ML19323B932
| ML19323B932 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/06/1980 |
| From: | Ballentine J, Maehr S, Saputa E TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19323B910 | List: |
| References | |
| PROC-800506-04, NUDOCS 8005140432 | |
| Download: ML19323B932 (49) | |
Text
.
,
Sequoyah flucicar Plant DISTRIBUTION N
..
1C Plant Master File
- Superintendent
_fg_ Assistant Superintendent (Ope..)
Assistant Superintendent (Fla in t . )
Administrative Supervisor Ifaintenance Supervisor (M)
Assistant Maintenance Supervisor (M)
Maintenance Supervisor (E)
Assistant Maintenance Superviso'r (E)
SPECIAL TEST NO. I 1U Maintenance Supervisor (I)
_ffL Results Supervisor NATURAL CIRCULATION TEST _) U operations Supervisor ur Quality Assurance Supervisor Health Physics Stipervisor Public Safety Services Supv.
Chief Storekeeper Preop Test Program Coordinator
_ ___ Outage Director Chemical Engineer (Results)
Radiochem Laboratory
_
Instrument Shop
_/C_ Reactor Engineer (Results)
Instrument Engineer (Maint. I)
Mechanical Engineer (Results)
__ Sta f f ]ndus t rial Engineer (Pit Svs)
Training Center Coordinator
-
PSO - Chickamauga Engrg Unit - SNP Prepared By: E. Saputa Public Sa fety Services - SNP
/C Shift Engineer's Office Revised By: S. R. Machr _ _f_ ( Unit Control Room QA&A Rep. - SNP Submitted By: _I hj p m c/ _ Health Physics Laboratory Supervi/,or 1U Nuc1r Document Control. Unit, 606 EB-C 1U Superintendent, WBNP PORC Review: f//,, / g C_ Supe ri n ten den t , BTNP
\. Date Superintendent, BENP 1U NEB, W9C174C-K
._
)O % ,.
Supv., NPHPS ROB, MS Approved By: w_ hLQMyg kk Superpntendent NHC-IE:II Potter Security Officer, 620 CST 2-C
'
Nuc1r Materials Coord. - 1410 CUBB-C
,, Manager, OP-QASA Staff .
Dale Approved: C g g Resident NRC Inspector - S"P T C NSRS , 249A HBB-K Technical Support Center 1C .1hiS4 Tr> clinic / Ad vis o e Rev. No. Da t.- Revised Pane:, Rev. No. Date Revised Pages
/
0 [j h All
_
_
.
.
4 4
&
SPECIAL TEST NO. 1 NATURAL CIRCULATION TEST
SQNP SPECIAL TEST 1 Page 1 of 1
'
Rev. 0 4
.
NATURAL CIRCULATION TEST Table of Contents Page Natural Circulation Test 1 Special Operator Instruction 2 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 - Deficiencir 18 APPENDIX C - Power Measurement Techniques 19 APPENDIX D - Computer Points 30 APPENDIX E - Safeguard Blocking Procedure 34 APPENDIX F - Technical Specifications. Exceptions 45 TABLE 1 - Loop Flow and Core AT for Various Power Levels and Isolation Configurations 46
- -
SQNP SPECIAL TEST 1
-
Page 1 of 1
<
Rev. 0
.
NATURAL CIRCULATION TEST TEST DESCRIPTION The test will be initiated by simultaneously tripping all reactor coolant pumps while at 3% power. The transient response will be monitored and establishment of natural circulation verified. Core exit thermocouples will be monitored to determine the core flow distribution. After stable conditions have been established, forced circulation will be reestablished.
I 1
_
SQNP SPECIAL TEST 1 Page 1 of 1
< Bev. 0
.
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 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 opera cor 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 Any-Uncontrolled Rod Movement
- SI termination should be in accordance with plant EMERGENCY OPERATING PROCEDURES.
2
- _ . _ _
SQNP SPECIAL TEST 1 Page 1 of 10
, Rev. 0
.
1.0 OBJECTIVES 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-able limits during the coastdown transient.
1.3 To verify that steam generator level and feedwater flow can be con-trolled under conditions of natural circulation to maintain ade-quate cooling of the reactor coolant system.
1.4 To provide operator training. All operating shif ts will perform this test.
NOTE: Data acquisition does not need to be repeated for multiple test performances.
2.0 PREREQUISITES 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).
Date 2.3 All four reactar coolant pumps are in operation.
Date 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 mode, maintaining steam generator pressure at approximately 1005 psig.
-- -
_
Date 3
_
SQNP SPECIAL TEST 1 Page 2 of 10 Rev. O e
.
