L-89-309, Cycle XII Startup Rept

Cycle XII Startup Rept

ML17347B277
Person / Time
Site:	Turkey Point
Issue date:	08/21/1989
From:	Woody C FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-89-309, NUDOCS 8908250320
Download: ML17347B277 (37)

Text

';.gc Cp~RATED Dl UTION DEMONSTR ~

SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8908250320 DOC.DATE: 89/08/21 NOTARIZED: NO FACIL:50-251 Turkey Point Plant, Unit, 4, Florida Power and Light C AUTH.NAME AUTHOR AFFILIATION WOODY,C.O.

Florida Power

& Light Co.

RECIP.NAME RECIPIENT AFFILIATION DOCKET g 05000251

SUBJECT:

"Unit 4 Cycle XIZ Startup Rept." W/890821 ltr.

DISTRIBUTION CODE: IE26D COPIES RECEIVED: LTR l ENCL

(

SIZE:

TITLE: Startup Report/Refueling Report (per Te&c Specs)

NOTES RECIPIENT ID CODE/NAME PD2-2 LA EDISON,G INTERNAL: IRM TECH ADV

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TOTAL NUMBER OF COPIES REQUIRED:

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M P.O.

ox O,Juno Beach,FL 33408-0420

'p ~%K AUGUST. 2 1

)989 L-89-309 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.

C.

20555 Gentlemen:

Re:

Turkey Point Unit 4 Docket No. 50-251 Startu Re ort The attached Startup Report is being submitted in accordance with Technical Specification 6.9.1.a.

The Unit 4 Cycle XII Startup Report documents the first use of fuel assemblies with Integral Fuel Burnable Absorbers (IFBA), extended burnup modifications, reconstitutable top nozzles, standardized fuel pellets, reduced fuel rod backfill pressures, 4g fuel rod plenum springs, and 304L stainless grid sleeve material.

Very truly yours, 0.

Woody Acting Senior Vice President Nuclear COW/GRM/cm Attachment cc:

Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 8P08250820 8~/0821 PDR ADOCK 0=000251 P

PDC an FPL Group company

FLORIDAPOWER ANDLIGHTCOMPANY TURKEYPOINT PLANT UNIT4 CYCLE XII STARTUP REPORT

INTRODUCTION This report contains the official summary of the Startup Physics Tests performed on Turkey Point Unit 4 at the beginning of Cycle XII.

The testing program was conducted in accordance with Operating Procedure 0204.3, Initial Criticality After Refueling, and Operating Procedure 0204.5, Nuclear Design Check Tests During Startup Sequence After Refueling, and meets the minimum requirements of ANSI/ANS 19.6.1, Revision 0

(12-13-85),

Startup Physics Tests for Pressurized Water Reactors.

Testing commenced on May 19, 1989, at 0148 and was completed on May 21, 1989 at 0637.

The Westinghouse Nuclear Design Report for Unit 4, Cycle XII, (WCAP-12010) is the design data from which deviations were measured for the purpose of verifying that acceptance criteria were met.

The acceptance criteria stated are the more conservative of ANSI/ANS 19.6.1.,

Revision 0 or Operating Procedure 0204.5.

All of the tests included in this report meet their acceptance criteria.

The contents of this report provide the documentation required by Technical Specification 6.9.1.a.

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TABLEOF CONTENTS PAGE Introduction Table ofContents 1.0 Unit4 Cycle XIICore 1.1 Loading Pattern 1.2 Rod Pattern 1.3 Rod Drop Times 2.0 InitialCriticality 2.1 ICRR Vs. Dilution 3.0 Summary ofTests 3.1 Nuclear Heating 3.2 Reactivity Vs. Period 3.3 Boron Endpoint, Most Reactive Bank 3.4 Rod Worth (PPM), Most Reactive Bank 3.5 Rod Worth (PCM) 3.6 Temperature Coefficient 3.7 HZP DifferentialBoron Worth 3.8 HZP Differential &,Integral CBC Worth Plot 4.0 Shutdown Margin 5.0 Power Distribution Maps 5.1 25% Flux Map 5.2 47% FluxMap 5.3 100% Flux Map 6.0 Critical Boron Concentration 6,7 10 12 12 13 15 16 17 18 19 20

