ML20211A196
| ML20211A196 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 09/19/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| TAC-62972, NUDOCS 8610150018 | |
| Download: ML20211A196 (38) | |
Text
/
.1 DUKE POWER COMPANY McGUIRE-NUCLEAR STATION:
. McGUIRE UNIT 2 j CYCLE 3
- STARTUP REPORT September 19, 1986 i~
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I 1 TABLE OF CONTENTS Page
~ List of Tables ii List of Figures lii 1.0 Introduction 1 2.0 Criticality 3
.3.0 Zero Power Physics Testing 4 3.1 .All Rods Out Boron Endpoint Measurement - 8 PT/0/A/4150/10 3.2 All Rods Out Isothermal Temperature Coefficient 9 Measurement - PT/0/A/4150/12 3.31 Control Rod Worth Measurement - PT/0/A/4150/11 12 3.4 Control Rod Worth Measurement: Rod Swap - 15 PT/0/A/4150/11A 4.0 Power Escalation Testing 17 4.1 Incore and NIS Recalibration: Post Outage - 22 PT/0/A/4600/02E
'4.2 Thermal Power Output Measurement - PT/0/A/4150/03 25 4.3 Reactivity Anomalies Calculation - PT/0/A/4150/04 27 4.4 Incore and Nuclear Instrumentation System 28 Correlation Check - PT/0/A/4600/02A 4.5' Target Flux Difference Calculation - 29 PI/0/A/4150/08 4.6 Core Power Distribution - PT/0/A/4150/02A 30 i
's LIST OF TABLES Page
- 1. Overlap Data 5
- 2. Nuclear Heat 6
- 3. _ Reactivity' Computer Checkout 7
- 4. Control Rod Worth Measurement: Rod Swap 16
- 5. Core Power Distribution Results - 45.3% Full Power 18
- 6. Overlap Data 21
- 7. Quarter Core Flux Map Data for PT/0/A/4600/02E, Incore 23 and NIS Recalibration: Post Outage
- 8. Thermal Power Output Measurement Results 26
- 9. Core Power Distribution Results - 100% Full Power 31 I
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" t' 'O LIST OF FIGURES Page
- 1. Unit 2 Cycle 3 Core Loading Pattern 2
- 2. ARO ITC Heatup and Cooldown Data: First Run 10
- 3. ARO ITC Heatup and Cooldown Data: Second Run 11
- 4. Control Bank C Rod Worth 13
- 5. Control Bank D Rod Worth 14
- 6. Power Distribution - 45.3% 19
- 7. Relative Errors in Power Distribution from 20 Predicted - 45.3%
- 8. Incore and NIS Recalibration Results 24
- 9. Power Distribution - 100% 32
- 10. Relative Errors in Power Distribution from 33 Predicted - 100%
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1.0 Introduction Core loading for McGuire Unit 2 Cycle 3 was started on April 18, 1986 at 2130. Core loading was completed on April 24, 1986 at 0245. Criticality, zero power physics testing and power escalation testing were performed under PT/0/A/4150/21, Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing starting June 17, 1986 at 2030 and ending July 5, 1986.
Figure 1 gives the Unit 2 Cycle 3 core loading pattern.
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- Figure 1 YcGuire Lni: 2
[ ,g h QUADRANT 1 2 Core Loading Pattern 4 3 ASS.#
INS.#
P21 P44 P09 P39 P23 P3,4 PO4 g 105 119 69 43 68 96 81 P29 PSS G05 N59 G25 N46 G28 N05 G43 PQ7 P15 g 205KT R154 212KT R113 #52K R133 4P53K R134 213KT R107 31%f P27 G45 POS N55 G03 N04 P56 NOS G56 N13 P16 G12 P37 3 88 117 209KT R139 F05K Rit! 0559 4101 F32K R138 218KT 22af 59 P03 P2O N46 Q37 L62 G38 N12 033 L22 G35 N07 Pio P25 4 46 R103 F2R 107 F24K Rt45 F31K 331KT 8837K R127 208KT Rit7 4102 POS Q24 N61 G27 N41 G01 N06 N63 N62 Q42 N38 G22 N21 Gid P49 5 FOOK 334KT 20tKT 85 8Pt7K 122 OP27K R143 218KT 60 58 220KT R126 F19K 72 P0i N20 QSO L46 G46 N31 Q40 N45 060 N17 G39 L35 G36 N15 P12 g F22K R104 F35K R116 OP23K R106 Sc20K 52 8P40K Ridd 124 80 R131 F03K 83 N36 Q13 N37 352 N14 P02 N16 Gli N35 G26 N47 Q46 P51 7 P59 G47 P14K R125 4P58K 207KT 73 F50K Rt49 OPiSK 51 F2R 217KT 108 225KT F04K 139 P48 N56 N22 N09 P31 L25 P46 N01 N30 N53 P30 N54 P55 g PO5 N52 R110 137 R124 2114T R150 84 R129 121 94 Rt36 114 R152 21RT R148 101 N57 G51 N24 P43 N34 059 N44 GCE N51 G58 PS2 g P11 G31 N43 G49 202KT F34K 125 8802K R108 4P51K 45 56 APSR