ML17348A513

Cycle XII Startup Rept. W/900821 Ltr

ML17348A513
Person / Time
Site:	Turkey Point
Issue date:	08/08/1990
From:	Arlon Costa, Dyches A, Harris K FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-299, NUDOCS 9008310010
Download: ML17348A513 (31)

Text

t ACCELERATED DISTRlBUTION DEMONSTRATION SYSTEM t

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9008310010 DOC.DATE: NOTARIZ ED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION COSTA,A. Florida Power & Light Co.

DYCHES,A.R. Florida Power & Light Co.

HARRIS,K.N. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION SUBJECT W/900821 lt'nt Nuclear Plant Unit 3,Cycle XII Startup Rept."

DISTRIBUTI IE26D COPIES RECEIVED:LTR ~

ENCL ~

SIZE: ~C TITLE: Startup Report/Refueling Report (per Tech Specs)

NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 ., 0 PD2-2 PD 1 1 EDISON,G 2 2 INTERNAL: IRM TECH ADV NUDOCS-'ABSTRACT RGN2 FILE 01 1

1 1

1 1

1 EG ~

CH'A%gg RTON 02 1

1 1

1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P l-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10

.. Box 029100, Miami, FL, 33102-9100 AUG 2 5 3990 FPL L-90-299 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Unit 3 Docket No. 50-250 Startu Re ort The attached Startup Report is provided in accordance with Technical Specification 6.9.1.a. The Unit 3 Cycle XII Startup Report documents the first use of the Debris Resistant Fuel Assembly (DRFA) design, axial blankets, Reconstitutable Top Nozzle (RTN), fuel assemblies modified for extended burnup, burnable absorber assemblies updated via the Core Component Update Program, Standardized Fuel pellets, and thimble plug removal.

If you have contact us ~

any questions concerning this information please Very truly yours, K. N. arris Plant ice President Turkey Point Plant Nuclear KNH/JEK/3k Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Ins@dtmr,. USNRC, Turkey Point Plant

~,-.JPPB 1 CjA j. P +PC).-'PS PDR ADGCK P=rPPP ~ rC)

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an 1:Pi. Group company

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT NUCLEAR PLANT UNIT 3 CYCLE XII STARTUP REPORT i v7 OPt xA l AV6[1 990).Owl

~ INTRODUCTION This report contains the official summary of the Startup Physics Tests performed on Turkey Point Unit 3 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'heck 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 24, 1990, at 0050 and was completed on May 25, 1990 at 0629.

The Westinghouse Nuclear Design Report for Unit 3, Cycle XII, (WCAP-12538) 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.

Author:

Arlon Costa Reactor Engineer Reviewed by:

Anita R. Dyches Reactor Engineer Reviewed by: ~

~

~o J.L. erryman

~

Reactor Support Supervisor Approved by:

G. L. Ma Reactor Supervisor PTN

II TABLE OF CONTENTS PAGE ACKNOWLEDGEMENT INTRODUCTION TABLE OF CONTENTS I.O UNIT3 CYCLE XII CORE .....

1.1 Fuel Design Changes ..

1.2 Loading Pattern .

1.3 Rod Pattern and Rod Drop Times ....

2.0 INITIALCRITICALITY 4 2.1 ICRR vs. Dilution . 5 3.0

SUMMARY

OF TESTS 3.1 Nuclear Heating 3.2 Reactivity vs. Period 3.3 Boron Endpoints 3.4 Rod Worth (ppm), Most Reactive Bank .. 9 3.5 Rod Worth (pcm) .. 9 3.6 Temperature Coefficient . ~

3.7 HZP Differential Boron Worth 4.0 SHUTDOWN MARGIN 12 5.0 POWER DISTRIBUTION MAPS ........ ~.................... 12 5.1 30% Flux Map 13 5.2 50% Flux Map 14 5.3 100% Flux Map 15 6.0 CRITICALBORON CONCENTRATION 16

1.0 UNIT 3 CYCLE XII E 1.1 FuelDesi nChan es The Cycle 12 reload introduces for the first time: the Debris Resistant Fuel Assembly (DRFA) design, axial blankets, the Reconstitutable Top Nozzle (RTN), fuel assemblies modified for extended burnup, burnable absorber assemblies updated via the Core Component Update Program, standardized fuel pellets, and thimble plug removal. Additionally, the core has 9 reconstituted fuel assemblies that contain 16 stainless steel and 4 low enriched rods.