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This section presents the as-loaded core configuration (Figure 1); the Control and Shutdown Rod pattern (Figure 2); and the Rod Drop Times for all rods as measured in Procedure 4-PMI-028.3 RPI Hot Calibration, CRDM Stepping Test, and Rod Drop Test (Figure 3).

Allrods met the drop time limitof2.4 seconds as per Technical Specification 3.2.3.

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- 0" 15 14 13 12 11 10 EACTOR FUEL LOCATIO YPOINTPLANTUNIT CYCLE NO. XII FIGURE 1

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2 NN06 HF23 NN28 HF16 NN12 HF06 Z19 PP30 R80 RR34 Z10 RR36 PP54 R68 Z23 P

Z57 RR42 RR03 PPOS R59 RR10 PP10 R67 RR12 RR44 Z51 N

Z46 RR45 PP52 PPOS R58 RR21 8PF1 4WZ NN33 R86 RR22 SPFO 6WZ PP22 R89 PP35 RRSO 259 M

236 RR51 PP56 NN49 R92 RR02 SPF1 SWZ PP19 R51 PP37 PP03 R57 RR27 8PFO 7WZ NN50 R69 PP53 RR41 Z20 PP33 R79 RROS PP15 R78 RR16 8PFO 2WZ NN19 PP50 PP34 R82 PP28 NN29 RR17 8PF1 3WZ PP14 R62 RR13 PP40 R70 NNOS HF07 NN39 HF15 RR37 ZOS PP11 R66 RR11 555 RR14 SPF1 OWZ NN15 R12 PP25 PP43 PP32 R53 RR29 4PFO 2WZ NN46 262 K10 R93 RR30 4PFO 4WZ NN47 PP42 PP46 R90 PP21 R95 PP31 RR09 8PF1 1WZ NN16 R63 PP12 R64 RR01 554 RR38 206 NN10 HF13 NN40 HFOS NN11 HF20 RR39 PP07 R83 RR20 8PFO SWZ PP20 R75 PP41 RR31 4PFO 1WZ NN48 RR32 4PFO 3WZ PP44 PP04 R74 RR08 8PFO 5WZ PP09 R55 RR33 NN09 HF02 PP45 R52 RR07 PP18 RSS RR25 SPFO'WZ NN37 PP48 PP38 R81 PP29 NN25 RR24 8PFO 1WZ PP01 R72 RR19 PP51 R65 228 RR52 PP36

<<fr NN51 R54 RR28 SPF1 6WZ PP13 R77 PP49 PP17 R76 RR18 8PFO 9WZ NN52 R61 PP39 RR43 Z22 E

261 PP47 PP02 R60 RR15 8PFO 3WZ NN35 R56 RR23 SPF1 2WZ PP23 R84 PP27 RR49 Z45 D

Z48 RR46 RR06 PP24 R71 RR26 PP16 R87 RR04 RR47 256 221 PP26 R91 RR40 202 RR35 PP55 R73 Z24 B

Verified By FORM 6446-*RS: I-tb-06/89 NNOS HF11 NN36 HF10 NN07 HF01 Assembly No.