Ride OP2tK So F10K 222KT 130 Qi9 Gio N25 G20 N42 G30 LO9 Q29 N50 P53 P41 N64 G07 L18 N26 10 PtOK Rit8 F39K R147 F074 Rt40 F09K 228KT BP36K Rit9 90 123 Rt42 8P28K 31MT N27 Q44 N32 Q34 N28 N33 N49 G53 N18 Q32 NO3 G16 P13 ig P26 Q15 F29K 95 $P13K R112 103 55 67 2tRT R132 F12K 111 F38K 229KT 2274T 312KT P57 P60 N11 G23 L47 009 NO2 000 L60 Q17 N58 P40 P18 4g 147KT R105 8ptiK 126 8P06K Rii5 F01K 210KT F30K R153 120 A151 R122 P24 N10 054 N29 P54 N39 GiB N19 P38 004 P32 13 P17 G41 0558 R121 F16K R123 226KT 214KT 203KT 204KT 223KT 91 R135 F33K R141 P14 P36 G02 N40 Q21 N60 G57 N23 G55 P47 P50 g4 R137 221KT Ri2o 4P54K R130 AP49K R109 30iKT R128 75 100 P45 P42 P35 P19 P33 P22 P28 15 57 71 270KT 127 318KT 53 133 R P N M L K J H G F E D C B A o
2
. o 2.0 Criticality - PT/0/A/4150/28 On June- 17, 1986 at 1235 boron samples of the reactor coolant system, pressurizer and_ volume control tank were taken in preparation for the approach to criticality. These samples indicated reactor coolant boron to be 1537 ppm, pressurizer boron to be 1537 ppe and volume control' tank boron to be,1544 ppm. Since it was desired to go critical with a significant amount of Control Bank D inserted (*750 pcm), a target value of 1343 ppm was chosen for reactor coolant boron concentration. This represented the predicted BOL, ARO, HZP, No Xenon, equilibrium Samarium critical boron concentration of 1418 ppm'less 75 ppm. Calculations using the unit Data Book indicated a volume of 8205 gallons of demineralized water should be added to the system to dilute from 1537 ppm to 1343 ppm.
At 2030 on June 17, 1986, this dilution of the reactor coolant system was started. The dilution was secured at 2150 after 8207 gallons of demineralized water had been added to the system. After appropriate system mixing, Chemistry samples indicated reactor coolant system boron was 1318 ppm, pressurizer boron was 1312 ppm and volume control tank boron was 1313 ppm.
At 0150 on June 18, 1986, rod withdrawal commenced starting with Shutdown Bank A. As rods were withdrawn, both source range detectors were observed and rod motion was stopped each time flux level doubled. At these points a set of counts were taken on each source range detector and Inverse Count Rate Ratio (ICRR) plotted to monitor the approach to criticality. The unit achieved criticality at 0303 on June 18, 1986 with Control Bank D at 34 steps withdrawn. The predicted critical position per OP/0/A/6100/06, Reactivity Balance Calculation was 34 steps withdrawn on Control Bank D.
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.. o 3.0 Zero Power Physics Testing- (ZPPT)
Zero Power Physics Testing for McGuire 2 Cycle 3 started June 18, 1986 and was completed June 26, 1986. The output of Power Range Detector N43 was used as input to the reactivity computer for Zero Power Physics Testing.
All acceptance criteria for ZPPT were met.
A minimum of one decade of overlap between the source range and the intermediate range detectors was verified on June 18, 1986. The results are shown on Table 1.
The point of adding nuclear heat was determined June 18, 1986 at 1041.
This was done by establishing a slow positive startup rate and observing a change in plant parameters such as an increase in Reactor Coolant System average temperatures (Tave) with a change in the reactivity trace and an increase in pressurizer level. Table 2 gives the results of the two tries.
-6 amps on Nuclearheatwasdeterminedtobeatafluxlevelof1.6{x10 the reactivity computer picoammeter (N43) and_6.02 x 10 amps on Intermediate Range Detector N35 and 5.73 x 10 amps on Intermediate Range Detector N36. From these resuly the tegt band for ZPPT except for flux mapping was determined to be 10 to 10 amps on the reactivity computer.
Excessive noise below 10 7 amps prevented the test band from being any lower.
