3-98 Pen 1 % S.G. #4 Level (wide range) LR-3-98 Pen 2 % S.G. #1 Pressure PI-1-2A Psig S.G. #2 Pressure PI-1-9A Psig S.G. #3 Pressure PI-1-20A Psig
; S.G. #4 Pressure
; PI-1-27A Psi 8 S.G. #1 Feedwater flow FI-3-35A gpm O. -
S.G. #2 Feedwater flow - FI-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 i
S.G. #2 Steam flow FI-1-10A lbs/hr S.G. #3 Steam flow FI-1-21A lbs/hr S.G. #4 Steam flow l FI-1-28A lbs/hr l Loop #1 T-average i TI-68-2E o F Data by: / 18 i
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- SQNP SPECIAL TEST 2 Page 3 of 3 Rev. 1 i
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, DATA SHEET 5.1 i
, Loop #2 T-average TI-68-25E ,F Loop #3 T-average o
TI-68-44E F Loop #4 T-average TI-68-67E ,F Loop #1 AT TI-68-2D % Loop #2 AT TI-68-25D % Loop #3 AT TI-68-44D % Loop #4 AT TI-68-67D % (0-55 F = 0-100%) t l ' NIS Channel N-41 (Power Range Channel 1) Computer Point N0049A % NIS Channel N-42 (Power Range Channel 2) Computer Point N0050A % NIS Channel N-43 (Power Range Channel 3) Computer Point N0051A % i NIS Channel N-44 (Power Range Channel 4) Computer Point N0052A % Remarks: [ l l Data by: / Reviewed by: /
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. SQNP SPECIAL TEST 2 Page 1 of 1
- Rev. 1 O)
( DATA SHEET 5.2 Date Time Unit Attach the computer printout from the following parameters. Refer to Appen-t dix D for the computer log points and setup procedure. These parameters
! should be printed every minute until equilibrium conditions are reached.
- At this time, the interval can be changed to 2- or 3-minute intervals.
At 15-minute intervals from time =0, print out a core thermocouple map as outlined in Appendix D. Attach maps to this data sheet. Pressurizer pressure Pressurizer Level RCS Loop 1 Hot Leg Temp RCS Loop 2 Hot Leg Temp RCS Loop 3 Hot Leg Temp RCS Loop 4 Hot Leg Temp RCS Loop 1 Cold Leg Temp RCS Loop 2 Cold Leg Temp
; RCS Loop 3 Cold Leg Temp i RCS Loop 4 Cold Leg Temp Steam Generator 1 Pressure Steam Generator 1 Narrow Range Level 1 O
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Steam Generator 2 Pressure
'# Steam Generator 2 Narrow Range Level 1 -
Steam Generator 3 Pressure - Steam Generator 3 Narrow Range Level 1 Steam Generator 4 Pressure Steam Generator 4 Narrow Range Level 1 Power Range Channel 1 Power Range Channel 2 Power Range Channel 3 Power Range Channel 4 Incore Thermocouples #1 through #5 (upper head) l O 20
SQNP SPECIAL TEST 2 Page 1 of 1 Rev. 1 O . APPENDIX A References
- 1. FSAR
- 2. Technical Specifications
; 3. Plant Operating Instructions: SOI 3.2 SOI 68.2 E01 5 t
6 - l I O 21 o -
SQNP SPECIAL TEST 2 Page 1 of 1
' Rev. 1 i i l
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, APPENDIX B 1
Test Deficiencies # Test Deficiency Recommended Resolution l l Final Resolution l l 1 i l Originator / Signature Date PORC Review of Final Resolution Date Approval of Final Resolution / Plant Superintendent Date O V 22 4.
SQNP SPECIAL TEST 2 Page 1 of 11
. Rev. 1 .O APPENDIX C 1
i. I Procedure for Determining Core Power Level a l i h a p O I O 23 g . .
SQNP SPECIAL TEST 2 Page 2 of 11 Rev. 1
. APPENDIX C Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)
- 1. Reference ( ~ 550 F) Calorimetric (Before NC test) a) Output used to adjust M/D Power Monitor Program's power conversion constant.
! B. M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in per-cent power and equal to the primary calorimetric output.
- 2. Power Monitoring
() a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 5 or 6 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to once every 2 minutes or as necessary to. continuously monitor core power. O 24
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SQNP SPECIAL TEST ' Page 3 of 11 Rev. I 1o , APPENDIX C l l l 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-i fled for each loop as rapid as possible. l 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 j j 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. l l () . . r
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SQNP SPECIAL TEST 2 Page 4 of 11 Rev. 1 0; , APPENDIX C i 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 E 10 L-11 r C 10 E-5 D 10 E-11 E 6 J-8 F 8 P-9
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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 5-path selector switches set to normal, run a flux trace. c) With all 5 path selector switches set to Emergency, run a second flux trace. d) Determine the detector normalization constants from Data Sheet C.2. 26 g e
- SQNP SPECIAL TEST 2 Page 5 of 11 Rev. 1 0'
\- ' APPENDIX C j Core Power Determination i 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-
{'i rent. Update as required. Address Value Function - Set the Power K0901 1 Normalization Factor
, Selects the Modified K5525 1 " Flux Hap Print" Programs K0900 0 Initiated Pass Number Calibration Constant K0864 Variable (g) for M/D Power Monitor (I) 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 entered in (K0864).
If no value has been entered into (K0864) enter 0.25. Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906) O 27 F
SQNP SPECIAL TEST 2 Page 6 of 11 Rev. 1 APPENDIX C Core Power Determination PART B: (Continued) r l
- 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 g required. NOTE: The calculated power (UO906) is printed after each pass and may be trended by the P-250 if desired. The individ-l ual detector normalized integrals are also printed, t 1 ( - l l . I I O 28 N
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SQNP SPECIAL TEST 2 Page 7 of 11 Rev. 1 APPENDIX C TABLE C-1 Tgmp Cp(1) m"
, F BTU /lbe,F lbs/hr 556 1.260 3.6448 x 10 7 7
554 1.255 3.6553 x 10 552 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 7 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 7 540 1.221 3.7254 x 10 7 . 538 1.217 3.7348 x 10 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 7 i l (1)These values are from the 1967 ASME Steam Tables. Values are for a pressure i of 2250 psia. t O 29 g . . . . . - _ . . . . . . . ., . .- .. -. 4 -*
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.w, SQhP SPECIAL TEST 2 Page 8 of 11 Rev. 1 APPENDIX C Data Sheet C.1 Date Time Unit Power Tavg F Loop 1 Loop 2 Loop 3 Loop 4 Item # Calculation Procedure Units R2/TP-411J R6/TP=421J R10/RP-431J R13/RP-441J l Loop AT - Inservice (at test point) Volts 2 Loop AT = (#1) x (1) F 3 Loop NI = (#2) x Cp (from Table C.1) BTU /lba 6
4 Loop RCS Flow (from Table C.1) 10 1bm/hr 6
. U 5 Loop Reactor Power = (#3) x (#4) 10 BTU /hr Total Reactor Power = (#5) 0 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307 HVf 8 % Reactor Power = (#7) x 0.02932 %
> (1) Conversion factor for AT obtained from scaling document. Remarks: Date By: Checked By: 4 9
SQNP SPECIAL TEST 2 Page 9 of 11 Rev. 1 O APPENDIX C (Continued Ag= By= Cy= Dy= E y= F y= AE= BE* E= DE* E* E*
, Ng = 1.00 A
NB=
= AE =
B N N N = ' E =
! C=A[N N C
ND
- D--
= CE =
D N N
' D N = DE =
E=E N E N
= NE EE =
Ng = A]{ I I N N
, Definitions:
i A,B,C,D' N N N N N, FN = Normalued integral from summary map for each - detector in a normal path in the first pass A,B' E, EE, FE = Normalized integral from summary map for each E E E' detector in an emergency path in the second pass N,N,N,N..N,N A B C D E y = D'etector normalization factor for each detector
- Remarks:
Data By: Date I .
/
31 l ~
~
k
SQNP SPECIAL TEST 2 Page 10 of 11 Rev. 1 (3
. APPENDIX C i
l Part C: Using Thermocouples The incore thermocouples can be used as an indication of both core flow distribution and power shifts during natural circulation. Prior to running a thermocouple map or trending the eight quadrant tilts (four center line and four diagonal tilts) the following should be verified: K0701-K0765 = 1, For the flow mixing factors K5501 = 0, Indicates the measured core AT is unreliable K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the run-ning frequency of the Thermcouple Averaging Pro-gram at 1, 2, . . . X 8 seconds or 64 seconds for us. The thermocouple programs breaks the core down into eight quadrants-- l I four centerline and four diagonal quadrants (see Figure C-1). Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot. - The quadrant tilts are indicative of power shifts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts: I Quadrant Addressable Value 1 U1159 2 U1160 3 U1161 4 Ull62 5 Ull51 6 U1152 7 Ull53 8 U1154 A Short Fcrm Map should be run periodically or upon request from the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for obtaining thermocouple maps. 7s The trend output and Short Form Maps should be attached to this l ( ,) procedure at the end of the test. 32 w
- s
SQNP SPECIAL TEST 2 Page 11 of 11 Rev. 1 APPENDIX C CENTER.LINE QUARTER CORE SYMMETRY Cdd Le.os
' *3 4 .
; N-43 m 2,f m N-42 -
. , O O 1 3
/ ,
1 14 2 s i. i=N e s e r-11a ley ( .y ._ P j 4 3 1 ( ) ExCORE DETECTORS
- o v ,f v o W-41 2 1 N-44 l ;
l Cdd Lap i O
~
( . , I f Of ACONAL QUART ER-CORE SYMMETRY 225* 315' s , 6 I 8' , 6 S. T Nx
. , tS- ;s-Fi3are C-t O
33 I
% ~
1 SQNP SPECIAL TEST 2 Page 1 of 4 REV. 1 APPENDIX D Procedure For Use Of Computer System For Data Collection The following parameters will be monitored during this test using the plant computer system. Parameter Computer Point Pressurizer Pressure PO480A Pressurizer Level LO480A I 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 P0400A Steam Generator 1 Narrow Range Level 1 LO400A Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level 1 LO420A , Steam Generator 3 Pressure PO440A Steam Generator 3 Narrow Range Level 1 LO440A Steam Generator 4 Pressure P0460A . Steam Generator 4 Narrow Range Level 1 LO460A Power Range Channel 1 (Quadrant 4) N0049A Ps ier Range Channel 2 (Quadrant 2) N0050A Power Range Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A I- Inc re Thermocouples T0001A through T0065A O 34 h'
SQNP SPECIAL TEST 2 Page 2 of 4 I Rev. 1 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 PO420A 2 LO480A 8 T0446A 14 LO423A l
3 T0419A 9 T0479A 15 P0440A l 4 T0406A 10 TO466A 16 LO443A P0460A 5 T0439A 11 PO400A 17
. 6 T0426A 12 LO403A 18 LO463A BLOCK 2 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A
' T0059A 3 N0051A 9 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. l 1. Push DIGITAL TREND button j 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select 0 on keyboard *
- 5. Push VALUE 2 button
- 6. Push STOP button Repeat the above 6 steps for each cata block to be used.
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.
- 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 keyboard.
- 5. Push VALUE 1 button
- 6. Select column number (1 to 18) on keyboard
- 7. Push VALUE 2 button (j 8. Push START button 35 i
SQNP SPECIAL TEST 2 Page 3 of 4 Rev. 1 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 I
- 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.,
I 2 = 2 min., etc) on keyboard
- 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
. 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard -
- 3. Push VALUE 1 button
- 4. Select C on key. board
- 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 i 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. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
- 4. Push STOP button O
36 f a
.. . s
SQNP SPECIAL TEST 2 Page 4 of 4 Rev. 1 ( APPENDIX D To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button i 2. Select the computer point address (i.e. T0043A)
{ on the alphanumeric keyboard j 3. Pusb ADDRESS button
! 4. Sele : per number (1 to 12) on keyboard
- 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the I
minimum value of the parameter to be monitored
- 7. Select range on the keyboard
- 8. Push VALUE 3 button
- 9. Push START button Repeat these steps until all of the desired analog points are being recorded.
j Prior to initiation of the transient, and as required thereafter, incore thermocouple maps will be recorded at the programmers console in the computer room. To 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 (f #
- 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 I
1 O 37 i e . me* . m. ,* +=
h SQNP SPECIAL TEST 2 Page 1 of 3 Rev. 1 ( - APPENDIX E Verification of Vital Equipment Energized Verification Component Power Feed Location (Initials or N/A if not required) General Supply
; Fan IA 480V S.D. Bd 1Al-A i
General Exhaust Fan lA 480V S.D. Bd 1A2-A General Supply Fan IB 480V S.D. Bd IB1-B
' General Exhaust Fan IB 480V S.D. Bd 1B2-B C/A Vent Bd 1A2-A 480V S.D. Bd 1A2-A Rx Vent Bd 1A-A 480V S.D. Bd 1Al-A 1 / 'N Control & Service Air k/ s -
Compressor A 480V S.D. Bd 1A2-A Control Room . A/C Comp. A-A 480V. S.D. Bd 1A2-A Control Room AHU A-A ' 480V S.D. Bd 1Al-A Control & Service Air 480V S.D. Bd IB1-B Compressor B '
' Control Room A/C 480V S.D. Bd 1B2-B Cc=p. B-B Control Room AHU B-B 480V S.D. Bd 1B2-B Component Cooling System Rx HOV Bd 1Al-A Booster Pump A-A Intore Instrument Room Rx HOV Bd 1Al-A CIRC. Pump 1A Incore Instrument Room Rx HOV Bd 1Al-A Chilled Water Compressor O
38
SQNP SPECIAL TEST 2 Page 2 of 3 Rev. 1 rx (sy) APPENDIX E Verification i Component Power Feed Location (Initials or N/A if not required) Incore Instrument Room Rx MOV Bd 1Al-A Air Conditioner I Boric Acid Transfer Rx HOV Bd LAl-A Pump 1A-A Boric Acid Tank A Rx MOV Bd 1Al-A Heater A-A Boric Acid Tank C Rx MOV Bd 1Al-A Heater A-A Boron SIS INJ Tank Rx HOV Bd 1Al-A Heater IA-A Incore Inst Room Cire Rx MOV Bd Pump 1B 1B1-B
/'N Incore Inst Room \ms) Rx MOV Bd Cooler Fan 1B1-B Incore Inst Room Rx MOV Bd Chilled Water Comp 1B IB1-B Boric Acid Tank A Rx MOV Bd Heater B-B 1B1-B ~
Boron SIS INJ Tank Rx HOV Bd Heater B-B 1B1-B Boric Acid Tank C Rx HOV Bd Heater B-B 1B1-B Boric Acid Transfer Rx MOV Bd Pump 1B-B 1B1-B Component Cooling Rx HOV Bd System Booster Pump B-B 1B1-B Containment Annulus C/A Vent Vacuum Fan IA Bd 1Al-A Cent. Charging Pump 1A-A C/A Vent Room Cooler Fan Bd 1Al-A t (u'l l l 39 9 .
- .- w r
* *g
SQNP SPECIAL TEST 2 Page 3 of 3 Rev. 1 o . APPENDIX E Verification Component (Initials or Power Feed Location N/A if not required) t Component Cooling and Aux C/A Vent Feedwater Pumps Space Bd 1Al-A Cooler Fan __ CRDM Room C/A Vent A/C Bd 1A2-A Cent. Charging Pump 1B-B C/A Vent Room Cooler Fan Bd IB1-B Aux Feedwater Pump C/A Vent
, Space Cooler Fan Bd IB1-B Containment Annulur. C/A Vent Vacuum Fan IB Bd IB1-B a CRDM Room C/A Vent
() f ' A/C Bd 1B2-B Upper Compartment Rx Vent Bd - Cooler Fan lA 1A-A
' ~
Upper Compartment Rx Vent Bd Cooler Fan 1C 1A-A Upper Compartment Rx Vent Bd Cooler Fan IB 1B-B Upper Compartment Rx Vent Bd Cooler Fan ID 1B-B Waste Gas Rx Vent Bd Compressor A 1A-A O 40
SQNP SPECIAL TEST 2 Page 1 of 11 Rev. 1 O APPENDIX F V 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-matica11y. (3) a safety injection can be initiated manr. ally from the switch in the control room if conditions warrant.
- 1. Install temporary jumpers and temporary alteration control tags to logic cards A216, test peint 1, to the logic ground on the logic test 9
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: / q - Verified by: / b . 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 tes.ts from high AP caused by degraded test conditions. (This block will also defeat all AP SI alarms).
- 2. Verify status lights-1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51,
- 73, 76 are all clear prior to starting blocking procedure.
- 3. Move test trip switch PS .il5A 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 l h, 41 t %
SQNP SPECIAL TEST 2 Page 2 of 11 Rev. 1 (3 U . APPENDIX F 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
't TACF must note the jumper and the lif ted wire, t
i NOTE: Orange "Out of Service" stickers should be placed on all status / alarm windows as the 120V source is connected. t
- 4. Lift and tape the wire on the rack side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-7 and verify 1-XX-55-6B/25 is clear.
' Performed by: /
Verified by: / i 5. Hove test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
. Perforsed by: /
, Verified by: /
- 6. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear.
Performed by: /
. Verified by: / .
- 7. Hove test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 8. Lif t and tape the wire on the rack side of terminal L-5 in the rear of 1-R-7. Apply 120-VAC source to terminals L-5 and L-6 in the rear of 1-R-12 and verify 1-XX-55-6B/73 is clear.
Performed by: / Verified by: / l ! 42 i
SQNP SPECIAL TEST 2 Page 3 of 11 Rev. 1 O APPEhDIX F l 9. Hove test trip switch PS-516D in 1-R-12 to the trip position and verify
; the amber light above the switch comes on.
Performed by: / , Verified by: /
- 10. Lift and tape 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. Hove test trip switch PS-525B in 1-R-8 to trip position and verify the amber light above the switch comes on.
Performed by: / l i 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. Hove test trip switch PS-525A in 1-R-8 to the trip position and verify
- I the amber light above the switch comes on.
Performed by: / Verified by: /
- 14. Lif t and tape the wire on the rack side of tenminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.
Performed by: / Verified by: /
- 15. 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: / 43
SQNP SPECIAL TEST 2 Page 4 of 11 Rev. 1
. APPENDIX F
- 16. Lif t and tape the wire on the rack side of terminal L-7 in the rear of
. 1-2-11. Apply 120-VAC source to terminals L-7 and L-8 in the rear of I 1-R-11 and verify that XX-55-6B/51 is clear.
Perforned by: / Verified by: /
; 17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 18. Lift and tape the wire on the rack side of terminal L-5 in the rear or 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is clear.
Performed by: / Verified by: /
, Temporary Mgdification to High Steam Flow Coincident with Low S.G. Pressure (L,j or Low-Low avg Safety Injection
- 19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be cleared.
Performed "by: / Verified by: / . NOTE: If the alarms will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables.should be checked and the source of the problem corrected.
- 20. Move 7.est trip switch TS412D in R-2 to the trip position and verify the a: ber light above the switch comes on.
Performed by: / Verified by: /
.21. Lift tnd tape the wire on the rack side of terminal M-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify l .
XA-5',-6A/30 will clear. Performed by: / Verified by: / 1 l 44 Ie I,
SQNP SPECIAL TEST 2 Page 5 of 11 Rev. 1 APPENDIX F N'~,N ) i
- 22. Move test trip switch TS-422D in R-6 to the trip position and verify j the amber light above the switch comes on.
Performed by: / I 7erified by: /
- 23. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: /
- 24. Move test trip switch TS432D in R-10 to the trip prsition an1 verify the amber light above the switch comes on.
Performed by: / _ Verified by: /
- 25. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-10. Apply a 120-VAC source to terminals M-3 and M-4 and verify
() XA-55-6A/30 will clear. Performed by: /- Verified by: /
- 26. Hove 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: / I t'
- 27. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: / NOTE: The avg inputs to the high steam flow S.I and str.am 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 t.n a reactor trip, an S. I. alarm, but no S. I. initiation.) {J$ 45 p . . - - . - - * * * -
SQNP SPECIAL TEST 2 l Page 6 of 11 l Rev. 1 Oi - APPENDIX F i
- 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.
Performed by: / Verified by: / , j 29. Move test trip switch FS522B in R-3 to the trip position and verify the i amber light and anntaciator XA-55-6B/ come on. Performed by: / Verified by: / NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal.
- 30. Apply Temporary Alteration Control Tags forms to all the above test trip switches to ensure that they remain in the trip position.
! Damage to the bistable could occur if the switch is moved back to ! the normal position. Record the temporary alteration numbers below:
I
. RACK TEST SWITCH TEMP ALT. NO.
R-7 PSS15A / . R-7 PSSISB / R-12 PSS16C . / R-12 PS516D /
, R-8 PS525B /
1 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 /
To return the steamline Delta-P S.I. to normal condition, the following steps
. should be followed.
O) s 46
SQNP 4 SPECIAL TEST 2 Page 7 of 11
, Rev. 1 0'-
APPENDIX F i a _', NOTE: The orange "Out of Service" stickers should be removed from the alarm / status window as each histable is put back in service. I
- 31. Remove the 120-VAC source from L-5 an! L-6 in 1-R-11. Retermt, ate 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.
I 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: 6
/
- 34. Move test trip switch PS-526D in 1-R-11 to the normal position and -
verify the amber light above the switch and 1-XX-55-6B/51 are clear.
, Performed .by: /
Verified by: /
- 35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.
Performed by: / Verified by: /
- 36. Hove test trip switch PS-525A in 1-R-8 to the 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 from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.
Performed by: / (,,) Verified by: / 47 e
SQNP SPECIAL TEST 2 Page 8 of 11 Rev. I t APPENDIX F l I
- 38. 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.
I 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. Move 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 cn L-7.
' Performed by: /
Verified by: /
.44. Nove 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: / a p 48 m 9
SQNP SPECIAL TEST 2 Page 9 of 11 Rev. I rm -(y APPENDIX F
- 45. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Rete rmi-nate wire on L-9.
Performed by: /
! Verified by: /
- 46. Move 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. Toreturntgehighsteamflowcoincidentwithlowsteamgeneratorpressure or low-low avg to normal, perform the following steps.
- 47. Hove test trip switch FS522B in R-3 to the normal position and verify
-s ,
the amber light goes out and XA-55-6B/9 will clear.
\~# Performed by: / -
Verified by: /
- 48. 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: /
- 49. 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: /
- 50. Hove 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: / (~N L) 49 )
1
' SQNP SPECIAL TEST 2 Page 10 of 11 Rev. 1
APPENDIX F 4
l. j 51. 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: /
- 52. 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.
Performed by: / Verified by: /
- 53. 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: /
- 54. 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.
I k Performed by: / Verified by: /'
- 55. Remove the 120-VAC source from terminals M-3 and M-4 in R-2. Retermi-nate wire on M-3. ,
i Performed by: / Verified by: /
- 56. Move 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: /
/m
\._ s 50 l
A L
h SQNP SPECIAL TEST 2 Page 11 of 11 Rev. 1 APPENDIX F
- 57. Remove the Temporary Alteration Tags on the follosing test trip switches:
RACK TEST SWITCH TEMP ALT. NO. R-7 PSS15A / R-7 PS$15B / R-12 PS516C / R-12 PSS16D ,
/
R-8 PSS25B /
! R-8 PSS25A /
R-11 PS526D / R-Il RS526C / R-2 TS412D / R-6 TS422D / R-10 TS432D / R-13 TS442D / R-3 FS512B / R-3 FSS22B /
- 58. Hemove 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. i e O 51
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SQNP SPECIAL TEST 2 Page 1 of 1 Rev. 1 (% APPENDIX G Technical Specifications Exceptions 1 The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. 0 E E e : :
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%e 30$$ " o 8 90 . . . t a" EaEEEi 5 > #
0tOOd* "' a 5 su s a w $$$* M 2*O23$$ c e BaBBB"%{E A3AAe$2eee m B 8 d TECllNICAL 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 OTAT7 3.3.1) Inoperable because of low flow 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 S1 (3.3.2.1) bypassed X X X X X X X X X X liigh Steamflow coincident 9 w/ low steamline 1 pressure or low-low yvpl 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 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 O
v (3.4.1.2) X X X X X X X X 52 l
SQNP SPECIAL TEST 2 Page 1 of 1 Rev. 1 7 s, () TABLE 1 Loop Flow and Core AT for Various Power Levels and Isolation Configurations (Computer Estimates) l i I No. of Loops Operating (Nat. Circ.) Power Level 4 3 2 1
! .5% L= 3.7 L= 3.6 L= 4.1 "L = 5.2 AT = 10.3 AT = 12.5 AT = 16.4 AT = 26
.75% L= 3.7 L= 4.1 L= 4.7 L= 5.9 AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 N
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 gpm flow through operable loop. AT = Loop AT in *F. 53 e *
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i O . i I I i SPECIAL TEST No. 3 NATURAL CIRCULATION WITH LOSS OF PRESSURIZER }[ EATERS O O a i e I t O
SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 1 O . NATURAL CIRCULATION WITH LOSS OF PRESSURIZER KEATERS Table of Contents 9 Page 1 Test Description 2 Special Operator Instruction 3
.l 1.0 OBJECTIVES 4
2.0 PREREQUISITES 7 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPMENT 9 5.0 TEST INSTRUCTIONS 13 6.0 ACCEPTANCE CRITERIA O 14 DATA SHEETS . 18 APPENDIX A - References
' 19 APPENDIX B - Deficiencies APPENDIX C - Power Measursment Technique 20 APPENDIX D - Computer Points 30 i
APPENDIX E - Safeguard Blocking Procedure 34 45 APPENDIX F - Technical Specifications Exceptions i TABLE 1 - Loop Flow and Core AT for Various Power 46 Levels and Isolation Configurations N I I e O
SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 1 NATURAL CIRCULATION WITH LOSS OF PRESSURIZER HEATERS TEST DESCRIPTION
- The test will be initiated by tripping pressurizer heaters and reactor cool-ant pumps. Establishment of natural circulation will be verified and core exit thermocouples monitored to determine the core flow distribution. System pressure will be monitored to determine the rate of depressurization and, prior to reaching saturation, control of the saturation margin will be veri-fled through the use of primary system charging flow an.d secondary system steam flow.
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SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 1 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 Window 6 initiates An operator initiated reacto; 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
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
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SQNP SPECIAL TEST 3 Page 1 of 11 Rev. 1 lO ii 1.0 OBJECTIVES r 1.1 Verify natural circulation conditions can be established in all loops once the RCP's are tripped. l , 1.2 Verify the ability to maintain natural circulation and saturation margin with the loss of the pressurizer heaters. 1.3 Determine RCS depressurization rate after the RCP's and pressur-izer heaters are tripped. i g 1.4 Verify saturation margin can be controlled through the usc of primary charging flow and secondary steam flow. 1.5 To provide operator training, all shif ts will perform this test. NOTE: Data acquisition does not need to be repeated for multiple test performances. E e (::) . O h h 1 a 3 g e I
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SQNP SPECIAL TEST 3 Page 2 of 11 Rev. 1 ( ) L: 2.0 PREREQUISITIES 2.1 The reactor is critical at ~ 3% power and under manual control with control bank D at 160 steps or as specified by test engineer. (Power level determined as indicated in Appendix C.) Date 2.2 All four reactor coolant pumps in operation. Date 2.3 fteam generator level maintained at approximately 33% on the narrow range indicators by the auxiliary feedwater system Date 2.4 Pressurizer pressure being maintained at approximately 2235 psig automatically by pressurizer heaters and spray and pressurizer level at approximately 26-28%.
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I I Date - 2.5 RCS temperature (Tavg) approximately 550 F. I Date l
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2.6 Low Power Physics Test program has been completed ta the l 4 extent necessary for conduct of this test. ! l l
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Date l l 2.7 Steam generator pressure at approximately 1000 psig and being I maintained by steam dump to the condenser on pressure control. I (or power-operated relief valves). l Date
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SQNP SPECIAL TEST 3 Page 3 of 11 Rev. I p k/ 2.0 PREREQUISITES (Continued)
; 2.8 Connect recorders to the following test points:
! NOTE: Data acquisition steps need not be repeated for multiple test performances. N/A sign offs for these steps.
Recorder 1 Connect To: Monitoring: Channel #1 1-R-1, FP414B RCS Flow-Loop 1 Channel #2 1-R-1, FP424B RCS Flow-Loop 2 Channel #3 1-R-1, FP434B RCS Flow-Loop 3 i ! 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, LPS10 Steam Gen. #1 Level Channel #2 1-R-3, FP512B Steam Gen. #1, Steam Flow i Channel #3 1-R-3, PP514B Steam Gen. #1 Pressure Channel #4 1-R-23, LP502 Steam Gen. #2 Level i Channel #5 1-R-3, FP522B Steam Gen. #2 Steam Flow Channel #6 1-R-3, PP524B Steam Gen. #2 Pressure i
'- 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, PPS34B Steam Gen. #3 Pressure Channel #4 1-R-23, LP504 Steam Gen. #4 Level i Channel #5 1-R-4, PP544B Steam Gen. #4 Pressure - ) Channel #6 1-R-4, FP542B Steam Gen. #4 Steam Flow Recorder 4 Connect To: Monitoring: Channel #1 1-R-18, FP121A RCS Charging Flow Channel #2 1-R-23, FP132 RCS Letdown Flow l Channel #3 1-R-5, PP403A Wide range RCS Press Channel #4 1-R-22, TP454 Press Steam Temp Channel #5 1-R-20, TP453 Press Liquid Temp , Recorder 5 Connect To: Monitoring l Channel #1 L-3-163, TP13, 1-L-11B Aux Feed Flow to SG#1 l L-3-155, TP13, 1-L-11A Aux Feed Flow to SG#2 Channel #2 Channel #3 L-3-147, TP12, 1-L-11B Aux Feed Flow to SG#3 Channel #4 L-3-170, TP12, 1-L-11A Aux Feed Flow to SG#4
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SQNP SPECIAL TEST 3 Page 4 of 11 Rev. 1
'0 %)
2.0 (Continued) NOTE: Record the following on each strip chart: a) Unit number b) Date c) Procedure number d) Parameter scale and range e) Chart speed f) Name of data recorder l g) Recorder ID number i 2.9 Set up the P-250 computer trend printer to monitor the parameters indicated in Appendix D.
/
2.10 Record on the p-computer recorder.
- a. Flux j
- b. Average wide range TTC 10
- c. Average wide range hot
- d. Average steam-generator pressure
- e. Reactivity
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% 2.11 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix E. -
. /
6 2.12 Verify the input logic of safety injection on high steam line
- AP has been blocked in accordance with Appendix E.
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2.13 VerifytgehighsteamflowcoincidentwithLowS/Gpressureor Low-Low avg input to safety injection has been modified in accordance with Appendix E.
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2.14 Verify the following UHI isolation valves are gagged. FCV 21 / FCV 22 / FCV 23 / FCV 24 / m) 6 m ~ <y T
l SQNP SPECIAL TEST 3 Page 5 of 11 Rev. 1 IV ) 2.0 (Continued) 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. t Power Range / l i Intermediate Range / 3.0 PRECAUTIONS t 3.1 Maintain reactor coolant pump seal and thermal barrier differen-tial pressure requirements as given in SOI 68.2. 3.2 Do not exceed 5% nuclear power at any time while the test is in progress. 3.3 Abort test if any of the following temperature limits are exceeded: 3.3.1 Core exit temperature of 610 F. 3.3.2 AT as indicated by T H -T C f 65 F. I 3.3.3 avg Temperature of 578 F. ("% - 3.4 When equilibrium has been established after tripping the RCP's,
\_ ) avoid any sudden changes in feedwater flow or in steam generator ,
l water level. , i ! 3.5 After the reactor coolant pumps are tripped the gormal Tavg and AT indications will be come unreliable. AT and avg should be cal-culated by taking the difference and the average of the hot and i cold leg temperature indications respectively. . ! 3.6 Maintain saturation margin greater than 15 degrees Fahrenheit at all times. T 3.7 Monitor reactor power closely whenever adjustments to cold are made. Maintain cold above 531*F. 3.8 When RCS pressure drops below 1970 psig, manually block S.I. (set-point at 1870 psig). If not blocked, the reactor will trip when the setpoint is reached. 3.9 When RCS pressure is dropped below 1970 psig, isolation valves for the pressurizer PORV's should be closed. 3.10 Should a reactor trip take place during the conduct of this test at least one reactor coolant pump (#2) should be restarted prior to closing the reactor trip breaker, f-~3 3.11 Maintain D bank at 2 100 steps during the conduct of this test. Eq,) Should this limit be reached boron concentration will have to be increased. 7
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SQNP
. SPECIAL TEST 3 Page 6 of 11
'- Rev. I tb Y 4.0 SPECIAL TEST EQUIPMENT Calibration l
Instrument Specification Identification Verification Strip Chart Recorder Brush 260 or equivalent (4)
-Reactivity Computer Westinghouse Recorder (1) HP 7100B or equivalent If test instruments are changed during this test, the instrument information must be recorded here and an entry made in the chronological log book ex-plaining this change.
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SQNP SPECIAL TEST 3 Page 7 of 11 Rev. I q C/ 5.0 TEST INSTRUCTIONS NOTE: Data acquisition steps need not be repeated for multiple test performances. N/A signoffs for these steps. 5.1 Ensure the pressurizer backup heaters IA, 1B, and 1C will remain off by moving handswitches 1-HS-68-341A and 341D to 'Stop' posi-tion and moving 1-HS-68-341H to 'Stop-Pull to Lock'.
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5.2 Record the data indicated on Data Sheet 5.1.
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5.3 Start the computer trend printer printing as fast as possible.
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5.4 Shut off the pressurizer control heater group by moving 1-HS-68-341F to 'Stop'.
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! 5.5 Record the time, on the data recorder charts in the auxiliary instru-
. ment room and then start them at 125 mm/ min.
/ .
5.6 Shutdown the reactor coolant pumps in accordance with SOI 68.2 (Simultaneously).
/
NOTE: At the initiation of natural circulation the following tempera-ture response is expected. l T a) Wide range hot - increase T b) Wide range cold - slight increase or constant c) goreexitthermocouple-increase d) avg indication - unreliable e) Delta-T indication - unreliable f) Pressurizer level - increase 5.7 Verify natural circulation is established by following the opera-tional guidelines given in Appendix A of E0I-5.
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3 SQNP SPECIAL TEST 3
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Page 8 of 11 i Rev. 1
. . 50 (Continued) l r
I NOTE: Natural circulation will be stable when: T
- 1) AT between wide range hot and eold is constant
- 2) AT between wide rangeTcold and core exit thermocouple average tem 9erature is constant
- 3) Wide range hot a core exit thermocouple average tempera-ture (See Table 1) 5.7.1 Assume manual control of charging flow and match charging to letdown to maintain a constant RCS water mass. (i.e.
.I maintain pressurizer level ~ constant after equilibrium has been reached on natural circulation.)
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5.8 Once equilibrium has been established adjust trend printer inter-vals as specified by the test director.
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NOTE: The following steps will allow the pressurizer to cool and slowly decrease system pressure. The purpose is to determine the time that saturation margin can be maintained without the use of pres-surizer heaters and then verify the margin can be reestablished (g ,g) ' ' through charging or secondary steam flow. Reactor power level will be reduced to sipulate an actual shutdown situation with residual heat. - 5.9 The primary system press,ure will now be monitored to determine the rate of depressurization. The saturation margin should be monitored closely on the trend recorder and steam dump or RCS - charging flow increased in accordance with A0I-18 when the satu-I ration margin appraches 20 F or as specified by test engineer. l Caution: Low pressure S.I. should be blocked as pressure drops below 1970 psig to prevent tripping the reactor. 4
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i ' 5.10 After the RCP. trips, begin slowly reducing reactor power to approximately 1.5% and maintain this power level for the dura-tion of the test. (Reduce power at a rate of ~ 1.5% per hour).
/
l 5.10.1 When RCS pressure drops below 1970 psig, close the isola-tion valves for the pressurizer PORV's by placing their respective handswitches in the 'close' position.
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SQNP SPECIAL TEST 3 Page 9 of 11 Rev. 1 Q V 5.0 (Continued) I i 5.11 Once it is determined by the test director that sufficient data
- has been recorded to satisfy the requirements of this test or l saturation margin approaches 20 F, increase saturation margin j above 50 F through the use of charging flow and/or steam dump. ., Do not allow pressurizer level to go above 70%.
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NOTE: Margin yill increase by either increasing RCS pressure or re-ducing cold. Charging must be 1 creased to maintain pressurizer 9 level and pressure when reducing cold. 5.11.1 When RCS pressure is :ncreased above 1970 psig, open the isolation valves for the pressurizer PORV's.
/
5.12 Once saturation margin is above 50 F or pressurizer level reaches 70%, reactivate the pressurizer backup heaters selectively to increase RCS pressure back to 2235 psig.
/
5.13 Stop the recorders and trend printers and attach the printouts (~, and charts to Data Sheet 5.2. i / 1 5.14 Manually adjust PIC-68-3.40A to 40% output and energize the control heater group by moving 1-HS-68-341F to 'On'. Return PIC-68-340A to ' Auto'. l j i NOTE: Maintain RCS pressure at approximately 2235 by using Auxiliary Spray in accordance with SOI 68.3C if necessary. ) 5.15 Insert control bank D until the reactor is in the hot zero power test range.
/
CAUTION: Ensure pressurizer spray controller are at zero output prior to startiag the first reactor coolant pumps. 5.16 Restart all four reactor coolant pumps in accordance with S01-68.2 starting with RCP #2, 1, 3 and.then 4.
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SQNP SPECIAL TEST 3 Page 10 of 11 Rev. 1 O 5.0 (Continue.d 5.17 Return the pressurizer heaters to automatic control by moving 1-HS-68-341A, -341D, and -341H to the ' Auto' position.
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5.18 Return pressurizer level to approximately 26-28% and then return control to auto.
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5.19 RestoreghehighsteamflowcoincidentwithLowS/Gpressureor Low-Low avg input to safety injection in accordance with Appendix E unless the next test to be performed requires this modification j to be made. If this is the case, disregard this step, place N/A in the signature line, and initial. I
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5.20 Remove the block of the input logic of safety injection on high steam line AP in accordance with Appendix E unless the next test to be performed requires the block to be installed. If this is the case, disregard this step, place N/A in the signature line, and initial. t r'% .
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; 5.21 Remove the block of automatic actuation of safety injection in accordance with Appendix E unless the next test to be performed requires the block to be. installed. If this is the case, disre-gard this step, place N/A in the signature line, and initial.
j 5.22 Remove the gags from the following UHI isolation valves unless the valves are required to be gagged in the next test. If this is the case, disregard this step, place N/A in the signature line, and initial. FCV 21 / FCV 22 / FCV 23 / FCV 24 / J v 12
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SQNP SPECIAL TEST 3 Page 11 of 11 i Rev. 1 p
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- 5. 0 (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, and initial.
I Power Range / Intermediate Range / NOTE: Conditions can now be established for the conduct of the next test. 6.0 ACCEPTANCE CRITERIA
, 6.1 Core exit 1/C temperatures did not exceed 610 F.
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l 6.2 Delta-T for any loop does not exceed 65 F. i / t 6.3 T,yg for any loop does not exceed 578 F.
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6.4 RCS saturation margin can be controlled through the use of charging and secondary steam flow.
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6.5 Natural circulation can be established and maintained without the use of the pressurizer heaters.
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SQNP SPECIAL TEST 3 Page 1 of 3 Rev. I DATA SHEET 5.1 Initial Conditions Unis. Date Time Pressurizer Pressure j PR-68-340 Psig 4 Pressurizer Level
, LR-68-339 Red Pen %
! #1 Hot leg temp o f TR-68-1 F i
#1 Cold leg temp o TR-68-18 F
#2 Hot leg temp o TR-68-1 F
#2 Cold leg temp o TR-68-18 F
#3 Hot leg temp TR-68-43 ,F -
#3 Cold leg temp TR-68-60 ,
,F
#4 Hot leg temp o
- TR-68-43 -
F 1
#4 Cold leg temp TR-68-60 ,F l 1
l S.G. #1 Level (narrow range) ! LI-3-42 % S.C. #2 Level (narrow range) LI-3-55 % S.G. #3 Level (narrow range) LI-3-97 % 1S.G. #4 Level (narrow range) LI-3-110 % Recorded By Date 14 g . .
