ML20235V039

Cycle 4 Startup Rept. W/

ML20235V039
Person / Time
Site:	Mcguire
Issue date:	09/22/1987
From:	Tucker H DUKE POWER CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8710140500
Download: ML20235V039 (41)

Text

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F f-e DlIKE POWER COMPANY McGUIRE NUCLEAR STATION

. p UNIT 2 CYCLE 4

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STARTUP REPORT

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September 22, 1987

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l-TABLE OF CONTENTS l

P, age

>s List.of Tables 11 i

List of Figures lii 1.0 Introduction 1

2.0 Criticality 3

2.1 Prestartup NIS Realignment Following Refueling -

l PT/0/A/4600/78.

4 3.0 Zero Power Physics Testing 6

'3.1,All Rods Out Boron Endpoint Measurement -

10 PT/0/A/4150/10 i

3.2 All Rods Out Isothermal Temperature Coefficient 11 Measurement - PT/0/A/4150/12

~

3.3 Control Kod Worth Measurement - P1/0/A/4150/11 14 3.4 Control Rod Worth Measurement: Rod Exchange -

17 PT/0/A/4150/11A 4.0 Power Escalation Testing 19 4.1 Incore and NIS Recalibration: Post Outage -

25 PT/0/A/4600/02E 4.2 Thermal Power Output Measurement - PT/0/A/4150/03 28

]

4.3 Reactivity Anomalies Calculation - PT/0/A/4150/04 30 4.4 Incore and Nuclear Instrumentation System 31 Correlation Check - PT/0/A/4600/02A 4.5 Target Flux Difference Calculation -

32 PT/0/A/4150/08 l

I 4.6 Core Power Distribution - PT/0/A/4150/02A 33 h

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- 4 LIST OF TABLES.

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1.

Overlap Data' 7

2.

Nuclear Heat 8

3.

' Reactivity Computer Checkout 9

4.

Control Rod Worth Measurement: Rod Exchange

'18

5. -

Core Power Distribution Results - 15.5% Full Power 20

6. -

Core Power Distribution Results - 77.5% Full Power 23

- 7..

Overlap' Data 24

' 8.

Quarter Core Flux Map Data.for PT/0/A/4600/02E, Incore 26 and NIS Recalibration: Post Outage 9.

Thermal Power Output Measurement Results' 29

- 10.

Core Power Distribution Results - 100% Full Power 34 1

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LIST OF FIGURES Pagg 1.

Unit 2 Cycle 4 Core Loading Pattern 2

l 2.

Assemblies to Use for Calculating IR and PR 5

I Calibration 3.

ARO ITC Heatup and Cooldown Data: First Run 12 4.

ARO ITC Heatup and Cooldown Data:

Second Run 13 5.

Shutdown Bank B Rod Worth 15 6.

Control Bank D Rod Worth 16 7.

Power Distribution - 15.5% Full Power 21 4

8.

Relative Errors in Power Distribution from 22 Predicted - 15.5% Full Power 9.

Incore and NIS Recalibration Results 27 10.

Power Distribution - 100% Full Power 35 11.

Relative Errors in Power Distribution from 36 Predicted - 100% Full Power 1

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c 1.0 Introduction Following McGuire Unit 2 Cycle 3 core unloading, subsequent. fuel' 1

inspection revealed that fuel assembly.P06.(Cycle 3 core location R-05) had sustained damage due to haffle jetting.

Consequently, a core redesign.

was initiated and completed prior to Unit 2 Cycle 4 core loading.

3 Core loading for McGuire Unit 2 Cycle 4 was started on June 2, 1987 at 3

.zero power physics testing, and power escalation testing were performed

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2200.

Core loading'was completed on June 7,,1987 at 2305.

Criticality,

-under PT/0/A/4150/21, Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing and began

-July 2, 1987. The unit reached 100% power'for Cycle 4 on July 9, 1987.

1 The tests requiring hot full power equilibrium conditions were completed on July 13 and July 16, except for PT/0/A/4150/03, Thermal Power Output Measurement which was completed on August 28, 1987.