On June 18, 1986 at 1118, an on line checkout of the reactivity computer was performed. This was done by withdrawing _ Control Bank D until a positive reactivity insertion of $25 pcm was indicated on the reactivity computer. The time for the flux level to double was measured and from this doubling time (DT) the reactor period was calculated (period = DT/.693). Using the reactor period, the amount of reactivity was determined using the predicted data. This reactivity was compared to the reactivity computer indication. The test was repeated for a reactivity insertion of +50 pcm. The results met all acceptance criteria and are given in Table 3.
A negative reactivity insertion test was also completed satisfactorily.
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. o TABLE 1 Overlap Data Source Range Intermediate Range cps _ amps N31 N32 N35 N36 4.0 x 10 3 3.5 x 10 3
5.5 x 10
~II 5.0 x 10
~II 0 -10 -10 5.0 x 10 4.5 x 10 0 5.5 x 10 5.0 x 10
-10 -10 When SR blocked 6.0 x 10' 5.5 x 10' 5.5 x 10 5.0 x 10 5
.. .o TABLE 2 Nuclear Heat Reactivity Computer Intermediate Range N43 N35 N36
-6 1.05 x 10 4.95 x 10 ~7 4.86 x 10 ~7
-6 -7 ~
2.25'x-10 7.10 x 10 6.60 x 10 1.65 x 10 -6 6.02 x 10 -7
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AVERAGE amps 5.73 x 10 amps-Test Band: 10
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to 10
-6 amps on N43.
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. o TALLE 3 Reactivity Computer' Checkout
- Initial Flux Level (Amps) Period Doubling Time- Reactivity Reactivity +
Reactivity Computer Seconds Seconds- Computer (apc) DT (ap DT) % Error 4.0 x 10 -7 260.04 180.21 24.3 24.1 0.8 4
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4.0 x 10 260.66 180.64 24.4 24.1 1.2 7
2.0 x 10 217.9L 151.06 27.7 28.1 1.4 4.0 x 10 ~7 223.52 154.90 27.7 27.5 0.7 2.0 x 10~ 103.94 72.03 51.8 52.2 0.8 4.0 x 10 -7 106.35 73.70 51.8 51.3 1.0
-7 4.0 x 10 109.91 76.17 49.7 49.9 0.3
+ Apc - ApDT x 100 ApDT
c..
3.1 All Rods Out Boron Endpoint Measurement - PT/0/A/4150/10 This test was perfbreed June- 18,1986 at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />. Control Bank D was initially at 210 steps withdrawn, the Reactor Coolant System boron concentration was 1377 ppm and the Pressurizer boron-concentration was 1378 ppm.
Control Bank D was pulled to the All Rods Out (ARO) Configuration and the resulting reactivity change was converted to equivalent boron using the predicted Inverse Boron Worth. Control Bank D was then reinserted to the just critical condition and the test was repeated two more times.
The results of these reactivity changes were each added to the initial Reactor Coolant System boron concentration to give three values for the ARO Boron Endpoint. These values were averaged to give the final result of 1380 ppm. This value met the acceptance criteria for the Hot Zero Power (HZP) ARO Critical Boron concentration of 1418 150 ppm.
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3.2 All Rods Out Isothermal Temperature Coefficient Measurement -
PT/0/A/4150/12 -
This test was started on June 19, 1986 at 1516. The test measures Isothermal Temperature Coefficient (ITC) by plotting Reactivity versus Average Reactor Coolant System Temperature. The Moderator Temperature Coefficient (MTC) is found using the relationship as follows:
MTC (pcm/*F) = ITC - Doppler Temperature Coefficient The acceptance criteria on the ARO ITC was 0.08 i3.0 pcm/*F. The predicted Doppler Temperature Coefficient was -1.83 pcm/'F.
Two more sets of heatup/cooldown pairs were done to establish repeatability of the data. Control Bank D was at 219 steps withdrawn and the Reactor Coolant System boron concentration was 1386 ppm at the start of the test. 'The results are shown in Figures 2 and 3.
.The average ARO ITC was found to be -0.55 pcm/ F. This fell within the acceptance criteria band. This gave an ARO MTC of +1.28 pcm/ F.
Following the completion of this test, PT/0/A/4150/31, Determination of Rod Withdrawal Limits to Ensure Moderator Temperature Coefficient within Limits of Technical Specifications was performed. The results of,this test indicated there were no rod withdrawal limits needed for Cycle 3.
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ARO ITC Heatup and Cooldown Data : Second Run
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3.3 Control Rod Worth Measurement - PT/0/A/4150/11 On June 19, 1986 at 2118 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.05899e-4 months <br />, Control Bank C rod worth was measured using the established boration/ dilution method. There were no other rods in the core at the time. Control Bank C was predicted to be the highest worth bank and was measured using this method so as to serve as the reference bank for Control Rod Worth Measurements'by Rod Swap.
