ML19290C653
| ML19290C653 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/14/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19290C651 | List: |
| References | |
| PROC-791214-02, NUDOCS 8001220480 | |
| Download: ML19290C653 (37) | |
Text
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i -
e SPECIAL TEST NO. 2 NATURAL CIRCULATION WITH SDELATED LOSS OF OFFSITE AC POWER O
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- 1785 257 M*
8001220 + MMb
SPECIAL TEST NO. 2
,- 12/14/79 NATURAL CIRCULATION WITH SIMULATED LOSS OF OFFSITE AC POWER Table of Contents Page 1.0 OBJECTIVES 2 2.0 PREREQUISITES - -
3 3.0 PRECAUTIONS 6 4.0 SPECIAL TEST EQUIPMENT 7 5.0 INSTRUCTIONS 8 6.0 ACCEPTANCE CRITERIA -
DATA SHEETS 13 APPENDIX A - References APPENDIX B - Deficiencies APPENDIX C - Power Measurement Technique APPENDIX D - Computer Points APPENDIX E - Vital Eq'uipment List
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1785 258 M
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, SPECIAL NO. 2 12/14/79 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.
- e. Primary System at normal operating temperature and pressure.
This test will be conducted by simultaneously L ;1pping 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 and pressurizer heaters. After the appropriate time delay, the 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.
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1786 259 WOO
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, SPECIAL NO. 2
- , Page 1 of 11 i
, 12/14/79 1.0 OBJECTIVES 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 emergency 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.
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SPECIAL NO. 2 Page 2 of 11
' 12/14/79 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 determined as indicated in Appendix C).
/
2.2 All four reactor coolant pumps in operation.
/
2.3 RCS pressure at approximately 2235 psig and temperature of approximately 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 accordance with System Cserating Instruction SOI 3.2A and B.
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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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278 ~AIleast 190',000lilTons in"tETTindensate Storage TanksInd available to supply the auxiliary feedwater system.
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2.9 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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2.10 Excess letdown is available for service if required during the test.
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2.11 6.9-kV Shutdown Board 1A-A energized from 6900V unit board.
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2.12 6.9-kV Shutdown Board 13-B energized from 6900V unit board.
/
1786 2,61
Page 3 of 11 2.0 (Continued) 12/14/79 2.13 Diesel generators lA-A and IB-B in standby status.
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2.14 Control and auxiliary building service air compressors C and D in service powered from the auxiliary building common board.
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- 2. 15 Unit 1 turbine turning gear oil pump on the emergency DC supply.
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2.16 Waste Cas compressor B in service. (Powered from unit 2 Rx Vent Board 2A-A).
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2.17 Cloce/ Verify 1-FCV-1-17 by placing 1-HS-1-17A into manual and close possition. (1-HS-1-17A located on panel 1-M-4).
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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 circulation with the turbine-driven AFWP will be verified during the conduct of Special Test No. 7.
o 2.18 Record on / -computer recorder.
- a. Flux
- b. Average wide range T eold
- c. Average vide range T
- d. Averagesteamgenerakorpressure
- 2.19 , Connect recorder y o J eA llowing test points: --- -
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 - Loop 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. 1 L-3-163, TP13,1-L-llB Aux. Feed Flow to SG#1 Channel No. 2 L-3-155, TP13,1-L-llA 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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SPECIAL NO. 2 Page 4 of 11 12/14/79 2.0 (Continued) 2.20 Record on the recorder charts the following information:
- a. Unit number
- b. Date
- c. Procedure number
- d. Scale and range of parameters recorded es Chart speed
- f. Time c:atter interval
- g. Recorder I.D. No.
- h. Name of individual recording data NOTE: Ensure recorders are powered from vital AC.
2.21 Set the trend recorders and computer trend printer in the main control room to monitor the parameters indicated'in Appendix D.
/
- -~
... . . . . _,m we.v % .