SQNP SPECIAL TEST 3 Page 2 of 3 Rev. 1
. DATA SHEET 5.1 (Continued)
Unit Date Time S.G. #1 Level (wide range) LR-3-43 Pen 1 % S.G. #2 Level (wide range) LR-3-43 Pen 2 % S.G. #3 Level (wide range) LR-3-98 Pen 1 % S.G. //4 Level (wide range) LR-3-98 Pen 2 % S.G.~#1 Pressure PI-1-2A psig S.G. //2 Pressure PI-1-9A psig S.G. #3 Pressure PI-1-20A psig C. S.G. #4 Pressure PI-1-27A - psig S.G. #1 Feedwater flow . FI-3-35A gpm S.G. #2 Feedwater flow FI-3-48A gpm S.G. #3 Feedwater flow FI-3-90A spm S.G. #4 Feedwater flow FI-3-103A gpm S.G. #1 Steam flow F1-1-3A lbs/hr S.G. #2 Steam flow
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FI-1-10A lbs/hr S.G. #3 Steam flow FI-1-21A lbs/hr -h Recorded By
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SQNP SPECIAL TEST 3 Page 3 of 3 Rev. 1 O DATA SHEET 5.1 (Continued) Unit Date Time S.G. #4 Steam flow
! FI-1-28A lbs/hr I-i Loop Ill T-average o TI-68-2E F i
Loop //2 T-average o TI-68-25E F Loop //3 T-average o TI-68-44E F Loop /l4 T-average o TI-68-67E F Loop //l AT o TI-68-2D F Loop //2 AT o TI-68-250 F (.
- Loop #3_AT o TI-68-44D F
; Loop //4 AT TI-68-67D op (0-100% = 0-55 F AT) -
4 NIS Channel N-41 % NIS Channel N-42 %
, NIS Channel N-43 %
Nis Channel N-44 % l l l NOTE: Attach Computer Printout of Incore Thermocouple Temperature Map. Refer to Appendix D for the procedure for printing out of this map.
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Kecorded By Date O 16 - b'
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SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 1 LO , DATA SHEET 5.2 Attach copies of the computer trend printout and the brush recorder charts to this page. From the above data, starting after equilibrium has been reached, calculate the depressurization rate and the pressurizer cooldown rate (liquid temp)
; and record below.
I i Depressurization Rate __ psig/hr. Pressurizer Cooldown Rate F/hr. Calculated by / 1 Reviewed by / e NOTE: A plot of the RCS depressurization rate vs time can be made from the attached data if desired. ? e t i 17
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SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 1 V) APPENDIX A References
- 1. FSAR
- 2. Technical Specifications
- 3. Plant Operating Instructions: SOI 68.2, 68.3 E01 5 AOI 18 i
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SQNP SPECIAL TEST 3 Page 1 of 1 Rev. I f
; - APPENDIX B s
I Test Deficiencies # Test Deficiency I Recommended Resolution i () ~ Final Resolution Originator / Signature Date PORC Review of Final Resolution i Date l Approval of Final Resolution / Plant Superintendent Date 1 l l l l l O 19 O
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SQNP SPECIAL TEST 3 Page 1 of 10 Rev. 1 O APPENDIX C 1 Procedure for Determining Core Power Level l I i O . o 4 e I i l l O 20 t i
SQNP SPECIAL TEST 3 Page 2 of 10 Rev. 1 O V . APPENDIX C (Continued) t Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only) i 1. Reference ( ~ 550 F) Calorimetric (Before NC test) i' a) Output used to adjust M/D Power Monitor Program's power conversion constant. B. M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent power output; this output must be input to the M/D Power-Monitor Program u that the program output will be in percent power e.ad equal to the primary calorimetric output.
- 2. Power Monitoring l
-( ) 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 3 Page 3 of 10 Rev. 1 /^s V APPENDIX C t CORE POWER DETERMINATION j 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-fled for each loop as rapid as possible. C.2 Calculate the AT; multiply that AT by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (Table C-1). (Special Test No. 9 uses wide range AT so a correction factor is required to compensate for pump heating, refer to Appendix D of ST-9A). C.3 Sum the loop heat rates and convert to a percent reactor power. The output is used in Part B. I l ( )) e 8 O 22 k
SQNP SPECIAL TEST 3 Page 4 of 10 Rev. 1 j us APPENDIX C (Continued) Core Power Determination PART B: M/D Power Monitor Program 1
- 1. Set up the movable detector system for a 1 pass partial core e flux map as per TI-53. Select flux thimbles as per the table i 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 () 4 low power physics testing results and previous special testing experience.
- 2. Determine the detector normalization constants and enter them into the P-250 as follows:
a) Enter a value of 1.0 into the P-250 for the addresses shown - in the tabic below. b) With all 5 path selector switches set to normal, run a flux trace. c) With all 5 path selector switches set to Emergency, run a second flux trace, d) Determine the detector normalization constants .trom Data Sheet C.2.
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SQNP SPECIAL TEST 3 Page 5 of 10 Rev. 1 r ()' APPENDIX C (Continued) Core Power Determination PART B: (Continued) e) Enter these detector normalization constants into the P-250 l as shown in the table below.
- l. Drive P-250 Address A K0908 9
B K0909 i 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.
(1) Address Value Function -
, Se?. the Power '
K0901 1 Normalization Factor Selects the Modified K5525 1 " Flux Map Print" programs K0900 0 Initiated Pass Number Calibration Constant for K0864 Variable (1) M/D Power Monitor I ( ) 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 entered in (K0864). If no value has been entered into (K0864) enter 0.25. Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906) A v 24 1
\
l
SQNP SPECIAL TEST 3 Page 6 of 10 Rev. 1
/^g V APPENDIX C +
PART B: (Continued) For power determination, obtain a partial core flux map as per 4.
? TI-53. The M/D's need not be withdrawn between passes, and 'l passes may be repeated as often as a power determination is i required.
I NOTE: The calculated power (UO906) is printed after each pass
, and may be trended by the P-250 if desired. The individ-ual detector normalized integrals are also printed.
TABLE C-1 Temp Cp(1) 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 10 550 1.245 3.6765 x 10 7 548 1.240 3.6862 x 10 546 1.236 3.6959 x 10 7 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 7 540 1.221 3.7254 x 10 5 3t- 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 10 530 1.202 3.7729-x 10 ( )These values are from the 1967 ASME Steam Tables. Values are for a l pressure of 2250 psia. O 25 a a , , ~ - - - -
3 -
- n - _
o:- SQNF SPECIAL TEST 3 Page 7 of 10 Kev. 1 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 1 Loop AT - Inservice (at test point) Volts 2 Loop AT = (#1) x (1) F 3 Loop AH = (#2) x Cp (from Table C.1) BTU /lba 6 4 Loop RCS Flow (from Table C.1) 10 1be/hr 0 5 Loop Reactor Power = (#3) x (#4) 10 BTU /hr 6 Total Reactor Power = (#5) 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307 INT 8 % Reactor Power = (#7) x 0.02932 % (1} Conversion factor for AT obtained from scaling document. Remarks: 4 Date By: Checked By: e
=
( SQNP SPECIAL TEST 3 Page 8 of 10 Rev. 1 C\
. APPENDIX C (Continued)
DATA SHEET C.2 Cy = i AN= BN= DN* N= FN* i D E AE* E= CE= E= E* E*
.00 NA=
Ng =b = NkA = B N N j
- NC*
C N N C N = D
= CE =
D N N D N = = DE = E E N N A N
= EE =
N F=yN y N N (s Definitions: - A,B' N N N, DN ' N, FN = Normalized integral from summary map for each detector in a normal path in the first pass A,B,C,D' E E E E E, FE = Normalized integral from summary map for each detector in an emergency path in the second pass N,N' g E, NF = Detector normalization factor for each de-B C' D'
, tector
. Remarks: Data By: Date O 27
.g i
~ - -y. , , , - ,, . - . - .
SQNP SPECIAL TEST 3 Page 9 of 10 Rev. 1 APPENDIX C (Continued) Part C: Using Thermocouples The incore thermocouples can be used as an indication of both core flow distribution and power shifts during natural circulation. Prior to running a thermocouple map or trending the eight quadrant tilts (four center line and 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 l K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the run-ning frequency of the Thermcouple Averaging Pro-g ram a t 1, 2 , . . . . X 8 seconds or 64 seconds for us. The thermcouple programs breaks the core down into eight quadrants-- four centerline and four diagonal quadrants (see Figure C-1). Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot. - The quadrant tilts are indicative of power shifts and should be trended at approximately a 2-minute frequency. The following addressable valu.-s are the quadrant tilts: Quadrant Addressable Value - 1 U1159 2 U1160 3 U1161 4 U1162 5 U1151 6 U1152 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 possible. The P-250 Operator's Console Reference Manual provides instructions for obtaining thermocouple maps. The trend output and Short Form Maps should be attached to this procedure at the end of the test. 28 w
.l
SQNP SPECIAL TEST 3 Page 10 of 10 Rev. 1
\) APPENDIX C (Continued) ,
\
CE TER l.INE OUART EH-COME SYMMETRY l i '- ' Cdd Legs 3 4
, N-43 m ,,n. g.42 O O 3
( \
} l 1 1 2 4
\ ]
'M o' 4$d !.rgs M l'y A
( . .
- 2. '
4 3 l / . ( / EXCORE DETECTORS M-;/ o v oo v o"*AA 2 . I Cold Leggs O v Of AGONAL OVAHTER CORE SYMMETRY 225 315* s , s 5 S' 6
/ .h,,
7 s
. g,. ' ;, .
29
SQNP SPECIAL TEST 3
. Page 1 of 4 Rev. 1 t APPENDIX D t Procedure For Use Of Computer System i For Data Collection i The following parameters will be monitored during this test using the plant g computer system.
Parameter Computer Point Pressurizer Preasure PO480A Pressurizer Level LO480A
. RCS Loop 1 Hot Leg Temperature T0419A RCS Loop 1 Cold Leg Temperature T0406A RCS Loop 2 Hot Leg Temperature T0439A RCS Loop 2 Cold Leg Temperature T0426A RCS Loop 3 Hot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A 4 RCS Loop 4 Hot Leg Temperature T0479A 0)
~
\
RCS Loop 4 Cold Leg Temperature T0466A . Steam Generator 1 Pressure P0400A Steam Generator 1 Narrow' Range Level LO400A Steam Generator 2 Pressure P0420A - 1 Steam Generator- 2 Narrow Range Level LO420A Steam Generator 3 Pressure PO440A Steam Generator 3 Narrow Range Level LO440A Steam Generator 4 Pressure P0460A i 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 Ov Incore Thermocouples T0001A tr. rough T0065A 30
SQNP SPECIAL TEST 3 Page 2 of 4 j Rev. 1
- (~')
APPENDIX D (Continued) The computer trend typewriter will be used to monitor the following com-puter points. (Additional points may be added as required by the test
, director).
i BLOCK 1 Column Point Column Point Column Point l 1 P0480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO440A 5 T04'9A 11 PO400A 17 P0460A 6 T0426A 12 LO400A 18 LO460A BLOCK 2 Column Point Column Point 1 NG049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A
)
~
s 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.
- 1. Push DIGITAL TREND button *
- 2. Select block number (1 to 6) on keyboard i 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 2 button
- 6. Push STOP button i
Repeat the above 6 steps for each data block to be used. NOTE: A Block Trend Error message will occur if the data block is ini-tially clear. l i { ($3) 31 l l . s ,
N SQNP SPECIAL TEST 3 Page 3 of 4 Rev. 1 APPENDIX D (Continued) To set up the data blocks, perform the following series of steps for each point to be monitored.
- 1. Push the DIGITAL TREND button
- 2. Select the point address (i.e. PO480A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select block number (1 to 6) on keyboard.
- 5. Push VALUE 1 button
- 6. Select column number (1 to 18) on keyboard J 7. Push VALUE 2 button I
- 8. Push START button
- ,. Once the blocks are set up they can be initiated by performing the following steps for each block.
- 1. Push DIGITAL TREND button.
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 = 2 minute, etc.) The 30-second interval is l recommended for the duration of the test transient r~' 5. Push VALUE 3 button
(
- 6. Push START button l . If it is necessary to change the trend interval of a block or trend, perform the following.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button *
- 4. Select new interval number (0 = 30 sec., 1 = 1 min.,
2 = 2 min., etc) on keyboard
- 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select C on keyboard
- 5. Push VALUE 3 button
- 6. Push STOP button
. 4
- 32 l-
~ . ,-
SQNP SPECIAL TEST 3
, Page 4 of 4 Rev. 1
()
\#
APPENDIX D (Continued) In addition to the data recorded on the trend typewriter, the following points will be monitored on analog trend recorded. i
+
T0056A (Core exit temp). Others as needed (Recommend pressurizer pressure, steam generator level (WR) and steam generator pressure). f 3 After selecting the per to be used to record a value, ensure that it is
' cleared by performing the following steps.
I
- 1. Push ANALOG TREND function button
- 2. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
- 4. Push STOP button Tu start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button f 2. Select the computer point address (i.e. T0043A) i on the alphanumeric keyboard i
- 3. Push ADDRESS button
- 4. Select per number (1 to 12) on keyboard
() - 5. 6. Push VALUE 1 button 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 butt'n o
Repeat these steps until all of the desired analog points are being recorded. - Prior to initiation of the transient, and as required thereafter, incore thermocouple maps will be recorded at the programmers console in the computer room. To 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 33
SQNP SPECIAL TEST 3 Page 1 of 11 Rev. 1
) 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 I exists and what the problem is. (2) a reactor trip will take place auto-matica11y. (3) a safety injection can be initiated manually from the switch in the control room if conditions warrant. I
- 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: / l Verified by: / R-50 Panel Performed by: /
. Verified by: / ; Procedure for blocking automatic actuation of a safety injection on high steamline Delta-P. This block will prevent a reactor trip from occuring during the natural circulation tests from high AP caused by degraded test conditions. (This block will also' defeat all AP SI alarms).
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, -
73, 76 are all clear prior to starting blocking procedure.
- 3. Move test trip switch PS-515A in 1-R-7 to the trip position and verify the amber light above the switch comes on.
~
Performed by: / Verified by: / CAUTION: In the next step, and all following steps in which a voltage is being applied to the indicated terminals, ensure the applied voltage is of the same polarity as the terminals. This check should be done for every step that a voltage source is applied. Failure to apply the correct polarity will ground the rack power supply. (This problem can be avoided if only the hot wire from the voltage source in the rack is applied to the first terminal indicated in each step [the lower numbered terminal). The ! r~% U i 34 I ? ' 1 I
SQNP SPECIAL TEST 3 Page 2 of 11 i Rev. 1 i
'( APPENDIX E 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 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 status / alarm windows as the 120V source is connected.
- 4. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-7 and verify 1-XX-55-6B/25 is clear.
i Performed by: / Ver'ified by: /
- 5. Hove test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 6. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear.
Performed by: / Verified by: / , t
- 7. Move test trip switch PS-516C in 1-R-12 to the trip position and verify
, the amber light above the switch comes on.
Performed by: / Verified by: / I
- 8. Lif t and tape the wire on the rack side of terminal L-5 in the rear of 1-R-7. Apply 120-VAC source to terminals L-5 and L-6 in the rear of 1-R-12 and verify 1-XX-55-6B/73 is clear.
Performed by: / Verified by: /
\. ,,
35
SQNP SPECIAL TEST 3 Page 3 of 11 Rev. 1 APPENDIX E
- 9. Hove 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: l / l
! 10. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-12. Apply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-12 and verify 1-XX-55-6B/76.
Performed by: / Verified by: / t
- 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. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-8. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/28 is clear. .
i l
. Performed by: /
; Verified by: /
- 13. Hove test trip switch PS 525A in 1-R-8 to the trip position and verify -
the amber light above the switch comes on. Performed by: / l Verified by: /
- 14. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.
Performed by: / Verified by: /
- 15. Hove 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: / i Verified by: / 36 W
SQNP SPECIAL TEST 3 Page 4 of 11 Rev. 1 APPENDIX E
}] '
l6. Li f t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-II. Apply 120-VAC source to terminals L-7 and L-6 in the rear of 1-R-Il and verify that XX-55-6B/51 is cicar. l Performed by: __ /
.l Verified by: /
t
- 17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 18. Lift and tape the wire on the rack side of terminal L-5 in the rear or 1-R-II. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is clear.
Performed by: / t Verified by: / Temporary Hydification 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 bc cleared. .
I Performed by: /
' Verified by: /
NOTE: If the alaras will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected.
' 20. Hove test trip switch TS412D in R-2 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 21. Lif t and tape the wire on the rack side of terminal M-3 in the rear of 1-R-2. Apply a 120-VAC source to te.rminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: / (-)s
\m 37 k
,_ . _ _ . - _m ,
SQNP SPECIAL TEST 3 Page 5 of 11 Rev. 1 APPENDIX E
- 22. Hove test trip switch TS-422D in R-6 to the trip position and verify the amber light above the switch comes on.
Performed by: / l Verified by: / t f 23. Lift and tape the wire on the rack side of terminal H-3 in the rear of 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify 9 XA-55-6i./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. I.ift 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 g) q XA-55-6A/30 will clear.
Performed by: /- Verified by: /
- 26. Move test trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
- Performed by: /
Verified by: / Lift and tape the wire on the rack side of terminal M-3 in the rear of i 27. 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear. Performed by: / Verified by: / NOTE: The avg inputs to the high steam flow S.I and steam dump interlock are now blocked. The next steps will trip the steam flow inputs to the high steam flow Safety Injection signal so that an S.I. signal will be initiated on low steam generator pressure alone (600 psig). (This would result in a reactor trip, an S. I. alarm, but no S. I. initiation.) 38 L s
SQNP SPECIAL TEST 3
. Page 6 of 11 Rev. 1 i . APPENDIX E I
I 28. Hove test. trip switch FSS12B 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: / I 29. Hove test trip switch FS522B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/ come on. 9 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 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 SWITCH TEMP ALT. NO. U^ R-7 PS515A / R-7 PS515B / ' R-12 PS516C / R-12 PS516D / 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 / To return the steamline Delta-P S.I. to normal condition, the following steps
- should be followed.
3 (v 39 l
SQNP SPECIAL TEST 3 Page 7 of 11 Rev. 1 V 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. Move test trip switch PS-526C in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/50 are clear.
Performed by: / Verified by: /
, 33. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire I on L-7.
l l Performed by: /
~
Verified by: / h
- 34. Hove 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.
t Performed by: / Verified by: /
. 35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.
Performed by: / Verified by: /
- 36. Move test trip switch PS-525A in 1-R-8 to the normal position and verify the amber light and 1-XX-55-6B/26 are clear.
Performed by: / Verified by: /
- 37. Remove the 120-VAC source from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.
Performed by: / N' Verified by: / 40 ) 1 r -
SQNP SPECIAL TEST 3 Page 8 of 11 Rev. 1
/]
APPENDIX E
- 38. 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.
j Performed by: / Verified by: / r
- 39. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. Retermi-g nat.e 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: / 4
- 41. Remove the 120-VAC source from terminals L-5 and L-6 in 1-R-12. Retermi-g ,
nate wire on L-5. V Performed by: / Verified by: _ /'
- 42. Move test trip switch PS-516C'in 1-R-12 to the normal position and verify the amber light above the switch and 1-XX-55-6B/73 are clear.
Performed by: / Verified by:
- 43. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi-nate wire on L-7.
Performed by: / Verified by: /
- 44. 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: / p h l 41
SQNP SPECIAL TEST 3 Page 9 of 11 Rev. 1 [] is/ APPEND 1X E
- 45. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.
I j Performed by: _ / Verified by: / s
! 46. Nove 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.
I 4 Performed by: / Verified by: / NOTE: At this point the steamline Delta-P safety injection is in a normal operating mode. Toreturntgehighsteamflowcoincidentwithlowsteamgeneratorpressure or low-low avg to normal, perform the following steps.
- 47. Move test trip switch FSS22B 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. Hove 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: /
- 49. 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: /
- 50. Hove 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: / l Verified by: / l b) s_- 42 l l
_ ~ _. ___ _ __ _ . SQNP SPECIAL TEST 3
- 3. .
Page 10 of 11 l Rev. 1
, APPENDIX E
- 51. Hemove the 120-VAC source from terminals N-3 and M-4 in R-10. Retermi-nate wire on H-3.
Performed by: / Verified by: / 1 52. Hove 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.
-l Performed by: /
Verified by: / 5:1. Hemove the 120-VAC source from terminals M-3 and M-4 in R-6, Retermi-nate wire' on H-3. i
. Performed by: /
Verified by: /
$4. Hove test. trip switch TS442D in R-6 to the normal posit.f on and verify the amber light goes out and XA-55-6A/30 will clear.
- O~
2 Performed by: / Verified by; / SS. Hemove the 120-VAC source from terminals M-3 and M-4 in H-2. Retermi-nate wire on H-3. Performed by: / i Verified by: /
- 56. Hove 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: / Verifica by: / I O l 43 i c.
SQNP . SPECIAL TEST 3 Page 11 of 11 Rev. I j-)
.V APPENDIX E
- 57. Remove the Temporary Alteration Tage on the following test trip switches:
RACK TEST SWITCH TEMP ALT. NO. R-7 PS515A / R-7 PS515B /
' R-12 PS516C /
R-12 PS516D / R-8 PS525B / R-8 PSS25A / R-11 PS526D / R-11 RSS26C / R-2 TS412D /
, R-6 TS422D /
t R-10 TS432D / R-13 TS442D / ( R-3 FS512B / R-3 FS522B / 4
- 58. Remove the jumpers and the Temporary Alteration Tags from logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50. ,
i. R-47 Panel Performed by: / Verified by: / 3
- 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. 44 k
SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 1 G APPENDIX F Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. E tb o 1: 3
- Po e8" u nm g c $$$8E E o OEo o 5S 0 N U 30$U " o S 15 . . . t 6 nadH n? B a ?
UUUUU*
- O Y s u w s s $$$ E B*22esanue a: 2 %e f ? a e
3 (J a322a6;M ee TECilNICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment ifI Pressure SI (3.3.2.1) X X X X X X X X X X Sa fety 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 OTAT (3.3.1) Inoperable because of low flow 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) bypassed X X X X X X X X X X liigh Steamflow coincident 91 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 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 Cooland Loops Normal Operation p (3.4.1.2) X X X X X X X X J 45
. - . , _ . . . . . - . . - - - - = . - . .- _ -. -. - - .
SQNP SPECIAL TEST 3 Page 1 of 1 Rev. 1 TABLE 1 Loop Flow and Core AT for Various Pov - Levels and
. Isolation ( . figurations (Computer Estimates) 4 I
l' No. of Loops Operating (Nat. Circ.) . Power Level 4 3 2 1 I .5% L= 3.7 L= 3.6 L= 4.1- L= 5.2 1 . AT = 10.3 'T = 12.5 AT = 16.4 AT = 26 I
.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
- f. 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 o
AT = 26 AT = 31.4 AT = 41 AT = 65.4 a l W 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 gprn flow through operable loop. i AT = Loop AT in *F. 46 M r n v -, , , . . - . - - . - , . . . - , - ,- , . - - - - - . - . ~ . , - , . , a-. -,, -n. . . - . -,
w -~a .a - b O i SPECIAL TEST NO. 4 EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATI0ti ON NATURAL CIRCULATION O . O i l 1 l l lO
SQNP SPECIAL TEST 4 Page 1 of 1
.! Rev. 1
'O -
'! EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATION
! ON NATURAL CIRCULATION l
Table of Contents gag g Test Description 1 l Special Operator Instruction 2 1.0 OBJECTIVES 3 4 2.0 PREREQUISITES 4 i .l 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPMENT 9 5,0 INSTRUCTIONS 10 6.0 ACCEPTANCE CRITERIA 16 APPENDIX A - References 17
~ ! APPENDIX B - Deficiencies 13 APPENDIX C - Power Measurement Technique 19 -
APPENDIX D - Computer Points 29 APPENDIX E - Safeguard Blocking Procedure 33 APPENDIX F - Technical Specifications Exceptions 46 l TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 47 l l l i
)
l l l l.
SQNP SPECIAL TEST 4 Page 1 of 1 Rev. 1 , O TEST DESCRIPTION t
' With natural circulation established at ~ 1% rated thermal power and re-l l duced reactor coolant temperature, steam generators will be isolated l I sequentially to determine the effect on natural circulation conditions.
J l Isolation of up to 2 steam generators will be tested if limitations per-mit. Steam generators will then be sequentially returned to service to i verify that natural circulation can be reestablished. 4 1 1 i I O 1
SQNP SPECIAL TEST 4 Page 1 of 1 /~T Rev. 1 -U 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 Window 6 initiates An operator initiated reactor trip should be performed for any of the following conditior.s: 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
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
O 2 ,. .,
-- ~- - - . . _ ,
SQNP SPECIAL TEST 4 Page 1 of 14 Rev. 1 O 1.0 OBJECTIVES 1.1 Determine the effect of steam generator isolation on natural cir-culation conditions. 1.2 Verify that natural circulatic.a can provide sufficient flow to re-move decay heat after partial loss of heat sink. 1.3 Verify that natural circulation can be reestablished in primary loops after steam generators are returned to service. 1.4 To provide operator training. All operating shifts will perform this test. 1 i i (::) . 1 i O 3 W
SQNP SPECIAL TEST 4 Page 2 of 14 Rev. I ~. ; 2:0 PREREQUISITES 2.1 Reactor is critical and manually controlled at approximately 1% power. (Power level determined as indicated in Appendix C).
/
2.2 All four reactor coolant pumps in operation.
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2.3 Reactor coolant system pressure is being maintained automatically at approximately 2000 psig (PIC-68-340A setpoint = 37.5%) and average coolant temperature is being maintained at approximately 515 F.
/
2.4 Steam generator pressure is being maintained at approximately 763
' psig using steam dumps in automatic under pressure control.
I 6
/ -
i 2.5 Feedwater to the steam generators will be supplied Steam by the auxiliary generator levels feedwater system with flow control in auto. should be maintained at approximately 33% on narrow range indi-cators.
/ -
' 2.6 Steam generator chemistry is in a condition that the absolute mini-mum steam generator blowdown can be maintained through the test.
/
4 2.7 The 100 psi steamline differential pressure safety injection bist-ables have been blocked through temporary conditions as specified
.i in Appendix E.
/
2.8 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix E.
/
2.9 Verify the input logic of safety injection on high steam line AP has been blocked in accordance with Appendix E.
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M.,y/ 4 G
SQNP SPECIAL TEST 4 Page 3 of 14 Rev. I er b 2.0 (Continued) 2.10 VerifytgehighsteamflowcoincidentwithlowS/Gpressureor low-low avg input to safety injection has been modified in accordance with Appendix E.
/
2.11 Verify the following UHI isolation valves are gagged. FCV 21 / FCV 22 / FCV 23 / FCV 24 /
< ! 2.12 Verify the bistables supplying the low pressure signal to the
' high steam flow S.I. logic have been recalibrated in accordance with Appendix E.
/
1 NOTE: This allows cooling down to 450*F without getting a reactor trip. 2.13 Brush recorders have been set up to monitor test points at the O - reiiewi a tec ti : 2.13.1 Recorder No. 1 (6 Channel) . Channel Pa rameter Test Point Rack 1 RCS Flow-Loop 1 FP/414B l-R-1 2 RCS Flow-Loop 2 FP/424B l-R-1 . 3 RCS Flow-Loop 3 FP/434B l-R-1 4 RCS Flow-Loop 4 FP/444B l-R-1 l 5 Pressurizer Pressure PP/455B l-R-1 6 Pressurizer Level LP/459B l-R-1 l 2.13.2 Recorder No. 2 (6 Channel) Channel Parameter Test Point Rack ~ l SG 1 Pressure PP/416B 1-R-3 2 SG 1 Level LP/501 1-R-23 3 SG 1 Steam Flow FP/512B l-R-3 4 SG 2 Pressure PP/426B l-R-3 5 SG 2 Level LP/502 1-R-23 6 SG 2 Steam Flow' FP/522B l-R-3 5 4.*
SQNP SPECIAL TEST 4 Page 4 of 14 Rev. I i 2.0 (Continued) 2.13.3 Recorder No. 3 (6 Channel) Channel Pa ramete r Test Point Rack 1 SG 3 Pressure PP/436B 1-R-4
! 2 SG 3 Level LP/503 1-R-23 3 SG 3 Steam Flow FP/532B l-R-4 !
4 SG 4 Pressure PP/446B 1-R-4 5 SG 4 Level LP/504 1-R-23 6 SG 4 Steam Flow FP/542B l-R-4 2.13.4 Recorder No. 4 (4 Channel) Channel Parameter Test Point _ Rack l
, 1 SG 1 Aux Feed Flow L-3-163, TP 13 1-L-11B 2 SG 2 Aux Feed Flow L-3-155, TP 13 1-L-llA 3 SG 3 Aux Feed Flow L-3-147, TP 12 1-L-11B 4 SG 4 Aux Feed Flow L-3-170, TP 12 1-L-11A
/
NOTE: Record the following on all strip charts: a) Unit No. b) Date ' c) Procedure No. d) Parameter scale and range e) Chart speed f) Name of person recording data g) _ Recorder I.D. No. , 2.14 Record the following parameters on the reactivity computer recorders:
- a. Flux
- b. Average wide range Tcold
- c. Average wide range Thot
- d. Average steam generator pressure
- e. Reactivity l /
\ l 0 U 6
~ ' , , -
SQNP SPECIAL TEST 4 Page 5 of 14 Rev. 1 (
.w 2.0 (Continued) 2.15 Set up the P-250 computer trend printer to monitor the following parameters at 1-minute intervals, as specified in Appendix D.
- a. Pressurizer pressure
- b. Pressurizer level i c. Wide range Tcold (all loops)
- d. Wide range Thot (all loops)
- e. Steam generator pressure (all loops)
- f. Steam generator 1cvel (all loops)
- g. Power range channels
- h. Additional parameters as determined by the test engineer i,
/
' I 2.16 Trend 4 incore thermocouples as determined by the test engineer on the analog trend recorders in the main control room. It is suggested that these thermocouples be the hottest responding thermocouple in each core quadrant.
/
3 2.17 Control Bank D is at approximately 160 steps or as specified by {%,/ the test engineer to permit reactor power increase up to approxi-mately 1% (required control bank D position may be determined . during the hot zero power test program). -
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2.18 Pressurizer level control is in automatic, maintaining pressur-izer level at approximately 25%.
/
2.19 Normal charging and letdown are in service under automatic control.
/
2.20 A determination of the sensitivity of the NIS to changes in cold has been completed. (Special Test 9A.)
/
2.21 Intermediate and power range (low setpoint) high Icvel reactor trip setpoints have been set to 7% in accordance with Appendix C and D of SU-8.5.2. l Power Range / f (~) Intermediate Range / t x_- l 7 l .
SQNP SPECIAL TEST 4 Pa c 6 of 14 4 Rev. 1 ('\ O 3.0 PRECAUTIONS l I 3.1 Do not exceed 5% rated thermal power at any time while the test is in progress. 3.2 Abort test if any of the following temperature limits are exceeded. 3.2.1 Core exit temperature of 610 F 3.2.2 AT as indicated by THTC of 65 F 3.2.3 avg of 578 F for any loop 3.3 Maintain reactor coolant pump seal and thermal barrier differen-l tial pressure requirements as specified in SOI-68.2. 3.4 Avoid any sudden changes in feedwater flow or steam generator level. 3.5 Ensure seal flow to each reactor coolant pump is maintained at or slightly above 4 gpm during the test. 3.6 After the reactor coolant pumps are tripped, th9 normal avg and AT indications will become unreliable. AT and avg should be calcu-lated by taking the difference and the average of the hot and cold leg temperature indications respectively. 3.7 Do not exceed 1600 psi primary to secondary differential pressure limit. 3.8 Maintain reactor coolant, system cold leg temperatures as stable i as possible during system transients. This is required to deter-mine changes in core power level on the NIS channels. . 3.9 When testing with the reactor coolant in the low temperature range of 450 F to 500*F, maintain the lithic concentration at 2.0 to 2.2 ppm, the upper part of the specified lithic range. This is especially necessary if high boric acid concentrations I (~ 1000 ppm) are also being used. 3.10 Ensure control bank D position remains at > 100 steps. Should this limit be reached during the cooldown, boron concentration will have to be increased. 3.11 Ensure auxiliary spray is in service prior to tripping the reactor coolant pumps. Spray flow to the pressurizer can be controlled by adjusting charging flow, closing the normal charging path, or opening the n.ormal spray valves after the RCP's are tripped. 3.12 Should a teactor trip occur during the conduct of this test, at least one reactor coolant pump (#2) should be started prior to O closing the reactor trip breaker. 8
i SQNP SPECIAL TEST 4 , Page 7 of 14 ' Rev. 1 O 4.0 Special Test Equipment [ l Identification Calibration l Instrument Specification Number Verification t i Reactivity Computer Westinghouse ' Brush 260 Recorders Brush 260 or (3) Equivalent e
- Brush 400 Recorder Brush 400 or I (1) Equivalent I Recorder (1) HP7100B or j Equivalent l ,
t i 4 1 I I i I l l t l I If test instruments are changed during this test, the instrument information must be recorded here and an entry made in the chronological log book ex-plaining this change. . O 9 ?
SQNP SPECIAL TEST 4 Page 8 of 14 Rev. 1 b,. 5.0 INSTRUCTIONS 5.1 Start brush recorders, analog trend recorders, reactivity computer and P-250 trend blocks. t
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5.1.1 Establish auxiliary spray flow to the pressurizer.
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i CAUTION: Following reactor coolant pump tripTavg and AT indication will be unreliable. 5.2 Simultaneously trip all reactor coolant pumps. Reduce seal water flow to each pump to approximately 4 gpm. .
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5.3 Maintain steam generator level at approximately 33%.
/
t NOTE: At initiation of natural circulation the following initial response is expected: ( 1. Wide range hot, increase T
- 2. Wide range cold, slight increase or constant
- 3. Core exit thermocouples, increase -
- 4. Pressurizer level, increase Natural circulation will be stable when:
T
- 1.ATbetweenwiderangefhotand cold is constant
- 2. AT between wide range cold and core exit thermo-couple average temperature is constant
- 3. Wide range hot 2 core exit thermocouple average temperature (See Table 1) 5.4 Adjust setpoint on steam dump pressure controller PIC-1-33 as needed to maintain cold leg temperatures at the initial values.
/
5.5 Adjust setpoints on atmospheric relief valve pressure controllers for each loop to maintain steam pressure below 1025 psig before isolating any steam generators. This should prevent opening of main steam safety valves.
/
10
SQNP SPECIAL TEST 4 Page 9 of 14 Rev. 1 O 5.0 (Continued) 5.5.1 Establish maximum maintainable flow through normal letdown path, and manually increase charging flow to maintain a constant RCS water mass. Start an additional centrifugal charging pump if necessary. (Maintain pressurizer level
~ content after equilibrium has been reached on natural j circulation).
/
CAUTION: Monitor primary to secondary differential pressure very closely during the transient and do not allow it to exceed 1600 psi. i NOTE: Allow the pressurizer level to increase when T is increased. (Expected increase is approximate 1f h per
'F increase in avg).
5.6 Close HS1V FCV-1-22. Isolate feedwater flow and steam generator blowdown (if in service) for steam generator #3. Carefully con-trol feedwater additions to the remaining steam generators to hold the levels at approximately 33%. It may be necess9ry to adjust the steam dump pressure controller setpoint to reduce cold in the un-isolated loops so that the steam generator pressure in the isolated i loop remains below the setpoint of the atmospheric relief valve. l . 7 NOTE: During this transient the following responses can be expected.
- 1. Widerangefhot, increase
- 2. Wide range c Id for Loop 3, increase T *
- 3. Wide range cold for other loops, held constant using steam dump
- 4. Core exit thermocouples, increase (See Table 1)
- 5. Pressurizer pressure and level, increase 5.7 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop 3 AT is approximately zero.
l / l 5.8 Verify that the calculated value for Tavg for the remaining 3 loops has stabilized. If Tavg continues to increase and cannot ! be stabilized the test director should determine whether further l testing can be conducted. , / O 11 9
SQNP SPECIAL TEST 4 Page 10 of 14 Rev. 1 5.0 (Continued) NOTE: Verify Tavg is stable prior to cenducting the next step. s I CAUTION: Monitor primary to secondary pressure very closely during the transient and do not allow it to exceed 1600 psi. f 5.9 Close HSIV FCV-1-29. Isolate feedwater flow and steam generator blowdown (if in service) for steam generator #4. Carefully control feedwater additions to the remaining steam generators to hold the levels at approximately 33%. It may be nece9sary to adjust the steam dump pressure controller setpoint to reduce cold in the unisolated loops so that the stcain generator pressure in the isolated loops re-main below the setpoint of the atmospheric relief valves.
/
NOTE: During this transient, the following responses can be expected:
- 1. Wide range Thot, increase
- 2. Wide range Tcold for it, ops 3 and 4, increase
- 3. Wide range Tcold for loops 1 and 2, held constant using steam dump
- 4. Core exit thermocouples, increase
, p 5.10 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop 4 AT is approximately (y
zero. l
/
. 5.11 Verify that the calculat'ed value for Tavg for the remaining 2 loops has stabilized. If Tavg continues to increase and cannot be stabilized, the test director should determine whether further testing can be conducted.
l l' CAUTION: Monitor primary to secondary pressure very closely during the transient and do not allow it to exceed 1600 psi. If equilibrium has not been reached within one-half hour pro-ceed immediately to the next step. 5.12 Slowly reduce the setpoint on atmospheric relief valve controller PIC-1-31A and allow steam generator #4 pressure to reach approxi-i mate equilibrium with steam header pressure. Restore feedwater slowly to maintain ~ 33% level. I ! / O 12
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CQNP SPECIAL TEST 4 Page 11 of 14 Rev. 1 5.0 (Continued) 5.13 Open first FCV-1-150 and then MSIV FCV-1-29 and close atmospheric relief valve PCV-1-30. Carefully control feedwater addition to steam generators 1, 2, and 4 to maintain steam generator levels at approxi-mately 33%.
/
NOTE: During the transient, the following responses can be expected.
- 1. Wide range hot., decreases
- 2. Wide range c Id for Lcop 4, decrease
- 3. Wide rangeTTcold for Loop 3, no change
- 4. Wide range cold for Loops 1 and 2
- Increase by using steam dump 5.14 Allow natural circulation to stabilize. Steady state should be achieved when tia calculated loop AT's for loops 1, 2, and 4 are approximately equal.
/
t 5.15 Slowly reduce the setpoint on atmospheric relief valve controller PIC-1-24A and reduce steam dump to condenser, allowing steam'gener-ator #3 to reach approximate equilibrium with steam header pres-O sure of 1005 psig. Restore feedwater slowly to maintain ~ 33% - level. ,
/ __
5.16 Open first FCV-1-149 and then MSIV FCV-1-22 and close atmospheric relief valve PCV-1-23. , 1
/
NOTE: During the transient the following responses can be expected.
- 1. Widerangefhot, decrease
- 2. Wide rangeT c Id for loop 3, decrease
- 3. Wide range cold for loops, 1, 2, and 4, Increase using steam dump 5.17 Allow natural circulation conditions to stabilize. Steady state should be achieved when the calculated loop AT's are approximately equal.
/
5.18 Stop recording test data. l l 13 es
SQNP SPECIAL TEST 4 Page 12 of 14 Rev. 1 5, . 0 ' (Continued) 5.19 Insert control bank D until the reactor is in the hot zero power test range.
/
- CAUTION
- Ensure pressurizer spray controllers are at zero out-put prior to starting the first reactor coolant pump.
5.20 Restart all four reactor coolant pumps in accordance with S0I-68.2 starting with #2 then 1, 3, and 4.
/
5.21 Return control of the system to operations.
. /
i 5.22 Return the bistables supplying the low pressure signal to the high steam flow S.I. logic to their original setpoints in accordance with Appendix E unless the next test to be performed requires this modification to be made. If this is the case, disregard this step, place N/A in the signature line, and initial. O(_,/ / 5.23RestoreghehighsteamflowcoincidentwithlowS/Gpressureor low-low avg input to safety injection in accordance with Appendix E unless the next test to be performed requires this modification to be made. If this is the case, disregard this step, place N/A in the signature line, and initial. .
/
5.24 Remove the block of the input logic of safety injection on high steam line AP in accordance with Appendix E unless the next test to be performed requires the block to be intalled. If this is the case, disregard this step, place N/A in the signature line, and initial.
/
5.25 Remave the block of automatic actuation of safety injection in accordance with Appendix E unless the next test to be performed requires the block to be installed. If this is the case, disre-gard this step, place N/A in the signature line, and initial.
/
(3 v 14
SQNP SPECIAL TEST 4 Page 13 of 14 Rev. 1
'I 5.0 (Continued) 5.26 Remove the gags from the following UHI isolation valves unless the valves are required to be gagged for the next test. If this is the case, disregard this step, place N/A in the signature line, and initial.
4 FCV 21 / l FCV 22 / FCV 23 / FCV 24 / 5.27 Reset the intermediate and power range high level reactor trip setpoints as indicated by the test director in accordance with Appendix C and D of SU-8.5.2 unless the next test to be performed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial. Power Range / Intermediate Range / I e l l l l l (a~T 15 e
SQNP SPECIAL TEST 4 Page 14 of 14 Rev. 1 O~ Q.0 ACCEPTANCE CRITERIA l 6.1 Core exit thermocouple temperature does not exceed 610 degrees l Fahrenheit.