The measured worth of Control Bank C was 787 pcm. The predicted
. worth was 921 pcm i 138 pcm. This represented an error of -14.5% and was within the acceptance criteria of 15%. Figure 4 shows the measured integral and differential rod worths for Control Bank C.
Following the performance of PT/0/A/4150/11A Control Rod Worth Measurement: Rod Swap (discussed in Section 3.4), the core was left in a configuration suited for performing rod worth measurement for Control Bank D by boration/ dilution. This was done on June 26, 1986 at 0143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br />. Again, there were no other rods in the core. The measured worth of Control Bank D was 556 pcm. The predicted worth was 591 pcm 1 59 pcm. The error was -5.9%, well within the acceptance criteria, also. The resulting integral and differential rod worths for Control Bank D are shown in Figure 5.
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Figure 5 Control Bank D Worth 14
_ _ ._._ ~ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _
3.4 Control Rod Worth Measurement: Rod Swap - PT/0/A/4150/11A On June 20, 1986 the rod swap method of control rod worth measurement was started. Control Bank C was used as the reference bank and its worth was measured by the boration/dllution method (see Section 3.3).
Starting with the' reference bank essent .t1 the way in and the reactor just _ critical, each control and down bank was swapped into the core for the reference bank. Il integral worth of the test bank was determined from the difference i.. the critical rod position of the reference bank with and without the test bank in.the core.
The measured worths were compared with predicted worths and all banks
-were within the acceptance criteria of 30% or +200 pcm whichever was greater. While performing the rod swap measurement of Shutdown Bank D, the DRPI indicated a stuck rod in location L-03. The unit was taken to Mode 3 by inserting all rods. The rod in L-03 was then exercised and found to be free. A Rod Drop Timing Test was performed five times (with drop times ranging from 1.98 to 2.20 seconds) to verify this rod's operability. The unit returned to Mode 2 and rod worth measurement by rod-swap was completed.
The results of the rod swap test are given on Table 4.
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TABLE 4 Control Rod Worth Measurement: Rod Swap Bank Predicted Worth Neasured Worth Percent +
-Identification pcm pcm++ Difference Control Bank C 921 787* -14.5
. (reference)
Control Bank D 603 544 - 9.8 Control Bank B 669 654 - 2.2 Control Bank A 380 304 -20.0 525 J'f;f $S A
Shutdown Bank E 428 -16.9 Shutdown Bank D 429 415 - 3.3 Shutdown Bank C 423 404 - 4.5 Shutdown Bank B 919 842 - 8.4 Shutdown Bank A 6.0 365. 387 i
TOTAL R0D WORTH 5224 4765 - 8.8 l
- Measured by boration/ dilution method
+ Measured - Predicted x 00 Predicted i ++ Rounded to nearest pcm l
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4.0 Power Escalation Testing McGuire Unit 2 Cycle 3 Power Escalation testing started June 27, 1986 at 0145 and was completed July 11, 1986.
The unit went on line June 27, 1986 at 1558 and began increasing reactor power at 2 1/2% per hour.
The load increase was secured on June 28, 1986 due to secondary chemistry being out of specification. Load was later increased to approximately 45%
and held for flux mapping.
At 45.3% reactor power, Core Power Distribution, PT/0/A/4150/02A, was performed to verify the core power distribution technical specification limits for operation at 100% power would not be violated. All acceptance criteria for this test were met. Table 5 and Figures 6, 7, 8, 9 and 10 give the results of this test.
After performing PT/0/A/4150/02A, Core Power Distribution, power was increased from 50% to 80% and PT/0/A/4600/02E, incore and NIS Recalibration: Post Outage was performed during this time (see Section 4.1).
The unit reached 100% Full Power July 2 at 0200 and the remainder of power escalation testing was completed after reaching equilibrium conditions and is discussed in Section 4.2. Table 6 gives overlap data for intermediate range detectors between 3% and 100% Full Power.
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TABLE 5 Core-Power Distribution Results 45.3% Full Power Unit 2 Cycle 3 Map FCM/2/03/001-Date/ Time Map Taken 6/28/86 2304 Power Level 45.3%
Cycle Burnup 0.3 EFPD 12.8 MWD /MTU Boron Concentration 1165 ppe Control Rod Position Control Bank D at 210 steps withdrawn Maximum F : 1.5495'at Axial Loc. 34,'Horiz. Loc.
'*Y G-12
-Maximum F : 1.9584 at Axial Loc. 42, Horiz.