1785 263 m
Page 5 of 11 12/14/79 3.0 PRECAUTIONS 3.1 Maintain reactor coolant pump seal and thermal barrier differential pressure requirements as given in SOI 68.2. (It is recommended that component cooling pump C-S be utilized being powered from unit 2 480-V shutdown board 2B2-B and o gned 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 Do not exceed the following temperature limits:
3.3.1 Core exit temperature of 610 F 3.3.2 d T as indicated by T -T of 65 F h
3.3.3 RCS Tavg 578 F 3.4 When equilibrium is established af ter the initial transient, avoid any sudden changes in auxiliary feedwater flow or in steam generator water level.
3.5 Af ter the reactor' coolant pumps are tripped, the normal Tavg and A T indication will become unreliable. 4 T should be calculated taking the difference (T - T )cand Tavg calculated by taking the average of the hotandcoldkegtemperatureindications. . , .
~
3.6 Following the blackout and af ter 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 r7 Maintain pressurizer ~ievel T Yater than 20%. ~~
3.8 Reactor Coolant Pumps should not be restarted for 30 minutes af ter pump trip unless safety concerns necessitate the re-establishment of forced circulation.
1786 264 M
SPECIAL NO. 2 Page 6 of 11 14 . 0 Soecial Test Equitment Identification Calibration Instrument Specification Number Verificatier Strip Chart Recorder Brush 260 or equivalent 6-channel (2)
Reactivity Computer Westinghouse
- ..n . -
~ -, n If test instru=ents are changed durin, "lis test, the instrument infor=ation must be recorded here and an entry made in the chronological log book explaining this change.
1786 265 -
SPECIAL NO. 2 Page 7 of 11 12/14/79 5.0 TEST INSTRUCTIONS 5.1 Clear the unit 1 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.
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- 5.3 Place / verify 6.9-kV Shutdown board 1B-B manual transfer selector switch IS-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 13-B logic relay panel to the normal position.
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5.6 Place diesel generator 2A-A 43TL switch, located on 6.9-kV shutdown board 2A-A logic relay panel to the test position.
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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.
. . , . - /- ---
NOTE: This will prevent auto start of diesel ganerators 2A-A and 2B-B when the blackout signal is initiated on diesel generators LA-A and 13-B.
5.8 Record data indicated on Data Sheet 5.1.
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5.9 Place / verify pressurizer backup heaters lA-A and IB-B in automatic.
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5.10 Trip and lock out pressurizer backup heaters 1C & ;9 _
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5.11 Start the computer trend printer printing at 1-minute intervals. (See Appendix D, the interval may be changed if deemed necessary by the test engineer. )
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1785 266 _
SPECIAL NO 2 Page 8 of 11 12/14/79 5.0 (Continued) 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. When the reactor cooolant pumps are first tripped, the steam generator water level will first shrink, due to flow coastdown, and then swell as natural circulation reaches equilibrium.
Following RCP trip, the following response is expected:
Wide range T slight decrease or stable Wide range T eold increase CoreexitT/b increase T unreliable
[8T unreliable Pressurizer Pressure increase 5.13 As close to simultaneously as possible perform the following actions.
NOTE: Time zero
- a. Trip all 4 reactor coolant pumps /
- 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 dt;mp cantrqla.,1-H4-1-103A and 1-HS-1-103B to off.4nd place controllers to manual.
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5.14 Verify diesel generators lA-A and 1B-B started, energized their 6.9-kV shut-down boards and the following equipment sequenced onto the shutdown boards:
Component Cooling Water Pumps /
Auxiliary Feedwater Pumps /
Centrifugal Charging Pumps /
Pressurizer Heaters /
ERCW Pumps /
- Remove non-essential loads.
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.
. . 1785 261 -
SPECIAL NO. 2 Page 9 of 11 12/14/79 5.0 (Continued) 5.15 Re-establish normal letdown and transfer control of the pressurizer 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 vital equipment listed 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 (approximately 33%).
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5.19 Verify automatic control of auxiliary feedwater pumps and power-operated reliefs to maintain a normal operating level and pressure in the steam generators (approximately 33% level and 1000 psig).
