ML19290C662
| ML19290C662 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/14/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19290C651 | List: |
| References | |
| PROC-791214-04, NUDOCS 8001220545 | |
| Download: ML19290C662 (22) | |
Text
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SPECIAL TEST NO. 8 ESTABLISEMENT OF NATURAL CIRCULATIONS FROM STAGNANT CONDITIONS 9
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SPECIAL NO. 8 12/14/79 ESTABLISHMENT OF NATURAL CIRCULATIONS FROM STAGNANT CONDITIONS Table of Contents Page 1.0 OBJECTIVES 1 2.0 PREREQUISITES .
. 1 3.0 PRECAUTIONS 2 4.0 SPECIAL TEST EQUIPMENT 4 5.0 INSTRUCTIONS 5 6.0 ACCEPTANCE CRITERIA S APPENDIX A - References 8 APPE!OIX B - Deficiencies 9 APPENDIX C - Power Measurement Technique 10 i
1787 095 ..
SPECIAL NO. 8 12/13/79 TEST DESCRIPTION
. With stagnant (no flow) conditions existing throughout the primary system, core power will be increased t.o simulate decay heat and steam generators will be utilized to establish a h' eat 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 indication . Core exit thermocouples will be monitored to access core flow distribution.
1787 096
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- SPECIAL NO. 8 Page 1 of 5 12/lk/79 1.0 OMECTIVE 1.1 Verify establishment of natural circulation from stagnant (no flov) conditions in the primary system using reacs or power to simulate decay heat.
2.0 PREREQUISITES . .
2.1 Reactor critical in the hot zero power test range.
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2.2 All reactor coolant pumps operating.
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2.3 Steam pressure approximately 900 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 the normal no-load setpoint and being maintained by auxiliary feedvater system (motor-driven pumps).
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25 Control Bank D at approximately 160 steps or as specified by the test engineer to per=it reactor power increase up to approximately 3% (required control band D position may be determined during the hot zero power test program).
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. 2 6 0v,grpower AT t.hd4 a'WL .__ . -
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2.7 Overtemperature 4 T trip is disabled.
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2.8 Pressurizer level control in mar.ual.
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1787 097
UYLULAL RU. O Page 2 of 5 12/14/79
'2. 0 (Continued) 29 Record the folleving parameters.
291 Obtain thermocouple map at 15-sinute intervals.
292 Set up P-250 to monitor the following parameters at 5-minute intervals.
- a. Wide range 'f ps) cold
- b. Wide range T ps)
Power _ range h cst (all 1
- c. annels
- d. Intermediate range channel's
- e. (all loops)
- f. T"#*T (all loops)
- g. Icop flov (1 from all h loops)
- h. Steam generator level (all 4 loops)
- 1. Steam generator pressure (all 4 loops)
NOTE: Record the following information en each strip chart:
a) Unit number b) Date c) Special Test number d) Scale and range of measured parameter e) Chart speed f) Recorder ID number 293 Record on reactivity computer recorder.
- a. Flux
- b. Average vide range T eold
- c. Average vide range T D. Averagesteengenerek8rpressure 2 9.4 Record on Recorders.
- a. Recorder No. 1. _ _.
- .. .,- 5-lv -Icomde TE!" jug-
- 2. Loop 1 wide range T
- 3. Icop 1 steam genera %old cr pressure
- k. Loop 2 vide range T 5 Loop 2 vide range T
- 6. Icop2steamgenerafggdpressure
- b. Recorder No. 2
- 1. Loop 3 vide range T
- 2. Loop 3 vide range T 3 Loop 3 steam generaf.old or pressure
- k. Loop 4 vide range T 5 Icop k vide range T hot Id
- 6. Loop h steam generaE8r pressure
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2.10 Trend 3 incere T/C's as determined by the test engineer on the analog
-trend recorders on the main control board.
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.2.11 Crossover pipe stratification monitoring thermocouples are installed and operable.
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. 1787 098
SPECIAL NO. 8 Page 3 of 5 12/14/79 3.0 PRECAUTIONS, LIMITATIONS, AND ACTIONS 3.1 Do not exceed 5% rated thermal power.
3.2 Do not exceed any of the following temperature limits.
3.2.1 610 F for any core outlet thermocouples 3.2.? 65 F for any loop Delta-T 3.2.3 578 F for any loop Tavg 3.3 Avoid sudden changes in steam pressure.
3.4 Avoid sudden changes in auxiliary feedwater.
3.5 Maintain pressurizer pressure at about 2235 psig.
3.6 Onset of natural circulation may be accompanied by a power increase due to the introduction of cooler water into the core.