O Loc G-12 Maximum F :
Z 1.2622 at Axial Loc. 40 1
Maximum pin F 1.4500 at Horiz. Loc. G-12 Maximum error AH (fr m Predicted) 9.17% at Horiz. Loc. K-12 Maximum F /K(Z) 2.0149 at. Axial Loc. 42 Maximum % Reduction in AFD Wings N/A I Minimum % Margin to AFD Wings -49.2083% at Axial Loc. 39 R,,, (Tech Spec 3/4.2.3) 0.8359
, Total NC Flowrate (Process Computer) .407485 gal / min j Total Incore Axial Offset 8.197% ,
l Incore Tilts %:
Upper Core Lower Core Quadrant 1: 0.188% Quadrant 1: -0.190%
1 Quadrant 2: 0.361% Quadrant 2: 1.153%
L Quadrant 3: 0.505% Quadrant 3: 0.184%
Quadrant 4: -1.054% Quadrant 4: -
1.147%
1 NOTE: Axial location 1 is the bottom of the core.
Axial location 61 is the top of the core.
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f O F fl12.8 0 MCGUIRE DCTECTOR RUN (UNIT 2QYgtE faUCLCAll PCAKI:JG FACTORS FOR ENTilALPY RISE FOR ASS DLAf TiiE POWF.R NnRNALIZAT1till g
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01 02 03 04 05 06 07 00 09 to 11 12 13 14 15 l
O O A 0.509 0.655 0.647 0.688 0.666 0.666 0.511 8
.o D 0.527 0.796 1.117 0.966 1.163 0.999 1.197 0.982 1.112 0.790 0.523 g C 0.529 1.115 1.102 1.074 1.213 1.074 1.285 1.101 1.190 1.064 1.105 1.121 0.541 O O D 0.807 1.120 1.052 1.220 0.969 1,2 18 1,164 1.239 0.947 1.193 1.054 1.138 0.836
- 8 E 0.497 g.117 1 101 1 250 1 012 1.249 1 031 0 987 1 005 1.166 1 004 1.206 1.309 1.167 0.536 F 0.639 0.945 1.255 0.942 1.169 1.064 1.244 1.085 1.155 1.009 1.214 1.022 1.275 0.995 0.674 i$ ,
0 G 0.645 1.184 1.091 1.197 0.961 1.192 1.077 1.164 1.019 1.169 1.020 1.338 1.139 1.193 0.658 C
8 O #
H 0.664 1.011 1.270 1.078 0.922 1.063 1.14P 0.921 1.163 1.067 0.922 1.139 1.284 1.012 0.676 1.242 0.673
- O J 0.614 1.163 1.087 1.206 0.969 1.165 0.997 1.159 1.052 1.216 0.970 1.17J 1.101 o
c u "
K 0.639 0.970 1.210 0.924 1.159 1.015 1.146 1.024 1.168 1.058 1.178 0.895 1.209 1.021 0.690 g y ,
O u ,4 L 0.510 1.111 1.063 1.156 0.993 1.171 0.967 0.876 0.921 1.219 1.061 1.201 1.101 1.155 0.532 $0 0 $$ #
M 0.765 1.099 1.042 1.220 1.008 1.258 1.097 1.190 0.981 1.225 1.050 1.113 0.795 g
- 1.126 1.127 0.506
- 14 0.502 1.096 1.129 1.122 1.332 1.136 1.282 1.289 1.100 1.121 I
0 P 0.917 0.780 1.141 1.010 1.190 0.998 1.242 1.015 1.122 0.798 0.524 ,
H 0.505 0.646 0.634 0.650 0 660 0.676 0.515 O e i
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04 05 06 07 08 09 to 11 12 13 14 15 h M
' 01 02 03 i i a$ 9 0.007 i
O A 0.011 0.010 0.009 -0.020 -0.020 -0.007 ~t I
u -0.013 -0.011 0.003 0.010 0.008 -0.007 -0.019 -0.006 0.008 =0.002 -0.007 ts O
3 C -0 016 -0.014 -0.007 -0 003 0.005 0.000 -0 025 -0 017 0.025 0.006 -0.010 -0.019 -0.038 3 e
, ns
. D -0.019 -0.016 -0.003 -0.001 0.002 -0.024 -0.054 -0.017 0.025 0.021 -0.006 -0.032 -0.053 N N 9 O C 0.040 0.009 -0.020 -0.018 0.040 -0.034 -0.041 -0.047 -0.016 0.036 0.049 0 .011# -0.027 -0.034 -0.035 G
! r 0.039 0.on -0.02 3 0.038 0.038 -0.011 -0.034 -0.0i0 0.040 0.0u -0.001 -0.044 n.038 -0.014 -0.014 3 ,
o s c I G 0.016 -0.005 -0.003 0.024 0.037 0.016 -0.014 0.019 0.043 0.037 =0.031 -0.084 -0.046 -0.012 -0.004 3 e H 0.019 =0.024 -0.008 0.027 0.028 0.022 0.042 0.052 0.029 0.018 0.028 -0.028 -0.020 -0.024 0.001 gy oo u g
- J 0.067 0.013 0.000 0.016 0.028 0.040 0.066 0.024 0.010 -0.003 0.027 0.045 -0.013 =0.051 -0.026
[ Ya
- l K 0.039 0.012 0.013 0.058 0.047 0.037 0.049 0.050 0.029 -0.006 0.030 0.092 0.014 -0.038 -0.037 g ,