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Y POINT PLANTUNITN CYCLE No. XII FIGURE 2 15 14 13 12 11 10 9

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2-1 1.33 1.93 1.33 1.95 P

1.34 1.95 1.32 1.93 1.35 1.92 1.33 1.98 1.27 1.92 N

M 1.37 2.05 1.32 1.95 1.32 1.95 1.27 1.77 1.35 1.93 1.36 2.0 1.35 1.97 1.35 1.95 1.27 1.78 1.33 1.93 1.33 1.93 1.33 1.95 1.32 1.94 K

1.35 1.92 1.35 1.97 1.33 1.85 1.35 1.92 1.35 1.90 1.33 1.93 1.35 2.0 1.32 1.92 1.33 1.95 1.32 1.93 1.32 1.92 1.35 1.92 1.32 1.92 1.33 1.92 1.30 1.80 1.35 1.97 1.35 1.98 1.25 1.77 E

1.33 1.93 1.37 1.88 1.33 1.98 D

1.30 1.90 1.30 1.92 1.32 1.93 1.40 2.04 B

LEOEND TIMETO DASHPOT TIMETO BOTTOM

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2.0 INITIALCRITICALITY The approach to criticalitybegan May 19, 1989, N 0158 hours0.00183 days <br />0.0439 hours <br />2.612434e-4 weeks <br />6.0119e-5 months <br /> in accordance with Operating Procedure 0204.3, InitialCriticalityAfterRefueling. Criticalitywas achieved May 19, 1989, 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> by withdrawing control rods to 180 steps on Bank D and diluting the RCS with 19,400 gallons ofwater.

Upon attaining criticality the flux level was increased to 1 x 10-8 amps on the intermediate range to obtain critical data.

Tavg Control Bank D Boron Flux 5470F 210 Steps 1530 ppm 1 x 10-8 amps TABLE2.1 FLUX Picoammeter 1.05 x 10-8 amps N-35 1.5 x 10-8 amps N-36 1.6 x 10-8 amps The followinggraph (Figure 4) is a plot ofthe ICRR during the approach to criticality. *Rl:1-yrz

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3.0 Summa ofTests This section provides a summary of the results of the low power physics tests along with the Westinghouse design data.

This report compares design and measured data using difference'nd percent difference2.

For each test, the acceptance criteria is listed at the bottom ofthe table.

'The difference = predicted - measured.

For calculating the percent difference, the equation is:

Predicted Value Measured Value X 100%

3.1 Nuclear Heatin The point ofadding Nuclear Heat was determined in accordance with Operating Procedure 0204.3, InitialCriticalityAfterRefueling, Step 8.15 and Appendix A.

This is performed by establishing a small positive startup rate and measuring the point (fluxlevel) at which T<yg departs from its established, steady value.

Nuclear Heating was measured to firstoccur at:

TABLE3.1.1 FLUXLEVEL(AMPS)

Picoammeter 3.17 x 10-7 N-35 4.5 x 10-7 N-36 4.56 x 10-7 Allphysics tests were conducted at or below 1.0 x 10-7 amps on the picoammeter connected to N-44 to assure Nuclear Heating did not occur..

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3.2 Reactivi Vs. Period Reactivity Computer checkout was done in accordance with Operating Procedure'0204.3, InitialCriticalityAfterRefueling, Step 8.17 and Apperidix B.

This checkout is performed by inserting small positive and negative reactivities using rod motion, measuring the period generated and the indicated worth, and then comparing design worths to measured worths for the given period.

TABLE3.2.1 P~d

+123.8

-191.5

+155.2

-266.6

+52.2 Reactivit cm

+45.5

-44.5

+37.5

-30.0

+86.0 Reactivit desi

+45.8

-47

+38

-31.2

+87.8 Diff %

.66 5.62 1.33 4.0 2.09 Acceptance Criteria is +/- 10.0%. *R1:1-yrc

3.3 BoronEnd pints PPM The Boron Endpoints noted below are determined as per Operating Procedure 0204.5, Appendix A. Ajust-critical condition is established as near as practicable to the required rod configuration (i.e., ARO and control Bank C in). The RCS boron concentration was determined and then adjusted analytically for the ppm worth of the reactivity (measured in pcm) by which the actual critical state deviated from the design condition. Appendix A was performed for the ARO boron endpoint and latter for the CBC in boron endpoint.