2.0 (Continued) 2.6 Steam generator level is being maintained at approximately 33% on the narrow range indicators with auxiliary feedwater.
Date 2.7 RCS temperature (T,y ) is being maintained at approximately 550 F.
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 1-R-1, FP-444B RCS Flow, Loop 4 Channel No. 5 1-R-1, PP-455B 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 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 4
., .
- _
_. . .
_
e
SQNP SPECIAL TEST 1 Page 3 of 10
.
Rev. 0
.
2.0 (Conti.nued)
Recorder No. 4 Connect To: Monitoring Channel No. l' 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 Main Feed Flow, SG#4 NOTE: If auxiliary feedwater is to be used in place of main feedwater, brush recorder #4 should be in-stelled 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-llB Aux.FeedFlow to SG#3 Channel No. 4 F-3-170,TP12,1-L-11A Aux.FeedFlow to SG#4
/
-
NOTE: Record the following on each strip chart:
a) Unit number b) Date c) Procedure number d) Parameter scale and range c) Chart speed f) Name of person recording data g) Recorder ID number 2.8.2 Record on p-comnuter recorder
- a. Flux
- b. Average wide range cold
- c. Average wide range hot
- d. Average Steam generator pressure
- e. Reactivity
/
2.9 A steady feed to the steam generators should be set up to mini-mize temperature variation in the RCS.
/
5
_. . . _ . . ,_ .. .. . .- _ _ _ .
,
_
SQNP SPECIAL TEST 1 Fage 4 of 10
. Rev. 0
.
2.0 (Continued) 2.10 Verify the input logic of safety injection on lli steam line AP has been blocked in accordance with Appendix E.
/
2.11 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.
/
2.12 Verify the automatic actuation of safety injection has been blocked in accordance with Appendix E.
/
2.13 Verify the following UHI isolation valves are gagged.
FCV 87-21 /
FCV 87-22 /
FCV 87-23 /
FCV 87-24 /
2.14 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 /
l 3.0 PRECAUTIONS l 3.1 Do not exceed 5% nucicar power.
3.2 Abort test if any of the following temperature limits are exceeded:
3.2.1 610 F for any core o'itlet thermocouple.
3.2.2 65 F for any loop Delta-T.
3.2.3 578 F for any' loop avg.
1 I
6' ;
1
- - . ..
SQNP SPECIAL TEST 1 Page 5 of 10
. Rev. 0
.
3.0 (Continued) 3.3 Avoid rapid changes in steam pressure, steam generator level, and feedwater flow to prevent rapid cooling of the reactor coolant.
3.4 Maintain reactor coolant pump seal and thermal barrier differential requirements as given in SOI 68.2.
3.5 T After the reactor coolant pumps are tripped, thg normal avg and AT indications will become unreliable. AT and avg should be calculated by taking the difference and the average of the hot and cold leg temperatures indications respectively.
T 3.6 flaintain cold at the pretrip temperatures by adjusting the steam dump setpoint.
3.7 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.
3.8 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.
.
7
-
-
- ~~'~
SQNP SPECIAL TEST 1 Page 6 of 10
. Rev. 0
.
4.0 SPECIAL TEST EQUIPMENT Calibration Instrument Specification Identification Verification Strip Chart Recorder Brush 260 or equivalent (4)
Reactivity Computer Westinghouse Recorder (1) IIP 7100B or equivalent 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.
8-
~
~ . -
. .-
SQNP SPECIAL TEST 1 Page 7 of 10
.
Rev. 0
.
5.0 INSTRUCTIONS 1
NOTE: Data acquisition steps need not be repeated for multiple test perfo rmances . 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.
/
5.2 Start the brush recorders in the auxiliary instrument room and start monitoring of data points on the computer trend typewriter.
/
CAUTION: Ccutinuously 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.
i NOTE: Steam generator pressure, level, and flev conditions should a held as close as possible to stable conditions through the duration of the transient. Reactor coolant system cold leg temperatures should be maintained within + 5"F of the initial values.
NOTE: At the initiation of natural circulation (RCP trip) the following response is expected.
a) Wide rangeTThot, - increase b) Vide range cold, - slight increase or constant c) d)goreexitthermocouple,-increase avg indication, - unreliable e) Delta-T indications, - unreliabic f) Pressurizer l' vel and pressure, - increase 5.3 Simultaneously trip all four reactor coolant pumps in accordance with SGI 68.2.
/-
5.4 Maintain RCP seal flow at a minimum of 6 gpm to each pump.
/
9 l
-
- - ..