.2 ~Ldi P <<

This section presents the as-loaded core configuration (Figure 1, page 2).

1.3 Rod Pattern and Rod Dro Times This section presents the Control and Shutdown Rod pattern and the Rod Drop Times for all rods as measured per Procedure 3-PMI-028.3 RPI Hot Calibration, CRDM Stepping Test, and Rod Drop Test (Figure 2, page 3).

All rods met the drop time limit of 2.4 seconds as per Technical Specification 3.2.3.

19 FLORIDA POWER AND LIGHT TURKEY POINT NUCLEAR UNIT 3 CYCLE 12 FIGURE 1: CORE CONFIGURATION 15 14 13 12 10 5 4 3 2 1 I I I I I I I I I- I AA-48 BB-53 AA-42 I I I I I HF-1 8 HF-21 HF-19 I I I I BB-34 CC-23 DD-46 M-41 DD-48 CC-22 BB-45 I I I I R-97 R-33 I I I I BB-54 DD-38 DD-18 CC-28 DD-03 CC-10 DD-20 DD-40 BB-36 I I I 4P129 R-14 R-01 4P128 I I BB-38 M-45 DD-30 CC-55 CC-47 CC-17 CC-34 CC-49 DD-32 M-30 BB-30 I I 4BP130 SP193 R-27 R-15 R-96 4P12 I I BB-35 DD-41 DD-33 BB-49 CC-06 DD-06 BB-43 DD-08 CC-05 BB-31 DD-34 DD-42 BB-28 4P124 R-42 R-11 R-40 R-26 -

4P126W CC-25 DD-21 CC-52 CC-08 DD-26 CC-39 CC-18 CC-33 DD-27 CC-03 - CC-50 DD-17 CC-21 R-10A 8P192 R-43 8P196 R-20 SP194 R-04 4P125 R-41 AA-43 DD-49 CC-31 CC-35 DD-14 CC-48 BB-47 DD-1 5 BB-33 CC-46 DD-02 CC-43 CC-1 2 DD-50 AA-39 HF-17 R-35 R-29 R-07 R-02 HF-03 BB-44 M-37 DD-16 CC-20 BB-39 CC-1 6 DD-04 M-17 DD-11 CC-32 BB-29 CC-19 DD-1 2 M-52 BB-56 HF-25 SS-1 R-32 R-28 R-09 R-37 R-06 HF-14 AA-44 DD-51 CC-14 CC-36 DD-09 CC-37 BB-37 DD-10 BB-27 CC-44 DD-05 CC-45 CC-1 3 DD-45 AA-41 HF-12 R-36 R-17 R-08 R-03 HF-26 CC-11 DD-28 CC-51 CC-02 DD-19 CC-38 CC-24 CC-40 DD-24 CC-04 CC-56 DD-25 CC-27 R-1 0 8P186 R-44 8P184 R-21 8P189 R-45 4P130 R-39 BB-48 DD-43 DD-35 BB-46 CC-01 DD-07 BB-50 DD-01 CC-07 BB-25 DD-29 DD-37 BB-40 8P185W R-1 6 R-24 R-22 R-OS 4P131W BB-41 M-21 DD-36 CC-53 CC-41 CC-15 CC-42 CC-54 DD-31 M-29 BB-42 SP195 R-100 R-38 R-12 SP19 4BP131 BB-32 DD-44 DD-22 CC-30 DD-13 CC-29 DD-23 DD-39 BB-52 8P187W R-25 R-46 SP190W BB-55 CC-26 DD-52 M-27 DD-47 CC-09 BB-51 R-1 8 R-1 9 Assembly ID AA-56 BB-26 AA-40 Insert ID HF-24 HF-04 HF-08 VERIFIED BY: -'ATE: Wb