. /
NOTE: If automatic control of auxiliary feedwater and power reliefs fail to maintain the normal steam generator level, change to manual control of auxiliary feedvater flow control valves and power relief valves.
5.20 Verify natural circulation.is established in accordance with the operational guideline of Emergency Operating Instruction 5 (Blackout),
~ ~~Kppendix A', and131n'hihTi~ eld ' state conditions for 30 minutes.
/
NOTE: Natural circulation flow will be stable when:
- a. O T between wide range T and T is constant.
hot eold
- b. d T between wide range T and core edt T/C average temperature is constant.
cold vs
- c. Wide range T ==. core exit T/C average temperature.
5.21 Turn off data recorders and note time on charts.
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5.22 Establish ventilarion and cooling :he remaining areas in accordance with E0I 5, Sections C through G sequent Operation Action).
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5.23 Perform section V " Recovery", steps I through K, of E0I 5.
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1785 2I)8
SPECIAL NO. 2 Page 10 of 11 12/14/79 5.0 (Continued) 5.24 Verify header varm and open FCV 1-1-17 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.
5.25 Adjust condenser dump controllers to 0%.
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5.26 Place steam dump controls 1-RS-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 hoc zero power test range. -- -
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5.28.2 Restart reactor coolant pumps one at a time.
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5.28.3 RCS pressure at agproximately 2235 psig and temperature at appr,oximate1 e Q 48J % _ __. - -
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5.28.4 Pressurizer pressure and level controls in automatic.
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5.28.5 Auxiliary Feedwater System in service and operating in 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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5.28.8 Collect data charts and attach to data sheet 5.2.
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1785 2a69 e
SPECIAL NO. 2 Page 11 of 11 12/14/79 6.0 ACCEPTANCE CRITERIA 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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6.3 T, for any loop did not exceed 578 F.
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t 6.4 Natural circulation was established and maintained while emergency 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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e 1785 270
Date SPECIAL NO. 2 Time Page 1 of 3 Unit 12/14/79 DATA SHEET 5.1 Initial Conditions Pressurizer Pressure PR-68-340 Psig Pressurizer Level LR-68-339 Red Pen I
- 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
- 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 te=p o TR-68-60 F S.G. #1 Level (narrow range)
LI-3-42 %
~~ ~
S.G. #2' Leiter (narrow range 7-*""""
LI-3-55 %
S.C. #3 Level (narrow range)
LI-3-97 T.
S.G. #4 Level (narrow range) '
LI~3-110 %
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 (vide range)
LR-3-98 Pen 2 %
Data by: /
-u. \186 271
SPECIAL NO. 2 Page 2 of 3 12/14/79 DATA SHEET 5.1 (Continued)
S.C. #1 Pressure PI-1-2A p318 S.G. #2 Pressure PI-1-9A psig S.C. #3 Pressure PI-1-20A psig S.C. #4 Pressure PI-1-27A psig S.C. #1 Feedwater flow FI-3-35A gpm S.G. #2 Feedwater flow FI-3-48A Spm S.G. #3 Feedwater flow FI-3-90A gpm S.G. #4 Feedwater flow FI-3-103A gpm S.G. #1 Steam flow -
FI-1-3A lbs/hr S.G. #2 Steam flow FI-1-10A lbs/hr S.G. #3 Steam flow
. FI-1 -21A. ,._ _ , _ _ , , _ , . _ , _ _ .