-l 1 ; /
6.2 AT for any loop does not exceed 65 degrees Fahrenheit..
/
T
.g 6.3 avg for any loop does not exceed 578 degrees Fahrenheit.
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6.4 Sufficient natural circulation could be maintained in active pri-mary loops to maintain stable temperatures following partial loss of heat sink.
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6.5 Natural circulation could be restored to inactive loops when
; associated steam generators were returned to service.
I
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e e 4 a e f t - 16 T
i SQNP SPECIAL TEST 4
" age 1 of 1 Rev. 1 O
. APPENDIX A References I
I i
- 1. FSAR l 2. Technical Specifications
- 3. Plant Operating Instructions SOI 68.2
' E01 5 4
O t r I l O 17 1
-,y.-w -
i. SQNP
- SPECIAL TEST 4
- j. Page 1 of 1 Rev. 1 >
t ' T' i APPENDIX B i i Test Deficiencies # t j ' Test Deficiency i i ) i i i t-I f i Recommended Resolution i 4 i 4 lO - i Final Resolution - i 4 4
?
! Originator / Signature Date PORC Review of Final Resolution Date I t l _ Approval of Final Resolution / , Plant Superintendent Date i I I i + l 1
-0 l 18 4
6.
-. -- - , - , s . .-,_,-.n.s. , , ,, n,- -,,----,,--,,,m-,--, a,,~en.- , _ , . , , - ,,,n,, _me,,x- -,-,,,,n,,,.n,-w,-w,,, ,
1 SQNP { SPECIAL TEST 4 l Page 1 of 10 l Rev. 1 O . APPENDIX C Procedure for Determining Core Power Level 9 O. 0
=
h I 1 a O 19
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SQNP SPECIAL TEST 4 Page 2 of 10 Rev. 1 APPENDIX C (Continued) Outline i f
- 1. Core Power Determination
) A. Primary Side Calorimetric (Forced Circulation Only)
~
- 1. Reference ( ~ 550 F) Calorimetric (Before NC test)
- ~j a) Output used to adjust M/D Power Monitor Program's power conversion constant.
1 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 l (,s),
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. P a l O I 20 l r
SQNP SPECIAL TEST 4 Page 3 of 10 Rev. 1 t
. 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-fled for each loop as rapid as possible. l 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. 8 I a 4 O 21 i 4 e
-,e- a - , - . , , . ,,- w -- - - -------g y
SQNP SPECIAL TEST 4 Page 4 of 10 Rev. 1
- q 1b APPENDIX C (Continued)
Core Power Determination l 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 i A 10 'L-5 _ B 10 L-11 l C 10 E-5 D 10 E-11 E 6 J-8 F 8 P-9 j These positions may be altered by the test engineer, based upon low power physics testing results and previous special
) .
testing experience. l ,
- 2. Determine the detector normalization constants and enter them into the'P-250 as follows:
i a) Enter a value of 1.0 into the P-250 for the addresses shown -
- in the table below.
b) With all 5-path selector switches set to normal, run a flux trace. I c) With all 5-path selector switches set to Emergency, run a < second flux trace. 4 d) Determine the detector normalization constants from Data Sheet C.2.
+
t O i 22 l 1
- f
{ - .-- - - - - . _ , - . - .- -.
SQNP SPECIAL TEST 4 Paga 5 of 10 Rev. 1 O 7' . APPENDIX C (Continued)
- i e-i Core Power Determination I
PAltT B: (Continued) e) Enter these detector normalization constants into the P-250 as shown in the table below. Drive P-250 Address A KO908 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 -
l Set the Power j K0901 1 Normalization Factor i Selects the Modified K5525 1 " Flux Map Print" programs K0900 0 Initiated Pass Number Calibration Constant for K0864 Variable (I) M/D Power Monitor i
! ( } Variable: The value entered is a ratio of the Primary Calorimetric Indicated Power (Item B on Data i Sheet C.1) to the M/D calculated power (UO906)
! times the current value entered in (K0864). l If no value has been entered into (K0864) enter l 0.25. l Item //8
- Data Sheet C.1 New (K0864) = Current (K0864) x (UO906) m i 23 f
e - --n.. - , -- , - . . --
a SQNP SPECIAL TEST 4 Page 6 of 10 Rev. 1 APPENDIX C (Continued) PART B: (Continued)
- 4. For power determination, obtain a partial core flux map as per TI-53. The N/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 af ter each pass and may be trended by the P-250 if desired. The individ-ual detector normalized integrals are also printed. TABLE C-1 Temp Cp( ) m F BTU /lbm F lbm/hr 556 1.260 3.6448 x 10 554 1.255 3.6553 x 10 7 7 552 1.250 3.6659 x 10
' 7 I 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
- 7 542 1.226 3.7155 x 10 7
540 1.221 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
. (I)These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia.
24 l ? i i i 1
.( - . - - - ,.
( v
'SQNP SPECIAL TEST 4 Page 7 of 10 Rev. 1 APPENDIX C (Continued)
Data Sheet C.1 # Power Tavg F Date Time Unit 1 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 Loon AT - Inservice (at test point) Volts i 2 Loop AT = (#1) x ( ) F 3 Loop AH = (#2) x Cp (from Table C.1) BTU /lba 6 4 Loop RCS Flow (from Table C.1) 10 1bm/hr , 0 5 Loop Reactor Power = (#3) x'(#4) 10 BTU /hr 6 Total Reactor Power = (#5) 6 i Loop'1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307 MVI 8 % Reactor Power = (#7) x 0.02932 % I3 Conversion factor for AT obtained from scaling document. Remarks: l Date By: , Checked By: i
SQNP SPECIAL TEST 4 l' Page 8 of 10 Rev. 1 o APPENDIX C (Continued)
.A
- N N N* N N N A = B *
- E E E E E E N = 1.00 3
A N g=A{f = AE = N N A N = N '-
= BE =
C C N N A l -N D= N = CE = D i , N N
!' N,=A- ND L
N = DE = j N 7'N A Ny = = EE = l N N
, ,q Definitions:
(l A' N N' N' N' N, FN = N rmalized integral from summary map for each - detector in a normal path in the first pass ) AE ' "E, CE , DE , EE, FE = Normalized integral from summary map for each
- detector in an emergency path in the second pass j N,N' g B C' D' E, Ny = Detector normalization factor for each detector I Remarks
A t
- Data By: Date 4
i 26 l l i s e I
+,. -r., - m.,.,, . - . . - . . , . , ,. , ,... . _ _ - .,-,-2. ,y--~~..e-.,.. .-c .
-w --,%-,. . , , . . , , - - ,
SQNP SPECIAL TEST 4 Page 9 of 10 Rev. 1 APPENDIX C (Continued) Part C: Using '1hermocouples 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 d K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before I { calculation is done. This in turn sets the run-ning f requency of the Thermcouple Averaging Pro-j
' gram at 1, 2, . ... X 8 seconds or 64 seconds for us.
The thermcouple programs breaks the core down into eight quadrants-- {'/) f ur centerline and four diagonal quadrants (see Figure C-1).
'r Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot.
The quadrant tilts are indicative of power shifts and should be trended at. approximately a 2-minute frequency. The following addressable values are the quadrant tilts: . t Quadrant Addressable Value 1 Ull59
' 2 U1160 U1161 I 3 4 U1162 i
! U1151 5
6 U1152 7 Ull53 8 U1154 A Short Form Map should be run periodically or upon request fromIt the test engineer as an indication of core flow distribution. should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for obtaining thermocouple maps. The Ltend output and Short Form Maps should be attached to this-
/)
i
\s / procedure at the end of the test. t
' 27 \ . L
1 SQNP , SPECIAL TEST 4 ! Page 10 of 10 i Rev. 1 O APPENDIX C (Continued) CENTER LINE OUARTER-CORE SYtAtAETRY l Cdd Loos v t i 3 4 - t N-4 3 m 2,g m N 42
; O O 3
[ 4 t I s 2 iso ( Milgt lcil97 l
\ .
g_ a a i i ExconE J DETECTORS i i d--f/ ovev o/ #'44 2 . I au Lys l O I t DI AGON At'OUAHT E R-CORE SYMMETRY 22$ 31$ s , 5 g- '\' 6
,o ,
7 o
'N
. ,2 Ec F.a uce c-i b
Cuneter Cora Do*ir.itmns of Symmotry 28
SQNP SPECIAL TEST 4 Page 1 of 4 Rev. 1 APPENDIX D Procedure For Use Of Computer System For Data Collection The following parameters will-be monitored during this test using the plant computer system. Parameter Computer Point Pressurizer Pressure PO480A Pressurizer Level LO480A RCS Loop 1 Ilot Leg Temperature T0419A RCS Loop 1 Cold Leg Temperature T0406A RCS Loop 2 Hot Leg Temperature T0439A RCS Loop 2 Cold Leg Temperature T0426A RCS Loop 3 llot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A
. RCS Loop 4 liot Leg Temperature T0479A RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressure P0400A Steam Generator 1 Narrow Range Level LO400A
^
- Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level LO420A
- Steam Generator 3 Pressure PO440A
}
Steam Cencrator 3 Narrow Range Level LO440A Steam Generator 4 Pressure P0460A Steam Generator 4 Narrow Range Level LO460A Power Range Channel 1 (Quadrant 4) N0049A Power Range Channel 2 (Quadrant 2) N0050A Power Range Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A O'. Incore Thermocouples T0001A through T0065A 29 On
~
.SQNP SPECIAL TEST 4 Page 2 of 4 Rev. 1 APPENDIX D (Continued)
The computer trend typewriter will be used to monitor the following computer points. (Additional points may be added as required by the test director). BLOCK 1 Column Point Column. Point Column Point 1 P0480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 P0400A 17 PO460A 6 T0426A 12 LO400A 18 LO460A BLOCK 2 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A 4 N0052A 10-13 Hottest T/C from each core Quadrant
\ 5 T0002A 14-18 As Required i
6 T0013A
- To initially clear each data block perform the following step for each block to be used.
- 1. Push DIGITAL TREND button *
- 2. Select' block number (1 to 6) on keyboard
. 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 2 button
- 6. Push STOP button Repeat'the above 6 steps for each data block to be used.
i r NGTE: A Block Trend Error message will occur if the data block is ini-tially clear, s a l (. l i 30 i
~
SQNP SPECIAL TEST 4 Page 3 of 4 Revi 1 i t'} (,,- APPENDIX D (Continued) To set up the data blocks, perform the following series of steps for each point to be monitored.
- 1. Push the DIGITAL TREND button -
- 2. Select the point address (i.e. P0480A)~on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select block number (1 to 6) on keyboard.
- 5. Push VALUE 1 button
- 6. Select column number (1 to 18) on keyboard
- 7. Push VALUE 2 button
- 8. Push START button I 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 (g
.r 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 bdtton To stop trending or block perform the following:
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select C on keyboard
- 5. Push VALUE 3 button 1
- 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, I ( steam generator level (WR) and steam generator pressure). 31 J
SQNP SPECIAL TEST 4 Page 4 of 4 Rev. 1 G
'h APPENDIX D (Continued)
Af ter :: electing 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 1 2. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
- 4. Push STOP button To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button Select the computer point address (i.e. T0043A) 2.
l on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select per number (1 to 12) on keyboard
- 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the minimum value of the parameter to be monitored
- 7. Select range on the keyboard
- 8. Push VALUE 3 button
- 9. Push START button Repeat these steps until all of the desired analog points are being recorded.
Prior to initiation of the transient, and required thereaf ter, 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 xi 32
SQNP 1 SPECIAL TEST 4 Page 1 of 13 Rev. 1 [) v APPENDIX E Safeguard Blocking Procedure The first step blocks automatic initiation of a safety injection. The safety injection alarm, manual S.I handswitch, and the reactor trip portion of the
. protection logic will remain in operation. If conditions exist that would normally initiate a safety injection; (1) the safety injection alarm will initiate telling the operator that the condition exists and what the problem ! is. (2) a reactor trip will take place automatically. (3) a safety injection i 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: / N.)T l Procedure for blocking automatic actuation of a safety injection on hiF h 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 O' v 33 k
SQNP SPECIAL TEST 4 Page 2 of 13 Rev. I b APPENDIX E ground will already be made up through the trip switch). The wire on the rack side of the terminal block must be lifted and taped for the terminal point where the jumper wire is connected. The TACF tag will be attached to the bistable switch and the TACF must note the jumper and the lif ted wire. NOTE: Orange "out of service" stickers should be placed on all status / alarm windows as the 120V source is connected.
- 4. Li f t .ind 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: /
(O .
- 6. Lift and tape the wire on the rack side of terminal L-7 in the rear of I-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 test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 8. Lift and tape the wire on the rack side of terminal L-5 in the rear of 1-R-12. Apply 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/73 is clear.
l Performed by: / j Verified by: / l 34 9 O
r SQNP SPECIAL TEST 4 , Page 3 of 13 i Rev. I
. APPENDIX E
- 9. flove test trip switch PS-516D in 1-R-12 to the trip position and verif y the amber light above the switch comes on.
1 Performed by: / Verified by: / I. 10. Lif t amt tape the wire on the rack side of terminal L-7 in the rear of l l-R-12. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-611/76. Performed by: / Verified by: /
- 11. tfove test trip switch PS-525B in 1-R-8 to trip position and verify the amber light above the switch comes on.
Performed by: / 4 Verified by: / i t 3 12. Lif t and tape the wire on the rack side of terminal L-7 in the rear sj of 1-R-8. Apply 120-VAC source to terminals L-7 and L-8 and verif y 1-XX-55-6H/28 is clear. 4 Performed by: / Verified by: /
- 13. t!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. l.ift and ts.pe the wire on the rack side of terminal. L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 in the rear of I-R-8 and verify that XX-55-6H/26 is clear.
Performed by: / l l Verified by: / I i O-35 S
SQNP SPECIAL TEST 4 Page 4 of 13 Rev. I q N) APPENDIX E
- 15. Move test trip switch PS-526D in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: / ,
- 16. Lif t and tape the wire on the rack side of terminal L-7 in the rear
, of I-R-II. Apply 120-VAC source to terminals L-7 and L-8 in the rear of I-R-11 and verify that XX-55-6B/51 is clear.
Performed by: / Verified by: / F
- 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.
l Performed by: / i Verified by: / l f"s 18. I.ift and tape the wire on the rack side of terminal L-5 in the rear (,) of I-R-il. Apply a 120-VAC source to terminals L-5 and L-6 and Verify, 1-XX-55-6B/50 is clear. . I - i Performed by: / Verified by: / Temporary Mydification to'lligh Steam Flow Coincident with Low S.G. Pressure or 1.ow-Low avg Safety Inje. Ion 19 Verif y annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be g cleared. Performed by: / Verified by: / NOTl;: If the alarms will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected. O 36 9
SQNP SPECIAL TEST 4 Page 5 of 13 Rev. 1 '0 APPENDIX E
- 20. Nove test trip switch TS412D in R-2 to the trip position and verify the amber light above the switch comes on.
> Performed by: / Verified by: /
- 21. Lif t and tape the wire on the rack side of terminal M-3 in the rear o f 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
' Performed by: / ! Verified by: /
i i
- 22. Nove 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
(,) 7-~ . of 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will cicar. 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.
j 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 in R-10 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: / I
.s uJ l 37
SQNP SPECIAL TEST 4 Page 6 of 13 Rev. 1 J APPENDIX E
- 26. flove 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: / 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 in R-13 and verify XA-55-6A/30 will clear.
Per' formed by: / Verified by: / i 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. Hove test trip switch FE512B in R-3 to the trip position and verify
(~5)
\- the amber light and annunciator XA-55-6B/2 come on.
7 Performed by: / Verified by: /
- 29. flove test trip switch FS522B in R-3 to the trip position and verif y the -
amber light and annunciator XA-55-6B/9 come on. Performed by: / Verified by: / NOTE: These twc trips will supply the 2 out of 4 logic required to get a Safety Injection Signal. i
+
v ' l 38 l t: (.
. ,r -> .- . .
A-SQNP SPECIAL TEST 4 Page 7 of 13 Rev. 1 [V' APPENDIX E
- 30. Apply Temporary Alteration Cont rol Tags forms to all the above test t rip switches to ensure that they remain in the trip position.
Damage to the histable could ocbur if the switch is moved back to the normal position. Record the temporary alteration numbers below: RACK TEST SWITCH TEMP ' ALT. NO. R-7 PS515A ". / ! R-7 PS515B / R-12 PS516C
/
R-12 PSS16D . / R-8 PS525B , / R-8 PS525A / R-11 PSS26D / R-11 RS526C / R-2 TS412D / R-6 TS422D / R-10 TS432D / R-13 .TS442D / , R-3 FS512B / - R-3 FS522B /
'the following step reduces th9 setpoint of the S/G pressure input to S.I.
to trip at 350 psig allowing avg to be reduced to 450'F.
- 31. Recalibrate the following bistables to the indicated setpoints and attach Temporary Alteration Control Tags.
4 Panel Bistable Satpoint R-12 PS-1-5A (PB516A) 350 psig Decreasing (21.66 MA Loop Current) Performed by: / Verified by: / R-11 PS-1-12A (PB526A) 350 psig Decreasing (21.66 MA Loop Current) Performed by: / Verified by: / (T 39
?
SONP SPECIAL TEST 4 Pr.ge 8 of 13 Rev. 1 l'G'"j APPENDIX E 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 ;> tpoint 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 steamlina 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. Hove test trip switch PS-526C in 1-R-11 to the normal position and I
verify the amber light above the switch and 1-XX-55-6B/50 are clear. Performed by: / Verified by: / l l
- 34. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Rete rmina te l wire on L-7.
i l Performed by: / ( Verified by: / l
/~'t U
40 e
4
- SQNP SPECIAL TEST 4 Page 9 of 13 Rev. 1 I APPENDIX E
- 35. Nove 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: /
I
' 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: / 1
; Verified by: /
- 37. Move test trip switch PS-525A in 1-R-8 to the normal position and verify the amber light and 1-XX-55-6B/26 are clear.
Performed by: / Verified by: / l 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.
j Performed by: / Verified by: / i {
- 41. 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 L": / Verified by / . \ .b 41 _r4,
SQNP SPECIAL TEST 4 Page 10 of 13 Rev. 1
';' , APPENDIX E , 42. Hemove the 120-VAC source from terminals L-5 and L-6 in 1-R-12. Retermi- ! nate wire on L-5.
i I Performed by: / ___ Verified by: /
- 43. Move test trip switch PS-516C in 1-R-12 to the normal position and g verity 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: / I 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. Performen by: / Verified by: /
- 46. Rcmove tie 120-VAC source i;om terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.
Perform"d by: / Verifie.1 by: /
- 47. Move 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.
Perfonied by: / Verified by: / NOTE: At this point the steamline Delta-P safety injection is in a normal operating nade. To retury the high steam flow coincident with low steam generator pressure or low-low avg to normal, perform the following steps.
~_/
42 l l
- l
SQNP SPECIAL TEST 4 Page 11 of 13 Rev. 1 (h APPENDIX E
- 48. Hove 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: /
, 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: / J
- 50. Remove the 120-VAC source from terminals M-3 and M-4 in R-13. Petermi-l nate wire on M-3.
Performed by: / Verified by: /
- 51. Hove 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 !!-3.
Performed by: / Verified by: /
- 53. Move test trip switch TS432D in R-10 to the normal pesition and verify the amber light goes out and XA-55-6A/30 will clear.
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: /
)
43 l ! w l
SQNP SPECIAL TEST 4 Page 12 of 13 i Rev. 1
. APPENDIX E 4
- 55. 11ove test trip switch TS442D in R-6 to the normal position and verify 4 . the amhnr 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-g n.ite wire on M-3.
Performed by: / Verified by: /
- 57. flove test trip switch TS412D in R-2 to the trip position and verify the amber light comes ora and XA-55-6A/30 will clear.
! Performed by: / l Verified by: / f l 58. Remove the Temporary Alteration Tage on the following test trip switches: O f. RACK TEST SWITCH TEMP ALT. NO. R-7 PS515A / R-7 PS515B / i R-12 PSS16C / R-12 PS516D / R-8 PS525B / R-8 PSS25A / , R-11 PSS26D / R-11 RSS26C /
- R-2 TS412D /
l R-6 TS422D / R-10 TS432D /
- R-13 TS442D /
l R-3 FS512B / l R-3 FSS22B / _ lo 44 4
, r . _ , , _ -,.- . <- -- -- -
SQNP SPECIAL TEST 4 Page 13 of 13 Rev. 1 APPENDIX E
- 59. 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: / l r The following step should be carried out to return the calibration of the S/G low pressure S.I. bistables to normal. I 4
- 60. The following bistables should be returned to their normal setpoints indicated on the calibration card for the particular bistable. (30.0 + .2MA)
Remove the temporary alteration control tags af ter the recalibration. NOTE: These calibrations 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 (PBS,16A) /
/
R-11 PS-1-12A (PB526A) /
/
R-11 PS-1-23A (PB536A) /
/
R PS-1-30A (PB546A) /
/
NOTE: All reactor safeguard systems modified for the special startup tests are back in a normal configuration at this time. O 45 b
SQNP SPECIAL TEST 4 Page 1 of 1 Rev. 1 O APPENDIX F Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. 8 d E e : :
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BEB BBNEN U 0 a3aaa63M ee TECifNICAL 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
@T(3.3.1)Inoperablebecauseoflowflow X X X X X X X X ttinimum temperature (3.1.1.4) X X X X ttoderator temperature coef ficient (3.1.1.3) X X X X Steamline AP SI (3.3.2.1) bypassed X X X X X X X X X X liigli Steamflow coincident 9 w/ low steamline 1
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 1evel low AFW start reset (3.3.2.1) X X Ifressurizer (3.4.4) X X X Ull! (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 A X X X X
/ Control Rod Insertion Limits (3.1.3.6) X X X X X X X \ - Reactor Coolant Flow Normal Operation (3.4.1.2) X X X X X X X X l 46 i
- . -. .. .- -- = - -- . . . -- _ ._ -_
l
; SQNP SPECIAL TEST 4 Page 1 of 1 Rev. 1 r
TABLE 1 Loop Flow and Core AT for
- Various Power Levels and Isolation Configurations (Computer Estimates)
No. of Loops Operating l (Nat. Circ.) i 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 W
.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% 1. = 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 L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE: L is % .of 97,000 gpm flow through operable loop.
i AT = Loop AT in F. O 47'
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SPECIAL TEST NO. 5 NATURAL CIRCULATION AT REDUCED PRESSURE i r i i I i l i e O i r i
SQNP SPECIAL TEST 5 Page 1 of 1 Rev. I 1 'v'
! NATURAL CIRCULATION AT REDUCED PRESSURE j Table of Conter.ts Me, 1
Test Description Special Operator Instruction 2 1.0 OB.JECTIVES 3 2.0 4 PREREQUISITES 3.0 PRECAUTIONS 7 9 4.0 SPECI AL TEST EQUIPMENT 10 S.0 INSTRUCTIONS 6.0 ACCEPTANCE CRITERIA 14 DATA SIIEETS 15 APPENDIX A - References 20 APPENDIX H - Deficiencies 21 APPENDIX C - Power Measurement Technique 22 I APl'ENDIX D - Computer Points 32 APPENDIX E - Safeguard Blocking Procedure 36 APPENDIX F - Technical Specifications Exceptions 47 T/JiLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 48 1
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SQNP SPECIAL TEST 5 - Page 1 of 1 Rev. 1 O. - TEST DESCRIPTION i The reactor coolant pumps are tripped with the reactor at 3% of rated power. i The reactor coolant system is depressuriz-d by turning off the pressurizer j l heaters and possibly turning on auxiliary sprays. Reactor power is re-
- I duced to 1.5% one hour af ter the pumps are tripped to approximate decay
- I heat conditions. Saturation margin is monitored and increased charging j { and/or steam flow is used to maintain test limits. k. E l .1 - I . I l i ! l \ l .; t lo e l l l \ l !. { h ( lO 1 l ~
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SQNP SPECIAL TEST 5 Page 1 of 1
- Rev. 1 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 Unexplaintd 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
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
O 2 , ,
r SQNP I SPECIAL TEST 5
~
Page 1 of 12
- Rev. 1
, 'i 1.0 OBJECTIVES 1.1 Verify the ability to maintain natural circulation at reduced RCS pressures.
; ; 1.2 Verify the accuracy of the saturation margin indication from the plant computer. ,
l 1.3 Provide operational experience at lower saturation margins and - the af fects of charging and secondary steam flow on the controi of the saturation margin. l I 1.4 To provide operator training, all shifts will perform this test.. NOTE: Data acquisition does not need to be repeated for multiple i test performances, i i l s i I e 4 1 O 3 t
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SQNP SPECIAL TEST 5 Page 2 of 12 Rev. 1
'O V 2.0 PRIGEQUISITES NOTE: This test can be done in conjunction with Test III, Natural Circulation With Loss of Pressurizer IIeaters.
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 peactor coolant pumps in operation. j Date 2.3 Steam generator level maintained at approximately 33% on the i narrow range indicators by the auxiliary feedwater pumps. i 4 Date 2.4 Pressurizer pressure and level being maintained automatically at approximately 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. I Date 2.7 Steam generator pressure at approximately 1000 psig and being maintained by steam dump to the condenser on pressure control. Date p
.G 4
SQNP SPECIAL TEST 5 Page 3 of 12 Rev. I
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2.0 PHEREQUISITES (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. l Recorder 1 Connect To: Monitoring: Channel #1 1-R-1, FP414B RCS F1w-Loop 1 i Channel #2 1-R-1, FP424B RCS Flow-Loop 2 l 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, FPS 12B Steam Gen. #1 Steam Flow
! Channel #3 1-R-3, PPS14B Steam Gen. #1 Pressure i
Channel #4 1-R-23, LP502 f cam Gen. #2 Level Channel #5 1-R-3, FPS 22B Steam Gen. #2 Steam Flow Channel #6 1-R-3, PP524B Steam Gen. #2 Pressure Recorder 3 Connect To: Monitoring: Channel #1 1-R-23, LP503 Steam Gen. #3 Level Channel #2 1-R-4, FP532B Steam Gen. #3 Steam Flow Channel #3 1-R 4, PP534B Steam Gen. #3 Pressure Channel #4 1-R-23, LP504 Steam Gen. #4 Level Channel #5 1-R-4, FP542B Steam Gen. #4 Steam Flow Channel #6 1-R-4, PP544B Steam Gen. #4 Pressure - Recorder 4 Connect To: Monit ring: 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 #2 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 O 5
SQNP SPECIAL TEST 5 Page 4 of 12 Rev. 1
.' l' ' 2.0 P.R_ER..E.QUISITES (Continued)
NOTE: Record the following on each recorder chart. ! a) Unit # b) Date c) Procedure # d) Parameter Scale and Range e) Chart Speed f) Name of person recording data j g) Recorder I.D. # i 2.9 Record on p-computer recorder a) Flux b) Average wide-range cold c) Average wide-range hot d) Average steam-generator pressure e) Reactivity Date 2.10 Set the trend recorders and computer trend printer in the main control room to monitor the paramet'ers indicated in Appendix D. 1 I
+
Date NOTE: Data acquisition need not be repeated for multiple test . ., : performances. N/A signoffs for these steps. I { 2.11 Verify the input logic o,f safety injection on Hi Steam Line AP has been blocked in accordance with Appendix E.
/
2.12 Verify the Hi Steam Flow coincident with Lo S/G pressure or lo i Tav input tr, Safety Injection has been modified in accordance with Appendix E.
/
2.13 Verify the automatic actuation of Safety Injection has been blocked in accordance with Appendix E.
/
r ( 6
- l. 9
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SQNP SPECIAL TEST 5 Page 5 of 12 Rev. 1 ( b 2.0 (Continued) 2.14 Verify the following UHI isolation valves are gagged:
$ FCV 87-21 /
l f FCV 87-22 /
"'" 87-23 /
l FCV 87-24 / l 2.15 Intermediate and power range (Iow setpoint) high level reactor trip setpoints have been set to 7% in accordance with Appendix l 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 SOI 68.2. p 3.2 Do not exceed 5% nuclear power at any time while the test is in V progress. 3.3 Abort test if any of the following temperature limits are exceeded: 3.3.1 Core exit temperature of 610*F. 3.3.2 AT as indicated by T H
-T C f 65 F. .
' T 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. T 3.5 After the reactor coolant pumps are tripped the 9ormal 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 15 degrees Fahrenheit at all times. T 3.7 Monitor reactor power closely whenever adjustments to cold are made. Maintain cold above 531 F. v n 7
4 i-
- SQNP SPECIAL TEST 5 Page 6 of 12 Rev. 1 i
I - 3.0 (Continued) 3.8 Should a reactor trip qccur 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 Maintain D bank at 2 100 steps during the conduct of this test. Should this limit be reached, boron concentration will have to i be increased. i 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. l l 9 4 i l l l
/8 p
-- , ,-w.- --, - - , . e -, -- - v . , - r,e-, -
SQNP SPECIAL TEST 5 Page 8 of 12 Rev. 1 5.0 TEST INSTRUCTIONS NOTE: Data acriuisition need not be expected for multiple test performance. N/A signoffs for these steps. 5.1 Ensure the pressurizer backup heaters lA, 1B, and 1C remain off by moving handswitches 1-ilS-68-341A and 341D to the 'Stop' posi-tion and moving 1-115 - 6 8 -3 4 111 to 'Stop-Pull to Lock'. l l e 5.2 Record the data indicated on Data Sheet 5.1. 4
/
5.3 Start the computer trend printer printing at the fastest interval possible. l
/
5.4 Shutoff the pressurizer control heater group by moving 1-ilS-68-341F to 'Stop'.
/
5.5 Record the time, on the data recorder charts in the auxiliary instrument room and then start them at 125mm/ min. i i i
/ .
5.6 Shutdown the reactor coolant pumps in accordance with S0I-68.2 (simultaneously).
/
NOTE: At the initiation of natural circulation the following temperature response is expected. I T l a) Wide range hot - increase l T b) Wide range cold - slight increase or constant c) goreexitthermocouple-increase d) avg indication - unreliable c) Delta-T indication - unreliabic f) Pressurizer level and pressure - increase i 5.7 Verify natural circulation is established by following the opera-tional guidelines given in Appendix A of E0I-5.
/
O 10 l t
-,- -.. . , - . - - - - c,
. SQNP SPECIAL TEST 5 1 -
Page 7 of 12 Rev. 1 f Uj 4.0 SPECIAL TEST EQUIPMENT 1 . l 4 : Calibration Instrument Specification Identification Verification
- f. .
Strip Chart Recorder Brush 260 or equivalent , (4) , Reactivity Computer Westinghouse Recorder (1) HP 7100B or Equivalent i 1 If test instruments are changed during this test, the instrument informa-tion must be recorded here and an entry made in the chronological log book j -explaining this change. O l 9 I I I
SQNP SPECIAL TEST 5 Page 9 of 12
- Rev. 1
) 5.0 TEST INSTRUCTIONS (Continued)
, NOTE: NaturalCirculationwillgestablewhen: T
- 1) AT between wide range hat and cold is constant.
- 2) AT between wide rangeTcold and core exit thermocouple average temperature is constant.
t 3) Wide range hot E core exit thermocouple average temperature. l (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. (Hold pressurizer level ~ constant after equilibrium I is reached on natural circulation).
/
5.8 Once equilibrium has been established adjust trend printer print-out intervals as specified by the test director.
/
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. ! /
NOTE: If desired, the d' pressurization e 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).
/
t l 5.10.1 When RCS pressure drops below 1970 psig, close the isola-l tion valves for the pressurizer PORV's by placing their f respective handswitches in the 'close' position. ! / l
- 'u)
( - 11
SQNP SPECIAL TEST 5 Page 10 of 12 Rev. 1
, \~- 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.
1
! /
NOTE: Do not allow the saturation margin to decrease below 20 F. i The margig can be increased by either increasing RC3 pressure or reducing cold. Charging must be Tincreased to maintain pressurizer level and pressure when reducing cold. l 5.12 Using 1967 ASME steam tables, determine the saturation margin using the pressure and temperature recorded in Data Sheet 5.3 and plot this value along with the saturation margin taken from the analog trend recorder vs time on Data Sheet 5.4.
/
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.
/
5.13.1 When RCS pressure is increased above 1970 psig, open the isolation valves for the pressurizer PORV's. - 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 determined from the steam tables. 4
/
, 5.15 Increase RCS pressure back to 2235 by selectively energizing the
- pressurizer backup heaters.
/
5.16 Insert control bank D until the reactor is in the hot zero power test range.
/
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Q/ l 12 l l l l -
SQNP SPECIAL TEST 5 Page 11 of 12 Rev. I 5.0 TEST INSTRUCTIONS (Continued) 5.17 Restart all four reactor coolant pumps in accordance with SOI 68.2 beginning with 2, 1, 3 and then 4. f a
/
5.18 Return pressurizer level to approximately 27% and return RCS pressure and level control to automatic.
/
NOTE: Conditions can now be established for the conduct of the next test. I 5.19 Remove the block of input logic of Safety Injection on Hi Steam Line AP in accordance 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.
/
5.20 Remove modification to Ili Steam Flow coincident with Lo S/G pressure or lo 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.
/
5.21 Remove block of automatic initiation of 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, dis-regard this step, place N/A in the signature line and initial.
/
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 / sJ 13
SQNP SPECIAL TEST 5 Page 12 of 12 Rev. 1 ( V) 5.0 TEST INSTRUCTIONS (Continued) 4 , 5.23 Reset the intermediate and power range high level reactor trip setp9ints as indicated by the test director in accordance with l Appendix C and D of SU-8.5.2 unless the next test to be per-formed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial. Power Range / Intermediate Range / 6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperatures does not exceed 610 F.
/
6.2 Delta-T for any loop does not exceed 65 F.
/
4 6.3 avg for any loop does not exceed 578'F. () 6.4 Natural circulation can be established and maintained at reduced . low RCS pressure.
/
6.5 The plant computer calculated saturation margin is in agreement with margins determined using recorded plant parameters within , d *
+ 3%.
/
1 (s 14 a n
4 SQNP SPECIAL TEST 5 Page 1 of 3 Rev. 1
. DATA SHEET 5.1 Initial Conditions i 4
Unit Time Date i i Pressurizer Pressure j PR-68-340 psi 8 Presst.rizer Level i LR-68-339 Red Pen % i #1 Hot leg temp o TR-68-1 F
#1 Cold leg temp o TR-68-18 F l
#2 Ilot leg temp o TR-68-1 F
#2 Cold Icg temp o TR-68-18 F
#3 llot leg temp o TR-68-43 F
#3 Cold leg temp o TR-68-60 F
#4 Ilot leg temp o i TR-68-43 F
#4 Cold Icg temp o TR-68-60 F
.S.G. #1 Level (narrow range)
{ LI-3-42 % S.G. #2 Level (narrow range) LI-3-55 % S.G. #3 Level (narrow range) 1 LI-3-97 % S.G. #4 Level (narrow range) 1 LI-3-110 %
/
Recorded By Date 15 O
- - - - - _ , , , w y p- ,. --, . , - - . ,w-w
SQNP SPECIAL TEST 5 Page 2 of 3 Rev. 1 O DATA SHEET 5.1 Unit. Time Date i S.G. #1 Level (wide range) LR-3-43 Pen 1 % < S.G. #2 Level (wide range) ~ ' LR-3-43 Pen 2 % S.C. #3 Level (wide range) LR-3-98 Pen 1 %
! S.G. #4 Level (wide range)
LR-3-98 Pen 2 % $ I S.G. #1 Pressure I PI-1-2A psig S.G. #2 Pressure PI-1-9A psig S.G. #3 Pressure PI-1-20A psig i S.G. #4 Pressure
! PI-1-27A psig '
4 S.G. #1 Feedwater flow
! F1-3-35A gpm
, S.G. #2 Feedwater flow l FI-3-48A gpm S.G. #3 Feedwater flow
-l
, 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
/ .(
Recorded By Date , 16 l l
3 SQNP SPECIAL TEST 5 Page 3 of 3 Rev. 1
, DATA SHEET 5.1
. Unit Time Date .
! S.G. #3 Steam flow i F1-1-21A lbs/hr 1 l S.G. #4 Steam flow
? F1-1-28A lbs/hr Loop #1 T-average o
TI-68-2E F i l Loop #2 T-average TI-68-25E _
,F Loop #3 T-average ,
TI-68-44E F Loop #4 T-average TI-68-67E ,F l l l Loop #1 A T t 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 % NIS Channel N-43 % l .NIS Channel N-44 % t
- . NOTE
- Attach Computer Printout of Incore Thermocouple Temperature Map.
4 Refer to Appendix A for the procedure for printing out of this map.
/
Recorded By Date 17
=
9 - . - , - e n< g wp r- ' ' ' ""'
- +, --n e---- e--e--- , ~9 T
a SQNP SPECIAL TEST 5 i -Page 1 of 1 Rev. 1 O l DATA SHEET 5.3 Unit Time Date
?
i i , Lowest of PI-68-340, 334A,
; 323A or 322A (PI-68-66A if below Highest Incore Computer Saturation
- i. 1700 psig) T/C Martin on Trend 4
Time = 0 m 9 l O . S 9 e J 1 i i O 18 l-~ . - - - . _ - - . ._. . _ _ . _ . _ _ . _ . . . . . _ , _ . _ . . , _ , . . _ _ _ _
i l SQNP
- SPECIAL TEST 5
. Page 1 of 1 1
4 l Rev. 1
- O .
DATA SHEET 5.4 i 4 (To be plotted on graph paper and attached) i l i f I 1 t O l t . O 19 l
.-,,.--.,,~,..,,n-----n,, - - - - - . , - - . . . . - , - . , . . - , , . , , -
._= _. - . - - . . . . - . . . - . . .__. __ _ - __ -
s SQNP SPECIAL TEST 5 Page 1 of 1 Rev. 1 O j DATA SHEET 5.3 ' 1 i } , Unit Time Date j l . Lowest of PI-68-340, 334A, l ! 323A or 322A l i . (PI-68-66A if below Highest Incore Computer Saturation ; 1700 psig) T/C Martin on Trend l Il
, 4.
Time = 0 , l 4 , i 1 6 i O .
~
,I dB S e I f I u O l 18
- 7
_ _ . , . .~. _
SQNP SPECIAL TEST 5 Page 1 of 1
. Rev. 1 0 , APPENDIX A References t
I t 1. FSAR
- 2. Technical Specifications
- 3. Plant Operating Instructions E01-5 9
SOI-68.2 t O . T l l l l 1 O 20
SQNP SPECIAL TEST 5 Page 1 of 1 Rev. 1
' . APPENDIX B Test Deficiencies #
Test Deficiency
. +
i i < t i .
- .' i i .
1 i .
}
I Recommended Resolution d l
\J .
l l 8 l 1 i . s
= .
5 Final Resolution a Originator
/
Signature Date PORC Review of Final Resolution Date
. Approva1 of Final Resolution /
. Plant Superintendent Date 21 4' ,
.-. ., -, , .%.__y. , ,..-.m.,- -_ _ , , g , , ,, . - . , , , , _ ,_,,y,
i I l SQNP ! SPECIAL TEST 5 ) Page 1 of 10 , J Rev. I
\
O APPENDIX C r
}
l l Procedure for Determining Core Power Level I 1 l l l i l I 1 e I 1 i l l O - l t i s l l l l I 1 i
-\
l l l 1 l O l l l 22 I I _ _. _ . _ . _ _ _ _._.____I
SQNP SPECIAL TEST 5 Page 2 of 10 Rev. 1 ,y %_) APPENDIX C Outline
- 1. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)
- 1. Reference (~ 550 F) Calorimetric (Before NC test) a) Output use'd to adjust M/D Power Monitor Program's power conversion constant.
11 . M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
i a) The output of the REF primary calorimetric will give a percent power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in percent
' power and equal to the primary calorimetric output.
- 2. Power Monitoring a) The M/D Power Monitor Program will calculate the integral power as seen by one pass of 5 or 6 detectors. After the output has been calibrated to be equhl to the REF primary calorimetric it will be rerun up to once every 2 minutes or as necessary to continuously monitor core power.
t i
,o Lj 23
SQNP SPECIAL TEST 5 Page 3 of 10 Rev. 1 ( APPENDIX C CORE POWER DETERMINATION k l 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 CalculatetheAT;multiplythftATbythespecificheatand the Westinghouse best estimate flow rate of the core average temperature (Table C-1). (Special Test No. 9 uses wiue range t 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. O . 9 O s 24
% ne. = 6 ~ 'W q,
s--- - , , --+ --
SQNP SPECIAL TEST 5 Page 4 of 10 Rev. 1 APPENDIX C i Core Power Determination i 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 i 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 i -
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 5-path selector switches set to normal, run a' flux trace.