SQNP SPECIAL TEST 1 Page 8 of 10 Rev. 0
.
.
5.0 (Continued) 5.5 flaintain pressurizer pressure control in automatic and manually adjust charging flow to match letdown and maintain a constant RCS water mass.
/
NOTE: Pressurizer heaters and auxiliary spray may be controlled manually as needed.
5.6 Carefully control additions of feedwater to the steam generators to maintain levels at approximately 33%. Do not allow steam generator level to drop below 24% on narrow range indicators.
/
'
NOTE: Natural circulation flow will be stable when:
T a) AT between wide range T hot andT cold is constant.
b) AT between wide range cold and core exit T/C average temperatur is constant.
T c) Wide range hot ~ core exit T/C average temperature.
(See Table 1).
5.7 Af ter steady state conditions have been reached mark each re-corder chart to indicate equilibrium has been reached and continue recording data.
/
5.8 Insert control bank D as specified by test engineer until the hot zero power test range is reached.
/
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-Linue to collect data through the restart.
/
5.10 After steady state conditions have been reached, restart reactor coolant pump #1 in accordance with SOI 68.2. Continue to collect data through the restart.
/
10
.. . . . . -.. .
SQNP.
SPECIAL TEST 1 Page 9 of 10
- Rev. 0
.
5.0 (Continued) 5.11 After steady state conditions have been reached restart reactor coolant pump #3 in accordance with SOI 68.2. Continue to col-1ect data through the restart.
_ /
5.12 After steady state conditions have been reached restart reactor coolant pump #4 in accordance with SOI 68.2. Continue to col-1ect data through the restart.
/
5.13 Stop the brush recorders in the auxiliary instrument room, and terminate tren6 recording on the plant computer.
/
5.14 Incorporate the brush recorder charts and computer printouts on Data Sheet 5.2.
/
5.15 Remove the block of input logic of safety injection on Hi st..an 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.
/
5.16 Remove modification to Hi 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.
/
5.17 -Remove block of automatic initiation of 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.
4
/
11
-- __ __ _ _
.
SQNP SPECIAL TEST 1 Page 10 of 10
. Rev. 0
.
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 signature line, sad initial.
Power Range /
Intermediate Range /
6.0 ACCEPTANCE CRITERIA 6.1 Core exit T/C temperature does not exceed 610 F.
/ __
6.2 Delta-T for any loop does not exceed 65 F.
/
6.3 avg for any loop does not exceed 578 F.
/
6.4 -Delta-T established between wide hot and cold is stabic and less than 65 F.
/
6.5 Delta-T established between wide range cold and core exit T/C average temperature is stable and less than 65 F.
/
12
, 'I
!
I
~
d - - ~. _ _
_
l
SQNP SPECIAL TEST 1 Page 1 of 3-
. Rev. 0
.
DATA SREET 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 TR-68-43 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).
. Recorded by /-
13-
-_ _ - . _- z. _ .m .
_ .
SQNP SPECIAL TEST 1 Page 2 of 3
, Rev. 0
.
DATA SIIEET 5.1 INITIAL CONDITIONS l
Unit Date Time Steam Generator 1 Level (WR) %
LR-3-43 Pen 1 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 psig PI-1-9A Steam Generator 3 Pressr::e psig 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 gpm (FI-3-48A)
Steam Generator 3 Fee <lwater Flow gpm (FI-3-90A)
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 l
\
)
SQNP SPECIAL TEST 1 Page 3 of 3
. Rev. 0
.
, DATA SIIEET 5.1 INITIAL C0hTITIONS Unit Date Time Steam Generator 3 Steam Flow lbs/hr (FI-1-21A)
Steam Generator 4 Steam Flow lbs/hr (FI-1-28A)
Loop 1 Tavg F (TI-68-2E)
Loop 2 Tavg y (TI-68-25E)
Loop 3 Tavg y (TI-68-44E)
Loop 4 Tavg O y
(TI-68-67E)
Loop 1 AT O p
(TI-68-2D)
Loop 2 AT O y
(TI-68-25D)
Loop 3 AT y (TI-68-44D)
.
Loop 4 AT 0 7
(TI-68-67D)
NIS Channel N-41 g j NIS Channel N-42 % ;
NIS Channel N-43 g l
-NIS Channel N-44 g
'
Recorded by /
Checked by /-
15' i
--
- ._ _
SQNP SPECIAL TEST 1 Page 1 of 1
,
Rev. 0
.
!
DATA SlfEET 5.2 Attach copies of the computer trend printout and brush recorder charts to this page.
t I
.
l J
16
!