lbs/hr S.G. #4 Steam flow FI-1-28A lbs/hr Loop #1 T-average TI-68-2E ,F Loop #2 T-average TI-68-25E ,F Loop #3 T-average TI-68-44E ,F Loop #4 T-average TI-68-67E ,F Data by: /
1785 272
SPECIAL NO. 2 Page 3 of 3 12/14/79 DATA SHEET 5.1 (Continued)
Loop #1 T TI-68-2D %
Loop #2 T TI-68-25D %
Loop #3 T
- TI-68-44D Loop #4 T TI-68-67D %
(0-52 F = 0-100~)
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 %
NIS Channel N-44 (Power Range Channel 4) - > -
Computer Point N0052A - %
Remarks:
Data by: /
Reviewed by: /
1785 273
.Date SPECIAL NO. 2 Time Page 1 of 1 Unit 12/14/79 DATA SHEET 5.2 Attach the computer printout from the following parameters. Refer to Appendix 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 RCS Loop 4 Cold Leg Temp steam Generator 1 Pressure Steam Generator 1 Wide Range Level Steam Generator 1 Narrow Range Level 1 Steam Generator 1 Narrow Range Level 2 Steam Generator 1 Narrow Range Level 3 Steam Generator 2 Pressure . - > -
Steam Generator 2 Wide Range Level Steam Generator 2 Narrow Range Level 1 Steam Generator 2 Narrow Range Level 2 Steam Generator 2 Narrow Range Level 3 Steam Generator 3 Pressure Steam Generator 3 Wide Range Level Steam Generator 3 Narrow Range Level 1 Steam Generator 3 Narrow Range Level 2
~ ~ . _ _ _
Steam Generator 3 Narrow Range ~EsvEl 3 ~ ^
Steam Generator 4 Pressure Steam Generator 4 Wide Range Level 3 team Generator 4 Narrow Range Level 1 Steam Generator 4 Narrow Range Level 2 Steam Generator 4 Narrow Range Level 3 Power Range Channel 1 Power Range Channel 2 Power Range Channel 3 Power Range Channel 4 Incore Thermocouples #1 through #5 (upper head)
)786 274
SPECIAL NO. 2 Page 1 of 1 12/14/79 APPENDIX A References
- 1. FSAR
- 2. Technical Specifications
- 3. Plant Operating Instructions: SOI 3.2 SOI 68.2 E0I 5 1785 275
Unit Form Date Appendix B 2/6/79 Page of Rev.
Page of Test Deficiencies #
Test Deficiency Recomended Resolution
.._ , , _ _ . _ . - ~ , , - - . ~ -
Final Resolution Originator /
Signature Date PORC Review of Final Resolution Date Approval of Final Resolution Plant Superintendent
/
Date
!
- J{ _
SPECIAL NO. 2 Page 1 of 10 12/30/79 APPUDIX C
. Punchlist:
- 1. Part C - Thermocouples
- 2. Part B - Address in P-250 for:
- a. Priority scan option selection
- b. Power calibration constant
- c. Calculated power e
- " #eW . . . . hg @M====
1786 277
SPECIAL NO. 2 Page 2 of 10 12/30/79 APPENDIX C (Continued)
Outline I. Core Power Determination A. Primary Side Calorimetric (Forced Circulation Only)
- 1. Reference (N 550 F) Calorimetric (Before NC test) a) Output used to adjust M/D Power Monitor Progras's power conversion constant.
B. M/D Power Monitor Program
- 1. Power Conversion Constant Adjustment.
a) The output of the REF primary calorimetric vill give a % power output; this output must be input to the M/D Power-Monitor Progras so that the program output vill be in percent power and equal to the primary calorimetric output.
- 2. Power Monitoring
.t ) The M/D Power Monitor Program vill 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 vill be rerun up to once every 2 minutes or as necessary to continuously monitor core power.
1786 278 -
SPECIAL NO. 2 Page 3 of 10 12/30/79 APPENDIX C CORE POWER DETEIMINATION PART A: Primar-f side calorimetric - Data Sheet C.1 (Forced Circulation)
C.1 Use two DVMs and measure the voltage at the test points specified for each loop as rapid as possible.
C.2 Calculate the 4 T; multiply that A T by the specific heat and the Westinghouse best estimate flow rate of the core average temperature (Table C-1). (Special Test No. 9 uses vide range A T so a correction factor is required to compensate for pump heating, refer to Appendix D of ST-9A).
- C.3 Sun the loop heat rates and convert to a percent reactor power. The output is used in Part B.
1786 279
SPECIAL NO. 2 Page 4 of 10 12/30/79 APPENDIX C (Continued)
Core Power Determination PART B: M/D Power Monitor Program
- 1. Set up the movable detector system for a 1 pass partial core flux map as per TI-53. Select flux thimbles as per the table below for the flux map.