- c) With all 5-path selector switches set to Emergency, run a second flux trace.
d) Determine the detector normalization constants from Data Sheet C.2. .. O %,m 25 e . *
,- w es i
i SQNP l SPECIAL TEST 5 l Page 5 of 10 I Rev. 1 )
\ ,~
N- APPENDIX C 1 s Core Power Determination 1
; PART B: (Continued) l l- e) Enter these detector normalization constants into the P-250 I as shown in the table below.
1 Drive P-250 Address A KU908 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- . i rent. Update as required. [ l Address Value Function i K0901 1 Set the power normalization factor Selects the modified " Flux Map K5525 1 Print" programs i K0900 0 Initiated Pass Number' Calibration Constant for M/D Power
- K0864 Variable (I) Monitor (I) 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 entered in (K0864). If no value has been entered into (K0864) entec 0.25.
Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x nN,) 26 l l
- y - . --
l
SQNP SPECIAL TEST 5 Page 6 of 10 Rev. 1
/h 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 detect'or normalized integrals are also printed.
, TABLE C-1 Cp(1) m f;emp BTU /lbm,F . lbm/hr 556 1.260 3.6448 x 10 7 7
554 1.255 3.6553 x 10 552 1.250 3.6659 x 10 7 7 550 1.245 3.6765 x 10
' 7 548 1.240 3.6862 x 10 7
546 1.236 3.6959 x 10 7 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 7 540 1.221 3.7254 x 10 538 1.217 3.7348 x 10 7 536 1.213 3.7443 x 10 534 1.209 3.7538 x 10 7 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.
, 27 1
i
,,e- ,
gs J, 3 [';
- t )
(~} v v SQNP SPECIAL TEST 5 Page 7 of 10 Rev. 1 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 1 Loop AT - Inservice (at test point) Volts 2 Loop AT = (#1) x (1) F 3 Loop AH = (#2) x Cp (from Table C.1) BTU /lba 0
4 Loop RCS Flow (from Table C.1) 10 lbm/hr 6 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 .NT 8 % Reactor Power = (#7) x 0.02932 % (1) Conversion factor for AT obtained from scaling document. Remarks: Date By: Checked By: e
SQNP SPECIAL TEST 5 Page 8 of 10 Rev. 1 O N.) , APPENDIX C DATA SHEET C.2
= C *
- FN
- A N N N N N=
AE* E E E E E" NA = 1.00 NA N = AN = AE = B B N N N = = E = C N N A N = N = CE = D N NE = = E = N N NE N p=AN = EE = rN rN f Definitions: A' N, CN , DN ' N, FN = Normalized integral frem summary map for each 7 N detector in a normal path in the first pass A,B,C,D' E, FE = Normalized integral from summary map for each E E E E detector in an emergency path in the second pass N,N,N' E'
= Detector normalization factor for each detector A B C D' F Remarks:
im ( ,) Data By:__ Date ! 29 a w
. SQNP SPECIAL TEST 5 Page 9 of 10 Rev. 1 0 : APPENDIX C l
j PART C: Using Thermocouples 5~ ,
' The incore thermocouples can be used as an indicat' ion 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:
I
- 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 a t 1, 2, . . . X 8 seconds or 64 seconds for us.
! i The thermcouple programs breaks the core down into eight quadrants--
p 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 U1159 2 U1160 3 U1161 4 U1162 5 Ull51
; 6 U1152 7 U1153 8 U1154 A Short Form Map should be run periodically or upon request from the test engineer as an indication of core flow dihtribution. It should be put on the Utility Typewriter if possible. ,The P-250 Operator's Console Reference Manual provides instructions for ob-taining thermocouple maps.
The t' rend output and Short Fore Maps should be attached to this procedure at the end of the test. 30
SQNP SPECIAL TEST 5
. Page 10 of 10 , Rev. 1 O APPENDIX C CENTER LINE OUARTER. CORE $YMMETRY Cdd Logs 1 i 3 4 .
l l N-43 m 2,a* m N-42
' O O i
. ; y I i 3 , 2 '4 l }
' 180 n* W3f $ r}s '
/kiley ( -) .
- 2. l 4 3 '/
( ) EXCORE DETECTORS o v oo v oN*AA M-4/ 2 . I f Cold Lag.c O > s , DI AGONAL QUART ER-CORE SYMMETRY l 225' 315* s . 6 A e
>\ .
,\
- N, .
- ,fs 6' l 9 Fi9 ure C-(
f v 31
SQNP SPECIAL TEST 5 Page 1 of 4 Rev. I f (~') APPENDIX D 'x _' ( Procedure For Use Of Computer System For Data Collection The following parameters will be monitored during this test using the plant I computer system. Pa rameter Computer Point Pressurizer Pressure P0480A Pressurizer Level LO480A l
; 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 l I RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressure P0400A Steam Generator 1 Narrow Range Level LO400A Steam Generator 2 Pressure P0420A i
Steam Generator 2 Narrow Range Level LO420A
. i Steam Generator 3 Pressure PO440A Steam Generator 3 Narrow Range Level LO440A
. Steam Generator 4 Pressure P0460A 1
Steam Generator 4 Narrow Range Level LO460A
. Power Range Channel 1 (Quadrant 4) N0049A
. Power Range Channel 2 (Quadrant 2) N0050A 1
Power Range Channel 3 (Quadrant 1) N0051A l
<r :.T. Power Range Channel 4 (Quadrant 3) N0052A y ,! ,
I
..N Incore Thermocouples T0001A through T0065A 32
SQNP SPECIAL TEST 5 Page 2 of 4 Rev. 1 () 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). Bl.0CK 1 Column Point Column Point Column Point 1 P0480A 7 T0459A 13 PO420A 2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479h 15 P0440A 4 T0406A 10 T0466n 16 LO440A 5 T0439A 11 PO4004 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 7-~s 6 T0013A d To initially cicar each data block perform the following step for each block . to be used.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Pust VALUE 1 button
- 4. Select 0 on keyboard -
- 5. Push VALUE 2 button
- 6. Push STOP button Repeat the above 6 steps for each data block to be used.
NOTE: A Block Trend Error message will occur if the data block is 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. PO480A) on the alphanumeric keyboard
! 3. Push ADDRESS button l 4. Select block number (1 to 6) on keyboard.
- 5. Push VALUE 1 button
- 6. Select column number (1 to 18) on keyboard
[)
- 7. Push VALUE 2 button
- 8. Push START button
, 33 l p , . . _ - .. -
SQNP SPECIAL TEST 5 i i Page 3 of 4 i 1 Rev. I
, APPENDIX D Once the blocks are set up they can be initiated by performing the follow-Ing steps for each block.
I
- 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. Pusn START button If it is r.ecessary to change the trend interval of a block or trend, perform the following.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select new interval number (0 = 30 sec., 1 = 1 min.,
, 2 = 2 min., etc) on keyboard
- 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
, 4. Select C on keyboard
- 5. Push VALUE 3 button
- 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).
After selecting the per to be used to record a value, ensure that it is cleared by performing the following steps.
, 1. Push ANALOG TREND function button -
- 2. Select per number (1 to 12) on keyboard
, 3. Push VALUE 1 button
- 4. Push STOP button O
34
SQNP i
/ SPECIAL TEST 5 i Page 4 of 4 l Rev. 1 APPENDIX D To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on the alphanumeric keyooard
- 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 l 8. Push VALUE 3 button i 9. Push START button i
i Repeat these steps until all of the desired analog points are being re-j corded. i l 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. t To initiate an incore thermocouple map at that location, perform the following
- steps.
()f 1. 2. Push IN-CORE T/C MAP function button Select 25 on keyboard for short-form current map .
- 3. Push VALUE 1 button Select output device code number 20 for programmers 4.
]
console on keyboard 1 5. Push VALUE 2 button
- 6. Select 1 on keyboard for a saort-form map j 7. Push VALUE 3 button
- 8. Push START button t
i N 35
- i
- 1. _
l
SQNP SPECIAL TEST 5 Fage 1 of 11 Rev. 1 O
%J APPENDIX E l Safeguard Blocking Procedure l
The first step blocks automatic initiation of a safety injection. The j safety injection alarm, manual S.I handswitch, and the reactor trip por-l tion of trt 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-matica11y. (3) a safety injection can be ir.itiated manually from the switch in the control room if conditions warrant. j 1. Install temporary jumpers and temporary alteration control tags to e logic cards A216, test point 1, to the logic ground on the logic test I 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 i;jection on high steamline Delta-P. This block will prevent a reactor trip frem occuring during the natural circulation tests from high AP caused by degraded test conditions. (This block will also defeat all AP SI alarms).
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, -
! 73, 76 are all clear prior to starting blocking procedure.
5 Hove test trip switch PS-515A in 1-R-7 to the trip posit'.on 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 ir 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. 1 O'd APPENDIX E ground will already be made up through the trip switch). The wire on the rack side of the terminal block must be lifted and taped for the terminal point where the jumper wire is connected The TACF tag will be attached to the bistable switch and the TACF must note the jumper and'the lifted wire. NOTE: Orange "Out of Service" sti bers should be placed on all status / alarm windows as the 120V source is connected. t
- 4. Lift and tape the wire on tha track side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-7 and verify 1-XX-55-6B/25 is clear.
Performed by: / Verified by: /
- 5. Move test trip switch PS-515B in 1-R-7 to the trip position cad verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 6. Lif t and tape the wire on the rack side of terminal L-7 in the rear of -
1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear. ' Performed by: / Verified by. / .
- 7. Nove test trip switc' PS-516C in 1-R-12 to the trip position and verify
) the amber light above the switch comes on. i Performed by: / Verified by: /
- 8. Lif t and tape the wire on the rack side of terminal L-5 in the rear of 1-R-7. Apply 120-VAC source to terminals L-5 and L-6 in the rear of 1-R-12 and verify 1-XX-55-6B/73 is clear.
Performed by: / Verified by: / l n v 37
i SQNP SPECIAL TEST 5 Page 3 of 11
, Rev. 1 l O
U. . APPENDIX E
- 9. Move test trip switch PS-516D in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 10. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-12. Apply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-12 and verify 1-XX-55-6B/76.
Performed by: / I i Verified by: /
- 11. Move test trip switch PS-525B in 1-R-8 to trip position and verify the i 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 7
1-R-8. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/28 is clear. i l Performed by: / Verified b'y: /
- 13. Move test trip switch PS-525A in 1-R-8 to the trip position and verify
- 1 the amber light above the switch comes on.
Performed by: / Verified by: / i 14. Lift and tape the wire on the ' rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear. Performed by: / Verified by: /
- 15. 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: /
's/ Verified by: /
38
SQNP SPECIAL TEST 5 Page 4 of 11 Rev. 1 O APPENDIX E
- 16. Lif t and tape the wire on the rack side of terminal L-7 in the rear of I-R-11. Apply 120-VAC source to terminals L-7 and'L-8 in the rear of I-R-Il and verify that XX-55-6B/51 is clear.
I Performed by: / Verified by: / i 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. Lif t and tape the wire on the rack side of terminal L-5 in the rear or 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is clear.
Performed by: / Verified by: / Temporary M dification to High Steam Flow Coincident with Low S.G. Pressure or Low-Low9avg 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 modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected.
- 20. Move test trip switch TS412D in R-2 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 21. Lift and tape the wire on the rack side of terminal H-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
~
Performed by: / Verified by: / 39
SQNP SPECIAL TEST 5 Page 5 of 11 Rev. 1 APPENDIX E
- 22. have 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. Hove test trip switch TS432D in R-10 to the trip position and verify the amber light above the switch comes on.
l 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
~N XA-55-6A/30 will clear.
(d Performed by: / Verified by: /
- 26. Move test trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
- Performed by: /
Verffied by: _ /
- 27. Lif t and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: / 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.)
40
- , - - - ,v-- - - - - - -
3-m- ,-- ,
SQNP SPECIAL TEST 5 Page 6 of 11 Rev. 1
- 6 V 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.
! Performed by: /
Verified by: / i
- 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.
Performed by: / Verified by: / NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal. I
- 30. Apply Temporary Alteration Control Tags forms to all the above test trip switches to ensure that they remain in the trip position.
Damage to the bistable could occur if the switch is moved back to the normal position. Record the temporary alteration numbers below: RACK TEST SWITCH TEMP ALT. NO. R-7 PS515A / . R-7 PSS15B / -
-i R-12 PS516C ,
/
R-12 PS516D / 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 / To return the steamline Delta-P S.I. to normal condition, the following steps should be followed. O 41 l l 1
SQNP SPECIAL TEST 5 Page 7 of 11 Rev. 1 s-
)
, 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 ia 1-R-11. Reterminate
! wire on L-5.
4 Performed by: / Verified by: / __ l
- 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.
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: / ,/~} V/ 34. Hove 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. j 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: / l Verified by: /
.36. Hove 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. 1-cmove the 120-VAC source from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.
Performed by: / (q,1 Verified by: / 42
SQNP SPECIAL TEST 5 Page 8 of 11 Rev. 1 7 ( l 4 APPENDIX E
- 38. 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.
I Performed by: /
; Verified by: __ /
t 39. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. Retermi-g 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: / l
- 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. Move test trip switch PS-516C in 1-R-12 to the normal position and verify the amber light above the switch and 1-XX-55-6B/73 are clear.
! Performed by: /
Verified by: /
- 43. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi-nate wire on L-7.
Performed by: / Verified by: /
- 44. 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: / ) (~N
.' l 43 l 1
l
= l - - - . .. _
SQNP SPECIAL TEST 5 Page 9 of 11 i Rev. 1 (, (/ APPENDIX E
- 45. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Rete rmi-
; nate wire on L-9.
Performed by: / Verified by: /
- 46. Move test trip switch PS-515A to the normal position and verify the g 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 ' '- etion is in a normal operating mode. Toreturntgehighsteamflowcoincidentwithlowsteamgeneratorpressure or low-low avg to normal, perform the following steps.
- 47. Move 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.
l I Performed by: / Verified by: /
- 48. 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: / 4 l 49. Pemove the 120-VAC source from terminals M-3 and M-4 in R-13. Retermi-i nate wire on M-3. Performed by: / Verified by: /
.50. 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: / 44
SQNP SPECIAI. TEST 5 Page 10 of 11 3 Rev. 1 O V APPENDIX E
- 51. 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: /
] 52. tbve test trip switch TS432D in R-10 to the normal position and verify l the amber light goes out and XA-55-6A/30 will clear.
t Performed by: / Verified by: /
- 53. 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: /
- 54. Move test trip switch TS442D in R-6 to the normal position and verify I the amber light goes out and XA-55-6A/30 will clear.
] Performed by: / .
Verified by: / ,
- 55. Remove the 120-VAC source fro'm terminals M-3 and M-4 in R-2. Retermi-nate wire on M-3.
I Performed by: / Verified by: /
- 56. Hove 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: / k x_/ 45 l
1 1 j ' SQNP
- SPECIAL TEST 5
, Page 11 of 11 Rev. 1 i O ,Y I
APPENDIX E
~
- 57. Remove the Temporary Alteration Tage on the following test trip switches:
RACK TEST SWITCH TEMP ALT. NO. R-7 PSS15A / R-7 PSS15D / R-12 PS516C / R-12 PS516D / R-8 PS525B / R-8 PS525A / R-11 PS526D / R-11 RSS26C / R-2 TS412D / R-6 TS422D / R-10 TS432D / R-13 TS442D / R-3 FS512B / R-3 FS522B ,
/
- 58. Remove the jumpers' and the hekneary Alteration Tags from logic cards A216, test point 1, to tffe logic ground on the logic test panels in R-47 and R-50. .
R-47 Panel Performed by: / Verifiediby: / 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. O 46
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MICROCOPY RESOLUTION TEST CHART
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SQNP SPECIAL TEST 5 Page 1 of 1 p Rev. 1 L] APPENDIX F Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. E d E e : 3
- 8e8
- u ne m g c $e%0 $ 5 o Seo o 50 8 3 t.)aet " 5 8 g . . . t a" K3nBB? * 'E a E a0000 3 %
~~~~s ?%5 " 2 (o
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225%38 1 333 ee#% e 8 e3ese63M ee TECHNICAL APECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment HI Pressure SI (3.3.2.1) X X X X X X X X X X Safety Limits (2.1.1) X X X X X X X X X OPAT (3.3.1) Inoperable because of low flow X X X X X X X X OTAT (3.3.1) Inoperable because of low flow X X X X X X X X Minimum temperature (3.1.1.4) X X X X Moderator temperature coef ficient (3.1.1.3) X X X X Steamline AP SI (3.3.2.1) bypassed X X X X X X X X _X X High Steamflow coincident 9 w/ low steamline 1 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 1evel 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 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 ph s 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. I
^
\
t TABLE 1 Loop Flow and Core AT for
. Various Power Levels and Isolation Configurations (Computer Estimates) l l,
e 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 N
.75% L= 3.7 L= 4.1 L= 4.7 L= 5.9 AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 L= 4.1 N 1% L= 4.5 L= 5.2 L= 6.5 AT = 16.3 AT = 19.8 AT = 26 AT = 41 N
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 L= 5.6 W 2.5% 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 operable loop. AT = Loop AT in F.
/ ')
48
O A SPECIAL NO. 6 C00LDOWN CAPABILITY OF THE CHARGING AND LETDOWN 9 . 3 h l i O l
- r. ,- - - --
SQNP SPECIAL TEST 6 Page 1 of 1 Rev. 1 O ' C00LDOWN CAPABILITY OF THE CHARGING AND LETDOWN l Table of Contents gate Test Description 1 Special Operator Instruction 2 1.0 OBJECTIVES 3 2.0 PREREQUISITES 3 3.0 PRECAUTIONS 6 4.0 SPECIAL TEST EQUIPMENT 7 5.0 TEST INSTRUCTIONS 8 i 6.0 ACCEPTANCE CRITERIA 10 0 DATA SIEETS 11 APPENDIX A - References 13
- APPENDIX B - Test Deficiencies 14 APPENDIX C - Computer Points 15 APPENDIX D - Safeguard Blocking Procedure 19 APPENDIX E - Technical Specifications Exceptions 30 TABLE 1 - Loop Flow and Core AT for Various Power 31 Levels and Isolation Configurations
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SQNP SPECIAL TEST 6 Page 1 of 1 Rev. 1 O ' TEST DESCRIPTION The reactor coolant pumps are tripped with the reactor subcritical and the primary system at hot standby. All steam generators are isolated on the secondary side. Charging and letdown are increased to maximum capacity.
. After 30 minutes charging and letdown is reduced to minimum. The cooldown
, rates are observed for these maximum and minimum conditions. O. . e J I i O 1 c-. m.. : .. . . _ , . , _ . _ _ . . , ,_ _,, _ ,
4 SQNP SPECIAL TEST 6
, Page 1 of 1 Rev. 1 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% l or to an Indicated Level of $ 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
*SI termination should be.in accordance with plant EMERGENCY OPERATING 1
- PROCEDURES.
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{ SQNP
. SPECIAL TEST 6 Page 1 of 8 Rev. 1 Q'
l.0 OBJECTIVES Tha objective of this test is to determine the capability of the charg-
; ing and letdown system to cooldown the reactor coolant system with the steam generators isolated and one reactor coolant pump in operation.
2.0 PREREQUISITES 2.1 The reactor is shutdown and borated to ensure adequate shutdown margin (Mode 2). Date 2.2 All four reactor coolant pumps are in operation. Date 2.3 Steam generator level being maintained at approximately 33% with the auxiliary feedwater system. l
' Date O 2.4 Reactor coolant system pressure and level under automatic control at approximately 2235 psig and 25% level. -
Date 2.5 Reactor coolant system temperature being controlled at approxi-mately 540'F by steam dump to the condenser under automatic (Steam generator pressure at approximately pressure control. 948 psig). Date 2.5 Steam generator chemistry is within normal guidelines such that steam generator blowdown can be isolated when the steam generators are isolated. Date 2.7 Set up one of the source range channels on NR-45 to monitor any changes'in the core flux level. I Date 3 l g .
SQNP. SPECIAL TEST 6 Page 2 of 8 l Rev. I 2.0 PREREQUISITES (Continued) i 2.8 Normal charging and letdown in service and under automatic
; control.
I
~l Date 2.9 Connect recorders to the following test points in the auxiliary instrument room.
q Recorder 1 Connect To: Nonitoringi Channel No. 1 1-R-23, TP130 Letdown HTX Outlet Temp. Channel No. 2 1-R-19, TP127 Reg. HTX Outlet Channel No. 3 1-R-15, TP126 Charging Tem. Channel No. 4 1-R-1, PP455B Pressurizer Pressure Channel No. 5 1-R-1, LP459B Pressurizer Level Recorder 2 Connect To: Monitoring:_ i t Channel No. 1 1-R-18, FP121A RCS Charging Flow l Channel No. 2 1-R-23, FP132 RCS Letdown Flow Channel No. 3 1-R-2, TP413E Loop 1 Hot Leg Temperature j Channel No. 4 1-R-6, TP413F Loop 1 Cold Leg Temperature Channel No. 5 1-R-2, TP423E Loop 2 Hot Leg Temperature Channel No. 6 1-R-6, TP423F Loop 2 Hot Leg Temperature Recorder 3 Connect To: Monitorinn Channel No. 1 1-R-2, TP433E Loop 3 Hot Leg Channel No. 2 1-R-6, TP433F Loop 3 Cold Leg 4 Channel No. 3 1-R-2, TP443E Loop 4 Hot Leg Channel No. 4 1-R-6, TP443F Loop 4 Cold Leg i i / i Date
! NOTE: Record the following on each recorder chart.
a) Unit number b) Date c) Procedure number d) Parameter scale and range e) Chart speed f) Name of person recording data g) Recorder ID number b v 4
SQNP SPECIAL TEST 6 Page 3 of 8 Rev. 1 2.0 PREREQUISITES (Continued) 2.9.1 Record the following parameters on the reactivity computer.
- a. Flux i b. Average wide range c Id T
j c. Average wide range hot , j d. Average steam generator pressure
- e. Reactivity i /
Date 2.10 Setup the P-250 computer trend printer to monitor the parameters indicated in Appendix D. I Date 2.11 Verify the input logic of safety injection on Hi Steam Line AP is blocked in accordance with Appendix E.
/
Date -() 2.12 Verify the Hi Steam Flow coincident with Lo S/G or Lo av input to Safety Injection is modified in accordance with Appendix E. . i
/ -
Date 2.13 Verify the automatic actuation of safety injection is blocked in accordance with Appendix E.
/
Date j i 2.14 Verify the following UHI isolation valves are gagged: , 1 FCV 87-21 / l FCV 87-22 / FCV 87-23 / FCV 87-24 / 2.15 Verify the auxiliary boiler is in service and supplying steam seals to the turbine.
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SQNP SPECIAL TEST 6 Page 4 of 8 Rev. 1 Q 2.0 PREREQUISITES (Continued) 2.16 Intermediate and power range (Iow 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 Before beginning, and while the test is conducted, verify ade-
; quate shutdown margin by rod and boron worth calculations.
3.2 The boron concentration in the pressurizer should not be less than the concentration in the reactor coolant loops by more than 50 ppm. Use pressurizer spray to equalize concentration. 3.3 Both source range channels should be in operation and monitored closely during the conduct of this test, j 3.4 Charging flow to the RCS must be at the same boron concentration
- as that required for shutdown.
I {/ s, S 3,5 The RCS should be sampled for boron concentration once toward the end of the 30-minute period of maximum letdown and charging and shutdown margin verified. l G l
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SQNP SPECIAL TEST 6 Page 5 of 8 Rev. 1 ,s s' 4.0 SPECIAL' TEST EQUIPMENT Identification Calibration Instrument Specification Number Verification i Strip Chart Recorder Brush 260 or (3) equivalent Reactivity Computer Westinghouse Recorder (1) HP 7100B or equivalent l l i e l I If test instruments are changed during this test, the instrument information 7- s. , must be recorded here and an entry made in the chronological log book explain-t J ing this change. 7
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SQNP SPECIAL TEST 6 Page 6 of S
- Rev. 1
-s 5.0 TEST INSTRUCTIONS t 5.1 If the reactor coolant system Tavg is above 540 F, reduce it i
by manually increasing steam dump to the condenser.
/
5.1.1 Start the recorders in the auxiliary instrument room at 25 mm/ min and trend printer. 5.2 Shutdown reactor coolant pumps 1, 3, and 4 in accordance with SOI 68.2. Ensure loop 1 pressuria.er spray valve is closed and i in manual control.
/
S.3 Isolate all four steam generators by closing main steam iso-lation valves and auxiliary feedwater valves.
/
5.4 Isolate steam generator blowdown if it is presently in opera-i tion by closing FCV-15-12 from the controller located next to the flash tank.
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5.5 Increase charging flow and letdown to the maximum allowable.
' /
5.6 Continue maximum letdown and charging for a 30-minute period and then reduce letdown and charging to the minimum allowable. I Continue recording data. f NOTE: Toward the end of the 30-minute period a boron analysis of the RCS should be done to verify adequate shutdown margin. 5.7 After running with minimum letdown and charging for a 30-minute period, stop the recorders and attach the ciarts to Data Sheet 5.1.
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5.8 Stop trend printer and recorder. g-~3 / l 8 l i l l 1
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SQNP SPECIAL TEST 6 Page 7 of 8 Rev. 1 O 5.0 TEST INSTRUCTIONS (Continued) 5.9 Open MSIV bypass valves and then the MSIV's when the steam generator pressure and steam header pressure are approximately equal. I FOTE: Control secondary s;.de pressure using the atmospheric dump valves until all MSIV's are open. 5.10 f, tart reactor coolant pumps 1, 3, and 4 in accordance with 30I 68.2.
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5.11 On Data Sheet 5.2, using recorded data, calculate the average rate of temperature change for the 30-minute periods of maxi-mum and minimum letdown and charging.
/
5.12 Remove the block of input logic of Safety Injection on Hi Steam Line AP in accordance with Appendix E, unless the next test to be performed requires the block to be installed. If this is the Ox . case, disregard this step, place N/A in the signature line and initial.
/
5.13Removemodi{icationtoHiSteamFlowcoincidentwithLoS/GPres-sure or lo av 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. L
/
5.14 Remove block of automatic initiation of Safety Injection in ac-cordance 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 the signature line and initial.
/
5.15 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 fg signature line and initial. V 9
SQNP SPECIAL TEST 6 Page 8 of 8 Rev. 1 A
, 5.0 TEST INSTRUCTIONS (Continued)
FCV 87-21 / FCV 87-22 / FCV 87-23 / FCV 87-24 / 5.16 Reset the intermediate and power range high level reactor trip setpoints as indicated by the test director in accordance with
', Appendix C and D of SU-8.5.2 unless the next test to be performed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial.
Power Range /
- Intermediate Range /
6.0 ACCEPTANCE CRITERIA T 6.1 The effect of charging and letdown variations on avg has been determined.
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I i l i C.4h 10 i
SQNP SPECIAL TEST 6 Page 1 of 1 Rev. 1 O DATA SHEET 5.1 Attach the recorder charts and computer printouts to this page.
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O . 1 i l i l 11 s - .. e = = " 7 --r - '"'" ""f
SQNP SPECIAL TEST 6 Page 1 of 1 Rev. I r's ( ) v DATA SHEET 5.2 tiaximiun Letdown and Charging Charging Flow gpm i Letdown Flow gpm Average Temperature Change F over the 30-minute period. I Avg. ange op Rate of Temperature Change = _ flinimum Letdown and Charging Charging Flow gpm Letdown Flow gpm Average Temperature Change F over the 30-minute period. Rate of Temperature Change = Avg. hb
.5 =
i Calculated by / l Reviewed by / h,
=
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- 1
SQNP SPECIAL TEST 6 Page 1 of 1 Rev. 1 O APPENDIX A References i
- 1. FSAR
; 2. Technical Specifications j 3. Plant Operating Instruction SOI 68.2 O .
1 0 O 13
3 i i SQNP
- SPECIAL TEST 6 Page 1 of 1
- - Rev. 1
. IO'
- . APPENDIX B i
Test Deficiencies # i
- j. Test Deficiency i
a l I i l
- Recommended Resolution i
i O 4 1 i I 4
- Final Resolution i
! . Originator / l Signature Date , i
- PORC Review of Final Resolution I
Date , - Approval of Final Resolution / l h Plant Superintendent Date 14
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SQNP SPECIAL TEST 6 Page 1 of 4 Rev. 1 [ v APPENDIX C Procedure For Use Of Computer System For Data Collection The following parameters will be monitored during this test using the plant computer system. Parameter Computer Point Pressurizer Pressure P0480A Pressurizer Level LO480A RCS Loop 1 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 HCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Hot Leg Temperature T0479A 4 RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressure P0400A s
- Steam Generator 1 Narrow Range Level LO400A j Steam Generator 2 Pressure P0420A
; Steam Generator 2 Narrow Range Level LO420A Steam Generator 3 Prescure PO440A ', Steam Generator 3 Narrow Range Level LO440A Steam Generator 4 Pressure P0460A Steam Generator 4 Narrow Range Level LO460A Power Range Channel 1 (Quadrant 4) N0049A Power Range Channel 2 (Quadrant 2) N0050A Power Rai.ce Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A i
Incore Thermocouples T0001A through T0065A 15 o
SQNP SPECIAL TEST 6 Page 2 of 4 Rev. 1 (~h APPENDIX C
'J ~ .
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 LO420A 3 T0419A 9 T0479A 15 PO440A 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 PO400A 17 P0460A i 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.
- 1. PushDIGIhALTRENDbutton
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 2 button
- 6. Push STOP button Repeat the above 6 steps for each d:'a block to be used.
NOTE: A Block Trend Error message will occur if the data block is initially clear. To set no the data blocks, perform the following series of steps for each point to be monitored.
- 1. Push the DIGITAL TREND button
- 2. Select the point address (i.e. PO480A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select block number (1 to 6) on keyboard.
- 5. Push VALUE 1 button
- 6. Select column number (1 to 18) on keyboard
- 7. Push VALUE 2 button
()
\-- 8. Push START button 16 e
SQNP SPECIAL TEST 6 Page 3 of 4 Rev. 1 APPENDIX C 1 On ce- the blocks are set.up they can be initiated by performing the following steps for each block.
- 1. Push DIGITAL TREND button.
i 2. Select block number (1 to 6) on keyboard i 3. Push VALUE 1 button
; 4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 = 2 minute, etc.) The 30-second interval is q 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
(-s To stop trending or block perform the following: v
- 1. Push DIGITAL TREND button
! 2. Select block number (1 to 6) on keyboard '
- 3. Push VALUE 1 button
- 4. Select C on keyboard
- 5. Push VALUE 3 button
- 6. Push STOP button In addition to the data recorded on the trend typewriter, the following points will be monitored on analog trend recorded.
4 I T0056A (Core exit temp). Others as needed (Recommend pressurizer pressure, steam generator level (WR) and steam generator pressure). After selecting the per to be used to record a value, ensure that it is cleared by performing the following steps.
- 1. Push ANALOG TREND function button
- 2. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
. 4. Push STOP button O
17
; SQNP i SPECIAL TEST 6
- Page 4 of 4 Rev. 1 (3
L/ ' l APPENDIX C i To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on the alphanumeric keyboard I 3. Push ADDRESS button j 4. Select per number (1 to 12) on keyboard
- 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the minimum value of the parameter to be monitored
- 7. Select range on the keyboard
- 8. Push VALUE 3 button
- 9. Push START button Repeat these steps until all of the desired analog points are being recorded.
Prior to initiation of the transient, and as required thereaf ter, incore thermo-couple maps will be recorded at the programmers console in tne computer room.
! To initiate an incore thermocouple map at that location, perform the following l steps.
(~) 1. Push IN-CORE T/C MAP function button
2. Select 25 on keyboard for short-long current map
- 3. Push VALUE 1 button
- 4. Select output device code number 20 for programmars console on keyb,oard.
- 5. Push VALUE 2 button
- 6. Select 1 on keyboard for a short-form map
- 7. Push VALUE 3 button
- 8. Push START button 1
0 18
SQNP SPECIAL TEST 6 Page 1 of 11 Rev. 1 /7 APPENDIX D U 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-j tion of the protection logic will remain in operation. If conditions i exist that would normally initiate a safety injection; (1) the safety l injection alarm will initiate telling the operator that the condition i exists and what the problem is. (2) a reactor trip will take place auto-t matically. (3) a safety injection can be initiated manually from the j 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 acchanic. 1 l R-47 Panel Performed by: / Verified by: / R-50 Panel Performed by: / Verified by: /
. Procedure for blocking automatic actuation of a safety injection on high ; steamline Delta-P. This block will prevent a reactor trip from occuring '
during the natural circulation tests from high AP caused by degraded test conditions. (This block will also defeat all AP SI alarms).
- 1. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, 73, 76 are all clear prior to starting blocking procedure.
- 3. Hove test trip switch PS-515A in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: / CAUTION: In the next step, and all following steps in which a voltage is being applied to the indicated terminals, ensure the applied voltage is of the same polarity as the terminals. This check should be done for every step that a voltage source is applied. Failure to apply the correct polarity will ground the rack power supply. (This problem can be avoided if only the hot wire from the voltage source in the rack is applied to the first terminal indicated in each step [the lower numbered terminal). The O 19
SQNP SPECIAL TEST 6 Page 2 of 11 Rev. 1 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 lif ted wire. NOTE: Orange "Out of Service" stickers should be placed on all status / alarm windows as the 120V source is connected.
- 4. Lif c and tape the wire on the rack side of terminal L-9 in the rear cf 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-7 and verify 1-XX-55-6B/25 is clear.
Performed by: '
/
Verified by: /
- 5. Hove test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 6. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear.
Performed by: / Verified by: /
- 7. Hove test trip switch PS-516C in 1-R-12 to the trip position and verify
, the amber light above the switch comes on.
i Performed by: / Veriued 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. Performed by: / Verified by: / O
- 20 e
SQNP SPECIAL TEST 6 Page 3 of 11 Rev. I n () APPENDIX D
- 9. Move test trip switch PS-516D in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 10. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-1., Apply 120-VAC source to terminals L-7 and L-8 in the re'ar of 1-R-12 and verify 1-XX-55-6B/76.
Performed by: / Verified by: /
- 11. Hove 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 b'y: / j 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. I Performed by: / Verified by: / i
- 14. Lift and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.
Performed by: / Verified by: /
- 15. Hove test trip switch PS-52iD in 1-R-11 to the trip position and verify the amber light above the s-itch comes on.
Performed by: /
/
Verified by: 4 21 s '
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SQNP SPECIAL TEST 6 Page 4 of 11 Rev. 1 'm> . APPENDIX D i j 16. Lif t and tape the wire on the rack side of terminal L ' in the rear of 1-R-11. Apply 120-VAC source to terminals L-7 and L-d in the rear of 1-R-11 and verify that XX-55-6B/51 is clear. Performed by: / Verified by: / ,
- 17. Hove test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
i Performed by: / Verified by: /
- 18. Lif t and tape the wire on the rack side of terminal L-5 in the rear or 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is cicar.
Performed by: / Verified by: / Temporary Mgdification to High Steam Flow Coincident with Low S.G. Pressure { ) or Low-Low avg Safety Injection
- 19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be cleared.
~
Performed by: / Verified by: / I NOTE: If the alarms will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected.
- 20. Move test trip switch TS412D in R-2 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: / l
- 21. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
l
/
,, Performed by: /
(_) Verified by: / 22
SQNP SPECIAL TEST 6 Page 5 of 11 Rev. 1
/ APPENDIX D
- 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:
/
e
- 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 e XA-55-6A/30 will clear.
Performed by: / Verified by: /
- 24. Move test trip sw*tch TS432D in R-10 to the trip position and verify the amber light above the switch comes on.
t i 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 g(') XA-55-6A/30 will clear.
f . Performed by: / . i Verified by: /
- 26. Move test trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 27. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: / T NOTE: The avg inputs to the high steam flow S.I and steam dump interlock are now blocked. The next steps will trip the steam flow inputs'to the high steam flow Safety Injection signal so that an S.I. signal will be initiated on low steam generator g pressure alone (600 psig). (This would result in a reactor g) trip, an S. I. alarm, but no S. I. initiation.) 23
SQNP SPECIAL TEST 6 Page 6 of 11 Rev. 1 O
. APPENDIX D
- 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. .
Performed by: / Verified by: / .
- 29. Hove test trip switch FS522B in R-3 to the trip position and verify the t
amber light and annunciator XA-55-6B/ come on. Performed by: / Verified by: / NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal.
- 30. Apply Temporary Alteration Control Tags forms to all the above test l trip swi.tches to ensure that they remain in the trip position.
Damage to the bistable could occur if the switch is moved back to l the normal position. Record the temporary alteration numbers below: l 1 RACK TEST SWITCH TEMP ALT. NO. t f - R-7 PSS15A / i R-7 PS515B / . R-12 PSS16C / R-12 PSS16D / g R-8 PS525B / R-8 PS525A / R-11 PSS26D / R-11 RS526C ._ /
- R-2 TS412D /
R-6 TS422D / R-10 TS432D / R-13 TS442D / R-3 FS512B / R-3 FSS22B /-
'To return the steamline Delta-P S.I. to normal condition, the following steps should be followed.' s .
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SQNP SPECIAL TEST 6 Page 7 of 11 Rev. 1 o b APPENDIX D 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. Move test trip switch PS-526C in 1-R-11 to the normal position and j
verify the amber light above the switch and 1-XX-55-6B/50 are clear. Performed by: / l Verified by: / I Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire 33. on L-7. Ferformed by: / Verified by: / 3 CJ
- 34. Move test trip switch PS-526D in 1-R-11 to the normal position and .
verify the amber light above the switch and 1-XX-55-6B/51 are clear. - Performed-by: '/ Verified by: /. I
- 35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.
.j Performed by: /
I Verified by: /
\
- 36. Move test trip switch PS-525A in 1-R-8 to the normal position and verify the amber light and 1-XX-55-6B/26 are clear.
Performed by: / Verified by: /
- 37. Remove the 120-VAC source from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.
/
() Performed by: Verified by: /
- 25 o
SQNP SPECIAL TEST 6 Page 8 of 11 Rev. 1 l'
#s -
APPENDIX D
- 38. Move test trip switch PS-525B in 1-R-8 to the normal positien 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: / i 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 cleary 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: / t
- 42. Hove test trip switch PS-516C in 1-R-12 to the normal position and
- -rify the amber light above the switch and 1-XX-55-6B/73 are clear.
4 Performed by: / Verified by: / j 43. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi-nate wire on L-7. Performed by: / Verified by: /
' 44. 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: /
/
i Verified by: 26 I
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SQNP SPECIAL TEST 6
., Page 9 of 11 Rev. 1 O APPENDIX D
- 45. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-
' note wire on L-9.
Performed by: / Verified by: /
- 46. Hove 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: / i Verified by: / NOTE: At this point.the steamline Delta-P safety injection is in a normal operating mode. Toreturntgehighsteamflowcoincident.withlowstc'amgeneratorpressure l or low-low avg to normal, perform the following steps. 1
- 47. Nove test trip switch FS522B in R-3 to the normal position and verify the imher light goes out and XA-55-6B/9 will cicar.
O Pr: formed by: / . Verified by: / .
- 48. Hove 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.
I Performed by: /
- Verified by: /
J
- 49. Remove the 120-VAC source from terminals M-3 and M-4 in R-13. Retermi- ,
nate wire on H-3. Performed by: / Verified by: /
- 50. Hove test trip swit ch 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: / O 27 l k' I
SQNP SPECIAL TEST 6 Page 10 of 11 Rev. I m
. APPENDIX D i
- 51. Remove the 120-VAC source from terminals M-3 and M-4 in R-10. Retermi-
- nate wire on M-3.
i Performed by: / Verified by: /
- 52. 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.
Performed 'by: / I 4 Verified by: /
- 53. 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: /
- 54. 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: /
- 55. Remove the 120-VAC source from terminals M-3 and M-4 in R-2. Retermi-nate wire on M-3.
Performed by: /
- t. Verified by: /
i
- 56. Move 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: / q 28
SQNP SPECIAL TEST 6 Page 11 of 11 Rev. I '~ APPENDIX D
- 57. Remove the Temporary Alteration Tage on the following test trip switches:
RACK TEST SWITCH TErtP ALT. NO. R-7 PSS15A / R-7 PS515B / R-12 PS516C / R-12 PSS16D /
' R-8 PS525B /
I i R-8 PS525A /
. R-11 PSS26D /
R-11 RS526C / l I R-2 TS412D / R-6 TS422D / R-10 TS432D / R-13 TS442D / l I R-3 FSS12B /
/
R-3 FS522B
- 58. Remove the jumpers and the Temporary Alteration Tags from logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.
I
- R-47 Panel Performed by: /
f Verified by: / T 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.