Figure 1 gives the Unit 2 Cycle 4~ core-loading pattern.

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QUADRANT ASS #

Figure 1 1

2 g3 g Core _ Loading Pattern 4

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1. 01K Rits 75 91 SP7M Riti 50 GEO R43 P12 G42 G43 G58 L49 Rod LO3 G31 G05 G0i Poi R42 Gio gg 119

1. SE R138 93 57 SiRT 101 FM 123 80 Si 221KT R142

1. 8K SE G09 R53 G12 G39 P20 R45 P07 R59 Pio G48 G45 R50 GOS gg Ri25 FM R146 53 46 rem R153 F7R 20ET 71 R151 IP9E Rit7 003 G14 R49 P34 R05 P59 PO4 P51 R12 P44 R63 G24 G56 13 e4 timi w7a Rio eP5m Rt22 One Rus paa R144 iPsa 22eKT 20mi p

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2.0 Criticality - PT/0/A/4150/28-

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On July.2, 1987 at'1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br />, 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 1652 ppm, pressurizer boron to be 1674 ppm and volume control tank boron to be 1661 ppm. Since it was desired to go critical with a significant' amount of Control Bank D inserted (N750 pcm), a target,value t

of 1406 ppm was chosen for reactor coolant bgron concentration..This l

represented the predicted BOL, ARO, HZP, No Xenon, equilibrium Samarium

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critical boron concentration of-1481 ppm less 75 ppm. Calculations using

'l the unit Data' Book (OP/2/A/6100/22) indicated a volume of 9816 gallons of 4

demineralized ~ water should be added to the system-to dilute from 1652 ppm

j to 1406 ppm. At 0102 on July 3, 1987, this dilution of the reactor coolant system was started. The dilution was secured at.0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> after 9816 gallons of demineralized water had been added to the system. After j

appropriate. system mixing, Chemistry samples indicated Reactor Coolant System boron was 1412 ppm, Pressurizer boron was 1406 ppm and Volume Control-Tank boron was 1411 ppm.

At 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br /> on July 3, 1987,~ 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 2040 on July 3, 1987 with Control Bank D at 40/41 steps withdrawn. The predicted critical position per OP/0/A/6100/06, Reactivity Balance Calculation was 84 steps. withdrawn on Control Bank D.

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'2.1.Prestartup NIS Realignment Following Refueling - PT/0/A/4600/78' This procedure'was. completed.on' June 6, 1987.at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />.

This test'was used to calculate. preliminary calibration' data 1for the-

' intermediate range'(IR) and power range:(PR) detectors.following

' refueling.

The. Cycle.-4 preliminary calibration data was determined by taking the-End of Cycle 3 (EOC3) calibration, data'and adjusting it by a weighted

-average.of the. ratio.of the sum of the predicted assembly, powers for

-the~ Cycle 4 loading to the: sum of the. measured assembly powers'from, the last Cycle 3 Incore/Excore calibration..The core locations used.

'to-calculate the. ratio'of the predicted Beginning of' Cycle'4'(B004)

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' assembly powers.to'the measured EOC3 values are shown.in Figure 2.

The predicted BOC4-to-EOC3 IR ratio was $1.00; the' predicted' BOC4-to-EOC3 PR ratio was $0.75..? Based on these.results, the IR.

. calibrations were not changed. The PR' calibrations were adjusted prior to Cycle 4 Initial Criticality.

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Assemblies to Use for Calculating IR and PR Calibration Setpoints

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3.0 Zero Power Physics Testing- (ZPPT)

Zero Power Physics Testing for McGuire 2 Cycle 4 started July 3, 1987 and was completed July 6, 1987. The output of Power Range Detector N42 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, July 3, 1987. The results are shown on Table 1.

The point of adding nuclear heat was determined July 3, 1987.

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 l'

temperatures (Tave) with a change in the reactivity trace and an increase in pressurizer level. Table 2 gives the results of the two tries.