... . .
, .
_
. l
- . - . -- ._ . - . - . - - . _ _ . - . - _ _ _ _ _ _ . _ . - - - . _ _ - _ . . . __- . - - . - - . . _ _ _
l SQNP SPECIAL TEST 1
! Page 1 of 1
- Rev. 0
.
! APPENDIX A
.
1 4
)
a References
! 1. FSAR l
i 2. Technical Specifications
!
j 3. Plant Operating Instructions E0I-5 l S01-68.2
!
l
}
i i
1 i
f
)
,
4 l
4
s i
!-
!
i
,
e
,
1 i
i f
f i
i 17
!
,
!
i
~,. ._ . _ , . . _ . _ _ . , _ , . _ _ . . , . . _ _ . _ _ , _ _ . ._,___._..___-,.._______.___a_._- _ _ _ _ _ . . _ _ _ _ . . . _ . ~ . _ _ . _ _ . _ . . _ _ _ . . _ _ . _ _ _ . . .
_ . . .. .-_
SQNP SPECIAL TEST 1 Page 1 of 1
.
Rev. 0
.
APPENDIX B Test Deficiencies #
Test Deficiency Recommended Resolution
.
Final Resolution
.
Originator /
Signature Date PORC Review of Final Resolution Date Approval of Final Resolution /
Plant Superintendent Date 18
-
. - - --
1
SQNP SPECIAL TEST 1 Page 1 of 11
-
Rev. 0
.
APPENDIX C Procedure for Determining Core Power Level l
,
I s
l 19 i
!
-
- -. . . . ..
.- - .-.
SQN?
SPECIAL TEST 1 Page 2 of 11
.
Rev. 0
.
l APPENDIX C
!
Outline t
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. P~ -- Conversion Constant Adjustment.
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-i Monitor Program so that the program output will be in percent power and equal to the primary calorimetric output.
- 2. Power Monitoring
'
a) The M/D Power Monitor Program will calculate the integral
'
power as seen by one pass of 5 or 6 detectors. After the output has been calibrated to be equal to the REF primary calorimetric it will be rerun up to once every 2 minutes or as necessary to. continuously monitor core power.
,
4 20-l
~
t ,e---- e .m- y
SQNP SPECIAL TEST 1 Page 3 of 11
,
.
Rev. 0
.
APPENDIX C CORE POWER DETERMINATION PART A: Primary side calorimetric - Data Sheet C.1 (Forced Circulation)
C.1 Use two DVMs and measure the voltage at the test points speci-fied for each loop as rapid as possible.
C.2 Calculate the AT; multiply that AT by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (Table C-1). (Special Test No. 9 uses wide range AT so a correction factor is required to compensate for pump heating, refer to Appendix D of ST-9A).
C.3 Sum the loop heat rates and convert to a percent reactor power.
The output is used in Part B.
.
.
k 21
.
.w_
SQNP SPECIAL TEST 1 Page 4 of 11
.
Rev. 0
.
APPENDIX C-CORR POWER DETERl!INATION PART B: !!/D Power Monitor Program
- 1. Set up the movable detector system for a 1 pass partial core flux map as per TI-53. Select flux thimbles as per the table below for the flux map.
Drive 10-Path Position Core Location A 10 L-5
_
B 10 L-11 C 10 E-5
- D 10 E-11 E 6 J-8 F 8 P-9 These positions may be altered by the test engineer, based upon low power physics testing results and previous special testing experience.
l 2. Determine the detector normalization constants and enter them
- into the P-250 as foilows:
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.
f c) With all 5 patn selector switches set to Emergenty, run a second flux '_ race.
d) Determine the detector normalization constants from Data Sheet C.2.
?
!
22
. . - . . -
.. . -
rm e W %
- W
- . _ . . - . . _ . _. . -
_.
SQNP SPECIAL TEST 1 Page 5 of 11
. Rev. 0
.
APPENDIX C CORE POWER DETERMINATION l,
j PART B: (Continued)
,
e) Enter these detector normalization constants into the P-250
!
as shown in the table below.
!
l Drive P-250 Address A K0908 i
B K0909 i
'
C K0910 1 D K0911
! E K0912 i
,
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 'l Normalization Factor Selects the Modified K5525 1 " Flux Map Print" Programs
'
j K0900 0 Initiated Pass Number i Calibration Constant for I K0864 Variable (I} M/D Power Monitor (1)Va riable: The value entered is a ratio of the Primary Calorimetric Indicated Power (Item B on Data v
Sheet C.1) to the M/D calculated power (UO906) times the current value entered in (K0864).