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SQNP SPECIAL TEST 6 Page 1 of 1 Rev. 1 V) APPENDIX E Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. O E E so u "o %
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) e .3 e e e 6 eee TECIINICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment HI Pressure SI (3.3.2.1) X X X X X X X X X X Safety Limits (2.1.1) X X X X X X X X X OPAT (3.3.1) Inoperable because of low flow X X X X X X X X OTAT (3.3.1) Inoperable because of low flow X X X X X X X X Minimum temperature (3.1.1.4) X X X X Hoderator 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 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 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 l 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 Flow
/"; (3.4.1.2) X X X X X X X X v
30
SQNP SPECIAL TEST 6 Page 1 of I f Re'v . 1 TABLE 1 i Loop Flow and Core AT for Various Power Levels and Isolation Configurations (Computer Estimates) i 4 No. of Loops Operating
, (Nat. Cire i 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 1
9
.75% L= 3.7 L= 4.1 L= 4.7 L= 5.9
- AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 W W W W 1 1% L= 4.1 L= 4.5 L= 5.2 L= 6.5 .
I l AT = 16.3 AT = 19.8 AT = 26 AT = 41 '
, !i N
1.5% L= 4.7 L= 5.2 L= 5.9 L= 7.5 AT = 21.4 i AT = 26 AT = 34 AT = 54 3 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 r NOTE: L is % of 97,000 gpm flow through operable loop. p AT = Loop AT in *F. O 31
O . i SPECIAL TEST NO. 7 SIML' LATED LOSS OF ALL ONSITE AND OFFSITE AC POWER < 1
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SQNP SPECIAL TEST 7 Page 1 of 1 Rev. 1 ,m, 6 : (,) l SIKULATED LOSS OF ALL ONSITE AND OFFSITE AC POWER Table of Contents Pise Test Descrption 1 Special Operator Instruction 2 1.0 OBJECTIVES 3 2.0 PREREQUISITES 4 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPMENT 10 5.0 TEST INSTRUCTIONS 11 { } 6.0 ACCEPTANCE CRITERIA 23 DATA SilEETS 24 APPENDIX A - References 32 APPENDIX B - Deficiencies 33 i APPENDIX C - Power Measurement Technique 34 APPENDIX D - Computer Point 44 APPENDIX E - Safeguard Blocking Procedure 48 APPENDIX F - Technical Specifications Exceptions 59 1 TABLE 1 - Loop Flou and Core AT for Various Power Levels and Isolation Configurations 60 t x._-
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SQNP SPECIAL TEST 7 Page 1 of 1 Rev. I Q SIMULATED LOSS OF ALL ONSITE AND OFFSITE AC POWER Test Description t i This test is intended to provide a significant demonstration of' reactor j operation in the natural circulation mode under the degraded condition of loss of all onsite and offsite AC power. For the purpose of plant and i equipment safety, this total blackout condition will be simulated by the t selective deenergizing of components and equipment.
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SQNP SPECIAL TEST 7 Page 1 of 1 Rev. 1 SPECIAL OPERATOR INSTRUCTION
*An operator initiated safety injection should be performed only for one or more of the following conditions:
Reactor Coolant System Subcoollug 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% Witle Range 5 0% Narrow Range i Unexplained Pressurizer Pressure Drop 2 200 PSI Containment Pressure Hi - (1.54 psig) Annunciator XA-55-6B Window 6' initiates i An operator initiated reactor trip should be performed for any 'of the following conditions: O 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 (Ilighest) > 610*F
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
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SQNP
- SPECIAL TEST 7 Page 1 of 21 Rev. 1 O 1.0 OBJECTIVES Theobjectivesofthistestare:
1.1 To demonstrate that following a loss of all onsite and offsite power, including the emergency diesel generators, the decay heat can be removed by natural circulation using the auxiliary feed-water system in the manual mode. s a. 1.2 It will be verified that hot standby conditions can0 e'b maintained by manual control of the auxiliary feedwater system /+ 1.3 It will also be verified that critical plant operations can be per-formed using emergency lighting, that the 125-volt vital battery has the ability to supply the 125-volt vital AC and that certain equipment areas do not exceed maximum design temperature. 1.4 To provide operator training, all operating shifts will perform this test. NOTE: Data acquisition does not need to be repeated for multiple test performances. l 3
SQNP -, SPECIAL TkST 7 Page 2 of 21 Rev. 1
,~ n ') 2.0 PREREQUISITES 2.1 Reactor is critical and manually controlled at approximately 1% . power with control bank D at 160 steps or as specified by test engineer. (Power level determined as indicated in Appendix C).
8 i / 2.2 All four Reactor Coolant Pumps in operation.
/
2.3 RCS pressure at approximately 2235 psig and temperature at approxi-mately 548 F, and pressurizer level at approximately 26-28%. i
/
2.4 Steam pressure approximately 1005 psig and being maintained by. steam dump to the condenser.
/
2.5 Steam generator level being maintained at approximatelf 33% on the narrow range indicators.
/ i i I 2.6 One main feedwater pump in service and the other tripped. ; .
/
2.7 Auxiliary feedwater syst'em lined up in standby in accordance - with SOI 3.2 ; s I / .k i 2.8 Steam generator chemistry in a condition that the absolute midimum' steam generator blowdown can be maintained during the duration of this test. (Zero blowdown is possible). .
/
i 2.9 Excess letdown is available for service if required during the test. ,
/ .
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SQNP SPECIAL TEST 7 Page 3 of 21 Rev. 1 ( 2.0 PREREQUISITES (Continued) 2.10 125-V Vital Battery Board I energized from 125-V Vital Battery I (BKR 107 closed), a l / 2.11 125-V Vital Battery Board II energized from 125-V Vital Battery II (DKR 107 closed).
/
2.12 125-V Vital Battery Board III energized from 125-V Vital Battery 8 III (BKR 107 closed).
/
2.13 125-V Vital Battery Board IV energized from 125-V Vital Battery IV (BKR 107 closed).
/
2.14 Verify that battery-powered lights are located in areas where operation of equipment is required af ter normal lighting is de-energized. (Operations to supply lights and position them where desired). () /
\/
NOTE: These temporary lights should only be located in areas
~
where operation of equipment would not normally take place in a black'out. Areas which must be operated during a blackout should be supplied with permanent battery powered lights. 2.15 Charging is being maintained with a centrifugal pump and in auto-matic control.
/
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- SQNP SPECIAL TEST 7 Page 4 of 21 Rev. 1 "1
v 2.0 PREREQUISITES (Continued)
, 9 /
7 2.16 Connect Recorders to the following test points: 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: i
' 1-R-23, LP501 Steam Gen #1 Level Channel #1 Channel #2 1-B-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 Channel #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 Recorder #4 Connect to: Monitoring: Channel #1 F-3-163, TP 13, 1-L-11B Aux Feed flow to S.G. #1 Channel #2 F-3-155, TP 13, 1-L-llA Aux Feed flow to S.G. #2
! Channel #3 F-3-147, TP 12, 1-L-11B Aux Feed flow to S.G. #3 Channe) #4 F-3-170, TP 12, 1-L-llA Aux Feed flow to S.G. #4 2.17 Set the trend recorders and computer trend printer in the Main Control Room to monitor the parameters indicated in Appendix D.
/
g 2.18 Install p-computer recorder to monitor the following:
- a. Flux
- b. Average wide-rangeTeold
- c. Average wide-range hot
- d. Average steam generator pressure
- c. Reactivity
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SQNP SPECIAL PEST 1 Page 5 of 21 Rev. 1 2.0 PREREQUISITES (Continued) 2.19 Evacuate construction personnel from all unit 1 and unit 2 work areas in the auxiliary and containment buildings.
; /
NOTE: This is a safety measure since these work areas will be without lighting for approximately 2 hours. 2.20 Record on the recorder charts the following information:
- a. Unit number
, b. Date .
I c. Procedure number
- e. Chart speed
- f. Time marker interval
- g. Recorder ID number
- h. Name of individual recording data
/
2.21 Verify the input logic of safety injection on Hi Steam Line AP has been blocked in accordance with Appendix E.
/
() 78 2.22 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. '
/
2.23 Verify the automatic actuation of safety injection has been blocked
~
in accordance with Appendix E.
/
2.24 Verify the following UHI isolation valves are gagged. , FCV 21 / FCV 22 / FCV 23 / FCV 24 / 2.25 Verify the auxiliary boiler is supplying steam seals to the turbine.
/
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SQNP SPECIAL TEST 7 Page 6 of 21 Rev. 1 0 2,. 0 PREREQUISITES (Continued) 2.26 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 / e I 3.0 PPICAUTIONS 3.1 Maintain reactor coolant pump seal and thermal barrier different-l ial pressure requirements as given in SOI 68.2. 3.2 Do not exceed 5%' nuclear power at any time while the test is in 4
, progress.
i 3.3 Abort the test if any of the following temperature limits are exceeded: l 3.3.1 Core exit temperature of 610 F T 3.3.2 AT as ind.icated by h- c of 65 F l 3.3.3 avg temperature of 578 F 3.4 When equilibrium is established after the initial transient, avoid i any sudden changes in Auxiliary Icedwater flow or in the Steam Generator water level. {
! 3.5 Ensure seal flow to each-Reactor Coolant pump is maintained at or
! slightly above 6 gpm during the test.
3.6 After the Reactor Coolant pumps are tripped, tge normal T and AT indication will become unreliable. AT and avgshould*EIcalcu-lated by taking the difference and the average of the hot and cold leg temperature indications respectively. 3.7 If the primary system pressure drops to a point where it is obvious that saturation pressure for the existing wide range hot leg or incore T/C temperatures will soon be reached, the pressurizer heaters will have to be energized or charging flow reestablished to increase system pressure. 3.8 NIS channels can be used to determine changes in core power level providing the RCS cold leg temperatures are maintained at approxi-mately the same value that existed before tripping the reactor coolant pumps, fi o l
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SQNP SPECIAL TEST 7 Page 7 of 21 Rev. 1
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3.0 PRECAUTIONS (Continued) S 3.9 The turbine auxiliary feedwater pump room has four temperature detectors designed to isolate the steam supply to the turbine if the temperature reaches 125 F. If ambient temperature reaches 115 F, start the AC-powered exhaust fan to help maintain tempera-ture.
' 3.10 Should a roactor trip occur during the conduct of *: tis test, at least one . _etor coolant pump (#2) should be started prior to closir.g the reactor trip breaker.
3.11 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. 1 , e i e O . t
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Sq,:P SPECIAL TEST 7 Page 8 of 21 Rev. 1
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(\ 4.0 Special Test Equipment Identification Calibration . Instrument Specification Number Verification
. Digital Voltmeters Fluke Model (DVM) (3) 3120A or equivalent
, Strip Chart Recorder, Brush 260 or equivalent (6-channel) (2) t Room Thermometers (7)
Reactivity Computer Westinghouse l Explosimeter Mine Safety Model #3 442760 l 0-100% explosive e Recorder (1) HP 7100B or equivalent , i
,()
1 If test instruments are changed during this test, the instrument information must be recorded here and an entry made in the chronological log book ex-plaining this change. i
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a SQNP SPECIAL TEST 7 Page 9 of 21 Rev. 1 V,m 5.0 TEST INSTRUCTIONS NOTE: For the purpose of operator training, the test instruction steps in Section 5.0 may be repeated. The steps should be
, performed sequentially and those steps indicated by a l double asterisk (**) should not be repeated.
**5.1 Close the following dampers on El 669 in the Auxiliary Building.
', 1-31C-1105 _
/
, 1-31C-1109 /
I 1-31C-1150 / l-31C-1148 / NOTE: These dampers and the following coolers will be shutdown to allow monitoring the air temperatures in the area of the turbine driven auxiliary feedwater pump room under blackout conditions.
**S.2 Adjust the thermostats on the General Vent Coolers 1C and 2C on El 669 to their highest settings. (Note their present setpoint).
0-TIC-313-610 As Found Dial Setting fs k 2-TIC-313-611 , As Found Dial Setting
**5.2.1 Shutdown the main control room air conditioning and place a i room thermometer 'on the operators' desk to monitor control room air temperature.
7 5.3 Position AUO's in the following positions in the plant to be avail-able to operate vital equipment, a) Auxiliary Feedwater Level Control Valves LCV-3-172,173,174, and 175. b) Turbine driven Auxiliary Feedwater pump. c) Power relief control valves PCV-1-5, 1-23, 1-12, and 1-30.
/
5.4 Clear the control and auxiliary building of all non-esser tial personnel and announce over the Public Address. System thit a blackout test will be beginning shortly.
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SQNP SPECIAL TEST 7 Page 10 of 21 Rev. 1
) 5.0 TEST INSTRUCTIONS (Continued) 5.5 Manuall adjust PIC-68-340B and PIC-68-340D to zero % output
. (closes pressurizer spray valves) and leave the controllers in
- manual control.
i
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5.6 Ensure the pressurizer backup heaters lA, IB, and 1C will remain off by moving handswitches 1-HS-68-341A and 341D to the "stop" position and moving 1-HS-68-341H to "stop-pull to lock". I / 5.7 Ensure Auxiliary Feedwater motor driven pumps lA-A and 1B-B will not start on the simulated blackout by moving switches 1-HS-3-118A and 1-HS-3-128A on 1-M-4 to the "stop" position.
/
5.8 Move switch 1-HS-30-217 to "stop" to shut off the AC auxiliary feedwater turbine pump room exhaust fan. Verify switch 1-HS-30-214 is in " Auto". (Both located in Turbine driven Aux. Feed pump room).
/
5.9 Just prior to initiating RCP trips, reduce charging flow to the minimum required to maintain seal injection flow. (FCV-62-89 should be fully closed).
/
5.10 Isolate RCS letdown by closing the following valves from their respective handswitches on 1-M-6. I l-FCV-62-69 /
' l-FCV-62-70 /
1-FCV-62-72 / l-FCV-62-73 / l-FCV-62-74 /
**5.11 Record the data indicated on Data Sheet 5.1.
/
, x 12
~
SQNP SPECIAL TEST 7
. Page 11 of 21 l Rev. 1 s
s_,f 5.0 TEST INSTRUCTIONS (Continued) I
; **S.11.1 Start the Computer Trend printer printing at 1-minute inter-vals.
/
**5.12 Record the time, date and initial the charts on the data recorders in the Auxiliary Instrument Room.
/
**5.13 Open 6.9KV ACB located on 6.9KV Common Board A that feeds the Auxiliary Building Lighting Bus A.
/
**5.14 Open 6.9KV ACB located on 6.9 K Common Board B that feeds the Auxiliary Building Lighting Bus B.
/
5.15 Start all four reactor coolant pump oil lif t pumps from 1-HS-68-84A, 85A, 86A, and 87A on 1-H-5.
/
NOTE: The following step should be conducted immediately before initi-I k ating the trips. 5.16 Isolate the control air supply to the air accumulator for the fallowing turbine drive.n Auxiliary Feedwater pump level control valves. 1-LCV-3-172 / 1-LCV-3-173 / 1-LCV-3-174 / 1-LCV-3-175 / 5.17 As quickly as possible shutdown the following equipment. As many people as possible should be utilized to complete this step so that a close approximation to a blackout can be simu-lated. NOTE: Zero Time = Check a) Trip pressurizer heater group 1D from 1-HS-68-341F on 1-M-4 7_.
~.-F 9
SQNP SPECIAL TEST 7 Page 12 of 21 Rev. I f- s 5.0 TEST INSTRUCTIONS (Continued) i
, b) Trip all four reactor coolant pumps from l l-IIS-68-8A, 31A, 50A, 73A i
c) Close main steam isolation valves from 1-HS-1-4, 11, 22, 29 on 1-M-4 i d) Trip the main feed pump presently in operation from either 1-HS-46-9A (Pump A) or 1-HS-46-36A (Pump B) NOTE: The next steps will remove the 125V Vital Battery chargers from service which places the entire 125VDC Vital load on the 125V Vital batteries.
**c) Open the breaker on 125V Vital Battery Board I from the No. I 125V Vital Battery charger. (BKR 225)
**f) Open the breaker on 125V Vital Battery Board II from the No. II 125V Vital Battery charger. (BKR 225)
**g) Open the breaker on 125V Vital Battery Board III from the No. III 125V Vital
{ ) Battery charger. (BKR 225)
**h) Open the breaker on 125V Vital Battery Board IV from the No. IV 125V Vital Battery charger. (BKR 225)
**i) Open 480-V standby Lighting Cabinet NO.
4 breaker, located on 480-V Shutdown i Board 1A2-A, Breaker 9C.
**j) Open 480-V Standby Lighting Cabinet No.
I breaker located on 480-V Shutdown Board 2A2-A, Breaker 9C.
**k) Open 480-V Standby Lighting Cabinet No.
2 breaker located on 480-V Shutdown Board IB1-B, Breaker 8D.
**': ) Open 480-V Standby Lighting Cabinet No.
3 breaker located on 480-V Shutdown Board 2B1-B, Breaker 8D. NOTE: At this point the normal lighting in the Control Building and the Auxiliary Building has been deenergized and the emergency lighting is energized from the 125-VDC Vital Battery. (,, i 14 s I
- SQNP SPECIAL TEST 7 I Page 13 of 21 Rev. 1 (D
'{ 5.0 TEST INSTRUCTIONS (Continued)
**m) Open 480-vac input breaker on Vital Inverter 1-I.
**n) Open 480-vac input breaker on Vital i Inverter 1-II.
I j *%) Open 480-vac input breaker on Vital
. Inverter 1-III.
**p) Open 480-vac input breaker on Vital Inverter 1-IV.
**q) Open 480-vac input breaker on Vital
! Inverter 2-I.
**r) Open 480-vac input breaker on Vital Inverter 2-II.
**s) Open 480-v input breaker on Vital Inverter 2-III.
l
**t) Open 480-v input breaker on Vital Inverter 2-IV.
**u) Turn vital battery room I exhaust fan off.
**v) Turn vital battery room II exhaust fan off.
**w) Turn vital battery room II exhu::st fan off.
**x) Turn vital battery room IV exhaust fan off.
NOTE: At this point in time the 125-v Vital Battery is' supply-ing all the 120-v Vital AC load as well as the Emergency Lighting.
**y) Begin monitoring and recording the parameters indicated on Data Sheet 5.2.
sheets 2 through 4, at the intervals indicated. NOTE: Monitor reactor power closely and make any adjuptments necessary to maintain approximately 1% power. c for each leg should be maintained at approximately the pretrip temperature. l 15 . l
.- SQNP l SPECIAL TEST 7 l Page 14 of 21
( Rev. 1
,s.
5.0 TEST INSTRUCTIONS (Continued) 5.18 Verify the steam-driven Auxiliary Feedwater pump has started and flow established to each steam generator.
/
NOTE: The Auxiliary Feedwater level control valves LCV-3-172, 173, 174, 175 will open shortly after the Aux Feed pump starts but will fail close in 4 or 5 minutes as the accumulators run out of air. Preparations must be made to operate these valves by hand when this happens. 5.19 Operators should be dispatched to take manual control of the
, Auxiliary Feedwater level control valvaa. and main steam power i operated relief valves.
/
5.20 Move the following handswitches to the "Close" position to simu-late loss of control to the main steam power operated relief valves. 1-HS-1-6 /
! 1-HS-1-13 /
1-HS-1-24 / h() , 1-HS-1-31 / 5.21 After the simulated blackout has taken place the operational guidelines in Appendix A of E0I-5 should be followed to verify natural circulation has been established.
/
5.22 Record the time that full manual control of the Auxiliary Feed-water level control valves takes place. Time 1-LCV-3-172 1-LCV-3-173 i 1-LCV-3-174 1-LCV-3-175 1
/
l i b 16
SQNP SPECIAL TEST 7 Page 15 of 21 j Rev. 1 0's 5.0 TEST INSTRUCTIONS (Continued) t
! 5.23 Bring the steam generator levels back to normal operating level i
' (approximately 33%) and manually adjust atmospheric dump and auxiliary feedwater flow to maintain the pretrip cold leg tempera-l ture. (Establish a steady feedwater flow. Do not stop and start j flow to control the level.)
/
**5.24 When equilibrium conditions have been established for each steam generator, make notes on Data Sheet 5.2 n' 2e time and continue recording data.
l
/
5.25 Maintain steam generator level at approximately 33% and reactor power at 1% for a two-hour period from the time of the simulated blackout.
/
NOTE: The pressurizer water level is not expected to rise above 70%, however, if it should, put excess letdown into ser-j vice to reduce the RCS water volume. Maintain letdown until level reaches 50%. (Note letdown established on () Data Sheet 5.2). Y . 5.26 At the end of the 2-hour period, manually adjust the Main Steam PORV pressure controllers PIC-1-6A, -13A, -24A, and -31A to ' approximately the outpu,t corresponding to the percentage each valve is open as indicated by the valve position indicator on the valve. I =
. /
5.27 Adjust the setpoint dial on the pressure controllers to 1000 psig (83.3% on dial) and individually return the power-operated relief valves to ' auto' control by putting first the valve handswitch in
' auto' and then the corresponding controller.
CAUTION: Let each steam generator come to equilibrium before putting the next power relief valve in Auto. l 1-HS-1-6 and PIC-1-6A / l 1-HS-1-13 and PIC-1-13A / 1-HS-1-24 and PIC-1-24A / 1-HS-1-31 and PIC-1-31A / v) 17
,. _. . . _ . . 2. : -
SQNP SPECIAL TEST 7 Page 16 of 21 Rev. 1 O
-# 5.0 TEST INSTRUCTIONS (Continued) 5.28 Individually return the control air supply to the Auxiliary Feed-water level control valves and adjust the flow controllers to ob-l tain approximately the equilibrium flow indicated before the air was returned.
1-LCV-3-172 / 1-LCV-3-173 / 1-LCV-3-174 / 1-LCV-3-175 / l
, 5.29 Return the Auxiliary Feedwater Ievel controllers to ' auto' and verify automatic control is resumed.
/
5.30 Return pressurizer spray controllers PIC-68-340B and PIC-68-340D to ' Auto *'. (Spray will not be available until the reactor coolant pumps are restarted). l 5.31 If the RCS pressure is below 2210 psig, allow one of the hand-
! switches for the pressurizer backup heaters to return to P-Auto.
e The heater should energize and increase RCS pressure. Control fs 4,j RCS pressure by energizing or deenergizing the backup heaters.
/
5.32 Manually adjust the output of PIC-68-340A to 40% output and ener-gize the pressurizer control heater group 1D. Return PIC-68-340A to ' Auto.'
/
5.33 Insert Control bank D until the reactor is in the hot zero power test range.
/
NOTE: The following steps return normal power to the vital instruments. The steps must be followed in sequence.
**5.34 Close 480vac input breaker on Vital Inverter 1-I.
/
**5.35 Close 480vac input breaker on Vital Inverter 1-II.
/
l 18 l ,
SQKP SPECIAL TEST 17 Page 17 of 21 Rev. 1
.Vl} 5.0 TEST INSTRUCTIONS (Continued)
**5.36 Close 480vac input breaker on Vital Inverter 1-III.
/
**5.37 Close 480vac input breaker on Vital Inverter 1-IV.
/
**5.38 Close 480vac input breaker on Vital Inverter 2-I.
/
s
**5.39 Close 480-vac input breaker on Vital Inverter 2-II.
/
A*5.40 Close 48-vac input breaker on Vital Inverter 2-III.
/
**5.41 Close 480-vac input breaker on Vital Inverter 2-IV.
/
**5.42 Close 6.9-kV ACB located on 6.9-kV Common Board A that feeds the L Auxiliary Building Lighting Bus A.
f3 (.) T / 1
! **5.43 Close 6.9-kV ACB located on 6.9-kV Common Board B that feeds the Auxiliary Building Lighting Bus B.
/
**5.44 Close 480-V Standby Lighting Cabinet No. 4 breaker, located on 480-V Shutdown Board 1A2-A, breaker 9C.
/
**5.45 Close 480-V Standby Lighting Crbinet No. I breaker, Ibeated on 480-V Shutdown Board 2A2-A, Breaker 9C. ,
/
**5.46 Close 480-V Standby Lighting Cabinet No. 2 breaker, located on 480-V Shutdown Board IB1-B, Breaker 8D.
/
**5.47 Close 480-V Standby Lighting Cabinet No. 3 bre,aker, located on 480-V Shutdown Board 2B1-B, Breaker 8D.
)s N.,
l i 19 g 4
SQNP SPECIAL TEST 7 Page 18 of 21 Rev. 1 ( 5.0 TEST It!STRUCTIONS (Continued) l
**5.48 Close the breaker on 125V Vital Battery Board I from the No. I 125V Vital Battery Charger. (BKR 225)
/
**5.49 Close the breaker on 125V Vital Battery Board II from the No. II 125V Vital Battery Charger. (BKR 225) l
/
**5.50 Close the breaker on 125V Vital Battery Board III from the No.
III 125V Vital Battery Charger. (BKR 225)
/
1 { **5.51 Close the breaker on 125V Vital Battery Board IV from the No. IV
. 125V Vital Battery Charger. (BKR 225) l
- /
I i NOTE: At this time the 125 vde Vital Battery, 120 vac Vital Instrument Power, and the Plant Emergency Lighting System are normal. g 5.52 Individually move handswitches 1-HS-3-ll8A and 1-HS-3-128A to () ' auto' position. When these switches are returned to Auto, the
; motor-driven Auxiliary Feedpumps will start so a close watch I should be maintained to verify proper automatic level control.
/
**5.53 Turn off the data recorders and note the time on the charts.
/
CAUTION: Prior to starting RCP 1 and/or 2 ensure pressurizer spray valves are closed. ,
, , 5.54 Restart reactor coolant pumps in accordance with SOI 68.2 starting with RCP 2, 1, 3 and then 4.
/
5.55 Return the pressurizer level to approximately 26% and return control to auto.
/
5.56 Ce-establish normal letdown and charging in accordance with SOI 62.lB.
/%
t V / l 20
SQNP SPECIAL TEST 7 Page 19 of 21 Rev. 1 (T
' J-5.0 TEST INSTRUCTIONS (Continued)
. 5.57 Open MSIV warmup bypass valves. Control them to maintain stable heatup and pressure conditions in the main steam pipfng. Do not exceed main steam piping heatup rate of 200 F/hr.
/
NOTE: Temperature can be monitored on computer log points T2300, T2301, T2302, and T2303. 4 5.58 When steam pressure across the MSIV's is less than 25 psi, with l IIS-1-4A, 11A, 22A, and 29A in close positions, reset main steam isolation valves by momentarily placing control switch MS-1-4A in the reset position.
/
5.59 Open the following MSIV's: $ FCV-1-4 / FCV-1-11 / FCV-1-22 / FCV-1-29 / O T
**S.6o net < the re11ewina dampers en 81 669 in the a xiliarv to their original positions:
s 11ai 8 . 1-31C-1105 / i 1-31C-1109 / 1-31C-1150 /
~
i 1-31C-1148 /
**5.61 Return the thermostats on General Vent Coolers 1C and 2C to their original setpoints.
**5.62 Return main control room air conditioning to normal.
/
**5.63 Turn vital battery room I exhaust fan on.
/
**5.64 Turn vital battery room II exhaust fan on.
/
i k.) 21
. . ._ a . .. .
SQNP SPECIAL TEST 7 Page 20 of 21 j Rev. 1 ,q \2~- 5.0 TEST INSTRUCTIONS (Continued) t f, **5.65 Turn vital battery room III exhaust fan on. l
**5.66 Turn vital battery room IV exhaust fan on.
/
5.67 Remove the block of the input logic of safety injection on Hi steam line AP in accordance 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 signature line and initial.
/
5.68 Remove modification to Hi steam flow coincident with Lo S/G pressure or Lo Tav safety injection input in accordance with Appendix E unless the next test to be performed requires this modification to_be made. If this is the case, disregard this step, place N/A in the signature line and initial.
/
5.69 Remove block of automatic actuation of safety injection in accord-ance with Appendix E unless the next test to be performed requires this lockout. If this is the case, disregard this step, place N/A in the signature line and initial.
'/
5.70 Remove the gag from the following UlII isolation valves unless the I valves are required to be gagged in the next test. If this is the case, disregard this step, place N/A in the signature line, and initial. FCV-87-21 / FCV-87-22 / { FCV-87-23 / FCV-87-24 / 5.71 Reset the intermediate and power range high level reactor trip set-points as indicated by the test director in accordance with Appendix C and D of SU-8,5.2 unless the next test to be performed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial. Power Range /
, Intermediate Range /
m, 22
SQNP SPECIAL TEST 7 Page 21 of 21 Rev. 1 l x- 6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperature did not exceed 610 F.
/
. 6.2 Delta-T for any loop did not exceed 65 F.
/
l 6.3 Tavg for any loop did not exceed 578 F. I
/
6.4 Natural circulation can be established and maintained with the degraded condition of a simulated loss of offsite and onsite power.
/
6.5 Emergency lighting in the plant is sufficient to operate critical l equipment in the loss of all normal lighting. l 6.6 Hot standby conditions can be maintained for a 2-hour period with gg critical equipment operating off of vital battery power.
/
6.7 Manual operation of auxiliary feedwater valves and main steam power reliefs can be coo'rdinated by the unit operator to main-tain stable plant conditions. t l 9 l l L A
]
23
SQNP SPECIAL TEST 7 Page 1 of 4 Rev. 1
'~'
. DATA SHEET 5.1 Initial Conditions Date Time Unit Pressurizer Pressure PR-68-340 psig l Pressurizer Level LR-68-339 Red Pen %
#1 Hot leg temp o TR-68-1 F
#1 Cold leg temp o TR-68-18 F
,/2 Hot leg temp o TR-68-1 F
#2 Cold leg temp o TR-68-18 F l
#3 llot leg t. o TR-68-43 F
#3 Cold leg temp o TR-68-60 F
#4 Hot ' leg temp o TR-68-43 F
, #4 Cold leg temp o TR-68-60 F S.G. #1 Level (narrow range)
LI-3-42 % S.G. #2 Level (narrow range)
' LI-3-55 %
S.G. #3 Level (narrow range) LI-3-97 % S.G. #4 Level (narrow range) LI-3-110 % Data By /
~
l 24 M
SQNP SPECIAL TEST 7 )
. Page 2 of 4 l ! Rev. 1 p/
v DATA SHEET 5.1 Date Time Unit S.G. #1 Level (wide range)
; LR-3-43 Pen 1 %
i S.G. #2 Level (wide range)
! LR-3-43 Pen 2 %
S.G. #3 Level (wide range) LR-3-98 Pen 1 % S.G. #4 Level (wide range) LR-3-98 Pen 2 % S.G. #1 Pressure PI-1-2A P818 S.G. #2 Pressure PI-1-9A P818 S.G. #3 Pressure PI-1-20A P8i8 S.G. #4 Pressure
- PI-1-27A Psig -
Attach computer printout of Incore Thermocouple Temperature Map. Refer to Appendix D for the procedure for p.rinting out this map. S.G. #1 Feedwater flow FI-3-35A lbs/hr S.G. #2 Feedwater flow FI-3-48A lbs/hr S.G. #3 Feedwater flow . FI-3-90A lbs/hr S.G. #4 Feedwater flow FI-3-103A lbs/hr S.G. #1 Steam flow t FI-1-3A lbs/hr l S.G. #2 Steam flow ~ FI-1-10A lbs/hr Data By: /
,rg 25
SQNP SPECIAL TEST 7
' Page 3 of 4
- Rev. 1
. DATA SHEET 5.1 l Date Time Unit i
l S.G. #3 Steam flow lbs/hr
- FI-1-21A S.G. //4 Steam flow FI-1-28A lbs/hr Loop #1 T-average o TI-68-2E F Loop #2 T-average o l TI-68-25E F Loop #3 T-average o .
TI-68-44E F Loop #4 T-average o l TI-68-67E F Loop #1 AT TI-68-2D % g g Loop #2 AT TI-68-25D % Loop #3 AT TI-68-44D % Loop #4 AT TI-68-67D % (0-52 F = 0-100%) NIS Channel N-41 % NIS Channel N-42 % NIS Channel N-43 % NIS Channel N-44 %
. Temperature reading in Turbine-driven Auxiliary o Feedwater Pump Room F l
Data By / l j'~' i ! w 26
SQNP SPECIAL TEST 7 Page 4 of 4 Rev. 1 4 DATA SHEET 5.1 4
} Date Time Unit 4
i s
'! Temperature reading outside turbine-driven Auxil-l lary Feedwater Pump Room (Elevation 669) F Hain control room temperature F Remarks:
1 i ]' I -l Data By: / Reviewed By: / l .
+
f .- . 0 4 } f e j . . . . i I
- O 27 i
g
- 4 g4 . . , +4 . . = am *=
..,...--m.........,. .._,-,.m-. ..-..m,,.-.~.,.,,...y-.,-----_-mcy..-w...-..~r -
SQNP SPECIAL TEST 7 Page 1 of 4 Rev. 1 I O \- /
, DATA SHEET 5.2 Attach the computer printout from the following parameters. Refer to Appendix D for the computer log points and setup procedure.
4 Pressurizer pressure
, Pressurizer Level l RCS Loop 1 Ho,t Leg Temp RCS Loop 2 Hot;, Leg Temp i RCS Loop 3 Hot Leg Temp ; RCS Loop 4 Hot Leg Temp
- RCS Loop 1 Cold Leg Temp RCS Loop 2 Cold Leg Temp RCS Loop 3 Cold Leg Temp RCS Loop 4 Cold Leg Temp Steam Generator 1 Pressure Steam Generator 1 Narrow Range Level Steam Generator 2 Pressure Steam Generator 2 Narrow Range Level Steam Generator 3 Pressure Steam Generator 3 Narrow Range Level Steam Generator 4 Pressure Steam Generator 4 Narrow Range Level Power Range Channel 1 Power Range Channel 2
('] Power Range Channel 3 Power Range Channel 4 Incore Thermocouples #1 through.#5 (upper head) NOTE: The preceding parameters sh'ould be printed every 1 minute until equilib-rium conditions are reached. At this time the interval can be changed as required, The data points on page 3 of this data sheet will have to be recorded by hand at the indicated intervals using a DVM. Print out core T/C maps as required. l O 28
= ,i .
SQNP SPECIAL TEST 7 Page 2 of 4 Rev. 1
.,-~
DATA SHEET 5.2 Record the following temperatures at the indicated intervals. 3 Time Auxiliary
- Ele.669 Outside Main Control After Trip F.P. Room F.P. Room Room l 15 mins.
4-I 30 mins. 45 mins. i 60 mins. 75 mins. 90 mins. 105 mins. l l 120 mins. (' ) *If ambient temperature reaches 115 F, start the AC powered exhaust fan . Data By: / 29 ( l t
-- . , , _ , . . , - . ,.r - . _ , ,m_..,, . _ _ . - - - - , . . . , . _ - . _ . - - - - . . . . .
SQNP SPECIAL TEST 7 Page 3 of 4 Rev. 1 DATA SHEET 5.2 125-V Vital Battery and 120 vac Vital Instrument Power (Battery Output Voltage) 125v Vital 125v Vital 125v Vital 125v Vital 120vac Vital 120vac Vital 120vac Vital 120vac Vital Batt BD I Batt BD II Batt BD III Batt BD IV Inst Pwr Bd Inst Pwr Ed Inst Pwr Bd Inst Pwr Bd 1-I 1-II l-III l-IV Initial Conditions Immediately Following B.O(T) T + 10 min. T + 20 min. T + 30 min. T + 40 min.
; T + 50 min.
T + 60 min. T + 70 min. T + 80 min. T + 90 min. T + 100 min. T + 110 min.
~
T + 120 min. r e Data by: /
w) (
.(..-.
SQNP SPECIAL TEST 7 Page 4 of 4-Rev. 1 DATA SHEET 5.2 125-V Vital Battery Room Temperatures & H 2
'L*"#1 , 125-V Vital Battery 125-V Vital Battery 125-V Vital Battery 125-V Vital Batter Room I Room II Room III Room IV Initial Temp H * % of Teisp H * % of Temp H,,* % of Temp 'H,,* % of Conditions $cale $cale Scale $cale T + 10 min '
T + 20 min T + 30 min T + 40 min
. M T + 50 min . T + 60 min T + 70 min T + 80 min T + 90 min T + 100 min . T + 110 min , T + 120 min CAUTION: If H28PProaches 50% of sc' ale 8 (2% 2H ) turn exhaust fans on.
Remarks: Data by / Reviewed by /
i SQNP SPECIAL TEST 7
- Page 1 of 1 )
tev. 1 '
^
5 APPENDIX A References
- 1. FSAR i
- 2. Technical Specifications
- 3. Plant Operating Instructions S0I 3.2 S0I 68.2 E0I 5
- 5 l O 32 i
SQNP SPECIAL TEST 7 Page 1 of 1 Rev. 1 APPENDIX B l 1 f Test Deficiencies # t.
?
1 4 - Test Deficiency i 6 8 i . -t t Recomended Resolution I i j Final Resolution .
, ~
. - c 8
J Originator / Signature Date l ! PORC Review of Final Resolution , Date l Approval of Final Resolution / 4 Plant Superintendent Date j - .g b
- O 33 t
4 y ... i
+e-- -
-n-w -,e ,
,,v.rm----,--.-c e---,.,-a, > , - - . - e--,,,-er- -e ,w o r. ,- ,--,-.--as.n.nwre-mow,-msw<~.ev,,-v--
SQNP SPECIAL TEST 7 Page 1 of 10 Rev. 1 0 4 e
; APPENDIX C Procedure for Determining Core Power I.evel l I G
l 4 O 34 1
~
I I
SQNP SPECIAL TEST 7 Pa8e 2 of 10 Rev. 1 O b' ' APPENDIX C Outline I. Core Power Determination i
, A. Primary Side Calorimetric (Forced Circulation Only) i
- 1. Reference ( ~ 550 F) Calorimetric (Before NC test) .
I a) Output used to adjust M/D Power Monitor Program's power con-version constant. 11 . M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output. i 2. Power Monitoring 3 a) The M/D Power Monitor Program will calculate the integral t_ 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. t i O 35 I a e
SQNP SPECIAL TEST 7 Page 3 of 10 Rev. 1 V("T
; APPENDIX C
, CORE POWER DETERMINATION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation) 1' i
- C.1 Use two DVMs and measure the voltage at the test points speci-3 fled for each loop as rapid as possible.
C.2 Calculate the AT; multiply that AT by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (Table C-1). (Special Test No. 9 uses wide range AT so a correction factor is required to compensate for pump heating, refer to Appendix D of ST-9A). C.3 Sum the loop heat rates and convert to a percent reactor power. The output is used in Part B. I s I l 36 e, *"
SQNP SPECIAL TEST 7
; Page 4 of 10 l Rev. 1 w( APPENDIX C i
t Core Power Determination 1 PART B: M/D Power Monitor Program l [ 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 i B 10 L-11 C 10 E-5 D 10 E-11 E 6 J-8 i F 8 P-9 O b 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 5 path selector switches set to normal, run a flux trace.
c) With all 5-path selector switches set to Emergency, run a second flux trace.
~
d) Determine the detector normalization constants from Data Sheet C.2. k O 37 l \ l g . - 4
SQNP SPECIAL TEST 7 Page 5 of 10 Rev. 1
/~
e )
\-/ APPENDIX C 1
I ' Core Power Determination i i PART B: (Continued)
. e) Enter these detector normalization constants into the l P-250 as shown in the table below.
Drive P-250 Address 1 A K_0908 i B ff0909 C _s K0910 D K0911 E K0912 F ,,K0913 . .
- 3. Verify that the P-250 parameters listed in the I'2110 wing table have the proper value and that the P-250 time and date'are cur-rent. Update as required.
Address Value Function Set the Power K0901 1 Normalization Factor Selects the Modified K5525 1 " Flux Map Print" programs I K0900 0 Initiated Pass Number Calibration Constant for K0864 Variabic(1) M/D Power Monitor (1) Variable: The value entered is a ratio of the Primary Calori-metric Indicated Power (Item B on Data Sheet C.1) to the M/D calculated power (UO906) times the cur-t rent value entered in (K0864). If no value has been entered into (K3864) enter 0.25. Item #8 Data Sheet C.1 New (K0b64) = Current (K0864) x (UO906) 4" 38 ! l I l l l
SQNP SPECIAL TEST 7 Page 6 of 10 Rev. 1 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 re-quired.