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Nuclear he9t was determined to be at an average flux level of 6.95,y10 amps on the reactivity computer picoammeter (N42}7and 4.85 x 10 amps on Intermediate Range Detector N35 and 4.25 x 10 amps on Intermediate Range Detector Ng6. Froy these results the test band for ZPPT was determined to be 10 to 10 amps on the reactivity computer. -

On July 4, 1987, an on line checkout of the reactivity computer was j

performed. This was done by withdrawing Control Bank D until a positive I

reactivity insertion of N+25 pcm wac 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). bsing i

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.

l The results met all acceptance criteria and are given in Table 3.

An electronics only negative reactivity insertion test was also completed satisfactorily as part of PT/0/B/4600/55, Reactivity Computer Periodic j

Test.

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TABLE 1

. Overlap Data Source. Range Intermediate Range-cps amps-

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~0 Test Band: 110 to 10" amps'on N42..

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(g ad 3.1 All Rods Out Boron Endpoint Measurement - PT/0/A/4150/10

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This-test'was performed July'4, 1987 at 0710 hours0.00822 days <br />0.197 hours <br />0.00117 weeks <br />2.70155e-4 months <br />.

Control Bank D

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was init'ially at 222 steps withdrawn,'the Reactor. Coolant System boron concentration was 1497. ppm and'the~ Pressurizer boron c

concentration was 1500 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 Differential Boron Worth.

Control = Bank D was then reinserted to. the just~ critical condition and 'the test was repeated.

The'results of;these reactivity changes.were each added to the initial Reactor Coolant System boron concentration to give two values-for the'ARO Boron Endpoint. These values ~were averaged to give the final result of 1499. ppm. This value met the acceptance criterion for the' Hot Zero Power (HZP) ARO Critical Boron concentration of' 1481 ISO ppm.

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'3.2 All Rods Out Isothermal Temperature Coefficient Measurement -

PT/0/A/4150/12 h

i This test was performed on July'4, 1987 at 1300.

The test measures i

Isothermal Temperature Coefficient (ITC) by plotting Reactivity j

versus Average Reactor Coolant System Temperature. The Moderator 4

Temperature Coefficient (MTC) is found using the relationship as J

i follows:

1 MTC (pcm/*F) = ITC - Doppler Temperature Coefficient The acceptance criterion on the ARO ITC was 3.30 3.0 pcm/ F.

The predicted Doppler Temperature Coefficient was -1.70 pcm/ F.

Control Bank D was at 200 steps withdrawn and the Reactor Coolant System boron concentration was 1494 ppm at the start of the test.

The heatup/cooldown was performed a second time to establish repeatability of the data. The results are shown in Figures 3 and 4.

The average ARO ITC was found to be +2.40 pcm/ F.

This fell within the acceptance criterion band. This gave an ARO MTC of +4.10 pcm/ F which was within acceptable Technical Specification limits.

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 4.

11

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^ % ? a. 3.3fControl1 Rod Worth' Measurement - PT/0/A/4150/11 On July"4,;1987 at.1600 hours, Shutdown' Bank B rod worth was' measured using the established boration/ dilution method.. There were no-other . rods-in the' core _at the time. Shutdown Bank B 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 Exchange. .The' measured worth ofl Shutdown 1 Bank B was 899 pcm.. The predicted worth was 915 pcm t 92 pcm. This represented an error of 1.7% and 'was within the acceptance criterion of 15%. Figure 5 shows the -measured: integral ~and differential rod' worths for Shutdown Bank B. Following the performance'of PT/0/A/4150/11A Control Rod Worth . Measurement: ' Rod Exchange-(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 July 5,;1987 at 1040 hours. 'Again,there.were'no'other' rods in the core. ~The measured worth of. Control Bank D was 641 pcm. The predicted; The error was -3. % well within'the worth was 666 pcm 1 67 pcm.- 8 acceptance' criterion, also..The'resulting integral and differential. ~~ -rod worths for Control' Bank D are shown in Figure 6. . l. ; 14 ) b ~~

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P .i j ~. l ) i .{ h COntrOI Bank D Worth Differential and Integral RCC Bank (ACCA) Worth 'l

l 13

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r 5

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r f> .f

3.4 control Rod Worth Measurement

Rod Exchange - PT/0/A/4150/11A-On July 4,.1987 the. rod exchange method of control rod worth measurement.was performed. Shutdown Bank B was used as'the reference bank and its worth was measured by the boration/ dilution method'(see 1