Drive 10-Path Position Core Location A
B C
D E
F 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: pith
- select 6r~ Twitches set toEmergency[runa second flux trace.
d) Determine the detector nor=alization constants from Data Sheet C.2.
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 1785 280
SPECIAL NO. 2 Page 5 of 10 12/30/79 APPENDIX C (Continued)
Core Power Determination PART B: (Continued)
- 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.
Address Value Function K0901 1 Set the power nor=alization factor Sele::ts the modified K5525 1 " Flux Map Print" progrs=s K0900 0 Initiated Pass Number Calibration Constant for M/D K086h Variable Power Monitor (1 Variable: The value entered is a ratio of the Primary Calorimetric Indier.ted Power (Iten B on Data Sheet C.1) to the M/D calculated pove- (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 (K086k) x (UO906)
- 4. For pereer determination, obtain a partial core flux =ap 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 detector normalized integrals are also printed.
. + - -
1786 281
SPECIAL NO. 2 Page 6 of 10 12/30/79 APPENDIX C (Continued)
TABLE C-1 o
Cp(1) m femp F BTU /lbm F lbm/hr 7
556 1.260 3.6448 x 10 7
554 1.255 3.6553 x 10 7
552 1.250 3.6659 x 10 7
550 1.245 3.6765 x 10 548 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 10 540 1.221 3.7254 x 10 538 ,
1.217 3.7348 x 10 536 1.213 3.7443 x 10 534 1.209 3.7538 x 10 7
532 1.206 3.7633 x 10
- - .- 530. - - ----1v203 -- 3.7729 x 10 (1)These values are from the 1967 ASME Steam p1bles. Values are for a pressure of 2250 psia.
1785 282 p
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0 1
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p 2 m h 3 o t m ) # o 7 9 r s o 1 ( o 0 2 f e r L 3 0 t f C x 9 d e ( ) + 2 0 e r t e ) 5 n u a l 3 #3 0 x i d ( b # ( a e a ( p x ) t c e p T = o 7 b o c C ) o rI o
= #
r i m 6 (
P v x x o r e # T r r e w+ ( =
e n e ) ) f w o i
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1 2
(
P o P2 = r e A T t I ( ( w rp r w a o r oo e o r l - = = l o t o w P o u F t cI o f c T T H c a P r l S a e+ o r a C - e R r o C A A A R R 1 o t
c t p p p p l
p ap t a c c e a o o o o o t o a R f n o c n oo c TL e I L I I I R % n o :
i s y r B e : :
- v s y d e
n k B e
m e o r k 1 2 3 b 5 6 7 8 C a e c t t m t e a I e a h D R D C C gDw-C i' , I 'I- ! l i .lll ' l!
SPECIAL NO. 2 Page 8 ofl0 12/30/79 APPENDIX C (Continued)
A = B = C =
N N N D
N" -
N" N g= B, = C, = D, = E, = r=
s NA - 1.00 . -
N =b = Ak =
B B N N N ~ " "
C **
Cy Cy N "
D" "
N N D
N E =b- = DE =
b b "E
Ny
p = EE
N N De finitions,: _ _ , _ _ ___ _ ..
A,B,C,D,E,F = Normalized integral from smry map for each N N N N N N detector in a normal path in the first pass A,B' E E E' E' E' E
= Normalized integral from summary map for each detector in an emergency path in the second pass N.N' A B C' D' E' F
~ ** #"* ** " "" # ' # **" * ""U #
Remarks:
Data By: Date 1786 284 M
SPECIAL NO. 2 Page 9 of 10 12/30/79 APPENDIX C (Continued)
Part C: Using Themocouples The incore thermocoupir.s 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 A T is unreliable K0791 = 0.075, Core bypass flov fraction K5010 = 8, Tells thermocouple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the running frequency of the Therscouple Averaging Program at 1, 2, . . .. X 8 seconds or 64 seconds for us.