TABLE3.3.1 BORON ENDPOINTS (PPM)

ARO CBC Measured 1538 1399 Westin house 1572 1424 Difference 34PPM 25 PPM Acceptance Criteria is +/- 50 ppm

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3.4 ROD WORTH Rod worths were measured as per Operating Procedure 0204.5, Appendices D and F.

The Reference Bank (highest predicted worth) was diluted into the core.

The boron concentration prior to and subsequent to this insertion was determined and the difference in the two boron concentrations is. defined's the boron (Rod) worth of the Bank (Table 3.4). The differential and integral worth ofcontrol bank C was measured and plotted (Figure 5).

TABLE3.4 ROD WORTH (PPM)

CBC Measured 139 Westin house 148 3.5 ROD WORTH PCM The remaining rod bank worths were measured using the rod swap technique, "swapping" negative reactivity insertions on the bank being measured with positive reactivity insertions from the Reference Bank.

TABLE3.5.1 CBD CBC'BB CBA SBB SBA Measured 691 1314 375 1177 1180 1000 ROD WORTH (PCM)

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-2.93

+0.42

+3.73

-4.1 Total 5737 5713

-24

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The isothermal and moderator temperature coefficients were determined using Appendix B in Operating Procedure 0204.5, Nuclear Design Check Tests During Startup AfterRefueling.

The values determined forthis testing sequence (in pcm/OF) are:

TABLE3.6.1 ISOTHERMALTEMPERATURE COEFICIENT (PCM/oF)

Rods D 214/213 MeasuredI

-.88 Design Westin house

-1.7 Diff

-.82 Acceptance Criteria is +/- 2 pcm/<F ofdesign.

TABLE3.6.2 MODERATORTEMPERATURE COEFFICIENT (PCM/oF)

Rods D 214/213 MeasuredI

+.92 Design>

Westin house

+.1 Diff

-.82 Acceptance Criteria is <+ 5 pcm/OF.

IThis is the average ofone heat up and one cool down measurement.

2This value has been adjusted forboron and temperature sensitivity. *Rl:I-yri.

3.7.

HZP DIFFERENTIALBORON WORTH The HotZero Power (HZP) Differential Boron worth was measured using Control Bank C, which had a bank worth of1314 pcm. The value obtained forthis test was:

TABLE3.7.1 HZP DIFFERENTIALBORON WORTH (PCM/PPM)

Measured 9.45 Westin house 8.58 9o Diff

-9.2 Acceptance criteria is ( +/- 15%. *Rl;I-yrz

HOT ZERO POWER DIFFERENTIAlANDINTEGRAlCONTROL BANKC WORTH VS BANKPOSITION FIGURE 5 UNIT 4

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4.0 SHUTDOWN MARGIN The Shutdown Margin was calculated prior to power escalation to verifyadequate shutdown capability. For this calculation the total ofthe design rod worths (minus the most reactive stuck rod) were reduced by 10%. The results show adequate shutdown margin at BOC and EOC. The followingis a summary ofthe results:

Control Rod Worth %h

~Cele XII BOC EOC AllRods Inserted Less Worst Stuck Rod (l) Less 10%

6.41 6.53 5.77 5.88 Control Rod Re uirements

%h Reactivity Defects (Doppler, Tang, Void, Redistribution)

Rod Insertion Allowance (2) Total Requirements Shutdown Margin (l)- (2) %h,p Required Shutdown Margin (%b,p) 1.90 3.27 1.52

.50 3.42 3.77 2.35 2.11 1.00 1.77 Source: WCAP 12010 *R1:I-yn

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-0.7 1.0$ 5 1.289 1.200 1.072 1.256 1.212 1.2 2.4 1.0 1.29$ 1.183 1.390 1.257 1.127 1.309 3.2 5.0 6.0 1.192 1.251 1.010 1.189 1.253 0.996 0.2 0(l 1.1 1.223 1.123 1.294 1.187