1 If no value has been entered into (K0864) enter 0.25.
Item #8 Data Sheet C.1
- New (K0864) = Current (K0864) x (UO906)
L i- 23
- - , . , - , - _ _ , . , - - - . . _ . . - . . - - --.--.-,. -
- - . - . .- - .-- . .-
,
SQNP 4
SPECIAL TEST 1 Page 6 of 11
. Rev. 0
.
APPENDIX C
,
,
CORE P0kTR DETER!!INATION
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, j and passes may be repeated as often as a power determination is required.
i NOTE: The calculated power (UO906) is printed after each pass i and may be trended by the P-250 if desired. The individ-t ual detector normalized integrals and axial offsets are j also printed.
,
i j 5. The M/D Power Monitor printout should be attached to this pro-
- cedure.
l
-
i I
!
1
,
l
!
'
l i
1
!
'
i I
e i
I
<-
24 l
- .
l o
--
9- ,. -
gg -
, _ - - - , -- -w g
- -_ - - _ -
SQNP 4
SPECIAL TEST 1 I
Page 7 of 11
- Rev. 0
.
APPENDIX C
- PART C: Using Thermocouples 1
j The incore thermocouples can be used as an indication of both core flow distribution and power shif ts during natural circulation.
Prior to running a thermocouple map or trending the eight quadrant tilts (four center lines and four diagonal tilts) the following j 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 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-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 tilte are indicative of power shifts and should be trended at approximately a 2-minute frequency. The following addressable values are the quadrant tilts:
i j Quadrant Addressable Value 1
1 U115()
2 U1160 3 U1161 4 U1162 5 i'1151
-
6 U1152 7 U1153 8 U1154 l A Short Form Hap should be run periodically or upon request from the test engiucer as an indication of core flow distribution. It should be put on the Utility Typewriter if possible. The P-250 Operator's Ccusole Reference Manual provides instructions for ob-taining thermocouple maps.
The trend output and Short Form Haps should be attached to this procedure at the end of the test.
25
_ _ .
- , . - _
SQNP SPECIAL TEST 1 Page 8 of 11
-
Rev. 0
.
APPENDIX C TABLE C-1 Temp Cp(1) di 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 7 550 1.245 3.6765 x 10 7 548 1.240 3.6862 x 10 7 546 1.236 3.6959 x 10 544 1.231 3.7057 x 10
,
542 1.226 3.7155 x 10' 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 7 532 1.206 3.7633 x 10 7
'
530 1.202 3.7729 x 10 1
i These values are from the 1967 ASME Steam Tables. Values are for a pres-sure of 2250 psia.
26
_. -,
SQNP SPECIAL TEST 1 Page 9 of 11
.
Rev. 0
.
APPENDIX C FIGURE C.1 CEfdl(R.LitJE QUARTEft COHE SYPAMETilY Cold Lear o 3 4 N-43 m ,,,. y. .l,z j O O 5
[ \
4 1 s 2
'm( /
o* h5L Logs ElUr / ) ,
- 2. l 4 3 /
g ) ExconE y cETecTOns ovevo H--? / l N-44 2 l l
Csli Ley .
-
l Of AGOf4 A L QUART ER. CORE SYF.iMETR Y 725 315*
s ,
5
%,
3 , G
' :.,
T
'N s
\
,
YO %q 135 45 Fi9ure C-l 27
. -
. . . .
. ..
._
SQNT SPECIAL TEST 1 Page 10 of 11 Rsv. 0 ,
APPENDIX C
- Data Sheet C.1 Date. Tine Unit Power Tavg F
'
Loop 1 Loop 2 Loop 3 I 4 hem # Calculation Procedure Units R2/TP-411J R6/TP-421J R10/RP-431J R1 , itP-441J Test Point 1 Loop A T - Inservice (at test point) Volts 2 Loop A T = (//1) x ( F 3 Loop A H = (#2) x Cp (from Table C.1) BTU /lbm 6
.g 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 INT N S % Reactor Power = (//7) x 0.02932 */,
( Conversion factor for AT obtained from scaling document.
Remarks:
Date By:
Checked By:
_.