Section'3.3). '~ With the reference bank essentia11y'a11'the way in and the. reactor. Just critical, each control'and shutdown bank was exchanged'with the reference bank.- The integral worth of the bank being measured (i.e... ' the test bank) was' determined from' the ' difference in 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 ~andt all' banks were within' the acceptance criteria of 130% or +200 pcm whichever was' greater. The~results of'the rod exchange test are given on Table 4. e 'e 6 17

f. [

g. :r TABLE 4' Control Rod' Worth Measurement: Rod Exchange

+ ~ Bank'. ' Predicted Worth Measured Worth: , Percent Identification. pcm. pcm++ Difference Shutdown Bank B 915 899* 1.7 -(reference) Control Bank D 66~ -633 - 4.2 Control Bank C f34 722 -10.2 Control Bank B : ^737 750 + 1.8-Control Bank A 346 295 -14.7 . Shutdown Bank E 500 460 - 8.0 Shutdown Bank D-491 474 - 3.5 Shutdown' Bank C-491 463 - 5.7-Shutdown Bank A' 327 323 - 1.2 TOTAL ROD' WORTH 5272 5019 - 4.8

• Measured by boration/ dilution method

, Measured - Predicted x 100 Predicted ++ Rounded to nearest pcm i 1 I 4 18 I

l i u q l 1 f 4.0 Power Escalation Testing j McGuire Unit 2 Cycle 4 Power Escalation testing started July 6,1987 at ] 1405 and was completed July 9, 1987. The unit went on line July 6, 1987 at 1052 hours and began increasing ~ reactor power at N2 1/2% per hour. 1 Load was increased to approximately 15% and held for flux mapping. At 15.5% 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 7 and 8 give the results of this test. After performing PT/0/A/4150/02A, Core Power Distribution, power was increased to 50% at approximately 2.5%/hr. From 50% to 80%, PT/0/A/4600/02E, Incore and NIS Recalibration: Post Outage, was performed (see Section 4.1). During final calibration of the excore detectors at 78%, a full core flux map was taken as a final check of core tilt parameters prior to increasibg power to 100%. Table 6 gives the results of this flux map. The unit reached 100% Full Power July 9 at 0911 hours. The remaining tests requiring hot full power equilibrium conditions were e opleted and are discussed in Section 4.2 - 4.6. 1 19

4. TABLE.5 Core Power Distribution Results 15.5% Full Power Unit 2 Cycle 3 Map FCM/2/04/001 Date/ Time Map Taken 7/06/87 0524 hours Power Level 15.5% Cycle Burnup 0.05 EFPD 2.1 MWD /MTU Boron Concentration 1456 ppm Control Rod Position Control Bank D at 149 steps withdrawn Maximum F : 2.4067 at Axial Loc. 34, Horiz. Loc C-10 Maximum F. 1.3568 at Axial Loc. 35 g Maximum pin F 1.6496 at Horiz. Loc. C-10 b ( r m Predicted) 16.81% at Horiz. Loc. H-8 Maximum error FAH Maximum F /K(Z) 2.4305 at Axial Loc. 35 q Maximum % Reduction in Axial Flux None Difference (AFD) Wings Minimum % Margin to AFD Wings -37.9286% at Axial Loc. 35 R (Tech Spec 3/4.2.3) 0.8832 Total Reactor Coolant Flowrate 383,604 gallons / minute (Process Computer) Total Incore Axial Offset +9.891% Incore Tilts %: Upper Core Lower Core Quadrant 1: 3.894% Quadrant 1: 1.8'/9% Quadrant 2: 1.980% Quadrant 2: 3.181% Quadrant 3: -3.565% Quadrant 3: -2.482% Quadrant 4: -2.310% Quadrant 4: -2.578% NOTE: Axial location 1 is the bottom of the core. Axial location 61 is the top of the core. I 20

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' k.h Y ;, l} ' j.R .,; a. ' TABLE 6 I k Core Power Distribution Results 77.5% Fu11 Power y Unit 2 Cycle 3-Map FCM/2/04/016 Date/ Time Map Taken 7/8/87 1039. hours ~ Power Level 77.5% 1 1.0 EFPD 42.0 MWD /MTU Cycle Burnup Boron' Concentration 1168~ ppm . Control' Rod Position Control Bank D.at 202 steps withdrawn .v 2.0186 at Axial Loc. 40, Horiz.

q Maximum F :.