-5.4

-5.3 1.268 1.26$

0.0 1 ~ 059 1.205 1.260 1.111 1.252 1 ~ 284 6.7 3.8

-2,0

( ~

1.194 1.169 1.03C 1 ~ Zid 1.221 1 ~ OCT C.Z 4.3 2.9

~ ~

1.025 1 ~ 016 R.O 1.260 1.054 1.204 1.0C7 1.9

-1.2 1.233 1.224 1.053

1. 208 1. ZR1 1. 047

1. 1 0.3

-1. 3 1.262

1. ZIC 1.8 I.OCJ 1.0C7 2(2

~

~

1.196 I.ZIC 1.221 1.248

-2.0 R.7 1.116 1.270 1.127 1.257 0.9 l(0 1.243 1.190 1.253 1.1$ 9 0.8 0.5 1.185 1.290 1.187 1.294

-0.2

-0.4

~

~

1.2N 1.100 1.252 1.111 I(C. 1.0

~ ~

1.107 1.217 l(221 1.268 2.8 2.6 1.10$

1.073 3.2 1.271 1.257 1.1 l.225 1.212 1.1 1 ~ 200 l(291 0.$

1. 119 1.1$ 2 2.$

1. 228

1. 268 3.1

1. 132 1.182 1.2 0.635 0.125

'2.2

~

~

1.129 0.625 1.126 0.024 0.3 0.2 1 F 237 1.046 1.25C 1 ~ 072 1.4 0.7 0.339 0.33$

O.J 0.653 0.452 0.2

~

~

1.174 1.250 1.187 1.255 0.9 O.C 0.952 1.374 0.902 0.993 1.305 0.072 4.1 S.i J.C 1.212 1.129 1.249 1.121 3.0 0.5 1.131

1. 099 2.0 1.231 1.12$ 1.121 1.2%9 1.124 1.099

-1.2

~.4 2.2 0.237 0.231 2.5 0.203 0.274 2.5 0.236 0.231 2.1 N

H 0.701 0.652

$ +0

~ ~

0.346 0.338 I(~

I ~ 154 1.315 1.072 1.254 7.9 0.7 0.657<1.211 0.020 I

1.124 7.7 7.5 l.213 l.212 0.2 l.Zdi 1.257 R.l

~

~

O.CSI 1 ~ 071 0.425 1.073 7.7 0.1 0.315 0.33$

-4.8 1.JSC 1.250 1.292 1.255 1.1$ 7 1.2'9l 8.0 5.3 0.1 1.207 1.257

%.0

~.409 O.C53 C.7 1.114

1. 127 0.9

1. 068 1.101 3.0 1.363 1.309 R.C

~

~

0.854 0.873

-1.9 0.221 0.274 0.232 0+278

-%.5

-0.7 1.08C 1.194 1.279 1.111 1.252 1 F 284 2.2

-0.5 0.4

~

~

1.274 1.153 1.243 1.29C 1.1$ 7 1.26$

1.5 2.8

-2.0

~ ~

I(173 I(255 1.000 l(1$9 I.Z53 0.994 1.3 0.1 0.4 1.224 1.252 R.J

1. 042 l.111 C.C 1.260 1.291 3.9 1.119 1.228 O.C41 1(107 1.255

~ (452 5.7

-2.2 1.1 1.15I 1.241 1.1$ 7 1.294

-Z-C

-2.7 1.191 1.212 1.7 1.19$ 1.001 0.32$

1.254 1 072 0.338

-I~ 4 4(4 2.$

1.044 1.124 S.C

~

~

1.225 1.144 1.253 1.119 2.2 1.9 0.378 O.CRC

-11.0 1.234 1.257 1 ~ 7

~ ~l.070 1.073

-0.2

~

~

1.133 1.254 1.127 1.257 0.5 0.1

~ ~

~

0.409 0.125

-3.9

~

~

0.445

~.453 1 ~ 9 1 ~ 127 l.101 2.3

~

~

~.362

~.338 1.2

0. 234 0.232 0.9 IKASUOED F DELTA H EXPECTED F DELTA H DIFFEkENCE ROD POSiTiON Location in 8tegy Classification INCORE TAT N