_ -
SQNP SPECIAL TEST 1
- Page 11 of 11
' Rev. O APPENDIX C DATA SHEET C.2 A
N
- U N" N N N N"
- A E E E E E E Ng = 1.00 A NA 3E N = N = =
B 5~N N A B N =
~
N = BE =
C C N N A
N = N = CE =
D, D J N N=Ag = ND"E =
i'~N k'N
=
A
=
NEgE =
N N if ~ F N N De finitions :
A,E,C,D,E'F g g
= Normalized integral from su:mnary map for 3 N N N each detector in a normal path in the first pass A,B'g
= Normalized integral fron: suiamary map for each E E' E' E' E detector in an emergenej path in the second pass N,N,N' #'" # " #* *" " " # # "' ""
g g C D' E' F tector Remarks:
Data By: Date Checked By: Date _
29
SQNP SPECIAL TEST 1 Page 1 of 4
. .
Rev. 0
. APPENDIX D Procedure For Use Of Computer System For Data Collection The following parametern 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 IIot Leg Temperature T0459A
. RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Ifot Leg Temperature T0479A RCS Loop 4 Cold Leg Temperatur( T0466A Steam Generator 1 Pressure P0400A 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. 0
.
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).
BLOCK 1 Column Point Column Point Column Point 1 PO480A 7 T0459A 13 PO420A
}'
2 LO480A 8 T0446A 14 LO420A 3 T0419A 9 T0479A 15 PO440A i 4 T0406A 10 T0466A 16 LO440A 5 T0439A 11 PO400A 17- PO460A
, 6 T0426A 12 LO400A 18 LO460A 9
BLOCK 2 Column Point Column Point 1 N0049A 7 T0017A 2 N0050A 8 T0043A 3 N0051A 9 T0059A j 4 N0052A 10-13 Ifottest T/C from each core Quadrant 5 T0002A 14-18 As Required 6 T0013A 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. 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.
.
31
~ ~~
SQNP SPECIAL TEST 1 Page 3 of 4
.
Rev. 0
.
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. 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 Once the blocks are set up they can be initiated by performing the follow-ing steps for each block.
- 1. Push DIGITAL TREND button.
- 2. Select block number (1 to 6) on keyboard
- 3. Push.VALUE 1 button
- 4. Select internal number 0 = 30 sec., 1 = 1 minute, 2 = 2 minute, etc.) The 30-second interval is recommended for the duration of the test transient
- 5. Push VALUE 3 button
- 6. Push START button If it is necessary to change the trend interval of a block or trend, perform the following.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button
- 4. Select new interval number (0 = 30 sec., 1 = 1 min.,
2 = 2 min., etc) on keyboard
- 5. Push VALUE 3 button
- 6. Push START button To stop trending or block perform the following:
- 1. Push DIGITAL 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 i
l I
32
_ _
_
s "V
- . - _ _ _ _ - _ _ _ _ _ _ _ _
SQNP SPECIAL TEST 1 Page 4 of 4
.
Rev. 0
.
APPENDIX D In addition to the data recorded on the trend typewriter, the following points will be monitored on analog trend recorded.
T0056A (Core exit temp).
Others as needed (Recommend pressurizer pressure, steam generator level (WR) and steam generator pressure).
Af ter selecting the per to be used to record a value, ensure that tt is cleared by performing the following steps.
- 1. Push ANALOG TREND function button
- 2. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
- 4. Push STOP button To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on the alphanumeric keyboard
- 3. Push ADDRESS butt on
- 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 Reucat 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 prograneners console in the computer room. To initi'te an incore T/C map at that location, perform the following i 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 l
- 6. Select 1 on keyboard for short form map i
- 7. Push VALUE 3 button
- 8. Push START button 33
- _
.
SQNP SPECIAL TEST 1 Page 1 of 11
.
Rev. 0
,
APPENDIX E Safeguard Blocking Procedure The first step blocks automatic initiation of a safety injection. The safety injection alarm, manual S.I handswitch, and the reactor trip por-tion of the protection logic will remain in operation. If conditions exist that would normally initiate a safety injection; (1) the safety -
injection alarm will initiate telling the operator that the condition exists and what the problem is. (2) a reactor trip will take place auto-matically. (3) a safety injection'can be initiated manually from the switch in the control room if conditions warrant.
- 1. Install temporary jumpers and temporary alteration control tags to logic cards A216, test point 1, to the logic ground on the logic test pancis in R-47 and R-50.
NOTE: These jumpers will be specially made for this purpose and installed by an instrument mechanic.
R-47 Panel Performed by: /
Verified by: /
R-50 Panel Performed by: /
Verified by: /
Procedure for blocking automatic actuation of a safety injection on high steamline Delta-P. This block will prevent a reactor trip from occuring during the natural circulation tests from higl; 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 34
..
m
SQNP SPECIAL TEST 1 Page 2 of 11
. Rev. 0
.