Loc C-12 Maximum F : 1.2992'at' Axial Loc. 42 g N ' Maximum pin F 1.4285 at Horiz. Loc. C-06 Maximum error F (from predicted) 10.61%.at Horiz. Loc. G-09 Maximum F /K(Z) 2.0779 at Axial Loc 43 Maximum % Reduction in Axial Flux None Difference (AFD) Wings Minimum'% Margin to AFD Wings -19,6562% at Axial Loc. 39 R (Tech Spec 3/4.2.3) 0.8981 Total Reactor Coolant Flowrate 392,532 gallons /mioute (Process Computer) Total Incore Axial Offset 11.921% Incore Tilts %: Upper Core Lower Core Quadrant-1: 1.854% Quadrant 1: 1.002% Quadrant 2: 0.436% Quadrant 2: 1.357% Quadrant 3: -0.743% Quadrant 3: -0.991% Quadrant 4: -1.547% Quadrant 4: -1.368% NOTE: Axial location 1 is the bottom of the core. Axial location 61 is the top of the core. 23

L-TABLE 7 Overlap Data Intermediate Range (Volts) Thermal Power Date Time N35 N36 Best Estimate (%) 7/05/87 1457 7.732 7.640 3.534' 7/06/87 0945 8.326 8.238 11.537 7/06/87 1213 8.540 8.524 17.523 7/06/87 1416 8.722 8.646 24.693 7/07/87 1425 9.132 9.059 55.379 I l 7/08/87 0300 9.297 9.225 77.358 7/09/87 1510 9.470 9.398 100.171 h

y .x_ $l[([ if W.,3 W *. x+ > + A, -o 4.1 ~Incore'and NIS Recalibration: Post Outaae - PT/0/A/4600/02E O e g,/ This test'was started on July 7, 1987 at 1210 hours and was.run during the power escalation from.50% to 80% Full Power. The data obtained from this test were 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 quarter: core fisx maps and . l* s, associated excore' detector currents at eight different axial offsets. M as indicated in Table 7. (The quarter core flux map pattern had previously;been verified as an accurate representation of axial-offset through PT/0/A/4150/23,- Quarter Core Flux Map Qualification Test). These data were then input into a benchmarked off-line-computer program which generated the output shown in Figure 9. The appropriate factors were then input into the plant instrumentation systems and all acceptance criteria were met. .Jc ,ps-

i

? l I f /. +' -1 I; g,,e e r D3. s ff-i-! \\ f 25 (' i s

y b n r q i, 'Ei tj TABLE 8 i y, y Quarter Core Flux Map Data for .PT/0/A/4600/02E,'Incore and NIS Recalibration: Post Outage Map; Average Thermal-Power (%) Incore Axial Offset (%) n P 1)( QCM/2/04/003' 50.440 '16.701' L),QCM/2/04/006 57.150 9.072 2 l[t 3) 'QCM/2/04/007r 59.150 7.883 4) .QCM/2/04/008 61.830 7.040- ' 5)- QCM/2/04/009; 64.450 6.095 y, ' 6)f'QCM/2/04/013~ "-75.500 0.408 O, Y 7)L QCM/2/04/014 77.540 0.468 .h '8). QCM/2/04/015 77.930 2.852' e t. e k% l l r 26 1 1