SBB CBA CBB CBC mj m

~22 Map Ma. PM4XH<

Power % 48.94 heal Offset -.Z1 Msxp N 4H 1.523 1.0073 1.0122 0.9993 0.9812 CBD 188 MELxp N Q 1.822 *Rill-yrz

((elj

~

~

-(,

0

( ~,'tV; hk

~

(

~

~ NV

15 14 13 10 9

0.236

~. 229 2.9 7

6

~. 27$

~. 230

0. 275

~ <<889 1.1

~.5 f

r r

1 lf>>

N 0.235 0.228 2.$

~.430 0.414 3.0

~

~

0.343 1.086 0.332 1.052 3.3 3.3 0.664 1.274 0'43 1.245 3.3 R.J 1.107 1.146 1.085 1.1R7 2.0 1.6 0.433 0.415 4.3

1. 127 1.099 R.C 1.215 1.225

~.0 1.180 l.173 0.6 1.290

1. 281 1.3 0.345 0.332 3.3 1.088 1.053 3.3 1.241 1.226 1.3

~

~

1.175 l.105 0.8 1.27C

1. 206

-0.8 1, 180 1.1$ 7 0 ~ 1

1. 120 1.088 2.9 0.659

~.644 2.3

~ ~

1.007

1. 088

-O.l

0. 8$3 0 <<d68 1.7

~ ~

1.276 1.247 R.J 1,38C 1.342 3.3 l.091 l.009 0.2

~

~

1.163 1<<130 2<<9 1.110 1.130 1.$

1. 2$6

1. 204 0.1

1. 175 1.175 0<<0 1.280

1. 204

<<0

~ ~

1.261 1.149 1.287 1.19$

1.290 1.191 1.289 l<<191

-2.3 3.5 0.2 0.6 1.215 1.217 1.09C 1.249 1.24C 1.251 1.090 1<<RSl 2.7 2.0 0.2 0.2 1.074 1.219 1.27C 1.255

1. 102 1. 251 1. Z09 1. 251

-'2.5

-'Z.S

-'1.0

'0.2

~.644 0.644

0. ~

0.339 0.332 1,9

~ ~

~

~ ~

1.247 1.073 1.247 1.053 0<<0 1.9 0.426 0.415 2.6

~ ~

1.226 1.110 1.226 1.099 0.0 1.1

~ ~

~ ~

1.175

1. 175 0.0

1. 303 1.290 1.0 1.162

1. 185

-1.9 l.210 1.225 0 ~ 6

~ ~

1.097 1.2C9 l<<155

1. 102 l.206 1. 173 0.4 1.3 1.5 1.237 1.1CJ 1.260 1<<246 1.1$ 7 1.201 0.0 2.0 1.0 0.430

0. 414 3.8

~ ~

1.069

1. 052 1.7 1.226 1.245 1.6 1.10C 1.127 lrb 0.345 0.332 J.9 0.630 0.643

-2.1 1.099 0.243 1.085 0.22d 1.2 6.5 0.282 0.274 5.1 0.8$ 9 1.364 0.867 1.337 R,S 2.0 1.104 1.086 1.7 1.311 l.289 1.7 1.282

1. 287 0.4

~

~

1.007 1.156 1.099 1.090 1.156 1.09d 1.0 0.0 0.0 1.206 1.277 1.207 1<<289 0.0 0.9 1.079 1.006 0.6