NOTE: The calculated power (UO906) is printed after each pass and may be trer.ded by the P-250 if desired. The individ-ual detector normalized integrals are also printed. TABLE C-1 i Cp(I) m f Tgmp lbm/hr F BTU /lbm F l 7 556 1.260 3.6448 x 10 554 1.255 3.6553 x 10 7 552 1.250 3.6659 x 10 G 3.6765 x 10 7 V 550 1.245 7 548 1.240 3.6862 x 10 7 546 1.236 3.6959 x 10 7 544 1.231 3.7057 x 10 4 7 542 1.226 3.7155 x 10 7 540 1.221 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 O)These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia. 39 i
) -
q ,/ SQhT SPECIAL TEST 7 Page 7 of 10 Rev. 1 APPENDIX C Data Sheet C.1 Date Time Unit Power Tavg F Loop 1 Loop 2 Loop 3 Loop 4 Item # Calculation Procedure' Units R2/TP-411J R6/TP-421J R10/RP-431J R13/RP-441J l Loop AT - Inservice (at test point) Volts 2 Loop AT = (#1) x (1) F 3 Loop AH = (#2) x Cp (from Table C.1) BTU /lbe 6 4 Loop RCS Flow (from Table C.1) 10 1bm/hr 6 5 Loop Reactor Power = (#3) x (#4) 10 BTU /hr 6 Total Reactor Power = (#5) 6
. Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr
; 7 Reactor Power = (#6) x 0.29307 MWI N 8 % Reactor Power = (#7) x 0.02932 % ,
(I) Conversion factor for AT obtained from scaling document. Remarks: e s Date By: Checked By:
SQNP SPECIAL TEST 7 Page 8 of 10 Rev. 1 APPENDIX C Ag = By= C y= Dy= Ey= Fy= l AE= BE = g= DE * - E* E* N3 = 1.00 l N B
* ^
- B N N I
NC *
- C N N N = N A
= NCCE =
D~ D N N
* =
NE* E N N Ny =A = EE = N N
> Definitions:
O A,B' N, FN = Normalized integral from summary map for - N N N' N' each detector in a normal path in the first pass A' E, DE ' E' = Normalized integral from summary map for E E' E each detector in an emergency path in the second pass . -. - N,N' B A C, N D , NE ' F
= Detector normalization factor for each detector i
Remarks: 1 Data By: Date nu 41 l s l
SQNP SPECIAL TEST 7 l ( Page 9 of 10 l (, Rev. 1 I
/~k APPENDIX C Part C: Using Thermocouples o
i The incore thermocouples can be used as an indication of bott 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 foll'o wing should be verified: K0701-K0765 = 1, For the flow mixing factors t K5501 = 0, Indicates the measured core AT is unreliable K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the run-ning frequency of the Thermcouple Averaging Pro-gram at 1, 2, . ... X 8 seconds or 64 seconds for us. The thermcouple programs breaks the core down into eight quadrents-- four centerline and four diagonal quadrants (see Figure C-1). Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot. The quadrant tilts are indicative of power shifts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts:
, Quadrant Addressable Value l Ull59 2 Ull60 3 U1161 4 U1162 5 U1151 6 U1152 7 Ull53 8 Ull54 A Short Form Map should be run periodically or upon request from the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for obtaining thermo-couple maps.
! The trend output and Short Form Maps should be attached to this i prr,cedure at the end of the test. p
\ !
i 42
SQNP SPECIAL TEST 7 Page 10 of 10 Rev. I p APPENDIX C v CfNTER.LINE QUARTER-CORE SYMMETRY Cdd Le.os s . 3 4 . i
; N-43 m 2,g m N-42 O O
( \ 3 { , 2 l4
' sso d thf Lys -
ikiley ( -) . l zl < 3 1I ( ) ExCORE CETECTORS W-4/ ovevo N*AA 2 , 1 Cold Logs J . , . s CIAGON AL QUARTER CORE SYMMETRY
~
225' 315' , s , s G J , 6
\ '
N g e 4' o l Fi w e c-t O ' 43 t.
SQNP SPECIAL Test 7 Page 1 of 4 Rev. 1 Q v . APPENDIX D Procedure For Use Of Computer System For Data Collection
. The following parameters'will be monitored during this test using the plant computer system.
Parameter Computer Point Pressurizer Pressure P0480A Pressurizer Level LO480A RCS Loop 1 llot Leg Temperature T0419A
' RCS Loop 1 Cold Leg Temperature T0406A RCS Loop 2 Ilot Leg Temperature T0439A RCS Loop 2 Cold Leg Temperature T0426A RCS Loop 3 llot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Ilot Leg Temperature T0479A RCS Loop 4 Cold Leg Temperature T0466A l
Steam Generator 1 Pressure PO400A Steam Generator 1 Narrow Range Level 1 LO400A
') . Steam Generator 2 Pressure P0420A Steam Generator 2 Narrow Range Level 1 LO420A Steam Generator 3 Pressure PO440A Steam Generator 3 Narrow Range Level 1 LO440A Steam Generator 4 Pressure P0460A i
Steam Generator 4 Narrow Range Level 1 LO460A 1 < ! Power Range Channel 1 (Quadrant 4) N0049A l Power Range Channel 2 (Quadrant 2) N0050A I Power Range Channel 3 (Quadrant 1) N0051A Power Range Channel 4 (Quadrant 3) N0052A Incore Thermocouples T0001A through T0065A
; NOTE: One power range channel will be connected to the reactivity l
computer and will be unavailable for trend. I 1 I i 44
SQNP SPECIAL TEST 7 Page 2 of 4 Rev. 1 O APPENDIX D The computer trend typewriter will be used to monitor the following com-puter points. (Additional points may be added as required by the test
. director).
l BLOCK 1 i Column Point Column Point Column Point 1 P0480A 7 T0459A 13 P0420A
' 8 T0446A 14 LO423A 2 LO480A 3 T0419A 9 T0479A 15 P0440A 4 T0406A 10 T0466A 16 LO443A 5 T0439A 11 PO400A 17 PO4604 6 T0426A 12 LO403A 18 LO463A BLOCK 2 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A 4 N0052A 10-18 As Required
('-]) 5 T0002A 6 T0013A
; To initially clear each data block, perform the following step for each block to be used.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 2 button
- 6. Push STOP button Repeat the above 6 steps for each data block to be used.
NOTE: A Block Trend Error message will occur if the data block is ini-tially clear. 45 t
SQNP SPECIAL TEST 7 Page 3 of 4 Rev. I f) v APPENDIX D To set up the data blocks, perform the following series of steps for each point to be monitored. 1.' Push the DIGITAL TREND button
- 2. Select the point address (i.e. PO480A) on the I alphanumeric keyboard
} 3. Push ADDR'SS button
- 4. Select block number (1 to 6) on keyboard.
l S. Push VALUE 1 button
- 6. Select column number (1 to 18) on keyboard j 7. Push VALUE 2 button
, 8. Push START button 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 recor: mended for the duration of the test transient
- 5. Push VALUE 3 button
- 6. Push START button
{ g If it is necessary to change the trend interval of a block or trend, perform the following.
- 1. Push DIGITAL TREND button
- 2. celect 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 i 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard l 3. Push VALUE 1 button
- 4. Select 0 on keyboard
- 5. Push VALUE 3 button
- 6. Push STOP button In addition to the data recorded on the trend typewriter, the following '
. point.: will be maaitored on analog trend recorded.
T0056A (Core exit temp). Others as seeded (Recommend pressurizer pressure, steam generator level (WR) and steam generator () x./ pressure). 46
SQNP SPECIAL TEST 7 Page 4 of 4 Rev. 1 kN.l APPENDIX D , After selecting the per to be used to record a value, ensure that it is cleared by performing the following steps.
~
- 1. Push ANALOG TREND function button i 2. Select per number (1 to 12) on keyboard
, 3. Puch VALUE 1 button
- 4. Push STOP button i
To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select per number (1 to 12) on keyboard
- 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the minimum value of the parameter to be monitored
- 7. Select range on the keyboard
- 8. Push VALUE 3 button
- 9. Push START button Repeat these steps until all of the desired analog points are being recorded.
bS./ Prior to initiation of the transient, and at 15-minute intervals thereafter, - I incore thermocouple maps will be recorded at the programmers console in the l
' computer room. To initiate an incore thermocouple map at that location, per- '
form the following steps. .
- l. 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 O
47
SQNP SPECIAL TEST 7 Page 1 of 11
] Rev. 1
) APPENDIX E i
Safeguard Blocking Procedure The first step blocks automatic initiation of a safety injection. The I
. saf ety injection alann, 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 sud what the problem is. (2) a reactor trip will take place auto-l matically. (3) a safety injection can be initiated manually from the l switch in the control room if conditions warrant.
- 1. Install temporary jumpers and temporary alteration control tags to a
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: / l 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 tes.ts from high AP caused by degraded test conditions. (This block will also defeat all AP SI alarms).
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, I 73, 76 are all clear prior to starting blocking procedure.
- 3. flove 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: / 4 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 v 48
SQNP SPECIAL TEST 7 Page 2 of 11
, Rev. 1 b APPENDIX E grour.d will already be made up through the trip switch). The wire on the rack side of the terminal block must be lifted and i taped for the terminal point where the jumper wire is connected l
The TACF tag will be attached to the bistable switch and the i TACF must note the jug er and the lifted wire.
} NOTE: Orange "Out of Service" stickers should be placed on all , status / alarm windows as the 120V source is connected.
- 4. Lift and tape the wire on the rack side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of j 1-R.7 and verify 1-XX-55-6B/25 is clear.
1 Performed by: ,
/
Verified by: /
- 5. Hove test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
j Performed by: / l Verified by: /
- 6. Lift and tape the wire on the rack side of terminal L-7 in the rear of -
1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of
, 1-R-7 and verify 1-XX-55-6B/27 is clear. '
Performed'by: / Verified by: /
- 7. Move test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / I 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.
Performed by: / Verified by: _ _ .
/
l I 49
SQNP SPECIAL TEST 7 Page 3 of 11
- Rev. 1 APPENDIX E s_f .
I
; 9. Move 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: / j 10. Lif t and tape the wire on the rack side of terminal L-7 in the rear of j 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. 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
(-)3 s_ 1-XX-55-6B/28 is clear. Performed by: / Verified by: /
- 13. Hove test trip switch PS-525A in 1-R-8 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 14. Litt and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.
Performed by: / Verified by: /
- 15. Move test trip switch PS-526D in 1-R-11 to the trip position and verify the amber light above the rwitch comes on.
Performed by: / [) w.s Verified by: / 50
SQNP SPECIAL TEST 7 Page 4 of 11
; Rev. I p
b , APPENDIX E
- 16. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-II. Apply 120-VAC source to terminals L-7 and L-8 in the rear of a 1-R-11 and verify that XX-55-6B/51 is clear.
Performed by: / Verified by: /
- 17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify
! the amber light above the switch comes on.
Performed by: / Verified by: /
- 18. 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 cicar.
Performed by: / Verified by: / Temporary Mgdification to liigh 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. '
Performedb'y: / Verified by: / NOTE: If the alartr.s will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected. I
- 20. Hove test trip switch TS412D in R-2 to the trip position and verify 4-the amber light. above the switch comes on.
Performed by: / Verified by: /
- 21. Lif t and tape the wire on the rack side of terminal H-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: (O ,) / 51
- L 6,. e.
L ._ i
; SQNP SPECIAL TEST 7
, Page 5 of 11 Rev. 1
- s APPENDIX E
; 22. Hove test trip switch TS-422D in R-6 to the trip position and verify I 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 l
4 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify I. XA-55-6A/30 will clear. Performed by: / Verified by: /
- 24. Move test trip switch TS432D in R-10 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 25. Lif t and tape the wire on the rack side of terminal M-3 in the rear of 1-R-10. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: /
- 26. Hove test trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
1 Performed by: / Verified by: /
- 27. Lif t and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 and verify
, XA-55-6A/30 will clear.
Performed by: / Verified by: / 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 7- s , trip, an S. I. alarm, but no S. I. initiation.) () ~ 52
SQNP SPECIAL TEST 7 Page 6 of 11 Rev. I t APPENDIX E I
- 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.
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.
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 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 SWITCII TEMP ALT. NO. R-7 PSS15A / . R-7 PSS15B / , R-12 PS516C /
, R-12 PS516D /
R-8 PS525B / R-8 PS525A / R-11 PSS26D / R-11 RS526C / R-2 TS412D / R-6 TS422D / i R-10 TS432D / R-13 TS442D / R-3 FS512B / R-3 FS522B / To return the steamline Delta-P S.I. to normal condition, the following steps should be followed. s 53
SQNP SPECIAL TEST 7 Page 7 of 11 Rev. I s
\ ,
APPENDIX E i NOTE: The orange "Out of Service" stickers should be removed from the j alarm / status window as each bistable is put back in service.
- 31. Remove the 120-VAC source from L-5 and L-6 in 1-R-11. Reterminate wire on L-5.
Performed by: / Verified by: /
- 32. Move test trip switch PS-526C in 1-R-11 to the normal position and l verify the amber light above the switch and 1-XX-55-6B/50 are clear.
Performed by: / Verified by: /
- 33. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire on L-7.
Performed by: / Verified by: / l I
- 34. Move test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/51 are clear.
Performed ,by: / Verified by: / l 35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9. Performed by: / Verified by: /
.36. Move test trip switch PS-525A in 1-R-8 to the normal position and verify
, the amber light and 1-XX-55-6B/26 are clear.
Performed by: / Verified by: / i Remove the 120-VAC source from L-7 and L-8 in 1-R-8. Reterminate wire 37. ! on L-7. Performed by: /
,j Verified by: /
54 s
SQNP SPECIAL TEST 7 Page 8 of 11 Rev. 1 v
)
APPENDIX E
, 38. Move test trip switch PS-525B in 1-R-8 to the normal position and verify 5
the amber light above the switch and 1-XX-5-6B/28 are clear. j Performed by: / Verified by: / f 39. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. Retermi-nate wire on L-7. l Performed by: / Verified by: /
- 40. Move test trip switch PS-516D in 1-N-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.
w/ Performed by: / .
. Verified by: / ,
- 42. Move 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.
6 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.
I 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: / O 55 9,
SQNP SPECIAL TEST 7 Page 9 of 11 Rev. 1 /
. APPENDIX E
- 45. Hemove the 120-VAC source f rom terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.
Performed by: / i l Verified by: / I i 46. Move test trip switch PS-515A to the normal position and verify the j 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.
' Toreturntgehighsteamflowcoincidentwithlowsteamgeneratorpressure or low-low avg to normal, perform the following steps.
- 47. Move 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. Hove 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.
I Performed by: / Verified by: /
- 49. 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: /
-50. Hove 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: /
~
K.,,./ 56
SQNP SPECIAL TEST 7 Page 10 of 11 Rev. I 7x , APf?NDIX E
- 51. Hemove the 120-VAC source from terminals M-3 and M-4 in R-10. Retermi-nate wire on M-3.
Performed by: / Verified by: / , t
- 52. Move test trip switch TS432D in R-10 to the normal position'and verify 9
the amber light goes out and XA-55-6A/30 will clear. Performed by: / Verified by: /
- 53. Remove the 120-VAC source from terminals M-3 and M-4 in R-6. Retermi-
- nate wire on M-3.
l Performed by: / l Verified by: /
- 54. 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.
I l j ~/ Performed by: -
/
' Verified by: / -
- 55. 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: [
- 56. Hove 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.
1 f Performed by: / t i Verified by: / l l p d 57
'i.
l SQNP i SPECIAL TEST 7 l Page 11 of 11 l Rev. 1 APPENDIX E
- 57. Remove- the Temporary Alteration Tage on the following test trip swi t clies :
I I RACK TEST SWITCll TEMP ALT. NO. i R-7 PSS15A /
. R-7 PS515B /
{ R-12 PSS16C / R-12 PS516D / R-8 PSS25B / R-8 PSS25A / R-11 PSS26D / R-11 RSS26C / R-2 TS412D / R-6 TS422D / i R-10 TS432D / R-13 TS442D / R-3 FS512B / R-3 FS522B /
- 58. Remove the jumpers and the Temporary Alteration Tags from logic cards A216, test point 1, to the logic g.ound on the logic test panels in R-47 and R-50.
I 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. j 58
SQNP SPECIAL TEST 7 Page 1 of 1 Rev. 1 (a) APPENDIX F Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily hypassed or require special test exceptions to the limiting conditions f or operation during the performance of this and all other special tests. 8 E e : :
=
8e8 " u h . .o g a $5%85 5o 00 o o 58 83
%.3 E%" o 8 5" . . . n8*
B BBB? B
> ?
UUUUU* OE s% s - - $$$ "E a 2 25%aa1 e B; EBB %8 ? 8 8 Ov enaea6%M ea TECllNICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment HI Pressure SI (3.3.2.1) X X X X X X X X X X Sa f ety__ Lim _its_ (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 OTAT (3.3.1) Inoperable because of low flow X X X X X X X X Hinimum temperature (3.1.1.4) X X X X Hoderator temperature coef ficient (3.1.1.3) X X X X Steamline AP SI (3.3.2.1) bypassed X X X X X X X X X X liigh 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 Ulil (3.5.1.2) X X X X X X X X X X ' AFW (3.7.1.2) X X Diesel Gens. (3.8.1.1) X X A.C. Electrical iloards (3.8.2.1) X X l Batteries (3.8.2.3) X X RCS Flowrate (3.2.3) X X X X X X X X l Control Rod Insertion Limits (3.1.3.6) X X X X X X X
-Reactor Coolant Loops Normal Operation .n (3.4.1.2) X X X X X X X X U
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, SQNP 1 SPECIAL TEST 7 Page 1 of 1 Rev. 1 TABLE 1 Loop Flow and Core AT for Various Power Levels and
' Isolation Configurations (Computer Estimates)
No. of Loops Operating (Nat. Circ.) i 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 = A5.7 NOTE: L is % of 97,000 gpm flow through operable loop.
AT = Loop AT in *F. a 60 4
w - - a O , l i I l l i l l SPECIAL TEST NO. 8 l ESTABLISIIMENT OF NATURAL CIRCULATIONS FROM STAGNANT CONDITIONS 1 O 4 l t i l O M
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SPECIAL TEST 8 Page 1 of 1 Rev. I s- - - - ESTAllLISl[t!ENT OF NATURAL CIRCULATIONS FR0f1 STAGNANT CONDITIONS Tg le of Contents PdS" l Test. Description 1 Special Operator Instruction 2 1.0 OluECTIVES 3 2.0 PREREQllISITES 3 3.0 PRECAUTIONS 6 4.0 SPECIAL TEST EQUIPr!ENT 8
; 5.0 INS'IRUCTIONS 9 i
; 6.0 ACCEPTANCE CRITERIA 13 APPENDIX A - References 14 APPENDIX 11 - Def iciencies 15 APPENDlX C - Power Pleasurement Technique 16 API'ENDIX D - Safeguaril Blocking Proce< lure 26 i
APPENDIX E - Technical Specifications Exceptions 37 TABLE I - Loop Flow anil Core AT for Various Power Levels anil isolation Configurations 38 l
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' SPECIAL TEST 8 Page 1 of 1 Rev. 1 , /
A- TEST DESCRIPTION , I With stagnant (no flow) conditions existing throughout the primary system, core power will be increased to simulate decay heat and steam generators will
- j. be utilized to establish a heat sink. Establishment of natural circulation-
- will be verified by observing the response of the core exit thermocouples, ,
hot leg wide range temperature indication, and cold leg wide range temperature j' indication. Core exit thermocouples will be monitored to access core flow j distribution. g i I f f i i i e
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SQNP I I SPECIAL TEST 8 Page 1 of 1 Rev. 1 iO SPECIAL OPERATOR INSTRUCTION I
*An operator initiated safety injection should be performed only for one or , more of the following conditions:
I Reactor Coolant System Subcooling 5 10* Sudden Unexplained Decrease in Pressurizer Level of 10% or to an Indicated Level of 5 10% i 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% i Any Loop A T > 65 F l , Tavg > 578*F Core Exit Temperature (liighest) ? 610 F
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
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aynr SPECIAL TEST 8 l Page I of 11 Rev. 1
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V 1.0 OBJECTIVE 1.1 Verify establishment of natural circulation from stagnant (no flow) conditions in the primary system using reactor power to simulate decay heat. 1.2 To provide operator training. All operating shifts will perform this test. NOTE: Data acquisition does not need to be repeated for multiple test performances. 2.0 PREREQUISITES 2.1 Reactor critical in the hot zero power test range. l / I 2.2 All reactor coolant pumps operating.
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2.3 Steam pressure approximately 878 psig (Tavg ~ 531 F) and being maintained by the atmospheric relief valves or by steam dump to
! the condenser (preferred).
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2.4 Steam generator water level at approximately 33% and being main-tained by auxiliary feedwater system (motor-driven pumps).
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i 2.5 Control Bank D at approximately 160 steps or as specified by the test engineer to permit reactor power increase up to approximately 3% (requ. red control band D position may be determined during the i
- hot zero power test program).
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2.6 Pressurizer level control in manual.
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2.6.1 RCS pressure at approximately 2200 psig and in automatic control (slowly adjust setpoint to 62.5%). Pressurizer 1cvel at approximately 25%.
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SQNP SPFCIAL TEST 8
- P:go 2 of 11 Rev. 1
( , 2.0 (Continued) 2.6.2 The sensitivity of the NIS to avg has been completed. I i 2.7 Record the following parameters. 2.7.1 Obtain thermocouple map at 15-minute intervals. I I 2.7.2 Set up P-250 to monitor the following parameters at f ast as possible. { T
- a. Wide range T c Id (all loops)
- b. Wide range hot (all loops)
- c. Power range channels
- d. {ntermediate range channels
- c. avg (all loops)
- f. AT (all loops)
- g. Loop flow (1 from all 4 loops)
- h. Steam generator level (all 4 loops)
- i. Steam generator pressure (all 4 loops)
NOTE: Record the following information on each strip chart: l a) Unit number b) Date
]lg c) Special Test number d) Scale and range of measured parameter e) Chart speed f) Recorder JD number 2.7.3 Record on reactivity computer recorder.
' a. Flux
- b. Average w de rangeTcold i
i c. Average w.de range hot
- d. Average steam generator pressure
- e. Reactivity
. 2.7.4 Record on Recorders.
Recorder #1 Connect to: Monitoring: Channel #1 1-R-1, FP414B RCS Flow - Loop 1, Channel #2 1-R-1, FP424B RCS Flow - Loop 2 Channel #3 1-R-1, FP434B RCS Flow - Loop 3
. Channel #4 1-R-1, FP444B RCS Flow - Loop 4 Channel #5 1-R-1, PP455B Pressurizer Pressure Channel #6 1-R-1, LP459B Pressurizer Level
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SQNP SPECIAL TEST 8 Page 3 of 11 Rev. I m U 2.0 (Cont.inued) Recorder #2 Connect to: Monitoring: s Channel #1 1-R-23, LP501 Steam Gen #1 Level Channel #2 1-R-3, FPS 12B Steam Gen #1 Steam Flow Channel #3 1-R-3, PP514B Steam Gen #1 Pressure Channel #4 1-R-90 LP502 Steam Gen #2 Level Channel #5 1-R-2,'FP522B Steam Gen #2 Steam Flow l 1-R-3, PPS24B Steam Gen #2 Pressure I Channel #6 Recorder #3 Connect to: Monitoring: l 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 7 Channel #4 1-R-23, LP504 Steam Gen #4 Level Channel #5 1-R-4, FP542B Steam Gen #4 Steam Flow Channel #6 1-R-4, PP544B Steam Gen #4 Pressure Recorder #4 Connect to: Monitoring: Channel #1 F-3-163, TP 13, 1-L-11B Aux Feed Flow to SG #1 l Channel #2 F-3-155, TP 13, 1-L-11A Aux Feed Flow to SG #2
- Channel #3 F-3-147, TP 12, 1-L-11B Aux Feed Flow to SG #3 l Channel #4 F-3-170, TP 12, 1-L-11A Aux Feed Flow to SG #4 i ) /
y . 2.8 Trend 3 incore T/C's as determined by the test engineer on the analog ' trend recorders on the main control board. l 2.8.1 Make preparations to print out incore T/C's temperature
' on paper tape at approximately 5 minute intervals.
l / I i i 1 2.9 Verify the input logic of safety injection on Hi steam line AP
- has been blocked in accordance with Appendix D.
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l ! 2.10 Verify the Hi steam flow coincident w!th Lo S/G or Lo Tav input to safety injection has been modified in 4 :ordance with Appendix D. 2.11 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix D.
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SQNF SPEC 4AL TEST 8 . Page 4 of 11 Rev. I 2.0 (Continued) j 2.12 Verify the following Ul!I isolation valves are gagged. t l FCV 87-21 / l FCV 87-22 / FCV 87-23 / FCV 87-24 / l 2.13 Intermediate and power range (low setpoint) high level reactor I 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 W ECAUTIONS, LIMITATIONS, AND ACTIONS 3.1 Do not exceed 5% rated tt.ermal power. 3.2 Abort the test if any of the following temperature limits are l exceeded: 3.2.1 610 F for any core outlet thermocouples 3.2.2 65 F for any loop Delta-T 3.2.3 578 F for any loop avg 3.3 Avoid sudd<. changes in steam pressure. i 3.4 Avoid sudden changes in auxiliary feedwater. 3.5 Maintain pressurizer pressure at about 2200 psig. 3.6 Onset of natural circulation may be accompanied by a power in-crease due to the introduction of cooler water into the core. 3.7 During natural circulation, reactor coolant loop trai it time i is on the order of 3 to 5 minutes. ! 3.8 Maintain constant steam generators pressure througho-c test except l where specifically stated otherwise. 3.9 Maintain steam generator water level constant at ~ 33%. 3.10 Do not maintain no flow conditions in the primary system for i more than 30 minutes. l
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SQNP SPECIAL TEST 8 Page 5.of 11 Rev. 1 3.0 (Continued) i i 3.11 Reactor coolant pumps should not be restarted for 30 minutes af ter pump trip unless required by this instruction or unless safety con-cerns necessitate the re-establishment of forced circulation. t 3.12 Do not increase power at a rate faster than .75%/ min in order
! to minimize RCS pressure surges, k
i , 3.13 As reactor power is increased to 3%, a pressurizer pressure and level l surge is expected. If the pressure surge cannot be controlled below the PORV setpoint using' auxiliary spray, the reactor should be manually 9 tripped. 3.14 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. 3.15 Maintain D bank at 2 100 steps during the conduct of this procedure.
- Should this limit be reached, boron concentration will have to be 1 increased.
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SQNP SPECIAL TEST 8 Page 6 of 11 Rev. 1
-- 4.0 SPECIAL TEST EQUIPMENT s
e Identification Calibration Inctrument Number Specification Verification I i Reactivity Computer Westinghouse t Recorder (1) Brush or Equivalent Recorder (1) HP 7100 B or Equivalent 9 i I s If test instruments are changed during this test, the instrument informa-
. tion must be recorded here and an entry made in the chronological log book explaining this change.
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SQNP i SPECIAL TEST 8 Page 7 of 11 Rev. 1 U, S.0 INSTRUCTIONS CAUTION: If primary system temperatures are within 10 F of the limits specified in step 3.2: a) Insert control bank D until reactor power is in the hot zero power test range. b) Verify pressurizer spray valves closed c) Start loop 2 reactor coolant pump, d) Establish stability: pressurizer level and pressure, steam generator level and pressure, and primary system temperature. e) Return pressurizer level control to automatic. f) Start the remaining reactor coolant pumps one at a time. 5.1 Start recorders, P-250 trend block, and T/C printout.
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CAUTION: Following reactor coolant pump trip Tave and Delta-T indication will be unreliabic. 5.2 Trip reactor coolant pumps 1, 3, and 4 and allow flow in these loops to coast down for two minutes and then trip RCP 2. () 5.3 Stabilize steam generator water level at approximately 33%. .
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5.4 Close main steam dump valves to condenser. 1 5.5 Close auxiliary feedwater system level control valves.
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' 5.5.1 Reduce seal injection flow to the reactor coolant pumps to approximately 4 gpm.
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5.5.2 Initiate auxiliary spray to the pressurizer just prior to \ beginning withdrawal of control bank D in the next step. Be prepared to isolate the normal charging path in order to get full flow to the spray nozzle.
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SQNP SPECIAL TEST 8 Page 8 of 11 Rev. 1 r t N 5.0 (Continued) [ NOTE: Some control over the auxiliary spray flow can b'e obtained by opening the normal pressurizer spray valves from PIC-68-340B and PIC-68-340D and allowing the auxiliary
; spray flow to bypass the spray nozzle and directly enter ! the reactor coolant loop. By positioning these valves '
j the flow rate to the nozzle can be increased or decreased. I 1.e. Opening the valves will decrease the spray and g closing the valves will increase it. Increased spray flow can also be obtained by in-creasing charging flow with FIC-62-93. NOTE: During control bank withdrawal continuously monitor increase in: a) reactivity computer flux level, b) NIS indicated power level, and core exit thermo-couple temperature (except delayed response). 5.6 Approximately 5 minutes after auxiliary feedwater system level
; control valve closure open main steam dump valves to condenser as needed, place auxiliary feedwater level control valves in
. automatic, and begin control bank D withdrawal, as requested by the test engineer, until reactor power is at ~ 3%.
j a NOTE: Power should not be increased faster than .75% per min. l 5.7 Record control bank D po'sition: steps , / CAUTION: Onset of natural circulation may be accompanied by a power increase. Control bank D may be inserted to reduce the mag-nitude of the increase. Immediately following power transient, return control bank D to the position recorded in step 5.7.
! CAUTION: Reduction in T may result in a nonconservative, false
' NIS power levef ddication. Do not withdraw control bank D beyond the position recorded in step 5.7 unless requested by test engineer.
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SQNP SPECIAL TEST 8 Page 9 of 11 Rev. 1 5.0 (Continued) NOTE: At initiation of natural circulation the following initial response is expected.
- 1) Reactivity computer flux level increase 1 2) NIS power 91 vel indication increase
- 3) Wide range hot increase (See Table 1) l T slight increase or stable
- 4) Wide range cold
- 5) Core exit thermocouples 3 a) IncreaseifT/Ctemp.+(~17F)<initialfcold b) Decrease if T/C temp. + (~ 17 F) > initial cold g
CAUTION: Primary coolant system may be held in a stagnant condition (no flow) for a maximum of 30 minutes. If the NIS or pri-mary system temperature instrumentation does not indicate that natural circulation has started within 25 minutes after RCP trip, insert control bank D until reactor power is in the hot zero power test range, and restart reactor coolant pumps as previously described. 5.8 If an indication of natural circulation starting has not been ob-served within 2 minutes of the first obscrvable power increase, reduce steam generator pressure 50 psig or until natural circula-lation is initiated. Rate of pressure decrease should be accom-plished at a controlled rate as requested by the test engineer. Utilize auxiliary feed as necessary to maintain steam generator ('l) level constant. .
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e . NOTE: Natural circulation flow will be stable when: a) 6T between wide range T and T is constant. b) AT between wide range T and E8 d exit T/C average d I temperatureT is constant. c) Wide range hot ~ core exit T/C average temperature. j 5.9 When natural circulation flow has establishedT slowly regulate
; secondary side steam flow to slowly increase cold to ~ 547 F.
- During natural circulation loop transient time is long (3 to 5 minutes).
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5.10 Maintain natural circulation under the established condit$ans for approximately 15 minutes.
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5.11 Stop recording test data. !
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SQNP SPECIAL TEST 8 Page 10 of 11 i Rev. 1 N' 5.0 (Continued) 5.12 Insert control bank D until the reactor is in the hot zero power test range.
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t 5.13 Restart reactor coolant pumps one at a time as previously de-scribed starting with RCP 2, 1, 3, and then 4.
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5.13 Attach all strip charts, trend data, and T/C maps to this test procedure.
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5.15 Return pressurizer level control to automatic.
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5.16 Remove the block of input logic of safety injection on lli steam AP in accordance with Appendix D, unless the next test to be per-formed requires the block to be installed. If this is the case, disregard this step, place N/A in the signature line and initial. I k / 5.17 Remove modification to Ili steam flow coincident with Lo S/G pressure or Lo Tav input to safety injection in accordance with Appendix D, unless the next test to be performed requires the modification to be made. If this is the case, disregard this step, place N/A in the signature line and initial. t
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5.18 Remove block of automatic initiation of safety injection in accordance with Appendix D, unless the next test to be per-formed requires the modification to be made. If this is the case, disregard this step, place N/A in the signature line and initial. 1 I
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SQNP SPECIAL TEST 8 Page 11 of 11 Rev. I o p 5.0 (Continued) 5.19 Remove the gag from the following UHI isolation valves unless the next test to be performed requires the valves to be gagged. If this is the case, disregard this step, place N/A in the signature line and initial. FCV 87-21 / FCV 87-22 / i FCV 87-23 / I FCV 87-24 / { 5.20 Reset the intermediate and power range high level reactor trip setpoints as indicated by the test director in accordance with Appendix C and D of SU-8,5.2 unless the ncxt test to be performed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, and initial. Power Range / Intermediate Range / 6.0 ACCEPTANCE CRITERIA 6.1 Delta-T established between wide range hot and cold is stable and less than 65 F. .
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, 6.2 Delta-T established between wide rangeTeold and core exit T/C average temperature is stable and less than 65 F.
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1 SQNP SPECIAL TEST 8 Page 1 of 1 Rev. 1
.D , APPENDIX A J ! References
- 1. FSAR
- 2. Technical Specifications l
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- SQNP SPECIAL TEST 8 Page 1 of 1 Rev. 1
--O APPENDIX B 4
Test Deficiencies # 4 Test Deficicacy j . 1 I i i i Recomended Resolution , 'h Final Resolution , } e j . l l i i i p . Originator / , l Signature Date . t PORC Review of Final Resolution Date Approval of Final Resolution / Plant Superintendent Date l l-15
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. . _ _ . _ . -.____.m__ . _ _ . _ _ . . - . . . . _ . _ , , . . . ,__ ..._..._ , . . _ _ _ _ , , , _ . - _ _ _ , _ _ . . ~
SQNP
' SPECIAL TEST 8 ' Page 1 of 10 Rev. 1 I
f APPENDIX C Procedure for Determining Core Power Level l O I I i l O 16 l a---. - . - , - , . . . . , . . . - - , . . - - . - , - - , . - -
SQNP SPECIAL TEST 8 Page 2 of 10 Rev. 1 O ' APPENDIX C Outline
; 1. Core Power Determination i
A. Primary Side Calorimetric (Forced Circulation Only)
- 1. Reference (~ 550 F) Calorimetric (Before NC test) i a) Output used to adjust M/D Power Monitor Program's power conversion constant.
B. M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in per-cent power and equal to the primary calorimetric output.
- 2. Power Monitoring i a) Tlie M/D Power Monitor Program will calculate the integral T 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 8 Page 3 of 10 Rev. I b . APPENDIX C ! CORE POWER DETERMINATION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation) 5 C.1 Use two DVMs and measure the voltage at the test points speci-fled for each loop as rapid as possible. I C.2 Calculate the AT; multiply that AT by the specific ~ heat and j 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. I i 1 18 f
SQNP SPECIAL TEST 8 Page 4 of 10
, Rev. 1 O APPENDIX C (Continued)
Core Power Determination
. PART B: M/D Power Monitor Program
- 1. Set up the movable detector system for a 1 pass partial core i flux map as per TI-53. Select flux thimbles as per the table
' belcw for tbe 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 e i experience.
- 2. Determine the detector normalization constants and enter them into the P-250 as follows:
a) Enter a value of 1.0 into the P-250 for the addresses shown in the table below. b) With all 5-path selector switches set to normal, run a flux j trace. t . 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 8 Page 5 of 10 Rev. 1
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' 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 i i C K0910 i
' D K0911 I
i E K0912 F , K0913
- 3. Verify that the P-250 parameters listed in the following table have the proper value and that the P-250 time and date are cur-rent. Update as required.
Address Value Function Set the Power K0901 1 Normalization Factor i Selects the Modified 1 " Flux Map Print" Programs K5525 i 0 Initiated Pass Number K0900 Calibration Constant for K0864 Variable (I) M/D Power Monitor t II) Variable: The value entered is a ratio of the Primary Calori- j j metric Indicated Power (Item B on Data Sheet C.1) to the M/D calculated power (UO906) times the current value entered in (K0864). If no value has been entered into (K0864) enter 0.25. Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906) i l
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SQNP SPECIAL TEST 8 Page 6 of 10 Rev. 1 .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 i passes may be repeated as often as a power determination is l required.
NOTE: The calculated power (UO906) is printed after each pass I and may be trended by the P-250 if desired. The individ-ual detector normalized integrals are also printed. y TABLE C-1 Temp Cp(I) s F BTU /lbm F lbm/hr 556 1.260 3.6448 x 10 7 554 1.255 3.6553 x 10 7 552 1.250 3.6659 x 10 O 550 1.245 3.6765 x 10 7 7 548 1.240 3.6862 x 10 546 1.236 3.6959 x 10 7 7 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 7 540 1.221 3.7254 x 10 7 i 538 1.217 3.7348 x 10 7 536 1.213 3.7443 x 10 7 534 1.209 3.7538 x 10 7 I 532 1.206 3.7633 x 10 7 ! 530 1.202 3.7729 x 10 (O These values are from the 1967 ASME Steam Tables. Values ara for a pressure of 2250 psia. 21
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SQNP SPECIAL TEST 8 Page 7 of 10 Rev. 1, n oPENDIX C Or.ta Sheet C.I 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-4413 1 Loop AT - Inservice (at test point) Volts 2 Loop AT = (#1) x (I) F 3 Loop AH = (#2) x Cp (from Table.C.1) BTU /lbm 0 M 4 Loop RCS Flow (from Table C.1) 10 lbm/hr 6 5 Loop Reactor Power = (#3) x (#4) 10 BiU/hr 6 Total Reactor Power = (#5) 6 Loop 1 + Loop 2 + Loop 3 + Loop 4 10 BTU /hr 7 Reactor Power = (#6) x 0.29307 MWT l 8 % Reat.~.or Power = (#7) x 0.02932 % (1) Conversion factor for AT obtained from scaling document. Remarks: Date By: Checked By:
SQNP SPECIAL TEST 8 Page 8 of 10 Rev. 1 O APPENDIT. C A N* N* N= FN* N BN* AE
- E" E E* E" E N = 1.00 A
NB = = E = N N
=
NC" C N N N N =AN = CE = D ~ D D N N NE" E N N N =Ap , NE EE = F F F N N (, Definitions: ' 1
= Normalized inter sl from summary map for l
A' N N, CN ' N' N, FN each detector in a normal path in the
' first pass
= Normalized integral from summary map for A'E E, CE , DE , EE ' E each detector in an emergency path in the i second pass
# **' *~
j N,N' A B C' D' E' F
* * **' # " ""*1I***' " I*** #
tector t Remarks: i Data By: Date I i O O 23 1 v
SQNP SPECIAL TEST 8 Page 9 of 10 Rev. I m ( ) ' ' APPEMDIX C Part C: Using Thermocouples f The incore thermocouples can be used as an indication of both core j flow distribution and power shif ts during natural circulation. Prior to running a thermocouple map or trending the eight quadrant tilts (four center line and four diagonal tilts) the following should be verified: K0701-K0765 = 1, For the flow mixing factors K5501 = 0, Indicates the measured core AT is unreliable K0791 = 0.075, Core bypass flow fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the run-ning frequency of the Thermcouple Averaging Pro-gram 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). Quadrants 1-4 can be directly correlated with the excore detectors but quadrants 5-8 cannot. The quadrant tilts are indicative of power shif ts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts: I Quadrant Addressable Value 1 Ull59 2 U1160 3 U1161 4 U1162 5 U1151 i 6 Ull52 7 Ull53 8 U1154 , A Short Form Hap should be run periodically or upon request from the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for obtaining thermocouple maps. The trend output and Short Form Haps should be attached to this
/ ) procedure at the end of the test.
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SQNP SPECIAL TEST 8 Page 10 of 10 Rev. 1 O' APPENDIX C CENTER LINE OUARTER-CORE SYMMETRY
; Cdd L9s t , 3 4 .
' N-4 3 m 2,g m N 42 5 .
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/ EXCORE DETECTORS o u of v o N*44 ; H-41 2 .
I i Cold La p i 9 OI AGON AL dVART ER. CORE SYMMETRY 225* sis *
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g- * '\ 6 e N 7 x 13s* 45* l 25 l I i . .
SQNP SPECIAL TEST 8 Page 1 of 11 Rev. 1
/,
j APPENDIX D i Safeguard Blocking Procedure The first step blocks automatic initiation of a safety injection. The safely 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 j 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 j 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 j 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: / l R-50 Panel Performed by: / Verified by: / t, 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 tes.ts from high AP caused by degraded test conditions. (This block will also defeat all AP SI alarms).
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51, I 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
,f 26 a
SQNP SPECIAL TEST 8 Page 2 of 11 Rev. I b'i
'- 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. I
- 4. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-7 and verify 1-XX-55-6B/25 is clear.
1 Performed by: / 1 Verified by: / l S. Nove test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on. 1 Performed by: / Verified by: / O (i') 6. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 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 ember light above the switch comes on.
Performed by: /
', Verified by: /
- 8. Lif t and tape the wire on the rack side of terminal L-5 in the rear of 1-R-7. Apply 120-VAC source to terminals L-5 and L-6 in the rear of 1-R-12 and verify 1-XX-55-6B/73 is clear.
Performed by: / Verified by: / r %. 27 e
SQNP SPECIAL TEST 8 Page 3 of 11 Rev. 1 fx
)
' ' APPENDIX D l
; 9. Move test trip switch PS-516D in 1-R-12 to the trip position and verify ) the amber light above the switch comes on.