Figure 9 i

• Incor~e and NIS Recalibration l

Unit 2 Cycle 4 FULL POWER DETECTOR CURRENTS (MICR0 AMPS) CORRESPONDING TO VARIOUS INCORE AXIAL OFFSETS l INCORE DETECTOR N-41 DETECTORN-42 DETECTOR N-43 DETECTOR N-44 A!!AL CFFSET T B T B T B T B 30.0 376.4 287.1 351.3 258.6 -309.8 232.3 311.0 233.5 20.0 356.9 317.3 333.5 283.2 293.6 254.2 298.3 257.6 10.0 337.5 347.6 315.7 307.B 277.4 276.0 284.0 281.7 0.0 318.0 377.8 297.9 332.4 261.3 297.9 271.3 305.0 -10.0 298.6 400.1 290.1 357.0 245.1 319.7 257.8 329.9 -20.0 279.1 438.3 262.3 391.7 228.9 341.6 244.3 354.0 -30.0 259.6 468.6 244.5 406.3 212.7 363.4 230.8 378.2 a 0.9375' -0.9802 0.9677 -0.9755 0.9778 -0.9791 0.9697 -0.9825 r NORMALIZED DETECTOR VOLTAGES (VOLTS) AT VARIOUS AXIAL OFFSETS INCCRE DETECTOR N-41 DETECTOR N-42 IETECT R N-43 DETECTORN-44 j AXIAL DFFSET T B T-B - T B T-B T B T-B T B T-B 1 30.0 9.859 6.330 3.529 9.823 6.480 3.343 9.878 6.497 3.381 9.574 6.359 3.215 20.0 9.349 6.996 2.353 9.325 7.097 2.229 9.362 7.109 2.254 9.159 7.016 2.143 10.0 0.640 7.663 1.176 B.228 7.713 1.114 9.646 7.719 1.127 0.745 7.673 1.072 0.0 B.330 B.330 0.000 9.330 B.330 0.000 B.330 B.330 0.000 B.330 8.330 0.000 -10.0 7.820 0.997 -1.176 7.932 9.947 -1.114 7.814 B.941 -1.127 7.915 B.987 -1.072 -20.0 7.311 9.664 -2.353 7.335 9.563 -2.229 7.298 9.552 -2.254 7.501 9.644 -2.143 -30.0 6.801 10.330 -3.529 6.837 10.180 -3.343 6.702 10.163 -3.361 7.026 10.301 -3.215 AFD INCCRE/EXCORE RATICS FCR QUADRANTS 1 - 4 f =........... QUAD 4 GUAD 2 QUAD 1 2L'AD 3 N-41 N-42 K-43 N-44 M = 1.416 M = 1.495 M = 1.478 M = 1.555 l l I 27 r

C- ':y 1 >~- y i. . 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 August 28, 1987 at'0840 hours at'100% F.P. -The-results are shown in Table 8. The acceptance criterion of 12% difference between the offline computer and the plant computer was met. 9 D 1i-4 28 _ _ _ _ _ _j

o,.

.g. TABLEL9 . Thermal Power Output Measurement Results i s 1 Plant Computer Off-Line Computer Wf Wt ~ W-Primary. Heat Balance '98.86 3372.30 98.70 3366.74 Secondary Heat Balance 99.90 3407.66 99.95' 3409.20 ) O 29 .c ';i

( :p- [0 = : p: ;s;. E - 4.3. Reactivity Anomalies Calculation'- PT/0/A/4150/04 i This test compared the actual'. core reactivity to the predicted core ~ reactivity by.,.taking into account the actual Reactor Coolant System boron concentration,. Xenon.and Samarium worths, rod positions and L . power.. level and adjusting these to the ARO, Hot Full Power (HFP),. . equilibrium' Xenon'and Samarium condition. Theoretical,and actual Reactor Coolant System boron; concentration.for this' conditions were then compared. a The test, performed at 100% on July.14, 1987, indicated that the actual-AR0, HFP, equilibrium Xenon and-Samarium condition boron- ' concentration was 1067' ppm. This compares to a predicted value of'- 1047 ppm.- The 20. ppm difference translated into'a'186 pcm error .between actual and predicted reactivity worths.- This'was, however, within.the acceptance criterion for the test of 1500 pcm. O e 30 h_.-.d.__.____.___._____._

l- .e-A - 4.4 Incore and Nuclear Instrumentation System Correlation Check - PT/0/A/4600/02A. 1 .This test was'used to compare.the incore axial offset as indicated by-a fullicore flux map'to.the. axial offset indicated on the plant coraputer' by the excore detectors.- This test also verifies.the j 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 13, 1987 at'1313 hours. The indicated incore axial offset from. flux map,FCM/2/03/017 was 4.18%. The core average axial offset'from the excore detectors was 5.59%. These results gave an absolute difference of 1.41% and did not challenge the acceptance criterion of 13% difference. S 9 4 31