3.7 During natural circulation, reactor coolant losp transient time is on the order of 3 to 5 minutes. ,
3.8 Pressure should remain equalized between steam generators throughout the test.
I 3.9 Maintain constant steam generators pressure throughout test except where specifically stated oJ.erwise.
3.10 Maintain steam generator water level constant at e- 33%.
. 3.11 Dop ot maintain no.f. legsc radit4ena_in the primary system for more than 30 minutes.
3.12 Reactor coolant pumps should not be restarted for 30 minutes after pump trip unless required by this instruction or unless safety concerns necessitate the re-establishment of forced circulation.
3.13 Monitor condensate storage tank level throughout test.
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1787 099 _.
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SPECIAL NO. 8
. Page 4 of 6 12/14/79 1.0 4 Special Test Equipment Identification Calibration Instrument Scecification Number Verification
>.1 Reactivity computer Westinghouse o.2 Recorder Brush or equivalent
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s If test instru=ents are ch nged during this test, the instrument information must be recorded here and an entry made in the chronological log book explaining this change.
1787 100
SPECIAL NO. 8 Page 5 of 6 12/14/79 5.0 INSTRUCTIONS CAUTION: If primary system temperatures reach 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 e 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 recorder and P-250 trend block.
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5.2 Begin recording crossover pipe T/C temperatures at 5-minute intervals.
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CAUTION: Following reactor coolant pump trip Tave and Delta-T indication will be unreliable.
5.3 Trip all reactor coolant pumps simultaneously and record time:
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5.4 Stabilize steam generator water level at approximately the no-load level.
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5.5 Close main steam du=p valves to condenser.
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5.6 .Close auxiliary.fedvanagsyx em. level. control valves.
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NOTE: During control bank withdrawal continuously monitor increase in:
a) reactivity computer flux level, b) NIS indicated power level, and core exit thermocouple temperature (except delayed response).
5.7 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 with-drawal, as requested by the test engineer, until reactor power is at 1 percent.
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5.8 Record control bank D position: steps
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CAUTION: Onset of natural circulation may be accompanied by a power increase.
Control bank D may be inserted to reduce the magnitude of the increase.
Immediately following power transient, return control bank D to the position recorded in step 5.8.
1787 101 .
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orr., e av. o Page 6 of 6 50 -(Continued) 12/lb/I9 CAUTION: Reduction in T may result in a nonconservative, false NIS power levelindicatigg}d Do not withdraw control bank D beyond the position recorded in step 5.8 unless requested by test engineer.
NOTE: At initiation of natural circulation the following initial response is expected.
- 1) Reactivity computer flux level increase
- 2) NIS power level indicatica increase
- 3) Wide range T increase
- 4) Wide range -
slight decrease or stable ofd
- 5) Core exit thermocouples a) Increase if T/C temp.+ (~17 F) < initial T b) Decrease if T/C temp. + (~17 F) > initial T CAUTION: Primary coolant system may be held in a stagnant condition (no flow) for a maximum of 30 minutes. If the NIS or primary 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.
59 Reduce steam generator pressure 50 psig ( ~ 20 F) or until natural circulation is initiated. Rate of pressure decrease should be accomplished at a controlled rate as requested by the test engineer. Utilize auxiliary feed as necessary to maintain steam generator level constant.
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NOTE: Natural circulation flov , vill be stable when:
a) 4 T between vide range T and T is constant.
b) 4 T between vide range T and 88 N exit T/C average temperature is constant.
c) Wide range T c core exit T/C average temperature.
5 10 When natural circulation flov has established, slowly regulate secondary
~. side steam flov to-alowly w ase-T to ~ 547 F. During natural circulation loop transient time is 18 (3 to 5 minutes).
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5 11 Maintain natural circulation under the established conditions for approxi-mately 15 minutes.
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5.12 Stop recording test data.
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5.13 Insert control bank D until the reactor is in the hot zero power test range.
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5 1h Restart reactor coolant pu=ps one at a time as previously described.
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5 15 Attach all strip charts, trend data, and T/C maps to this test procedure.
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1787 102~~
SPECIAL NO. 8 Page 7 of 7 12/14/79 5.0 (Continued) 5.26 Return pressurizer level control to automatic.
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NOTE: Reactor trip and safety injection actuation signals specified in steps 5 16, 5.17, and 5 18 may remain disabled provided testing scheduled to be performed i==ediately f611oving 'this test requires disabling the trip or safety injection signal. If a trip is to remain disabled place N/A and your initials on the signature line.
5 17 overpower 4 T trip is operable.