I Performed by: /
, Verified by: /
l
!. 10. Lif t and tape the wire on the rack side of terminal L-7 in the rear of g
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: / I Verified by: /
- 11. Move test trip switch PS-525B in 1-R-S to trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: / I
. 12. Lift and tape the wire on the rack side of terminal L-7 in the rear of Apply 120-VAC source to terminals L-7 and L-8 and verify ll 1-R-8.
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 I the amber light above the switch comes on.
Performed by: / Verified by: /
- 14. Lift and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 and verify that XX-55-6B/26 is clear.
Performed by: / Verified by: /
- 15. Hove test trip switch PS-526D in 1-R-11 to the trip position and verify the amber light above the switch comes on.
-s Performed by: /
' Verified by: /
28
SQNP
! SPECIAL TEST 8 Page 4 of 11 Rev. 1 A
k( APPENDIX D
- 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.
t j Performed by: / Verified by: / I
- 17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 18. Lift and tape the wire on the rack side of terminal L-5 in the rear or 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/50 is clear.
t Performed by: / Verified by: / Temporary Mgdification to High Steam Flow Coincident with Low S.G. Pressure
/~ or Low-Low avg Safety Injection N-}' .
- 19. Verify annunciators XA-55-ts/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 rodifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected.
- 20. . Move test trip switch TS412D in R-2 to the trip position and verify the amber light above the switch comes on.
l Performed by: / Verified by: /
- 21. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / A t, / Verified by: / 29
SQNP SPECIAL TEST 8 Page 5 of 11 Rev. I /^s APPENDIX D (>t .
- 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: / I
, Verified by: /
l
- 23. Lift and tape the wire on the rack side of terminal M-3 in the rear of g 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. Hove test trip switch TS432D in R-10 to the trip position and verify-the amber light above the switch comes on.
j Performed by: / i Verified by: / t
- 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 N
XA-55-6A/30 will clear. Performed by: / Verified by: /
- 26. Move test trip switch TS-442D in R-13 to the trip position and verify I the amber light above the switch comes on.
Performed by: / Verified by: / i l' 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 steam flow S.I and steam dump interlock are now blocked. The next steps will trip the steam flow inputs to the high steam flow Safety Injection signal so that an S.I. signal will be initiated on low steam generator
. [ ') pressure alone (600 psig). (This would result in a reactor trip, an S. I. alarm, but no S. I. initiation.)
30 g_ -.
SQNP SPECIAL TEST 8 Page 6 of 11 Rev. 1
/7
,_ APPENDIX D
- 28. Hove test trip switch FSS12B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/2 come on.
Performed by: / Verified by: /
- 29. Hove test trip switch FS522B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/ come on.
Performed by: / Verified by: / NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal. 4
- 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 SWITCH TEMP ALT. NO. O) R-7 PSS15A / . R-7 PSS15B / , R-12 PSS16C / R-12 PS516D / R-8 PS525B / R-8 PS525A / R-11 PS526D / j R-11 RS526C / R-2 TS412D / R-6 TS422D / R-10 TS432D
-/
R-13 TS442D / R-3 FS512B . / R-3 FSS22B / l To return the steamline Delta-P S.I. to normal condition, the following steps should be followed.
;O V
31 1
. I
SQNP SPECIAL TEST 8
. Page 7 of 11 Rev. 1 \, ,
APPENDIX D
.; NOTE: The orange "Out of Service" stickers should be removed from the ; alarm / status window as each bistable is put back in service.
I-i 31. Remove the 120-VAC source from L-5 and L-6 in 1-R-11. Reterminate wire on L-5. Performed by: / l Verified by: / 4 ,
- 32. Move test trip switch PS-526C in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/50 are clear.
3 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: / l
, Verified by: /
O l
- 34. Move test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/51 are clear.
Performed.by: / Verified by: / l 35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9. Performed by: / f Verified by: /
.36. Move test trip switch PS-525A in 1-R-8 to the normal position and verify the amber light and 1-XX-55-6B/26 are clear.
Performed by: / Verified by: /
- 37. Remove the 120-VAC source from L-7 and L-8 in 1-R-8. Reterminate wire on L-7.
j_ Performed by: / V Verified by: / 32
SQNP SPECIAL TEST 8 Page 8 of 11 Rev. 1
/~ -l_/ APPENDIX D
- 38. Hove 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: / Remove the 120-VAC source from terminois L-7 and L-8 in 1-R-12. Retermi-39. ' nate wire on L-7. Performed by: __
/
l Verified by: / 1
- 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-A nate wire on L-5.
() Performed by: / . 1 s i ~ Verified by: / ,
- 42. Hove test trip switch PS-516C in 1-R-12 to the normal position and verify the amber light above the switch and 1-XX-55-6B/73 are clear.
b Performed by: /
' Verified by: /
\
4 43. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-7. Retermi-
'! nate wire on L-7.
Performed by: / Verified by: /
- 44. Hove test trip switch PS-515B in 1-R-7 to the normal position and verify l the amber light and 1-XX-55-6B/27 are clear.
t Performed by: / Verified by: / O
%) -
1 33
* \
l 1* I
SQNP SPECIAL TEST 8 Page 9 of 11 Rev. 1 t' ')
~' APPEND 1X D
- 45. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on L-9.
I Performed by: / Verified by: /
- 46. Move 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.
l Performed by: / Verified by: / NOTE: At this point the steamline Delta-P safety injection is in a normal operating mode. Toreturntgehighsteamflowcoincidentwithlowsteamgeneratorpressure or low-low avg to normal, perform the following steps.
- 47. Move 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.
O Performed by: / 1 Verifie.d by: / I-
- 48. Move test trip switch FS512B'in R-3 to the normal position and verify the ember light goes out and XA-55-6B/2 will clear.
l Performed by: / Verified by: / I
- 49. Remove the 120-VAC source from terminals M-3 and M-4 in R-13. Retermi-i nate wire on M-3.
Performed by: / Verified by: /
- 50. 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: / m 34 9
SQNP SPECIAL TEST 8 Page 10 of 11 Rev. 1 O
.u APPENDIX D
- 51. 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: /
- 52. Move test trip switch TS432D in R-10 to the normal position and verify i the amber light goes out and XA-55-6A/30 will clear.
Performed by: / Verified by: / J
- 53. Remove the 120-VAC source from terminals M-3 and M-4 in R-6. Retermi-nate wire on M-3.
Performed by: / l Verified by: /
- 54. Hove 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.
f.3
\J l Performed by: / _
' Verified by: / .
k
- 55. Remove the 120-VAC source from terminals M-3 and M-4 in R-2. Retermi-nate wire on M-3.
l Performed by: / Verified by: / i 4
- 56. Move 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: / l l l ( 35 s
SQNP SPECIAL TEST 8 Page 11 of 11 Rev. 1 APPENDIX D
- 57. Remove the Temporary Alteration Tage on the following test trip switches:
RACK TEST SWITCII TEMP ALT. NO. I i R-7 PS515A / 1 R-7 PSS15B / j R-12 PSS16C / R-12 PS516D / R-8 PS525B / R-8 PSS25A /
*R-11 PSS26D /
R-11 RSS26C / 1 R-2 TS412D / R-6 TS422D / i R-10 TS432D / R-13 TS442D / R-3 FS512B / R-3 FSS22B /
- 58. Remove the jumpers and the Temporary Alteration Tags from logic cards A216, test point 1, to the logic ground on the logic test panels in R-47 and R-50.
I R-47 Panel Performed by: / , Verified by: / t i
$ 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. e
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36
SQNP SPECIAL TEST 8 Page 1 of I Rev. I f~ V APPENDIX E Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. 0 4 'S E e :
- Po: s8" u h . .e g c $$$0$ $ o 3
OSo 780 0 Y o 8 gNe 3 M E "%
. . . t 8
- OOEOOI 3 UEUUU* 3 Y<
a m .-s .-< .-s EEE~ N B B22%3 T c O B 8 3 B B " 8 [m n8 G '
& 3 e e a ku e a 8 TECIINICAL SPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment HI Pre sure 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 OTAT (3.3.1) Inoperable because of low flow 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) bypassed X X X X X X X X X X HighSteamflowcoincidentglw/lowsteamline 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 1111 1 ( 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 p Reactor Coolant Loops Normal Operation (3.4.1.2) X X X X X X X X V
l 1 37
SQNP SPECIAL TEST 8 Page 1 of 1
. Rev. I 1 . Di > s '1
TABLE 1 l Loop Flow and Core AT for I' Various Power Levels and I Isolation Configurations l 1 (Computer Estimates) I t No. of Loops Operating (Nat. Circ.) l 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 W 1.5% L= 4.7 L= 5.2 L= 5.9 L= 7.5 AT = 21.4 AT = 26 AT = 34 AT = 54 l 2% L= 5.2 L= 5.7 L= 6.5 L= 8.2 AT = 26 AT = 31.4 AT = 41 AT = 65.4 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 i N 3% L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE: L is % of 97,000 gpm flow through operable loop. AT = Loop AT in 'F.
%.)
38 i i n 4 = w a .. i . f
w - ~ - - - ~ -a- - ..- - w s.a ,_-s - - - m_---_._sa,- -.-a- -
+,,,-asa a,. z,. . + , - . -
a-_. --a as- - -. - - - . - - d 4 0 1 I t i I SPECIAL TEST NO. 9A FORCED CIRCULATION C00LDOWN i ( i ! t l O
. . . _ , . , _ , _ . __ ._____ _ . . . _-._-.__...._.s. _ . _ , .. _._ - _ _ _ _ _ _. . , ..-_ ._ _ . _- _ _ , . . .
SQNP
; SPECIAL TEST 9A 8 Page 1 of 1 j
Rev. I t / i \l I FORCED CIRCULATION C00LDOWN Table of Contents
- PalLe Special Operator Instruction 1 Test Description 2 1.0 OBJECTIVES 3 2.0 PREREQUISITES 3 3.0 PRECAUTIONS 8 4.0 SPECIAL TEST EQUIPMENT 9 5.0 INSTRUCTIONS 9 DATA Si[EETS 15
{ ) CALCULATION SIIEET 17 APPENDIX B - Deficiencies 18 APPENDIX C - Power Measurement Technique 19 l APPENDIX D - AT Correction Determination 30 APPENDIX E - Safeguard Blocking Procedure 33 APPENDIX F - Technical Specifications Exceptions 46 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 47 I
/'~\
\ /
SQNP SPECIAL TEST 9A Page 1 of I c_s Rev. 1 U SPECIAL OPERATOR INSTRUCTION 1 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 l Unexplained Pressurizer Pressure Drop B 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
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
I I
.I a .s . _ ,.
j I i
SQNP SPECIAL TEST 9A Page 1 of 1 Rev. 1
~/
FORCED CIRCULATION C00LDOWN Test Description i t i This test will generate a correction factor which will be applied to I the excore detector outputs in order to compensate for PV downcomer j shadowing during a cooldown from ~ 550 F to - 450 F. I { The RCS will initially be ~ 3% power, in forced circulation. p cooldown'via steam dumps will be initiated and continue until avg
}
is approximately 450"F. During the cooldown primary side calorimetrics will be performed, movable detector integral power calculations performed, and excore detector data obtained simultaneously. Power should be maintained as constant as possible using the results of the primary side calorimetric and integral power calculations. Data reduction will be on a continuous basis. After reaching ~ 450 F the plant will be allowed to heat up and additional data will be obtained. Data reduction will average the cooldowa and heatup data and generate
'D an excore detector indicated power correction factor as a function of the average cold leg temperature.
i
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2 : (
SQNP
. SPECIAL TEST 9A Page 1 of 12 . Rev. I r) 1.0 OliJECTIVES l
Determine an excore detector indicated power correction factor as a function of the average cold leg temperature.
! 2.0 PREREQUISITES I
2.1,.The following initial conditions exist:
'2.1.1 Reactor power is at approximately 3% RTP.
l
/
2.1.2 Forced circulation on all four loops is established.
/
2.1.3 Steam generators are being fed by the auxiliary feed water system. Level is being maintained at approximately 8 33%.
/
2.1.4 Steam generators are steaming via the condens or atmos- . pheric steam dumps. (Preferred is to condenser for SG pressure equilization). '
/
2.1.5 Pressurizer pressure control in automatic and maintaining normal operating pressures. l / i ., 2.1.6 RCS temperature is approximately 550'F.
/
2.1.7 Shutdown banks are fully withdrawn and control banks are above their insertion limit. Rod control system is in manual. (Preferably all rods are out and control bank D is at ~ 160 steps).
/
O v 3 L
SQNP SPECIAL TEST 9A Page 2 of 12
' Rev. 1 j 2.0 PREREQUISITES (Continued) 2.1.8 Pressurizer level control in AUTO and maintaining approxi-1 mately 25% level.
/
l 2.2 The RCS and pressurizer boron concentrations are within 20 ppm. l 2.3 Sufficient water is available to provide makeup for the expected cooldown to 450 F.
/
2.4 Set up the following test signals on brush recorders. NOTE: Exact recorder / channel / parameter matching is not necessary. 2.4.1 Recorder No. 1 Channel Parameter Test Point Rack ()g 1 Przr Pressure PP/455B R1 2 Przr Level LP/459B R1 3 Lp 1 HL Temp TP/413E R2 4 Lp 2 HL Temp TP/423E R2 5 Lp 3 HL Temp TP/433E R2 6 Lp 4 HL Temp TP/443E R2 I / 2.4.2 Recorder No. 2 l Channel Parameter Test Point Rack i 1 LP 1 CL Temp TP/413F R6 2 LP 2 CL Temp TP/423F R6 3 LP 3 CL Temp TP/433F R6 4 LP 4 CL Temp TP/443F R6 5 LP 1 Flow FP/414B R1 6 LP 2 Flow FP/424B R1
/
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SQNP
- SPECIAL TEST 9A Page 3 of 12 Rev. 1 O 2.0 PREREQUISITES (Continued) i 2.4.3 Recorder No. 3 Channel Parameter Test Point Rack i
1 LP 3 Flow FP/434B R1 i 2 LP 4 Flow FP/444B R1
' 3 LP 1 SG Level LP/519B R5 4 LP 2 SG Level LP/529B R1 5 LP 3 SG Level LP/539B R1 g
6 LP 4 SG Level LP/549B RS
/
i 2.4.4 Recorder No. 4 j i Channel Parameter Test Point Rack
; I LP 1 SG Press PP/516B R12
{ 2 LP 2 SG Press PP/526B Rll 3 LP 3 SG Press PP/536B R11 4 LP 4 SG Press PP/546B R12
/
(-~
\
; 2.4.5 Recorder No. 5 .
l '
. Channel Parameter Test Point Rack 1 Aux F"d Flow to SG #1 TP-13 1-L-11B 2 Aux Fd Flow to SG #2 TP-13 1-L-11A i 3 Aux Fd Flow to SG #3 TP-12 1-L-11B 4 Aux Fd Flow to SG #4 TP-12 1-L-11A 2.4.6 Record the following parameters on the reactivity computer
; recorders.
t (a) Flux ! (b) Average wide range TTc Id i (c) Average wide range hot j (d) Average steam generator pressure (e) Reactivity l l (]I 5 6
SQNP SPECIAL TEST 9A Page 4 of 12 Rev. 1 2.0 PREREQl!! SITES (Continued) 2.5 Trend the f ollowing parameters on the process computer at ~ 5-minute j intervals.
; Wide range cold legs T0406A i T0426A J
T0446A t T0466A
, Wide range hot legs T0419A j T0439A T0459A T0479A
- Steam generator levels LO403A i LO423A I LO443A LO463A Loop Flow F0400A F0420A F0440A F0460A l
f 2.6 Obtain the wide range AT correction factors using Appendix D.
/
2.7 Perform the reference (REF) portion of the primary calorimetric Appendix C and a M/D trace simultaneously, Appendix C, Part B. Use the output of the primary calorimetric to set the M/D Power Monitor Program. i
/
4 2.8 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix E.
/
2.9 Verify the input logic of safety injection on high steam line AP has been blocked in accordance with Appendix E.
/
1 /- 6
SQNP SPECIAL TEST 9A Page 5 of 12 Rev. 1 2.0 PREREQUISITES (Continued) 2.10VerifytgehighsteamflowcoincidentwithlowS/Gpressureor low-low avg input to safety injection has been modified in accordance with Appendix E.
/
i i 2.11 Verify the following U.H.I. isolation valves are gagged.
, FCV-87-21 /
FCV-87-22 / FCV-87-23 / FCV-87-24 /
< 2.12 Recalibrate the bistables supplying the low pressure signal to
! the high steam flow S.I. logic in accordance with Appendix E.
/
O 2.13 Intermediate and power range 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 / i 2.14 CVCS is aligned to supply auto makeup.
/
E I i 7 l i
SQNP SPECIAL TEST 9A Page 6 c' 12 Rev. 1 3.0 PJJECAUTIONS, LIMITATIONS, AND ACTIONS 3.1 Do not exceed 5% RTP. Caution should be used in maintaining the desired power leve: because of flux shadowing of the excore detec-tors. Don't depend on the excore detectors. Use as many methods as possible to determine actual core power. I 3.2 During the cooldown the isothermal temperature coefficient will be small but may be of either polarity. Care should be taken when changing reactivity using control rods or boron concentration g because at some point the temperature cofficient polarity could change. 3.3 Maintain control bank D at ~ 160 steps if possible. This same { suggested minimum limit will be used during the natural circula-tion test. This height will minimize the effect of rod shadowing of the excore detectors and insure uniformity between forced and natural circulation test. 3.4 Mien operating below 525 F, ensure control bank D position remains at 2 100 steps. Should this limit be reached during the cooldown boron concentration will have to be increased. 3.5 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. I g 8
SQNP SPECIAL TEST 9A Page 7 of 12 Rev. 1 09 4.0 SPECIAL TEST EQUIPMENT e IDENTIEICATION CALIBilATION INSTRUMENT SPECIFICATION NUMBER VERIFICATION
, s l l 1
Reactivity computer Westinghouse { and Associated ( Equipment ',' i (4) 6-channel recorders Brush 260 or Equivalent
-(2) DVM's Fluke (1) Recorder HP 7100B or Equivalent
.l l l l 1 If test instruments are changed during this test, the instrument infor-mation must be recorded here and an entry made in the chronological log book explaining this change. , s J.. 9 i y-e e 'm+ ^*-
..,,v. - -- ,.,,.,.,,.-4. , .--.y ,y , y , v r - -=w ar-tre--me=-=
SQNP SPECIAL TEST 9A Page 8 of 12 Rev. 1
,, 5.0 INSTRUCTIONS NOTE: Perform SI-38, SI-48, and SI-127 periodically during the cooldown.
5.1 Coo _ldown NOTE: Depending on rod position and the magnitude and polarity of l the isothermal temperature coefficient dilution and/or horation may be required.
/
5 g 5.1.1 Verify that the system is in equilibrium with respect to power, RCS temperature, pressure and boron concentration. I Pressurizer pressure ~ 2235 + 50 psig S/G pressure ~ 1005 psig RCS-PRZR boron concentration within 20 ppm Successive boron concentration within 10 ppm Reactivity is approximately zero and constant
/
3.1.2 Start the test recorders on slow speed (Smm/ min). Record on the charts, the date, time, recorder ID, parameters measured, measurement range, test being performed and name I h of person recording data.
/
~
5.1.3 Start process computer trend block. I 5.1.4 Obtain a thermocouple map, per Appendix C, Part C, and repeat every 10 F during cooldown.
/
e 5.1.5 Record excore detector data on Data Sheet 1 and repeat every 10 F. One of the P.R. channels is connected to the reactivity computer so, record the Keithley amplifier output for that particular channel on Data Sheet 1. NOTE: Mark out "N- " and write in "KA."
/
10
SQNP SPECIAL TEST 9A Page 9 of 12 Rev. 1
/x d 5.0 INSTRitCTIONS (Continued) 5.1.6 Initiate the program for obtaining M/D trace data and re-cord on Data Sheet 2. Repeat every 10 F during cooldown.
Use applicable portions of Appendix C.
/
5.1.7 Initiate the primary side calorimetric and repeat every 10 F. Use applicable portions of Appendix C.
/
5.1.8 Initiate a cooldown by slowly increasing the rate of steam 9 dump and proceed to approximately 450"F core inlet tempera-
' ture. The rate should be approximately 30 F per hour with stabilized plateaus approximately every 10"F during cooldown.
l / 5.1.9 Use the control rods and soluable boron as necessary to maintain core power approximately constant. Core power is determined by the primary side calorimetric and the p M/D trace data. Refer to Appendix C, Parts A and B. 0 NOTE: Control bank D should be maintained at approximately 160 . steps if possible. .
- 5.1.10 Upon reaching approximately 450 F terminate the cooldown and allow the RCS to come to an equilibrium condition.
Continue to obtain data.
/
5.2 Heatup j 5.2.1 Allow the RCS to heatup at the same rate indicated above. , Obtain the same data at the same temperature plateaus.
/
5.2.2 Upon reaching approximately 550 F terminate the heatup and allow the RCS to come to an equilibrium condition. After one set of data has been obtained at ~ 550 F the test is
- over. Attach ALL data to this test.
.m
\
11 J
- m. . -.. - .
'SQNP SPECIAL TEST 9A Page 10 of 12 Rev. I m
INSTRUCTIONS (Continued)
^
5.0 5.2.3 Return the bistables supplying the low pressure signal to the high steam flow S.I. logic to their original setpoints in accordance with Appendix E unless the next test to be performed requires this modification to be made. If this in the case, disregard this step, place N/A in the signa-ture line, and initial.
/
l 5.2.4 Restore the high stc9m flow coincident with low S/G pressure or low-low avg input to safety injection in accordance with Appendix E unless the next test to be performed requires this modification to be made. If this is the case, disregard this step, place N/A in the signature line and initial.
/
i 5.2.5 Remove the block of the input logic of safety injection 1 on high steam line AP in accordance with Appendix E I 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. t / 5.2.6 Remove the block 'of automatic actuation of safety injec-tion in accordance with Appendix E unless the next test to be performed requires the block to be installed. If i this is the case, disregard this step, place N/A in the signature line, and initial. { l t t .
- Remove the gags from the following U.ll.I. isolation valves 5.2.7 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 / FCV-87-22 / FCV-87-23 / FCV-87-24 / s 12
SQNP SPECIAL TEST 9A Page 11 of 12 Hev. 1 '/ 5.0 INSTRUCTIONS (Co..tinued) 5.2.8 Heset the intermediate and power range high level reactor trip setpoints as indicated by the tent engineer in accord-ance with Appendix C and D of SU-8.5.2 unless the next test to be perf ormed requires this adjustment.. If this is the case, disregard this step, place N/A in the signature line, and initial. Power Hange / 1 Intermediate Range / I' 5.3 Data Heduction i NOTE: This reduction must be performed and an excore detector indi-cated power correction factor as a function of temperature determined before proceeding to the NC cooldown portion of this test.. 5.3.1 Use both the cooldown and heatup data. If for some reason
' the data was not obtained at exactly the required tempera-ture plateaus mark through that. temperature and record the actual measurement temperature.
b \- Excore Data: Sum the top and bottom currents for the 3 . (Data Sheet 1) channels in service and enter under sum. The Keithley amp output should be in sum - column. Transfer the data to the Calcula-tion Sheet. H/D Data: Transfer the calculated power level to the (Data Sheet 2) Calculation Sheet. Primary Calor.: Transfer the power level obtained from the (Appendix C) primary calorimetric to the Calculation Sheet. , Average Power: Using the incore data and primary calori-(Calculation metric data determ#.ne the actual core power Sheet) at each temperature plateau. A straight average should be used unless one method or the other proves unreliable. , I Power Normalization: Divide the average power obta'ined at to REF Average Power each temperature plateau by the aver-(Calculation Sheet) age power obtained at the reference (REF) condition, 550 F. This factor will in turn be used to correct the excore outputs.
\/ ~
13 3
= _ - . .
SQNP SPECIAL TEST 9A Page 12 of 12 Rev.'l
. 5.0 INSTRUCTIONS (Continued)
Power Corrected: Divide the measured excore detector cur-f.xcore Currents & rents by the power normalization factor. p Keithley Amp This in effect corrects all data for
' Output fluctuations on core power. The resulting currents then will only be a function of the cold leg temperature.
Excore Current: Divide the power corrected excore cur-Multiplier as a rents obtained at each temperature
; function of Cold plateau into the excore current ob- ' l Leg Temperature: tained at the REF condition. NOTE: the factors should increase as T decreases.
r plot the correction factors as a function j of T for each detector. The plots will c be used in the natural circulation cool-down phase of this test. i 4 A 6 f 4 9 0 14
! r - : ; O A 9 T S1 E E m u S E Tf m / o o L t A1I t I 4 o 4 B 7C SEgv e . - l QP ae D D N SSPR p o T C C m u S m y B B o b 3 t 4 t d
- - o e n N B w e
o
= i t
i v e A A i p R s o o P T n : o n I! T i o E t i i t m
- 1 E s o
i s S u S T P o E A P 1I T k E A n a k n m S D 0 - A T A E R O B n w B l a o 2 4 o t t o e D C o N B X d r
- E t t A ,
u n C h o C p S C R o T
/
m u S n o
- 1 t
t 4 o
- B N
p o T : y B n p e m 0 0 0 0 0 0 0 0 0 0 0 : k
. e 5 4 3 2 1 0 9 8 7 6 5 t a o T 5 5 5 5 5 5 4 4 4 4 4 n T N r //// / /////// e e e e m a p t w m m t a a o i o a M D P T C D o G 1 *
. _ _ . . __. _ . . . _ . _ _ m . _ . - __ _ _ _ _ . . _m.... _ _ .. m -
. . - . . . R._ .
.- D.
' ~
() ( . SQNP ; SPECIAL TEST 9A Page 1 of 1
- - DATA SHEET 2 Rev. 1
- LOW POWER MOVABLE DETECTOR FLUX MAP DATA Initial Final RCC Bank /RCCA Fositions (steps)
SDA SD3 SDC SDD Map No.:' RCS Tavg( F): IR-35 (amps): CA CB CC CD Date: Unit: IR-36 (amps): RCCA ( ) Controlling RCCA/RCC Bank: l Calculated Control RCCA i Power P-250 RCC Bank Time of Detector - Core Location Detector - Range Level UO906 Position F j RECORD A B C D E F A B C D E 550 540 e 530 520 510 500 490 480 470 t 460 450 , Detector A B C D E F Remarks: Detector Voltage Recorder Pot. l Data Taken By: Data Checked By: :
SQNP SPECIAL TEST 9A PaF" I of 1 Rev. I f-
%s CALCULATION SIIEET APPROXIMATE AVERAGE COLD LEG TEMPERATURES ( F)
REF. 510 500 490 480 470 460 450 Parameters 550 540 530 520 Ie # Novable Detector 1 (% RTP) Primary Calorim_i.ric 2 (% RTP) Average Power ' 3 _%( RTP) Power Normalization 4 1.00 _to REF condition N-Excore Currents 5 and N-
' Keithley Amp N_-
Outyut KA l Power Corrected N-Excore Currents N-l 6 3 Keithly Amp N-l KA Output N- 1.00 7 Corrections N- 1.00 Factors N- 1.00 KA 1.00 r Remarks: 1 i i k e Calculated by: Reviewed by: 17
SQNP SPECIAL TEST 9A Page 1 o f .1 Rev. 1 7 i
\
APPENDIX B Test Deficiencies # Test Detiilency e 1 l 1(econunended Resolution l I Final Resolution Originator / Signature Date
.PORC Review of Final Resolution l
Date I f'; v Approval of Final Resolution / Plant Superintendent Date i 1 18 l I
SQNP SPECIAL TEST 9A Page 1 of 11 Rev. 1 N _j APPENDIX C Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only) f 1. Reference (~ 550 F) Calorimetric (Before NC test) a) Output used to adjust M/D Power Monitor Program's power conversion constant. I
- 2. Non-reference Temperature Calorimetric (Cooldown) a) Output used at every temperature plateau as a continuous core power monitoring scheme.
b) Output is used in conjunction with the cuput of the M/D Power Monitor Program to assign a best estimate core power at each temperature plateau. The powers are used to nor-malize the excore detector outputs which in turn are plotted i as a function of the core inlet temperature. B. M/D Power Monitor Program c.
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric will give a percent power output; this output must be input to the M/D Power-Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.
- 2. Power Monitoring 1- 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 l calorimetric it will be rerun up to once every 2 minutes 3 or as necessary to continuously monitor core power.
1 1 a 19
_ . _ . . __ . . . _ . _ . _ _ . _ _ _ _ . ~ _ _ _ _ . . . . . _ . - _ . ___ __ _ _. . _ _ __ _ _ _ _ _ _ SQNP SPECIAL TEST 9A Page 2 of 11 I Rev. 1 O. . APPENDIX C l J CORE POWER DETERMINATION I . PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation) 1 C.1 Use two DVMs and measure the voltage at the test points
}
j specified for each loop as rapid as possible. ; I i C.2 Calculate the AT; multiply that AT by the specific heat and i the Westinghouse best estimate flow rate of the core average i temperature (Tabic C-1). (Special Test No. 9 uses wide range :
' AT so a correction factor is required to compensate for pump 3 f heating, refer to Appendix D of ST-9A). !
l C.3 Sum the loop heat rates and convert to a percent reactor power. , 4 The output is used in Part B and on the Calculation Sheet. t a !a I i i 9 l' (~)'
~.
20 L i
, _. _-.---_....-__-,--.-_.,__.----_m.__--______.,._,.,
SQNP l SPECIAL TEST 9A Page 3 of 11 l Rev. 1 1 APPENDIX C ! i l Core Power Determination I PARf II: ft/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 l I
, below for the flux map.
Drive 10-Path Position Core Location A 10 L-5
! B 10 L-11 I
- 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 '
i upon low-power physic.s 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. I b) With all 5 path selector switches set to normal, run a flux i ' 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. e) Enter these detector normalization constants into the P-250 as shown in the table below. 21 I
- n,
SQNP SPECIAL TEST 9A Page 4 of 11 Rev. 1 / k# APPENDIX C Core Power Determination PARE ft: (Continued) 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 current.
! Update as required.
l
- Address Value Function Set the 3 >wer normalization l factor K0901 1 Selects the modified " Flux
__K,5525 1 Map Print" program K0900 0 Initiated Pass Number Calibration Constant for K0864 Variable (I) for M/D Power Monitor j (I) Variable: The value entered is a ratio of the Primary Calorimetric Indicated Power (Item 8 on Data Sheet C.1) to the M/D calculated power (UO906) times the current value entered in (K0864).
! If no value has been entered into (K0864) enter
! 0.25.
'. Item #8 Data Sheet C.1 New (K0864) = Current (K0864) x (UO906)
- 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 individual detec-
~
tor normalized integrals are also printed.
~.,
)
22 Y
SQNP SPECIAL TEST 9A Page 5 of 11 Rev. 1 APPENDIX C PRIMARY SIDE CALORIMETRIC DATA SIIEET C.I Loop 1 05 66 #1 #8
^ ~~$ (~~ f2 ll3 04 L PFlow LoopRxPwr Approx. IIL CL AT L Pf3y
#4+c3 f.(2) #5xCp #gx#7 10f4)
RCS Temp R2/TP-gig) R6/TP-41g) #2-#3 Volts F F F Btu /lb lb/hr 10 Btu /hr
' F Volts F a
550(REF) 540~~
! @0 t 520 ! SE ! 500 490
! 480 i 2.70 460 450_ o k ' 460 . 470 4 ~50 4 . hu __ 500 - 510 ~ 520 '
; 530 540 5,5,0_
t 4 From appropriate scaling document. From Appendix D. (3)Cg Irom Table C-1 Remarks: 4)m from Table C-1 Data by: / Checked by: / l 23 j
SQNP SPECIAL TEST 9A Page 6 of 11 Rev. 1
)
- APPENDIX C PRIMARY SIDE CALORIMETRIC DATA SilEET C.1 Lo0P 2
#13 #14 #15 #16
.__.__#9 #10 #11 #12 LoopRxPwr CL AT L pAIJ) LoopFlow Approx. IIL
#12+c.f.(2) #13xCp #g4x#15 RCS Temp "F
R2/TP-42g) R6/TP-42g) #10-#11 Volts F Volts F F F Btu /lb 10f4) lb/hr 10 Bru/hr 5'>0 (REF) 540 530 520 51 1. 500 490 480_ _4/0-~ 460 { 0_,_ 460 470 480~ 490 500 510 520 530 l 540 550 k I Remarks: Data by: / Checked by: / 24 9 L
SQNP SPECI AL TEST 9A Page 7 of 11 Rev. I i APPENDIX C PRIMARY SIDE CALORIMETRIC 4 DATA SiiEET C.1 i Loop 3 t/22 #23 #24
//17 #18 ~ 19 t* #20 #21 L pFlow LoopRxPwr Approx. Ill CL AT L P Od) 4 RCS Temp R2/TP-41g) R6/TP-43gg'} #18-#19
#20+c.f.(2) #21xCp f4) #g3x#24 "F Volts "F Volts F F F Btu /lb 10 lb/hr 10 Btu /hr l
l l 550(REF). . - - _ 530 . 520 4 510 ? Sd6 490 i 480 -~ NO ~ l E0 ! Eso 4 i ~ EO~ " l 470 ' ~ ~'
& &O. .. ... ... _-
I bU 510
.N Y_
1 1 520 I h'30 l-b'4I) 550 J 1 .i r . Remarks: 1 l Data by: / i i Checked by: _
/
l i O. 25 a
- 4. .
_ _ _ , . . _ . _ . , . . . . . _ _ _ - , - __ __ _ _ _ _ _ _ _ _ _._,___i__ _
SQNP SPECIAL TEST 9A Page 8 of 11 Rev. 1 APPENDIX C PRiffARY SIDE CALORI?!ETRIC DATA SifEET C.I Loop 4
' #29 #30 #31 #32
" T2T ~ (12 6 #27 #28 b" P O L pFlow LoopHxPwr Approx. IIL CL 4T
#28+c.f.(2) #29xCp(I3) #g0x#31 4
RCS'['emp F H2/TP-44}8'T) Voltr. "O H6/TP-44g') #26-#27 Volts F F "F Btu /lb 10f4) lb/hr 10 Btu /hr 550(HEQ, __
$40 5'10 520 ----
$00 j .
4ii0
. ! Xn~b 470 ~ ~
l h60 1 450 i g
/^J
\- ESIO
- g. __
480
' T90 500 510 , 520 ! 10 l'
[40 j $50 l t Remarks:
- Data by: /
Checke1 by: / 0 26
.t-p f
- 3QNP SPECIAL TEST 9A Y.' Page 9 of 11 Rev. 1
. i 's_)
\
APPENDIX C PRIMARY SIDE CALORIMETRIC DATA SifEET C.1 Total
#35 #36
#33 #34 Total Reactor Power Reactor Power % Reactor Power Approx.
#34 x 0.29307 #35 x 0.02932 HCS Temp. #8 + g16 + //24 + #32 %
10 Btu /hr MWt "F
"SO(REF) i h40 530 520 510 500 ~
2.90 ~
' 58F-h!ON ..
l 42 i 4 ISO 460 410 bbN - 49_0 _ 500 510 520 l $3- .
~-
i Remarks: Data by: / Checkeel by: / l 27
SQNP SPECIAL TEST 9A Page 10 of 11 Rev. 1 (;/ ) APPENDIX C PRIMARY SIDE CALORIMETRIC Table C-1 Temp. Cp( ) fa F Btu /lb. F #m/hr 7 560 1.270 3.6239 x 10 550(REF) 1.246 3.6765 x 10 7 540 1.221 3.7254 x 10 7 530 1.202 3.7729 x 10 7 520 1.183 3.8179 x 10 7 510 1.168 3.8621 x 10 7 500 1.152 3.9044 x 10 7 490 1.140 3.9436 x 10 7 480 1.127 3.9837 x 10 470 1.117 4.0215 x 10 7 460 1.107 4.0589 x 10 j
. 450 1.098 4.0949 x 10 7
440 1.089 4.1294 x 10 i k ( }These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia.
's /
28
. ~ _ __ . . . _ = _ -. --- _ .- .. - - _. .. -.. _ _ - _ . . . - - . . . . - - .
SQNP SPECIAL TEST 9A Page 11 of 11 Rev. 1
.O APPENDIX C Ag= D
- N= DN* N= FN*
N FE
- A =
E Dg= C E*- E* E= N = 1.00 3 i A A N = N = "A E = N li~ B N N
= B"E =
N' = CT AN C N N Ng =A{ _t
= CE =
. N,= = DE =
E i icN P'N
= =
Ny= 4 N N Definitions: A,B,C' y g N, FN = Normalized integral from summary map for each N N' detector in a normal path in the first pass 1 Normalized integral from summary map for each j A,B,C,D,E,F E E E E E E
=
j detector in an emergency path in the second pass l 1 N,N' g B C, ND , N E ' F
= Detector normalization factor for each detector f f
t Remarks: ,
? .I
- r i
1 Data By: Date ; i i I 1 i A I U j 29 W
- ~ - - - - - - * - - - -- ,. ,_ _m.,y ,_,_,, , ,, ,, , , _ , , ,
SQNP SPECIAL TEST 9A Page 1 of 3 Rev. 1 LJ APPENDIX D WIDE RANGE AT CORRECTION D.' Use two DVM's and measure the voltage at the test points specified for each loop as rapidly as possible.
' D.2 Use the appropriate scaling to convert the DV voltages to F.
D.3 The correction factor (c.f.) determined in item 5 is used on Data Sheet C.1
+ to correct the calculated wide range AT for the AT across the core gener-ated by the Reactor Coolant Pumps.
t, I t I e l
,L]s 30
SQNP SPECIAL TEST 9A Page 2 of 3 Rev. 1 APPENDIX D WIDE RANGE AT CORRECTION i ___. LOOP 1 1 Item Parameter Location Heading Parameter i No. Rack / Test Point Volts F
- Loop 1 1 Ilo t Leg R2/TP-413E (1) t 1"0P 1 (1) 2 Cold Leg R6/TP-41JF Loop 1 3 W.R_. AT Item 1-Item 2 Loop i
_4 N.R. AT R2/TP-411G (I) W.R. AT 5 CorrectionFactor Item 4-Item 3 c.f.= LOOP 2 Loop 2 y) 1 Ilot Leg R2/TP-423E Loop 2 Cold Leg R6/TP-423F () _2 1,oop 2 3 W.R. AT Item 1-Item 2 Loop 2 - 4 N.R. AT R6/TP-421G (1) W.R. AT 5 CorrectionFactor , Item 4-Item 3 c.f.= I (' Scaling Document. g. / $ p 31 s
SQNP ; SPECIAL TEST 9A ) -) Page 3 of 3 Rev. I l ~
, APPENDIX D l.
. WIPI RANGh AT CORRECTION i-i
; 5 l Il- ltem Pa rameter Location LOOP 3 Reading Parameter
[ _No. Rack / Test Point Volts F ; Loop 3
.; (1)
_I _ llot Leg R2/TP-433E ,
- g. Loop 3 (g)
_ Cold Leg R6/TP-433F 2 Loop 3 3 W.R. AT Item 1-Item 2
; i Loop 3 1
4 N.R. AT R10/TP-431G (1)
, W.R. AT 5 CorrectionFactor Item 4-Item 3 c.f.=
I ~ LOOP 4 Loop 4 llot Leg _ _ ( _1 . R2/TP-443E i - Loop 4
! 2 Cold 1.eg R6/TP-443F
(} ' Loop 4 3 W.R. AT ltem 1-Item 2
*' , ~
Loop 4 4 4 N.R. AT R13/TP-441G (1) { W.R. AT 5 CorrectionFactor item.4-Item 3 c.f.= 3 (I) Scaling Document. i i 1 01 32 I
~.
J
SQNP SPECIAL TEST 9A Page 1 of 13 Rev. 1 (J'l APPENDIX E Safeguard Blocking Procedure The first step blocks automatic initiation of a safety injection. The safety injection alarm, manual S.I handswitch, and the reactor trip portion of the protection logic will remain in operation. If conditions exist that would l normally initiate a safety injection; (1) the safety injection alarm will initiate telling the operator that the condition exists and what the problem l is. (2) a reactor trip will take place automatically. (3) a safety injection van be initiated manually from the switch in the control room if conditions j 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. l R-47 Panel Performed by: / Verified by: / l 4 i R-50 Panel Performed by: / g w, Verified by: / '
\mI / .
i 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 te.sts 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, I
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 j the amber light above the switch comes on.
I 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 (O,
~.
33 9
SQNP SPECIAL TEST 9A Page 2 of 13 Rev. 1 '- APPENDIX E ground will already be made up through the trip switch). The
- wire on the rack side of the terminal block must be lifted and f
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. i
- 4. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-9 and L-10 and verify 1-XX-55-6B/25 is clear.