- [ ' i <t. ' [ 4.5 :Taraet Flux Difference Calculation - PT/0/A/4150/08 ~ -This test-was performed to. find the target axial flux difference s - (AFD),which is used to provide guidance for plant operation. ~ N

The test was performed on July.17,~1987... The target AFD at 100% F.P.

~ for quadrant 1 was.5.00%; for quadrant 2, 5.14%; for quadrant 3, ~ 5.33%;'and for. quadrant.4, 4.80%. All acceptance criteria for this-tes't were met. 0 i- ] 4 0 9 f J i j I 32 =L_______-_--

si ) 3, l . 4.6> Core Power. Distribution - PT/0/A/4150/02A' 4 On July 13,.1987'at 1313, 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%'Fu11 Power and equilibrium conditions.

All' acceptance criteria for this. test were met. ' Table 9 and r.,'; Figures 10 and 11 give the results of this test. 8 O 33

t W+ i v 3.. - gu yi ~' 7' 1 TABLE 10i

Core Power Distribution Results 100%' Full-Power' s

' Unit 24 Cycle 3-Map FCM/2/04/017 Date/ Time Map Taken 7/13/87 }422 hours W Power: Level < 100% -- -Cycle Burnup 6.0 EFPD-249.0 MWD /MTU " Boron Concentration '1066 ppm 1 - Control Rod Position Control Bank D at 217 st'eps withdrawn-Maximum F : 1.2083 at Axial Loc. 40 4 g 4 Maximum pin'F 1.4347 at Horiz. Loc.'C-04. , Maximum error (from predicted) '7.76% at Horiz. Loc..C-05 Maximum F /K(Z) 1.9333 at Axial Loc. 40 Maximum % Reduction in Axial Flux None Difference (AFD) Wings. Minimum % Margin to AFD Wings -1.4441% at Axial Loc. 23 R -(Tech Spec 3/4.2.3)/ 0.9616 Total Reactor Coolant Flowrate '391,075 gallons / minute (Process l Computer) " Total Incore Axial Offset +4.184% Incore Tilts.%: Upper Core Lower Core. Quadrant 1: 0.929% Quadrant 1: 1.407% Quadrant 2: 0.547% Quadrant 2: 0.574% Quadrant 3: 0.028% Quadrant 3: -0.812% 'M Quadrant 4: -1.504% Quadrant 4: -1.169%

NOTE.. Axial' location 1 is the bottom of the core.

[ Axial location 61 is'the top of the core. 34

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O :: e ~ h' Duxe POWER GOMPANY ^ .A-P.0, Box 331891' i-1 CHAMLOTTE, N,0, 28949 HAL B. TUCKER. M EPISONE 8 0 C T I $. *:*s *9 v- > September 25, 1987 i.Dr.lJd Nelson' Grace, Regional Administrator U.S.-Nuclear Regulatory Commission Region II- ' '101 Marietta St;- NW,. Suite 2900 Atlanta, Georgia.30323' Subjects McGuire Nuclear Station, Unit 2 Docket No. 50-370 Cycle 4 Startup Report

Dear Dr. Grace:

- Pursuant' to McGuire Nuclear Station's Technical Specifications, attached is the 'Startup Report for McGuire Nuclear. Station Unit'2 Cycle 4. '.Very truly yours, Hal B. Tucker ' SAG /87/j gc Attachment i xc (w/o attachments) Mr. Darl S. Hood . Office of Nuclear, Reactor Regulation -U.S. Nuclear Regulatory Commission Washington, D.C.. 20555 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station i I. i i ZE01 l}}