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 jtunper 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. 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. Move test trip switch PS-515B in 1-R-7 tc the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 6. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-7. Apply a 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-7 and verify 1-XX-55-6B/27 is clear.
Performed by: /
Verified by: /
- 7. Move test trip switch PS-516C in 1-R-12 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 8. 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: /
35
' ~
. - _
SQNP SPECIAL TEST 1 Page 3 of 11
- Rev. 0 4
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-H-12 and verify 1-XX-55-6B/76.
Performed by: /
Verified by: /
I1. Move test trip switch PS-525B in 1-R-8 to trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 12. Lift and tape the wire on the rack side of terminal L-7 in the rear of 1-R-8. Apply 120-VAC source to terminals L-7 and L-8 and verify 1-XX-55-6B/28 is clear.
Performed by: /
Verified by: /
- 13. Move test trip switch PS-525A in 1-R-8 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 14. 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. l Performed by: /
Verified by: / l 36 l
1
]
__. _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .
SQNP SPECIAL TEST 1 Page 4 of 11
.
Rev. 0
.
APPENDIX E
- 16. Lift and tape the wire on the ' rack side of terminal L-7 in the rear of 1-R-11. Apply 120-VAC source to terminals L-7 and L-8 in the rear of 1-R-11 and verify that XX-55-6B/51 is clear.
Performed by: /
Verified by: /
- 17. Move test trip switch PS-526C in 1-R-11 to the trip por.ition 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 or Low-Low avg Safety Injection
- 19. Verify annunciators XA-55-6A/30 and XA-55-6A/31 are clear or can be- '
cleared.
Performed 'by: /
Verified by: /
NOTE: If the alarms will not clear, do not proceed with-this modifica-tion as a reactor trip may result. The input bistables should
.
be checked and the source of.the problem corrected.
- 20. Move test trip switch TS412D in R-2 to the. trip position and verify the amber light above the switch comes on.
' Performed by: /
Verified by: /
- 21. Lif t and tape the wire on the ' rack side of terminal M-3 in the rear of 1-R-2. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: /
Verified by: /
.37
.
- -
}
- - ,_ -__
SQNP SPECIAL TEST 1 Page 5 of 11
. Rev. 0
.
APPENDIX E
- 22. Move test trip switch TS-422D in R-6 to the trip position and verify the amber light above the switch comes on.
Performed by: /
Verified by: /
- 23. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-6. Apply a 120-VAC source to terminals M-3 and M-4 and verify 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: / ,
l
- 26. -Move test trip switch TS-442D in R-13 to the trip posi. tion and verify the amber light above the switch comes on.
Performed by: /
i Verified by: /
- 27. Lift and tape the wire on the rack side of terminal M-3 in the rear of 1-R-13. Apply a 120-VAC source to terminals M-3 and M-4 and verify XA-55-6A/30 will clear.
Performed by: /
Verified by: /
NOTE: The- avg inputs to the high steam-flow S.I and steam dump interlock are now blocked. The next steps will trip the stead 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
_ _ - _ _ _ _ _ - - _ _ _ _
SQNP SPECIAL TEST 1 Page 6 of 11
.
Rev. 0
.
APPENDIX E
- 28. llove 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. Ilove test trip switch FS522B in R-3 to the trip position and verify the amber light and annunciator XA-55-6B/ come on.
1 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 SWITC11 TElIP ALT. NO.
R-7 PS515A /
R-7 PSS15B /
R-12 PSS16C /
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- /
To return the steamline Delta-P S.I. to normal condition, the following steps should be followed.
39
SQNP SPECIAL TEST 1 Page 7 of 11
.
Rev. 0 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: /
Verifico by: /
- 32. 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 clear.
Performed by: /
Verified by: /
- 33. Remove the 120-VAC source from L-7 and L-8 in 1-R-11. Reterminate wire on L-7.
Performed by: /
Verified by: /
- 34. f!ove test trip switch PS-526D in 1-R-11 to the normal position and verify the amber light above the switch and 1-XX-55-6B/51 are clear.
Performed by: /
Verified by: /
- 35. Remove the 120-VAC source from L-9 and L-10 in 1-R-8. Reterminate wire on L-9.
Performed by: /
Verified by: /
- 36. llove 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: /
40
SQNP SPECIAL TEST 1 Page 8 ef 11
,
Rev. 0 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.
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 on L-7.
i Performed by: / )
Verified by: / l l
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 ley: / j Verified by: /
41
SQNP SPECIAL TEST 1 Page 9 of 11
.
,
' Rev. 0 APPENDIX E
- 45. Remove the 120-VAC source from terminals L-9 and L-10 in 1-R-7. Retermi-nate wire on '-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.