The therscouple programs breaks the core down into eight quadrants-four centerline and four diagonal quadrants (see Figure C-1). Quadrants 1 k 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 ._ _
$ . . . 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 he Utility Typewriter if possible. The P-250 Operator's Console Reference
.enual provides instmetions for obtaining thermocouple maps.
The trend output and Short Form Maps should be attached to this procedure at the end of tne test.
1785 285
SPECIAL NO. 2 .
- vh, Page 10 of 10 i . ..p,;[4p' 12/30 h"-'"![' APPENDIX C j [. ; {/'Jg h1l- (c6ntinued) g[)Myt.
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SPECIAL NO. 2 Page 1 of 4 12/14/79 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 Hot Leg Temperature T0419A RCS Loop 1 Cold Leg Temperature T0406A RCS Loop 2 Hot Leg Temperature T0439A RCS Loop 2 Cold Leg Temperature T0426A RCS Loop 3 Hot Leg Temperature T0459A RCS Loop 3 Cold Leg Temperature T0446A RCS Loop 4 Hot Leg Temperature T0479A RCS Loop 4 Cold Leg Temperature T0466A Steam Generator 1 Pressure PO400A Steam Generator 1 Wide Range Level LO403A Steam Generator 1 Narrow Range Level 1 LO400A Steam Generator 1 Narrow Range Level 2 LO401A Steam Generator 1 Narrow Range Level 3 ELO402A Steam Generator 2 Pressure PO420A Steam Cenerator 2 Wide Range Level LO423A Steam Generator 2 Narrow Range Level 1 LO420A Steam Generator 2 Narrow Range Level 2 LO421A Steam Generator 2 Narrow Range Level 3 LO422A Steam Generator 3 Pressure PO440A Steam Generator 3 Wide Range Level LO443A Steam Generator 3 Narrow Range Level 1 'LO440A Steam Generator 3 Narrow Range Level 2 LO441A Steam Generator 3 Narrow Range Level 3 LO442A Steam Generator 4 Pressure PO460A Steam Generator 4 Wide Range Level LO463A Steam Generator 4 Narrow Range Level 1 LO460A Steam Generator 4 Narrow Range Level 2 LO461A Steam Generator 4 Narrow Range Level 3 LO462A 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 1785 287 . O
SPECIAL NO. 2 Page 2 of 4 12/14/79 APPENDIX D (Continued) The computer trend typewriter will be used to monitor the following computer points. (Additional points may be added as required by the test director) . BLOCK 1 Column Point Column Point Column Point 1 PO480A 7 T0459A 13 P0420A 2 LO480A 8 T0446A 14 LO423A 3 T0419A 9 T0479A L5 PO440A 4 T0406A 10 T0466A 16 LO443A 5 T0439A 11 PO400A 17 PO460A 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- 13 Hottest T/C from each core Quadrant 5 TOOO2A 1_4-18 As Required , , ._ 6 T0013A . To initially clear each data block perform the following step for each block to be used.
- 1. Push DIGITAL TREND button
- 2. Select block number (1 to 6) on keyboard
- 3. Push VALUE 1 button ~ ~
4; -SeltettotrTeytroard -
- 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.
- 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 1785 288 .
SPECIE NO. 2 Page 3 of 4 12/14/79 APPENDIX D (Continued) Once the blocks are set up they can be initiated by performing the following steps for each block.
- 1. Push DIGITE TREND batton.
- 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 S. Push VALUE 3 button
- 6. Push START button To stop crending 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 pof.nts 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 MALOG TREND function button
- 2. Select per number (1 to 12) on keyboard
- 3. Push VALUE 1 button
- 4. Push STOP button 1785 289
SPECIAL No. 2 Page 4 of 4 12/14/79 APPENDIX D (Continued) To start an analog trend perform the following steps.
- 1. Push ANALOG TREND function button
- 2. Select the computer point address (i.e. T0043A) on the alphanumeric keyboard
- 3. Push ADDRESS button
- 4. Select per number (1 to 12) on keyboard
- 5. Push VALUE 1 button
- 6. Select per position on keyboard. This is the minimum value of the parameter to be monitored
- 7. Select range on the keyboard
- 8. Push VALUE 3 button 9.