Performed by: / Verified by: /
- 5. Nove test trip switch PS-515B in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 6. Lif t and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/27 is clear.
Performed by: / l Verified by: /
- 7. Move test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: / i
- 8. Lift and tape the wire on the rack side of terminal L-5 in the rear of 1-R-12. Apply 120-VAC source to terminals L-5 and L-6 and verify 1-XX-55-6B/73 is clear.
Performed by: / Verified by: /
~_
34 1
SQNP SPECIAL TEST 9A Page 3 of 13 Rev. 1 (D
~# APPENDIX E
- 9. Hove test trip switch PS-516D in 1-R-12 to the trip position and verify the amber light above the switch comes on.
t Performed by: / Verified by: / 1 [ 10. Lift and tape the wire on the rack side of terminal L-7 in the rear of j 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: / i 11. Flove test trip switch PS-525B in 1-R-8 to trip position and verify the amber light above the switch comes on. Performed by: / Verified by: /
- 12. 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
(' ) l-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! / s
- 14. Lif t and tape the wire on the rack side of terminal L-9 in the rear of I
l-R-8. Apply 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: / b s v l 35
-- . . . , , - -r-,- - ,,--
- c e
SQNP SPECIAL TEST 9A Page 4 of 13 Rev. 1
\~T' . APPENDIX E 4
[
- 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.
,l Performed by: /
Verified by: / 9
- 16. Lift and tape the wire on the rack side of terminal L-7 in the rear g
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: / i 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: / t Verified by: / i
- 18. Lift and tape the wire on the rack side of terminal L-5 in the rear I) of 1-R-11. Apply a 120-VAC source to terminals L-5 and L-6 and verify l-XX-55-6B/50 is clear.
Performed by: / Verified by: / Temporary Mgdification to High Steam Flow Coincident with Low S.G. Pressure or Low-Low avg Safety Injection
. 19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be c1 cared.
; Performed by: /
Verified by: / NOTE: If the alarms will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the problem corrected. x, 36
SQNP SPECIAL TEST 9A Page 5 of 13 Rev. 1 .; APPENDIX E 20 Move test trip switch TS412D in R-2 to the trip position and verify the amber light above the switch comes on. 3 Performed by: / i Verified by: /
- 21. Lif t and tape the wire on the rack side of terminal M-3 in the rear j of 1-R-2. ' Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / 1 Verified by: /
- 22. Hove test trip switch TS-422D in R-6 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: / _ i
- 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: / I 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 o f 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: / (\ u) 37
SQNP SPECIAL TEST 9A Page 6 of 13 Rev. 1 s% APPENDIX E
- 26. Hove test trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
6
)
Performed by: / j Verified by: / t
- 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 in R-13 ,
I and verify XA-55-6A/30 will clear. l Performed by: / i Verified by: / NOTE: TheTavg 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 FS522B in R-3 to the trip position and verify the i amber light and annunciator XA-55-6B/9 come on.
Performed by: / l Verified by: / 1 NOTE: These two trips will supply the 2 out of 4 logic required to get a Safety Injection Signal. m 38
SQNP SPECIAL TEST 9A Page 7 of 13 Rev. 1 APPENDIX E
- 30. Apply Temporary Alteration Control Tags forms to all the above test trip switches to ensure that they remain in the trip position.
Damage to the bistable could occur if the switch is moved back to the normal position. Record the temporary alteration numbers below: RACK TEST SWITCH TEMP ALT. NO. R-7 PS515A / R-7 PS515B / R-12 PSS16C / R-12 PSS16D / R-8 PSS25B / j R-8 PS525A / l R-11 PS526D /
. R-11 RS526C /
R-2 TS412D / R-6 TS422D / R-10 TS432D / P) s, R-13 TS442D / i R-3 FS512B / I R-3 FS522B /
^
The following step reduces thy setpoint of the S/G pressure input to S.I. 4 to trip at 350 psig allowing avg to be reduced to 450 F.
- 31. Recalibrate the following bistables to the indicated setpoints and attach Temporary Alteration Control Tags.
Panel Bistable Setpoint R-12 PS-1-5A (PB516A) 350 psig Decreasing (21.66 MA Loop Current) Performed by: / Verified by: , / R-11 PS-1-12A (PB526A) 350 psig Decreasing (21.66 MA Loop Current) Performed by: /
- Verified l'y
- /
l l O 39 l I
SQNP SPECIAL TISI 9A Page 8 of 13 Rev. 1
~
APPENDIX E H-11 PS-1-23A (PB536A) 350 psig Decreasing (21.66 MA Loop Current) Performed by: / Verified by: /
!- H-12 PS-1-30A (PB546A) 350 psig Decreasing (21.66 MA Loop Current) i Performed by: /
Verified by: / NOTE: When calibrating bistables, approach the setpoint very slowly to reduce the cffect of the lead / lag module in the loop. Calibrate one loop at a time and have all loop histables tripped while calibrating. The same individuals may only calibrate 2 of these instruments. The remaining 2 instru-j ments must be calibrated by 2 other individuals. To return the steamline Delta-P S.I. to normal conditi a, the following steps should be followed. 8 NOTE: The orange "out of service" stickers should be removed f rom the alarm / status window as each bistable is put back in service.
- 32. Remove the 120-VAC source from L-5 and L-6 in 1-R-11. Reterminate wire on L-5.
Performed by: / Verified by: /
- 33. Hove test trip switch PS-526C in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/50 are clear.
f Performed by: / Verified by: /
'3 4 . Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire on L-7.
, Performed by: /
Verified by: / 40-
~, . - - ,
SQNP SPECIAL TEST 9A Page 9 of 13 Rev. 1 _i APPENDIX E
- 35. tfove test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/51 are clear.
Performed by: / Verified by: /
- 36. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate
{ wire on L-9. Performed by: / i Verified by: /
- 37. !!ove 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 ard 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.
I Performed by: / i Verified by: / f i 40. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. Retermi-3 nate wire on L-7. Perform <.d by: / Verified by: / _
- 41. Hove test trip switch PS-516D in 1-R-12 to the normal positio.t and verify the amber light above tLe rwitch and 1-XX-55-6B/76 are clear.
Pr fsc.o;d by: / Veri f .. by: / f 41
SQNP SPECIAL TEST 9A Page 10 of 13 Rev. 1 i APPENDIX E l 42. Remove the 120-VAC source from terminals L-5 and L-6 in 1-R-12. Retermi-i nate wire on L-5. Performed by: / g Verified by: / l I 43. Move 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: /
4 Verified by: / f
- 44. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-/. Retermi-nate wire on L-7.
. Performed by: /
Verified by: /
- 45. 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: /
- 46. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-6 nate wire on L-9.
I Performed by: / Verified by: /
- 47. Hove test trip switch PS-515A to the normal position and verify the amber light abov> 'he switch and 1-XX-55-6B/25 are clear.
Performed by: / Verified by: / NOTE: At this point the steainline Delta-P safety injection is in a normal operating mode. To returg the high steam flow coincident with low steam generator pressure or low-low avg to normal, perfn m the following steps. 7, 42
SQNP SPECIAL TEST 9A Page 11 of 13 Rev. 1 APPENDIX E
- 48. Move test trip switch FS522B in R-3 to the normal position and verify the amber light goes out and XA-55-68/9 will clear, e
i Performed by: /
.l Verified by: /
- 49. Move test ' trip switch FSS12B in R-3 to the normal position and verify l
the amber light goes out and XA-55-6B/2 will clear. Performed by: / Verified by: /
- 50. Remove the 120-VAC source from terminals M-3 and M-4 in R-13. Retermi-nate wiie on M-3.
Performed by: / Verified by: /
- 51. Hove 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. s- 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.
t Performed by: / Verified by: /
- 54. Remove the 120-VAC source from terminals M-3 and M-4 in R-6. Retermi-l nate wire on M-3.
i l Performed by: / l I Verified by: / 43 l 1
SQNP SPECIAL TEST 9A Page 12 of 13 Rev. 1 s APPENDIX E
- 55. flove test trip switch TS4420 in R-6 to the normal position and verify the amher light goes out and XA-55-6A/30 will clear.
Performed by: / l Verified by: /
- 56. Remove the 120-VAC source from terminals t!-3 and ti-4 in R-2. Retermi-nate wire on ?!-3.
1 Performed by: / Verified by: /
- 57. Plove test trip switch TS412D in R-2 to the t ip posit. ion and verify the amber light comes on and XA-55-6A/30 wi.1 clear.
Performed by: _ _ _ / Verified by: /
- 58. Remove the Temporary Alteration Tage on the following test trip switches:
RACK TEST SWITCll TEt!P ALT. NO. R-7 PS515A / R-7 PS515B / R-12 PSS16C / R-12 PS516D / R-8 PS525B / R-8 PSS25A / R-11 PSS26D / R-11 RS526C / R-2 TS412D / l R-6 TS422D / R-10 TS432D / R-13 TS442D / R-3 FSS12B / R-3 FS522B / 1 l l
SQNP SPECIAL TEST 9A Page 13 of 13 Rev. 1 APPENDIX E
- 59. Remove the jumpers aud 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: /
)
The following step should be carried out to return the calibration of the S/G j low pressure S.I. bistables to normal. t I
- 60. The following bistables should be returned to their normal setpoints indicated on the calibration card for the particular bistable. (30.0 + .2MA) j' Remove the temporary alteration control tags after the recalibration.
NOTE: These calibrations require 2 IM's per calibrction. The same r individuals may only calibrate 2 of the instruments. The
. f
) other instruments must be calibrated by other individuals.
Panel Bistable Performed By/ Verified By R-12 PS-1-5A (PB516A) /
/
4 i R-11 PS-1-12A (PB526A) /
/
R PS-1-23A (PB536A) / 2
/
i R-12 PS-1-30A (PB546A) /
/
4 NOTE: All reactor safeguard systems modified for the special startup , tests are back in a normal configuration at this time. l 4 9 i 45
SQNP SPECIAL TEST 9A Page 1 of 1 Rev. 1 JO V. APPENDIX F Technical Specifications Exceptions
'The table below identifies those technical specification-items which are temporarily bypassed or require special test exceptions to the limiting condit. ions for operation during the performance of this and all other special tests.
E d E e : :
- Pn e8" 9 Ue e g c $$$ 0$ 5 o 3So o SS O 3
%e 30$$ "
o 0 2 . . . to* U000 0E B> U U U U U O I
~w -a a E$$" E i a p (A 23 3 3 0%aaic 3 k U CO O o
% 8 % % % .E A B za zz z o m m 4 o o m
~,)
TECIINICAL SPECIFICATION. 1 2 3 4 5 6 7 8 9A 9B Containment HI Pressure SI (3.3.2.1) X X X X X X X X X X Safety Limits (2.1.1) X X X X X X X X X 0 PAT (3.3.1) Inoperable because of low flow 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 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) bypassed X X X X X X X X X X HighSteamflowcoincidentglw/lowsteamline pressure or low-low avg SI i, Reset flow to 0% and ' avg blocked X X X X X X X X X X Reset low steamline pressure X X X
-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 UHI (3.5.1.2) X X X X X X X X X X
. AFW (3.7.1.2)' X X l 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 p) (3.4.1.2) X X X X X X X X t.
46 l
SQNP SPECIAL TEST 9A Page 1 of 1 Rev. 1 TABLE 1 i j Loop Flow and Core AT for Various Power Levels and 4 Isolation Configurations
- (Computer Estimates)
No. of. Loops Operating (Nat. Circ.) 1-Power Level 4 3 2 1 N
.5% L= 3.7 L= 3.6 L= 4.1 L= 5.2 AT = 10.3 AT = 12.5 AT = 16.4 AT = 26 N
.75% L= 3.7 L= 4.1 L= 4.7 L= 5.9
! AT = 13.5 AT = 16.3 AT = 21.4 AT = 34 i O' 1% L= 4.1 L= 4.5 L= 5.2 L= 6.5 - I 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 I 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 i 3% L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE: L is % of 97,000 gpm flow through operable loop. AT = Loop AT in F.
's_
47 P y t+ < + - r,,--s-- -
~ , , ,e ,w.< ,ve, - , , , - w ,.cv ,,,w,--,--------,w-.
r i i i I i l. i l i l t SPECIAL TEST N0. 9B l i e
- l
}
; BORON MIXING AND C00LDOWN i l
l l I i 1 I i l I t 3 i i O
SQNP SPECIAL TEST 9B Page 1 of 1 Rev. 1 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 Window 6 initiates l An operator initiated reactor trip should be performed for any of the following conditions: b 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
*SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
i 1
SQNP SPECIAL T2ST 9B Page 1 of 1 Rev. 1 1
-s .v TEST DESCRIPTION 1his test will demonstrate that the Reactor Coolant System (RCS) can be uniformly borated approximately 100 ppm while in natural circula-tion. Boron samples will be taken continuously from the RCS (1 and 3) hot legn 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. i O J l t i 4 b s I ! %J 2-
SQNP SPECIAL TEST 9B Page 1 of 12 Rev. 1
^O i
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.
/
i 2.1.2 Natural circulations has been established.
/
gg 2.1.3 Steam generators are being fed by the auxiliary feedwater (,,) system. Level is being maintained at approximately 33%. I
; /
2.1.4 Steam generators are steaming via the condenser or atmos-pheric steam dumps. (Preferred is to condenser for SG pressure equilibrium).
/
l
, 2.1.5 Pressurizer heaters are being manually operated to main-tain normal operating pressure.
9
/
2.1.6 RCS average cold Icg temperature is approximately 547 F.
/
2.1.7 Shutdown banks are fully withdrawn and control banks are
> above their insertion limit. Rod control system is in f- s, - ,
manual. The rod height should be such that control bank (_,/ - D ends up at ~ 160 steps after the boration is complete. 3 l I
SQNP SPECIAL TEST 9B Page 2 of 12 Rev. 1 \__ m 2.0 PREREQUISITES (Continued) 2.1.8 PRZR level control is being maintained by manually matching charging to letdown.
/
2.2 The RCS and PRZR boron concentrations are within 20 ppm. I 2.3 The CVCS is in a normal at power make up and letdown configura-tion with the exception of the auxiliary spray valve. This valve will be operated as necessary to provide the spray function.
/
2.4 Sufficient boric acid is available for borating the RCS approxi-mately 100 ppm. l /
\
@ 2.5 Sufficient water is available to provide makeup for the expected cooldown to 450 F.
/
2.6 Prior to performing the cooldown portion of this test set up the I 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 LP1 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
SQNP SPECIAL TEST 9B Page 3 of 12 Rev. 1 t 2.0 PREREQUISITES (Continued) 2.6.2 Recorder No. 2 CilANNEL 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 l R6
- 4 LP4 CLTemp TP/443F
}
5 LP1 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 i 4 LP2 SG Level LP/529B R1 !. 5 LP3 SG Level LP/539B R1 6 LP4 SG Level LP/549B R5 l
2.6.4 Recorder No. 4
. O cuiNNEt PARinETER TEST r01NT RACx 1 LPl SG Press PP/516B R12 J ; 2 LP2 SG Press PP/526B Rll , ; 3 LP3.SG Press PP/536B Rll i 4 LP4 SG Press PP/546B R12 2.6.5 Recorder No. 5 CHANNEL PARAMETER TEST POINT RACK i
1 Aux Fd Flow to SG #1 TP-13 1-L-11B l 2 Aux Fd Flow to SG #2 TP-13 1-L-11A i 3 Aux Fd Flow to SG #3 TP-12 1-L-11B 4 Aux Fd Flow to SG #4 TP-12 1-L-11A
/
2.6.6 Record the following parameters on the reactivity computer recorders. ! a. Flux
- b. Average wide rangeTThot
- c. Average wide range cold
- d. Average steam generator level {
- e. Reactivity ,
i "O.- 5 o,, p. , _ - _ _ _ . . _
SQNP SPECIAL TEST 98 Page 4 of 12 Rev. I gy $ i 20 PREREQUISITES (Continued) 2.7 Trend the following parameters on the process computer at 5-minute intervals. l Wide range cold legs T0406A T0426A T0446A T0466A Wide range hot legs T0419A j T0439A T0459A T0479A Steam Generator Levels LO403A LO423A LO443A LO463A Loop Flow F0400A F0420A { F0440A j F0460A
/
2.8 Special Test 9A has been performed and data is available to correct the excore detectors for T shadowing. c
/
2.9 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix D.
/
2.10 Verify the input logic of safety injection on high steam line AP l has been blocked in accordance with Appendix D.
/
2.11VerifytgehighsteamflowcoincidentwithlowS/Gpressureor low-low avg input to safety injection has been modified in accordance with Appendix D.
/ ,x 6
SQNP
- SPECIAL TEST 9B Page 5 of 12 Rev. 1 O
V 2.0 PREREQUISITES (Continued) 2.12 Verify the following U.H.I. isolation valves are gagged. FCV-87-21 / h FCV-87-22 / t
; FCV-87-23 /
', FCV-87-24 /
l 2.13 Recalibrate the bistables supplying the low pressure signal to the high steam flow S.I. logic in accordance with Appendix D. t / NOTE: This allows cooling down to 450 F without getting a reactor trip. 2.14 Intermediate and power range high level reactor trip setpoints have been set to 7% in accordance with Appendix C and D of
, SU-8.5.2.
() Power Range Intermediate Range
/
/
3.0 PRECAUTIONS, LIMITATIONS, AND ACTIONS 3.1 Do not exceed 5% 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 feedwater flow rate or in steam generator level. I (*
'w))
7 i i 1
--,-r r
SQNP SPECIAL TEST 9B Page 6 of 12 Rev. 1
/") ~' 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 l the PRZR.
1 l 4 3.6 Caution should be used in maintaining power level below 5% RTP
, during the cooldown. Flux shadowing of the excore detectors j
will occur as the temperature in the downcomer of the pressure
~
vessel decreases. 3.7 During the boration hold Tcold approximately constant. I 3.8 During cooldown maintain control bank D at approximately 160 steps if possible. The excore shadowing correction factor was obtained in this configuration. 3.9 When testing with the reactor coolant in the low temperature
, range of 4S0 F to 500 F, maintain the lithic concentration at I 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 2 100 s'eps. Should this limit be reached during the cooldown, boron concentration will have to be increased.
3.11 Should a reactor trip oc, cur during the conduct of this test at least one reactor coolant pump (#2) should be started prior to . closing the reactor trip breaker. I 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. I
*A 8
m
,, , ..e-+
SQNP SPECIAL TEST 9B Page 7 of 12 Rev. 1 i 4.0 SPECIAL TEST EQUIPMENT IDENTIFICATION CALIBRATION INSTRUMENT SPECIFICATION NUMBER VERIFICATION t Reactivity Computer Westinghouse j and Associated l Equipment (4) 1 6 Recorders Brush 260 or { Equivalent 1 Recorder IIP 7100B or Equivalent l I i i 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. p
)
( 9
SQNP SPECIAL TEST 9B Page 8 of 12 Rev. 1 5.0 INSTRUCTIONS 5.1 Boration 5.1.1 Begin sampling the RCS and PRZR on a minute frequency and record the data on Data Sheet 1.
/
5.1.2 Verify that the system is in equilibrium with respect to power, RCS temperature, pressure, and boron concentration. PRZR pressure ~ 2235 1 50 psig S/G pressure ~ 1005 psig RCS - PRZR boron concentration within 20 ppm Successive boron samples within i 10 ppm Reactivity is approximately zero and constant
/
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 .
I i) Reactivity ii) Flux %
- b. 2nd strip chart recorder i) Average Th wide range
- 11) Average Tc wide range a I /
I 5.1.4 Energize PRZR heaters and initiate auxiliary sprays. Try I to energize all heaters. Ideally auxiliary sprays should
}
operate continually 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.
/
5.1.5 Initiate boration at approximately 500 pcm/hr via the borate mode.
/
~T (J
10 i l
SQNP SPECIAL TEST 98 Page 9 of 12 Rev. 1
,~
, J 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.
/
NOTE: Observe T and Th. They should remain approximately C constant 5.1.7 Terminate boration after = 100 ppm increase in RCS boron concentration at the end of 2 hours.
/
i l 5.1.8 Continue sampling until the boron concentration stabilizes
' and the system is again in equilibrium, as defined above.
i
; /
-{ ,
I () 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.
/
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
/
(N
%.) :
11 I
~
s i
SQNP SPECIAL TEST 9B Page 10 of 12 Rev. 1 0 5.0 JNSTRllCTIONS (Continued) 5.2.3 Start the test recorders on slow speed (5mm/ min). Record on the cha the date, time, recorder ID, parameters mea-sured, measurement range, charts speed, test being performed and name of person recording data.
/
5.2.4 Start process computer trend block.
/
5.2.5 Obtain a thermocouple map and repeat every 10 F during cooldown.
/
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 f} level fluctions. When the unit operator feels comfortable with the SG 1evels the cooldown rate may be increased.
~ /
1 5.2.7 Initiatethecooldownbyslowlyincreasinggherateof steam dump and proceed to approximately 450 F core inlet temperature, t l
.i i
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.
/
CAUTION: As the cold Icg temperatures decrease the excore detectors will not be dependable because of neutron shadowing. ( 12 a
SQNP SPECIAL TEST 9B Page 11 of 12 Rev. 1 C 5.0 _ INSTRUCTIONS (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.
/ _
5.2.10 Insert control rods until the reactor is subcritical.
/
5.2.11 Restart all four reactor coolant pumps in accordance with S01 68.2 starting with RCP //2,1, 3 and then 4.
/
5.2.12 Allow primary system to heat up to ~ 547 F. i 4
/
5.2.13 Return the bistables supplying the low pressure signal to the high steam flow S. I. logic to their original setpoirts 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 a N/A in the signature line, and initial.
/
I 5.2.14 Restore the high ste9m 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.
/
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.
! ,. /
13
- t
SQNP SPECIAL TEST 9B Page 12 of 12 Rev. 1 i 5.0 INSTRUCTIONS (Continued) 5.2.16 Remove the block of automatic actuation of safety injec-tion in accordance with Appendix D unless the next test to be perfonned requires the block to be installed. If this is the case, disregard this step, place N/A in the signature line, and initial.
/ ' 5.2.17 Remove the gags from the following U.H.I. isolation val.ves 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.
4 FCV-87-21 / FCV-87-22 / FCV-87-23 / FCV-87-24 / J l 5.2.18 Reset the intermddiate 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 unless the next test O
- to be performed requires this adjustment. If this is the case, disregard this step, place N/A in the signature line, .
and initial. . 4 Power Range / Intermediate Range / I 6.0 ACCEPTANCE CRITERIA a j 6.1 The RCS can be borated and the boron uniformly mixed in natural circulation. 3
?
* / __
t 6.2 The RCS can be cooled down to approximately 450 F on natural circulation.
/
O 14
l SQNP SPECIAL TEST 9B Page 1 of 1 Rev. I O . APPEhTIX A References
- 1. FSAR
- 2. Technical Specificat. ions l
O . 4 i d. J l 1 T i l l l 1 0 15
. . - - - - . , , , - _ .- - - - - -- .-c ..- , - - -e-
SQNP SPECIAL TEST 9B .
' Page 1 of 1 Rev. 1 LO APPENDIX B t t i t
Test Decificiencies # 1 Test Deficiency
-r ,
-l
- i. '
I, l t i i I t 2 1 i
! Recommended Resolution , ($]> .
I w I 1 I s 1
; -l i t 4
4 1 . j Final Resolution 4 i j Originator /-
- Signature Date
} 1 PORC Review of Final Resolution I 4
- Date l Approval of Final Resoltuion /
Plant Superintendent Date ] Oe 16 l _. 4 1 8 I
SQNP SPECIAL TEST 9B Page 1 of 9 Rev. I O APPENDIX C Procedure for Determining Core Power Level l O 17 l
_. . . - ._ --_= ._ . _. . SQNP SPECIAL TEST 98 Page 2 of 9 Rev. 1 O APPENDIX C j Outline T. Core Power Determination A. Excort detector output correction factor plots.
- 1. The plots obtained in Special Tcst 9A should be used to correct the excore detector outputs for changes in the core inlet tem-
; peratures.
H. M/D Power Monitor Program i
- 1. Power Conversion Constant Adjustment I
a) The output. of the REF primary calorimetric will give a percent i 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 pcwer as seen by one pass of 5 or 6 detectors. After the .
! output has been calibrated to be equal to the REF primary I calorimetric it will be rerun up to once every 2 minutes or as necessary to continuously monitor core power.
i 1 i i a ! o l O 18 l l 4 , - -
SQNP SPECIAL TEST 9B Page 3 of 9 Rev. 1 N. j APPENDIX C CORE POWER DETERMINATION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation) f C.1 Use two DVMs and measure the voltage at the test points speci-fied for each loop as rapid as possible. I C.2 Calculate the WT; multiply that WT 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 WT 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. i m,.
~a 19 l
+
SQNP
- SPECIAL TEST 9B Page 4 of 9 Rev. I s
u) f APPENDIX C Core Power Determination i 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.
9 Drive 10-Path Position Core Location
- A 10 L-5
' L-11 B 10 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 .
Iow-power physics testing results and previous special testing ' experience.
- 2. Determine the detector normalization constants and enter them into the P-250 as follous:
a) Enter a value of 1.0 into the P-250 for the addresses shown in the table below. b) With all 5-path selector switches set to normal, run a flux trace. c) With all 5 path selector switches set to Emergency, run a second flux trace. d) Determine the detector normalization constants from Data Sheet C.2. m 20 I
SQNP SPECIAL TEST 9B Page 5 of 9 Rev. 1 L ,i APPENDIX C PART ft: (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 mr.y be repeated as of ten 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(I) m F BTU /lbm F lbm/hr 7 556 1.260 3.6448 x 10 7 554 1.255 3.6553 x 10 552 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 7 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 e 7
! 540 1.221 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.
21
%J SQNP SPECIAL TES' 9B Page 6 of 9 Rev. 1 APPEhTIX C Data Sheet C.1 Power Tavg F Date Time Unit Loop 1 Loop 2 Loop 3 Loop 4 Item # Calculation Procedure Units R2/TP-411J R6/TP-421J X10/RP-431J R13/RP-441J t
1 Loop AT - Inservi.ce (at test point) Volts 2 Loop AT = (#1) x (1) 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 U 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 MVr N
% l 8 % Reactor Power = (#7) x 0.02932 (I) Conversion factor for AT obtained from scaling document.
Remarks: Date By: Checked By:
SQNP SPECIAL TEST 9B Page 7 of 9 Rev. 1 7s APPENDIX C
. DATA SIEET C.2 1
B D
- N= FN*
AN= N N N A D * = F
- E E E E E E l
N = 1.00 3 l A A N = N = AE = 5-N B N A N = N = BE = C C N N A N i N = N = CE = 4 D D N N N,=AN = N DE = b E E N N NE Ng = AN = EE =
' F F N N Definitions:
A' N, CN , DN , EN ' N = Normalized integral from summary map for each N detector in a normal path in the first pass A,B,C,D,E,F = Normalized integral from summary map for each E E E E E E detector in an emergency path in the second pass N,N,N' g B C D, NE ' F
= Detector normalization factor for each detector Remarks:
() Data By: Date 23
SQNP SPECIAL TEST 9B Page 8 of 9 Rev. 1 APPF'.iD1X C
.PART _C : Using Thermocouples The incore thermocouple s can be used as an inJication of both core flow distribution and sower shifts during natutil circulation.
4 I Prior to running a thermocouple map or trending t. eight quadrant
' tilts (four center line and four diagonal tilts) t,a following should be verified:
K0701-K0765 = 1, For the flow mixing factors KS501 = 0, Indicates the measured core WT is unreliable K0791 = 0.07f, 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 directly correlated with the excore detectors but quadrants 5-8 cannot. The quadraat tilts are indicative of power shifts and should be trended at approximately.a 2-minute frequency. The following addressable values are the quadrant tilts: i Quadrant Addressable Value I 1 U1159 4 2 U1160 2 3 U1161 4 4 U1162 5 U1151 i 6 U1152 7 U1153 8 Ull54 A Short Form Map should be run periodically or upon request from the test engineer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Console Reference Manual provides instructions for ob-taining thermocouple maps. The trend output and Short Form Maps should be attached to this
- procedure at the end of the test.
24 1
SQNP SPECIAL TEST 9B Page 9 of 9 Rev. 1 L) APPENDIX C i
/ CENTf A LINE OUARTEn-Cone SYPAMETRY l
l Co!1 Legs
' 3
' 4
- t/-43 m 2,n* tt .12
. , o O 3
{ \
; 1 2 l 4
. \ l i
im- o va t,p b,c ,. L ey
.y . _
- 2. 4 3 I I
) ExConE CETECTORS r/- 41 ovevo I tJ-44 2 ,
Csil Ley I DIAGON AL QUANTER CORE SYMMETRY 225 35* s ,
= m 5
3- * '\ 6 e .\ 7
. . x
- ,k 25 l
t F e , .- e C-t l'- v 25
SQNP SPECIAL TEST 9B Page 1 of 13 Rev. 1 APPENDIX D s Safeguard Blocking Procedure The first step blocks automatic initiat ion 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 accuation 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 als'o defeat all AP S.I. alarms.)
- 2. Verify status lights 1-XX-55-6B/1, 2, 3, 4, 25, 26, 27, 28, 50, 51,
. 73, 76 are all clear prior to starting blocking procedure.
- 3. Hove test trip switch PS-515A in 1-R-7 to the trip position and verify the amber light above the switch comes on.
Performed by: / l Verified by: / CAUTION: In the next step, and all foll. wing steps in which a voltage is being applied to the indicate, 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 _l 26
SQNP SPECIAL TEST 9B Page 2 of 13 Rev. 1 I I
~.-
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. I
- 4. Lif t and tape the wire on the rack side of terminal L-9 in the rear of 1-K-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: / l l
- 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 and verify 1-XX-55-6B/27 is clear.
Performed by: / I Verified by: /
- 7. Move test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
t Performed by: / Verified by: /
- 8. Lif t and tape the wire on the rack side of terminal L-5 in the rear of 1-R-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: /
/
% ,r 27
SQNP SPECIAL TEST 9B Page 3 of 13 Rev. 1 APPENDIX D
- 9. Hove test trip switch PS-516D in 1 n-12 to the trip position and verify the amber light above the switch comes n.
4 Performed by: / Verified by: /
- 10. 1.ift and tape the wire on the rack side of terminal L-7 in the rear of l-R-12. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/76.
Performed by: / Verified by: / l l
- 11. Hove test. trip switch PS-525B in 1-R-8 to trip position and verify the ,
amber light above the cwitch comes on. Performed by: / , Verified by: /
- 12. hift 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.
~ h' Performed by: / Verified by: /
- 13. Hove test trip switch PS-525A in 1-R-8 to the trip position and verify l the amber light above the switch comes on.
Performed by: / Verified by: / .
- 14. Lift and tape the wire on the rack side of terminal L-9 in the rear of 1-R-8. Apply 120-VAC source to terminals L-9 and L-10 in the rear of 1-R-8 and verify that XX-55-6B/26 is clear.
Performed by: / Verified by: _/ , O 28 _. _ _ ..m, , . ,-_,,_.,y, ,.
SQNP SPECIAL TEST 9B Page 4 of 13 Rev. 1 i i
~'
. 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: /
l Verified by: / i 16. Lif t and tape the wire on the rack side of terminal L-7 in the rear g of 1-R-11. Apply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-11 and verify that XX-55-6B/51 is clear. Performed by: / Verified by: /
- 17. Move test trip switch PS-526C in 1-R-11 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 18. Lif t and tape the wire on the rack side of terminal L-5 in the rear l l 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: /
I Temporary Mgdification to High Steam Flow Coincident with Low S.G. Pressure or Low-Low avg Safety Injection l 19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be ricared. Performed by: / Verified by: / NOTE: If the alarms will not clear, do not proceed with this modifica-tion as a reactor trip may result. The input bistables should be checked and the source of the probler corrected. I I
./
29
SQNP d SPECIAL TEST 9B Page 5 of 13 Rev. 1 9 APPENDIX D
- 20. Move' test trip switch TS412D in R-2 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: / i
- 21. Lift and tape the wire on the rack side of terminal H-3 in the rear 1 g of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: / Verified by: /
- 22. Hove test trip switch TS-422D in R-6 to the trip position and verify the amber light above the switch comes on.
Performed by: / Verified by: /
- 23. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear. -
/
Performed by: ! Verified by: /
- 24. Nove test trip switch TS432D in R-10 to the trip position and verify the amber light above the switch comes on.
I ; Performed by: /
' Verified by: / -
'j
- 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 l and verify XA-55-6A/30 will clear.
Performed by: / Verified by: / i O 30 t - -- "' --rse= g- we T' - - - m =v-1 C"9 -w v +'
SQNP SPECIAL TEST 9B Page 6 of 13 Rev. 1
)
APPENDIX D
- 26. flove test trip switch TS-442D in R-13 to the trip position and verify the amber light above the switch comes on.
{ Performed by: / Verified by: / _
. 27. Lif t and tape the wire on the rack side of terminal t!-3 in the rear j of 1-R-13. Apply a 120-VAC source to terminals ti-3 and t!-4 in R-13 and verify XA-55-6A/30 will clear.
Performed by: / I Verified by: / NOTE: The Tavg 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). g 28. ?!ove test trip switch FSS12B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/2 come on. Performed by: / Verified by: /
- 29. Flove test trip switch FS522B in R-3 to the trip position and verify the l amber light and annunciator XA-55-6B/9 come on.
Performed by: / Verified by: / NOTE: These two trips will supply the 2 oe- of 4 logic required to get a Safety Injection Signal.
/
31 m
SQNP SPECI AL TEST 98 Page 7 of 13 Rev. 1
/~g U 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 SWITCH TEMP ALT. NO. R-7 PS515A / i ' R-7 PSS15B / R-12 PSS16C / _
. R-12 PS516D /
J i R-8 PS525B / R-8 PS525A / R-11 PSS26D / R-11 RS526C / R-2 TS412D / 1 j R-6 TS422D / l R-10 TS432D / i
\
R-13 TS442D / i R-3 FS512B / R-3 FS522B / ] The following step reduces th9 setpoint of the S/G pressure input to S.I. to trip at 350 psig allowing avg to be reduced to 450'F.
! 31. Recalibrate the following bistables to the indicated setpoints and attach Temporary Alteration Control Tags.
! +
! Panel- Bistable Setpoint I
- i R-12 PS-1-5A (PB516A) 350 psig Decreasing (21.66 MA Loop Current}
Performed by: / Verified by: /
- R-11 PS-1-12A (PB526A) 350 psig Decreasing (21.66 MA Loop Current)
Performed by: / Verified by: / 32 i i _ l
SQNP SPECIAL TEST 98 Page 8 of 13 Rev. I 1
- APPENDIX D
{ R-Il PS-I-23A (P11536A) 350 psig Decreasing ! (21.66 t!A Loop Current.)
. Performed by: /
I Verified by: / I, R-12 PS-1-30A (P11546A) 350 psig Decreasing
- (21.66 MA Loop Current.)
I Performed by: / 1 Verified by: / e l 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 histables I t. ripped while calibrat.ing. The same individuals may only calibrate 2 of these instruments. The remaining 2 inst.ru- ! ments must be calibrate:1 by 2 other individuals. ! To return the steamline Delta-P S.I. to normal condition, the following stepn should be followed. { I NOTE: The orange "out. of service" stickers should be ::;4oved f rom
/. , 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.
4 Performed by: / I Verified by: /
- 33. Flove 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 cicar.
I '- t Performed by: / Verified by: / ! ' 34. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Heterminate i , wire on L-7. f , Performed by: / l Verified by: / 4 1 33 w ww m s w-. ,- -- - , - - ,,e-,,- o ,-- .,--y, , ,, , ,,--s- ,w,--ve - - - - eny e-- g,gr g-, - , - ee
SQNP SPECIAL TEST 9B Page 9 of 13 Rev. 1 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-XX-55-6B/51 are clear.
Performed by: / Verified by: / __
- 36. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.
Performed by: / _ Verified by: / j l ;
- 37. Move test trip switch PS-525A in 1-R-8 to the normal position and verify the amber licht 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.
I Performed by: /
' Verified by: /
t' i 40. Remove the 120-VAC source from terminals L-7 and L-8 in 1-R-12. Retermi-4 nate wire on L-7. Performed by: / _ Verified by: /
- 41. 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: / O O 34
SQNP SPECIAL TEST 9B Page 10 of 13 Rev. 1 s APPEND 1X D
- 42. Remove the 120-VAC source from terminals L-5 and L-6 in 1-R-12. Retermi-n.ite wire on I.-5.
Perfcrmed by: / i [ Verified by: /
- 43. Move 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.
g 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 switen 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.
I Performed by: / Verified by: /
- 47. Hove 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 retur9 the high steam flow coincident with low steam generator pressure or low-low avg to normal, perform the following steps. q_,s 35
i SQNP SPECIAL TEST 9H Page 11 of 13 Rev. 1 APPENDIX D
- 48. !!ove test trip switch FS522B in R-3 to the normal pcsition and verify the amber light goes out and XA-55-6B/9 will clear.
Performed by: / i Verified by: /
- 49. Hove test trip switch FS512B in R-3 to the normal position and verify
; the amber light goes "it and XA-55-6B/2 will clear.
Periormed by: / i - Verified by: _ /
- 50. Hemove the 120-VAC source from terminals M-3 and M-4 in R-13. Retermi-nate wire on M-3.
I Performed by: / f Verified by: / i
- 51. Hove 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.
I Performed by: / . 1 Verified by: / l
- 52. Remove the 120-VAC source from terminals M-3 and M-4 in R-10. Re te rmi-nate wire on M-3.
I Performed by: / Verified by: /
.E g 53. Hove test trip switch TS432D in R-10 to iks 'ormal position and verify the amber light goes out and XA-55-6A/3C eitt clear.
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: /
O 36 l l l l
SQNP SPECIAL TEST 9B Page 12 of 13 Rev. 1
. APPENDIX D
- 55. ?!vve test trip switen 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: /
$6. 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. Move 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 SWITCll TEMP ALT. NO. R-7 PS515A / R-7 PS515B / R-12 PSS16C / l R-12 PS516D / R-8 PS5258 / R-8 PS525A / [
R-11 PS526D /
I R-11 RS526C / R-2 TS412D / R-6 TS422D / R-10 TS432D / R-13 TS442D / R-3 FS512B / R-3 FS522B / n.' 37
SQNP SPECIAL TEST 9B Page 13 of 13 Rev. 1 APPENDIX D
- 59. 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: / 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 + .2t1A)
Remove the temporary alteration control tags after the recalibration. j NOTE: These calibrations require 2 IM's per calibration. The same i individuals may only calibrate 2 of the instruments. The other instruments must be calibrated by other individuals. llh Panel Bistable Performed By/ Verified By R-12 PS-1-5A (PB516A) /
/
l R-11 PS-1-12A (PB526A) /
/
f 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. 38 e
SQNP SPECIAL TEST 9B Page 1 of 1 Rev. 1 APPENDIX E Technical Specifications Exceptions The table below identifies those technical specification items which are temporarily bypassed or require special test exceptions to the limiting conditions for operation during the performance of this and all other special tests. 0 . E e :a
*8e8 u na .o g
c $$%8$ 5 o 3So o ES S ?
% v % n e %- A o 8 3". . . N O UaBBH? B
> E U$UUU* ec u u 3
w I
~
! A- %oTTT3SS o U s . O a e i f, fo 8 5 z%8%%%2 az z z o m m B 8 W m 8 TECHNICAL 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 OTAT (3.3.1) Inoperable because of low flow 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) bypassed 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 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
/^'s Control Rod Insertion Limits (3.1.3.6) X X X X X X X d Reactor Coolant Loops Normal Operation (3.4.1.2) X X X X X X X X 39
-- -?p
. . - . . . - - ~ . . - . . - __ - _ _ .
SQNP SPECIAL TEST 9B l . Page 1 of 1 4 Rev. I ." ), TABLE 1 Loop Flow and Core AT for Various Power Levels and Isolation Configurations (Computer Estimates) t i I No. of Loops Operating
) (Nat. Circ.)
i Power Level 4 3 2 1
.5% L= 3.7 L= 3.6 L= 4.1 L= 5.2 AT = 13.3 AT = I?.5 AT = 16.4 AT = 26
.75% L= 3.7 L = .4.1 L= 4.7 L= 5.9 l 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 ,
i - 1 .
! i 1.5% L= 4.7 L= 5.2 L= 5.9 L= 7.5 AT = 21.4 AT = 26 AT = 34 AT = 54 l
2% L'= 5.2 L= 5.7 L= 6.5 L= 8.2 I
. AT = 26 AT = 31.4 AT = 41 AT = 65.4 l-i - W. W W W 2.5% L= 5.6 L= 6.2 L= 7.1 .L = 8.9 AT = 30.1 AT = 36.5 AT =-47.1 AT = 75.9 3% ~ L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7 NOTE: L is % of 97,000 gpm flow through operable loop.
AT =-Loop AT in *F. 1
.J
! 40 I
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