0 L 0.013 0.014 0.016 0.062 0.060 0.031 0.022 0.073 0.074 -0.010 -0.008 0.022 -0.019 -0.024 -0.029 > e a.
e 0.004 0.024 -0.010 -0.006 -0.008 -0.010 -0.004 $
j l1 0.034 0.002 0.006 -0.001 -0.037 -0.032 0.028 M #
- N 0.036 0.003 -0.031 -0.046 -0.085 -0.047 -0.022 -0.039 -0.054 -0.027 -0.024 -0.024 m i
f, P 0.006 0,0g0 -0.0g7 -0,034 -0.014 -0.015 -0.056 -0.038 -0.001 -0.013 -0.008 54 R 0.019 0.024 0.031 0.037 =0.011 -0.021 -0.002 . o l
j e i
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- Tile MLAri VALUE = 0.0013 AND THE STANDARD DEVIATION a 0.0305 ruR THE ABOVE 193 VALUES 0.0917 AT K-12 g 0.0246 THE MAXINUM NAGNITUDE =
'I THE MEAN OF THE ABSOLUTE VALUES s
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TABLE 6 Overlap Data Intermediate Range (Volts) Thermal Power
- Power Level Date Time N35 N36 Best Estimate (%)
6% 6/27/86 1457 7.962 7.882 6.485 10% 6/27/86 1640 8.186 8.150 10.563 20% 6/28/86 0430 8.540 8.482 20.116 25% 6/28/86 0916 8.689 8.628 26.1313' 30% 6/28/86 1135 8.786 8.722 30.8582 50% 6/29/86 1712 9.051 8.983 50.6826 75% 6/30/86 1930 9.348 9.275 78.0439 100% 7/02/86 0430 9.465 9.391 99.9365 i
21
= 4.1 Incore and NIS Recalibration: Post Outage - PT/0/A/4600/02E This test was started on June 29, 1986 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> and was run during the power escalation from 50% to 80% Full Power. The data obtained from this test was used to set the nuclear instrumentation system amplifier gains, the axial flux difference function of the overpower AT setpoints and to determine the correlation between incore and excore axial offsets.
The data were collected by taking a quarter core flux map and associated excore detg tor currents at ten different axial offsets as indicatedinTable/U7(Thequartercorefluxmappatternhad '
dhh) previously been verified as an accurate representation of axial offset through PT/0/A/4150/23, Quarter Core Flux Map Qualification Test). This data was then input into an off-1 ne computer program-which generated the output shown in Figure The appropriate factors were then input into the plant instrumentation systems and ${)
all acceptance criteria were met.
l i
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22
TABLE 7 Quarter Core' Flux Map Data for PT/0/A/4600/02E, Incore and NIS Recalibration: Post Outage Map Average Thermal Power (%) Incore Axial Offset (%)
- 1) QCM/2/03/005' 49.198 9.911
- 2) QCM/2/03/006 51.027 7.486
- 3) QCM/2/03/007 53.480 4.251
- 4) QCM/2/03/008 55.583 2.783
- 5) QCM/2/03/009 57.885 0.870
- 6) QCM/2/03/010 60.358 -1.875
- 7) QCM/2/03/011 63.038 -2.978
- 8) QCH/2/03/012 65.200 -/.2?2
- 9) QCM/2/03/013 75.120 -5.16.1
- 10) QCM/2/03/014 78.160 -5.942 23
1
)
thit 2 Cycle 3 FULL PeutR SETECTOR CURA 9ff m!CR0AWII CORRESPSDINI TO W!OUS INC0AE AIIE OFFIETI ININ NTECT M F 41 IETECTE F 42 IETECT M F 43 NTECTE F 44 ABIE WFMT T I T 8 i 8 T I 30.0 506.4 304.3 475.2 331.6 405.4 295.1 432.5 317.4 20.0 407.1 435.5 453.7 371.2 3I0.7 333.2 415.7 357.3 10.0 47.6 406.6 432.1 410.9 372.0 371.3 390.0 397.0 0.0 440.0 537.7 410.6 450.5 355.2 409.4 302.0 43.7
-10.0 420.5 500.0 3M.1 490.1 330.5 447.5 365.1 476.3
-20.0 - 409.0 639.9 367.6 529.0 321.8 405.6 340.3 516.0
-30.0 389.4 691.1 34.1 569.4 305.1 523.7 331.4 55.7 2
R 0.9237 -0.9075 0.9364 -0.9017 0.9274 -0.9846 0.9262 -0.9030 NOME!!G NTECTR YOLTAGES !YOLTSI AT VARINI AIIE WFETS INCORE NTECT R N-41 NTECT M N-42 MTECTM N-43 lETECT M N-44 AIIE OFFIET T 8 T-I T I T-I T 8 T-8 i 8 T-I 30.0 9.420 5. 954 3.4M f.640 6.131 3.509 f.5N 6.005 3.542 9.433 6.059 3.374 20.0 f.056 6.74 2.310 9.203 6.I64 2.339 f.114 6.700 2.334 f.065 6.816 2.249 10.0 9.693 7.530 1.155 0.767 7.597 1.170 0.722 7.555 1.167 8.690 7.573 1.125 0.0 I.330 0.330 0.000 I.334 1.330 0.000 I.330 0.330 0.000 0.330 1.330 0.000