To return Lge high steam flow coincident with low steam generator pressure or 1^w-low avg to normal, perform the following steps.
- 47. !!ove test trip switch FS5223 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. !! ave t.est 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. R move 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. Move test trip switch TS442D in R-13 to the normal cosition and verify the amber light goes out and XA-55-6A/30 will clear.
Performed by: _
/
i Verified by: /
l l
i 42 1
,
.
SQNP SPECIAL TEST 1 Page 10 of 11
'
, Rev. 0
,
APPENDIX E
- 51. Remove the 120-VAC source from terminals 11-3 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 tiie amber light goes out and XA-55-6u/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.
Performed by: /
Verified by: /
- 55. Recove the 120-VAC source from terminals M-3 and M-4 in R-2. Retermi-na te wire on !!-3.
Performed by: /
Verified by: /
- 56. Ilove 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: /
43
SQNP SPECIAL TEST 1 Page 11 of 11 e
Rev. 0
,..
APPENDIX E
- 57. Remove the Temporary Alteration Tags on the following test trip switches:
RACK TEST SWITCII TEllP ALT. NO.
R-7 PS515A /
R-7 PS515B /
R-12 PS516C /
R-12 PSS16D /
R-8 PS525B /
R-3 PS525A /
R-11 PSS26D /
R-11 RS526C /
R-2 TS412D /
R-6 TS422D /
R-!d TS432D /
h-13 TS442D /
R-3 FS512B /
R-3 FS322B /
- 58. Remove the jumpers and the Temporary Alteration Tags f rom 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: /
Verificcl by: /
NOTE All reactor safeguard systems modified for the special startup tests are back in a normal configuration at this time.
44
SQNP SPECIAL TEST 1 Page 1 of 1 s
.. Rev. 0 e
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.
O
- 4 C t$ 1 b 4 t1 t 4 0 r-4
- c O 4 O ta 4 0 4 0 4 N O t O u 4 0 g C Q
.-
C 3 4 d O s 3 O O O H M O O V
.4 4 O O V O C H 4 N t1 0 4 H O d O ? H f.G O O O H 4 A O O O p .a . . .
4 O O c1 O O O V c3 O b % 4 4 4 C 4 3 C
.e4 % .e4 .H .e4 d in O d O O O O O H M t0 4 4 fr-. H H % H H H O d ed C Q C Z d d .H O d C 4 4 4 4 t3 .4
- C 0 C
%
.p to p M % 4 O LO O O M 4 4 4 d d cc 4 4 as O d d :$ .C H 9 O O
- A s; P: m O m m N m TECHNICAL FPECIFICATION 1 2 3 4 5 6 7 8 9A 9B Containment liI Pressure SI (3.3.2.1) X X X X X X X X X X Sa f e ty Lit.d t :. (2.1.1) X X X X X X X X X OP3T (3.3.1) Inoperable because of low flow X X X X X X X X X OTAT (3.J.1) Inoperable because of low flow X X X X X X X X X f!'iAiiaI Elempera ture (3.1.1.4) X X X X
!!oderator Lemnerature coef ticient (3.1.1.3) X X X X Steamline AP SI (3.3.2.1) by;assed X X X X X X X X X X liigh Steamflow coincidentgl w/ low steamline pressure or low-low avg SI IIese t flow to 01 anci' avg blocked X X X X X X X X X X Heset. 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 iHI l (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 Hatteries (3.8.2.3) X X RCS Flowrate (3.2.3) X X-X X X X X X Control Rad 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 45
SQNP SPECIAL TEST 1 Page 1 of 1
,, Rev. 0
.-
TABLE 1 Loop Flow and Core AT for Various Power Levels and Isolation Configurations (Computer Estimates)
No. of Loops Operating (Nat. Circ.)
Power Level 4 3 2 1
_ . . _ _
.5% "L = 3.7 L= 3.6 L= 4.1 L= 5.2 AT = 10.3 AT = 12.5 AT = 16.4 AT = 26
-
r
.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= 5 AT = 16.3 AT = 19.8 AT = 26 AT - ~,1
- _ l
,
1.5% L= 4.7 L= 5.2 L= 5.9 L= 7.5 AT = 21.4 AT = 26 AT = 34 l AT = 54
__L 1 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 3% L= 5.9 L= 6.5 L= 7.5 L= 9.7 AT = 34 AT = 41.2 AT = 54 AT = 85.7
!!O TE: L is % of 97,000 gym flow through operable loop.
AT = Loop AT in F.
46