Push START button Repeat these steps until all of the desired analog points are being recorded. Prior to initiation of the transient, and at 15-minute intervals 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. S'e lect output device code number 20 for program =ers 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
__. _m._.. 1786 290
SPECIAL NO. 2 Page 1 of 3 12/14/79
- APPENDIX E Verification Of Vital Equipment Energized 1
Verification (Initials or Component Power Feed Location N/A if not required) Ceneral Supply 480V S.D. Bd 1Al-A Fan IA General Exhaust 480V S.D. Bd 1A2-A Fan lA General Supply 480V S.D. Bd 131-B Fan 1B General Exhaust 480V S.D. Bd 1B2-B Fan IB C/A Vent Bd 1A2-A 480V S.D. Bd 1A2-A Rx Vent Bd 1A-A 480V S.D. Bd 1Al-A Control & Service Air 480V S.D. Bd 1A2-A Compressor A Control Room 480V. S.D. Bd 1A2-A- - > - A/C Comp. A-A
- Control Room 480V S.D. Bd 1Al-A AHU A-A Control & Service Air 480V S.D. Bd 1B1-B Compressor B
- .. . ..n -.. -~__ -.,. ,..
Control Room A/C 480V S.D. Bd 132-B Comp. B-B Control Room 480V S.D. Bd 132-B AHU B-B Component Cooling System Rx MOV Bd 1Al-A Booster Pump A-A Incore Instrument Room Rx MOV Bd 1Al-A CIRC. Pump 1A Incore Instrument Room Rx MOV Bd 1Al-A Chilled Water Compressor incore Instrument Room Rx MOV Bd lAl-A Air Conditioner 1-785 291 H* , een
SPECIAL NO. 2 Page 2 of 3 12/14/79 . APPENDDt E (Continued) Verification (Initials or Component Power Feed Location N/A if not required) Boric Acid Transfer Rx MOV Bd 1Al-A Pump 1A-A Boric Acid Tank A Rx MOV Bd 1Al-A Heater A-A Boric Acid Tank C Rx MOV Bd lAl-A Heater A-A Boron SIS INJ Tank R*. MOV Bd 1Al-A Heater 1A-A Incore Inst Room Cire Rx MOV Bd Pump 1B 131-B Incore Inst Room Rx MOV Bd Cooler Fan 131-B Incore Inst Room Rx MOV Bd Chilled Water Comp 1B 131-B Boric Acid Tank A - Rx MOV Bd Heater B-B 131-B Boron SIS INJ Tank Rx MOV Bd Heater B-B 131-B Boric Acid Tank C Rx MOV Bd
. Heater B,B_ _ , _ _ ,1B1-B , _ _.
Boric Acid Transfer Rx MOV Bd Pump 1B-B 1B1-B Component Cooling Rx MOV Bd System Booster Pump B-B 131-B Containment Annulus C/A Vent Vacuum Fan lA Bd 1Al-A Cent. Charging Pump 1A-A C/A Vent Room Cooler Fan Bd IAl-A 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 1785 292 9
- SPECIAL NO. 2
- Page 3 of 3 12/14/79 APPENDIX E (Continued)
Verification (Initials or Component Power Feed Location N/A if not required) Cent. Charging Pump 1B-B C/A Vent Room Cooler Fan Bd 131-B Aux Feedwater Pump C/A Vent Space Cooler Fan Ba 131-B . Containment Annulus C/A Vent Vacuum Fan IB Bd 1B1-B CRDM Room C/A Vent A/C Bd 1B2-B 14per Compartment Rx Vent Bd Cooler Fan IA 1A-A Upper Compartment Rx Vent Bd Cooler Fan 1C 1A-A Upper Compartment Rx Vent Ed Cooler Fan 1B 1B-B Upper Compartment Rx Vent Bd Cooler Fan ID 1B-B Waste Gas Rx Vent Bd Compressor A 1A-A
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1785 293
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