-10.0 7.f47 f.122 -1.155 7.193 f.063 -1.170 7.930 f.105 -1.167 7.962 f.007 -1.125
-20.0 7.644 f.914 -2.310 7.457 f.796 -2.339 7.54 f.800 -2.334 7.595 f.844 -2.249
-30.0 7.244 10.7% -3.4M 7.020 10.529 -3.509 7.154 10.655 -3.502 7.227 10.601 -3.374 AFI INCORE/EICORE RATIOS FOR OUADAANTS 1 - 4 0U48 4 0U48 2 00A01 00AO 3 N-41 N-42 N-43 N-44 M = 1.442 M=1.424 M = 1.427 M = 1.401 Figure 8 Incore and NIS Recalibration Results 24
. . - - . . - . - . - . . . . . _ _ _ _ . - _ _ _ - . _ - - . -- .__-... =
4.2 Thermal Power Output Measurement - PT/0/A/4150/03 This test was used to verify that the primary and secondary heat balances on the plant computer were consistent with primary and
-secondary heat balances on an offline computer. The test was run on July 11, 1986 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> after reaching 100% F.P. and the results are shown in Table 8.
The acceptance criterion of i2% difference between the offline computer and the plant computer was met.
25
n.
TABLE 8 Thermal Power Output Measurement Results Plant Computer Off-Line Computer
% Wt %
Primary Heat. Balance 101.00 3445.14 101.11 3448.77 Secondary Heat' Balance 100.15 3416.13 99.47 3392.79 l
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4.3 Reactivity Anomalies Calculation - PT/0/A/4150/04 :
1 This test compared the actual core reactivity to the predicted core reactivity by taking into account the actual Reactor Coolant System l boron concentration, Xenon and Samarium worths, rod positions and power level and adjusting these to the ARO, Hot Full Power (HFP),
equilibrium Xenon and Samarium condition and then comparing the e theoretical and actual Reactor Coolant System boron concentration for this conditions.
The test, performed at 100% on July 5,'1986 at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />, indicated that the actual ARO, HFP, equilibrium Xenon and Samarium condition boron concentration was 928 ppm. This compares to a predicted value of 966 ppm. The 38 ppm difference translated into a -341 pcm error between actual and predicted reactivity worths. This was, however, within the acceptance criterion for the test of iS00 pcm.
1 27
4.4 Incore and Nuclear Instrumentation System Correlation Check -
PT/0/A/4600/02A This test was used to compare the incore axial offset as indicated by a full core flux map to the axial offset indicated on the plant computer by the excore detectors. This test also verifies the incore/excore calibration data that had been implemented during PT/0/A/4600/02E, Incore and NIS Recalibation: Post Outage.
The test was performed at 100% on July 5, 1986lat 1336 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.08348e-4 months <br />. The indicated incore axial offset from flux map FCM/2/03/015 was 0.235%.
The core average axial offset from the excore detectors was 1.68%.
These results gave an absolute difference of 1.445% and did not challenge the acceptance criterion of i3% difference.
'l i
I 28 t
L
- s e
4.5 Target Flux Difference Calculation - PT/0/A/4150/08 This test was performed to find the target axial" flux difference (AFD) which is used to provide guidance for plant operation.
The test was performed on July 11, 1986 at 0915 after reaching 100% F.P. The target A'D i at 100% F.P. for quadrant I was 0.63%; for quadrant 2, 0.62%; for quadrant 3, 0.47%; and for quadrant 4, 0.88%.
! All acceptance criteria for this test were met.
4 i
i I,
29
.o e 4.6 Core Power Distribution - PT/0/A/4150/02A On July 5, 1986 at 1340, PT/0/A/4150/02A, Core Power Distribution, was performed to verify the core-power distribution technical specification limits for operation would not be violated. The reactor was at 100% Full Power and equilibrium conditions.
. All acceptance criteria for this test were met. Table 9 and Figures 9 and 10 give the results of this test.