~

~

1.366 1.337 R<<R 0.894 0.292 O.d67 0.274 3.1 6.5 0.235 0.228 3.1 1.119 1.156 1 ~ 005 1.1R7 J.l R.S 1.305 l.201 1.9 1.209 1.107 1.8 1.248 1.250 1.097 1.2SS 1 246 1 ~ 251 1 098 1 251 0.2 0.1

-0.1

~ 0.3 1.230 1.1C0 1.2CC 1.246 1.107 1.201

-0.6 1.6 1.2 1.130 1.127 0.3 1.114 0,239 1.005 0.228 2.6 4.5

0. 6CJ 0.643 3.1

~ ~

0.339 O.J32 2.1

~ ~ ~

1.204 l.245 3.1 1.060

1. 052 0.$

0.417 0.414 0.8 l.134 1.175 3.3

~

~

1.R09 1.225

-1.3 1.106 1.099 0.7 O.I1$

0.415 0.8 1 F 244 1.20C J.J 1.147 1.105 3.2

1. 210 1.22C 1.3 1.059 1.055 0.6 0.333 0.332 0.4 1.007 1.238 1.207 1.242 1.102 1<<251 1.2$ 9 1.251 1.4 lrd 0.2 0.7 1.13C 1.325 1.104 1.2$ 1 1.175 1.204 1.089 1.2$ 4 3.3 3.2 l<<S

-0<<2

~

~

~ ~

1.3$ 2 1.145 1<<342 1.130

3. ~

1<<3 1.252 1.151 1.247 1.130 0.4 1.9

~

~

~

~

1.100 0.875 1.101 1.088 0.868 1.0$ $

1.1 0 ~

1.2 0.647 O.CII 0.4 1.258 1.182 1.283 1.1$ 2 1.290 1.191 1.2$ 9 1.191 2.5 0.8 0.4 0.8 l<<153 1.175 lrb 1<<193 1.2RC

-R.C

~ ~

1.060 1.099 Rrb 1.245 1.0IS 0.412 1.247 l<<053 0.415

-0.2

~.0 0.8

~.651

~.JJC 0.644 0.332 1 ~ 1 1.0 1.077 1.247 1.132 1.102 1<<20C 1.173 2.2 3.0 3.5 1.2CO 1.147 1.185 1 ~ 290 1.105 1.225 2.3 3.2 3.2 1.228 1.245

-i<<4 l.037 l.052 1.4 0.405 0.414 2<<2 0.648 0'43 Orb 0.334 0<<332 0.0 0.230 0.278

~.231 0.229 0.275 0.229 0<<5 0.8 1.0 IKASDOED F DELTA H EXPECTED F DELTA H DIFFERENCE Bank I

SBh Location in Stegy ROD POSlTION Qml0 Map Na. PM4XII3 INCORE TlLT N

SBB CBh Power % 99.50 hxial Otfset +2.48 1.005B 1.0021 O.S99V O.S926 4SG'ax p N ha 1.4V5 CBD Mggp N q 1.920

-19>>r

• R111-yrZ

~

~ 1 C, r '%>>,

w'r..>>'4'(>>'r 8 r'r'>> l <<<<

5

'v 'rr 0',

~ ',

~ ~

r r

- '<<rr,

~f r".

>>">>'" )Ig>><<p;C'>>>>,'~<<.r,.

8.0 CRITICALBORON CONCENTRATION Unit4C cleXII The criticalboron concentration was calculated by adjusting a measured boron concentration to the equilibrium hot fullpower, all rods out condition. For Unit4 Cycle XIIthis calculation was performed at 900 MWD/MTU.

The followingis a summary ofthe results in PPM:

MEASURED1 1081 WESTINGHOUSE 1068 DIFF

-13 Acceptance Criteria is +/- 50 ppm

1) 1081 =

Actual Boron concentration (adjusted to equilibrium, HFP, ARO conditions) +

34':g~(Predicted HZP, ARO CB Measured HZP, ARO CB ) per ANSIStandard 19.6.1. *R1:1-yrx

i'd%