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5.18 Overtemperature 4 T trip is operable.
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I 6.0 ACCEPTANCE CRITERIA 6.1 Delta-T established between vide range T and T is stable and less than 65 F.
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6.2 Delta-T established between. wide range T and core exit T/C average temperatureisstableandlessthan65F3
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1787 103
SPECIAL NO. 8 Page 1 of 1 12/14/79 APPENDIX A References e
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Appendix B 2/6/79
- Page of Rev.
Page of Test Deficiencies #
Test Deficiency t
Recormended Resolution as
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Final Resolution
'e Originator /
Signature Date PORC Review of Final Resolution} Approval of Final Resolution , /
- Plant Superintendent Date
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SPECIAL NO. O Page 1 of 10 22/30/79 APPEITDIX C 4 Punchlist:
- 1. Part C - Ther=occuples
- 2. Part B - Address in P-250 for:
- a. Priority scan option selection
- b. Power calibration constant
- c. Calculated power 1787 106
SPECIAL NO. 8 I . Page 2 of 10 12/30/79 APPENDIX C (Continued)
- Outline I. Core Power Determination e
A. Primary Side Calorimetric (Forced Circulation Only)
- 1. Reference ( 550 P) 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
! 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 Pover-Monitor Program so that the program output vill be in percent power and equal to
. the primary calorimetric output.
- 2. Power Monitoring
, a) 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 l rerun up to once every 2 minutes or as necessary to continuously monitor core power.
i 1787 107 _u_ h. 4 1
SPECIAL NO. 1 Page 3 of 10
- 12/30/79 APPENDIX C CORE POWER DETERMINATION PART A: Primary side calo1 3etric - 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 Sum the loop heat rates and convert to a percent reactor power.. The output is used in Part B. e.mG J g1@' y a w _ -T
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SPECIAL NO. 8 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-path"seGr'E/Teches 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. Drive P-250 Address A K0908 B K0909 C K0910 D K0911 E K0912 F K0913 1787 109 q
SPECIAL NO. 8 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 normalization factor Selects the modified K5525 1 " Flux Map Print" programs K0900 0 Initiated Pass Number Calibration Constant for M/D K086h Variable Power Monitor (1 Varictle: 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 (K086k) = Current (K0864) x (UO906) i
- h. 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 detector normalized integrals are also printed.
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1787 110
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SPECIAL NO. 8 Page 6 of 10 12/30/79 APPENDIX C (Continued) TABLE C-1 Tcmp Cp( ) , m F BTU /lbm F lbm/hr 7 556 1.260 3.6448 x 10 554 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 10 546 1.236 3.6959 x 10 544 1.231 3.7057 x 10 7 542 1.226 3.7155 x 10 540 1.221 3.7254 x 10 7 1.217 .. 3.7348 x 10 ,. 538
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7 536 1.213 3.7443 x 10 7 534 1.209 3.7538 x 10 532 1.206 3.7633 x 10 7 530 1.202 3.7729 x._10__ (1)These values are from the 1967 ASME Steam Tables. Values are for a pressure of 2250 psia. 1787 111
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SPECIAL NO. 8 Page 8 of 10 i , 12/30/79 l APPENDIX C (Continued) i A N
= B N" b" N" N" N" A
E
= B E" k* E" E" E" N = 1.00 A
N.,
= = b- =
Ak = 3 N N N = = BE = C N b N, = b = "C% = D N N N ~ ~ ~ ~~ * E i s s - Np =bI
= EE I
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N N sefinitions:
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A' Normalized integral from summary map for each N N' b' N' N' N
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detector in a normal path in the first pass A,B' = Normalized integral from summary map for each E E E' E' E' E detector in an emergency path in the second pass N,N' = Detector normalization factor for each detector A B C' D' "E' F Remarks: Data By: Date N.
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_ - . . . - ...- ... - a - . . . . - - - . - ' SPECIAL NO. 8
- Page 9 of 10 12/30/79 APPENDIX C (Continued)
Part C: Using Thermocouples The incore ther=occuples 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 flow fraction K5010 = 8, Tells ther=occuple program how many readings of thermocouples are required for averaging before calculation is done. This in turn sets the running frequency of the Thermcouple 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-h 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 approxi=ately a 2-minut.e frequency. The.following addressable values are the quadrant tilts:. Quadrant Addressable Value 1 - U1159 2 U1160 3 Ull61 h U1162 ~ ~
-- . U1151 5_._ _
6 Ull52 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 fer obtaining thermocouple maps. The trend output and Short Form Maps should be attached to this procedure at the end of the test.
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