.(
4 l
l 30
c
.> o TABLE 9
' Core Power Distribution Results 100% Full Power Unit:2 Cycle 3 Map FCM/2/03/015 Date/ Time Map Taken 7/5/86 1408 Power Level 100%~
Cycle Burnup 5.89 EFPD 237.6 MWD /MTU Boron Concentration 926 ppm Control Rod Position Control Bank D at 215 steps withdrawn Maximum F" : 1.5338 at Axial Loc. 27, Horiz.' Loc.
- Y C-13 T
Maximum F : 1.8308 at Axial Loc. 31, Horiz.
O Loc C-13 Maximum F :
Z 1.2116 at Axial Loc. 32 Maximum pin F 1.3719 at Horiz. Loc. M-07 N
Maximum error Fg (from predicted) 5.94% at Horiz. Loc. G-05 Maximum F /K(Z) 1.8360 at Axial Loc. 33 Maximum % Reduction-in AFD Wings N/A Minimum % Margin to AFD Wings -5.6977% at Axial Loc. 34 R,,, (Tech Spec 3/4.2.3) 0.9219 Total NC Flowrate (Process Computer) 405228 gal / min Total Incore Axial Offset 0.235%
Incore Tilts %:
Upper Core Lower Core Quadrant 1: -0.698% Quadrant 1: -0.393%
Quadrant 2: 0.824% Quadrant 2: 0.506%
l Quadrant 3: -0.325% Quadrant 3: 0.114%
Quadrant 4: 0.199% Quadrant 4: -0.227%
NOTE: Axial location 1 is the bottom of the core.
Axial location 61 is the top of the core.
i i
31
-w-MCGUIRE OETECT02 Run (UNIT 2gCYCLE 3) U237R #
CUCLEA3 PEIKICG FECTO25 FOR E;THALPY RISE FOR ASS .4 L C S' THE PorER K002ALIZATION
.. e 01 02 03 04 05 06 07 08 09 to 11 12 13 14 15 9
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- 0.507 0.652 0.644 0.681 0.660 0.674 0.529
- D 0.529 0.792 1.101 0.962 1.167 0.993 1.189 0.995 1.151 0.826 0.550 *
., C 0.523 1.104 1.085 1.040 1.201 1.071 1.280 1.094 1.198 1.061 1.114 1.139 0.541 .
D 0.785 1.091 1.031 1 196 0.957 1.226 1.119 1 223 0.954 1.206 1.04J 1.117 0.816 E 0.507 1.125 1.086 1.222 1.037 1.211 1.015 0.960 0.993 1.190 1.041 1.220 1.092 1.147 0.526 F 0.652 0.983 1.252 0.970 1.171 1.053 1.246 1.092 1.196 1.033 1.218 0.995 1.243 0.986 0.667 G 0.645 1.171 1.086 1.198 0.940 1.189 1.003 1.189 1.034 1.182 1.001 1.266 1.103 1.184 0.660 11 0.667 0.977 1.245 1.092 0.923 1.076 1.181 0.959 1 185 1.073 0.927 1.112 1.261 0.997 0.682 [$
o J 0.644 1.162 1.074 1.209 0.980 1.187 1.032 1.205 1 073 1.216 0.983 1.201 1.090 1.202 0.665
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l l K 0.654 0.968 1.209 0.958 1.187 1.027 1.181 1.077 1.214 1.045 1.186 0.947 1.205 0.989 0.675 L 0.509 1.111 1.064 1.202 1.031 1.195 1.005 0.976 0.962 1.175 1.024 1.193 1.054 1.121 0.524 y as D n M 0.819 1.119 1.037 1.218 0.998 1.265 1.131 1.238 0.945 1.184 1.031 1.097 0.795 g 13 "'
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- 5 0.538 1.114 1.093 1.089 1.270 1.117 1.274 1.098 1.234 1.082 1.105 1.111 0.525 +4
,oo 4 A P 0.525 0.791 1.133 0.998 1.197 0.999 1.188 0.988 1.133 0.796 0.525 $
R B 0.516 0.664 0.660 0.687 0.663 0.669 0.520 p. .
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37 '
September 25, 1986 Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commaission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Subject:
McGuire Nuclear Station, Unit 2 Docket No. 50-370 Unit 2 Cycle 3 Startup Report
Dear Dr. Grace:
Pursuant to McGuire Nuclear Station's Technical Specifications, attached is the subject Startup Report. If you have any questions, you may contact Duke through normal Licensing channels.
Very truly yours,
/
Hal B. Tucker JBD/02/slb Attachment xc: Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation l U. S. Nuclear Regulatory Commission l Washington, D. C. 20555 Attention: Mr. B. J. Youngblood, Project Director i PWR Project Directorate No. 4 l Mr. W. T. Orders Senior Resident Inspector McGuire Nuclear Station I
I I i hO