TURKEY POINT NUCLEAR PLANT UNIT 3 CYCLE 12 FIGURE 2: CONTROL ROD BANK LOCATION AND ROD DROP TIMES I

15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I R I I I I I I B B I I I I N I 1.367 1.333 I I I P 1.933 1.867 I I I I SA SA I I I 1.350 1.367 I I N 1.967 1.950 I I I C D C I 1.350 1.367 1.333 I M 1.883 1.933 1.933 I I SB A A SB I 1.333 1.383 1.350 1.317 L 1.867 1.817 1.800 1.850 I B C SB C B I 1.383 1.317 1.350 1.333 1.333 I K 1.967 1.817 1.933 1.900 1.917 SA A A SA 1.333 1.333 1.350 1.367 1.883 1.783 1.767 1.967 D SB D SB D 1.300 1.367 1.350 1.367 1.317 1.833 1.917 1.783 1.950 1.867 SA A A SA 1.350 1.383 1.367 1.367 1.950 1.817 1.783 1.867 B C SB C B 1.317 1.333 1.350 1.333 1.317 1.917 1.867 1.883 1.850 1.883 SB A A SB 1.367 1.350 1.333 1.350 1.917 1.783 1.783 1.867 C D C 1.383 1.350 1.333 1.900 1.917 1.883 SA SA 1.367 1.333 1.950 1.967 B B 1.383 1.450 1.917 2.050 FUNCTION 8 OF CLUSTERS Control Bank D 5 Control Bank C 8 Control Bank B 8 LEGEND:

Control Bank A 8 CONTROL BANK Control Bank SB 8 TIME TO DASHPOT (s)

Control Bank SA 8 TIME TO BOTTOM (s)

2.0 INITIALCRITICALI I The approach to criticality began May 24, 1990, at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br /> in accordance with Operating Procedure 0204.3, Initial Criticality After Refueling. Criticality was achieved May 24, 1990 at 1132 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.30726e-4 months <br /> by withdrawing control rods to 175 steps on Bank D and diluting the RCS with 18,101 gallons of water. Figure 3 (pages 5 and 6) is a plot of the ICRR during the approach to criticality.

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

TABLE 2.1: CRITICAL DATA Tavg 547.7 oF Control Bank D 197 Steps RCS Boron 1462 ppm Picoammeter Flux 1 x10-8A N35 Flux 1.9 x 10-8 A N36 Flux 1.9 x 10-8 A

Figore 3.

ICRR VS. DILUTION H20 Umt 3 Cycle XII OP 0204.3 1

l I

I I l

~ ~

nfl

-~

I~

~

5 6 7 10 HQGallons) X 1000

J ICRR VS. DILUTION H20 Unit 3 Cycle Xll

+PJ'S/ OP 0204.3 Date: 5 z o 5

ICRR 1.0

.9

.8

~Z

.6

.5

.3 13 15 16 1Z 18 19 20 21 23 HQGallons) X 1000

3.0

SUMMARY

OF TE This section provides a summary of the results of the low power physics tests for Unit 3, Cycle XII along with the Westinghouse design data. For each test, the acceptance criteria is listed at the bottom of the table. This report compares design and measured data using Difference and Percent Difference.

Difference = Predicted - Measured For calculating Percent Difference, the equation is:

Predicted Value

%Dig= 1 x 100 Measured Value H.1 ~NI H The point of adding Nuclear Heat was determined in accordance with 1

Operating Procedure 0204.3, Initial Criticality After Refueling, Step 8.15 and Appendix A. This is performed by establishing a small positive startup rate and measuring the point (flux level) at which Tpvg departs from its established steady value. Nuclear Heating was measured to first occur at values presented on Table 3.1.1. 1 TABLE 3.1.1: FLUX LEVEL (AMPS)

Picoammeter N-'35 N-36 2.0 x 10-7 3.5 x 10-7 3.5 x 10-7 All physics tests were conducted at or below 1 x 10-7 amps on the picoammeter connected to N-44 to assure Nuclear Heating did not occur.

3.2 Reactive vs. Period t Reactivity Computer checkout was done 'in accordance with Operating Procedure 0204.3, Initial Criticality After Refueling, Step 8.17 and Appendix 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.

I TABLE 3.2.1: REACTIVITYVS. PERIOD DESIGN PERIOD REACTIVITY REACTIVITY

~SEC ~PCM ~PCM  % DIFF*

-187.1 -46.0 -48.5 + 5.4

+ 87.3 + 59.5 + 60.4 + 1.5

+ 57.3 + 80.0 + 82.3 + 2.9

• Acceptance Criteria is + 4% for, positive period and + 6% for negative period.

3.3 Boron End pints m The Boron Endpoints noted below are determined as per Operating Procedure 0204.5, Appendix A. A just-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 later for the CBC in boron endpoint.

TABLE 3.3.1: BORON ENDPOINTS (ppm)

MEASURED WESTINGHOUSE DIFFERENCE*

ARO 1376 1405 29 ppm CBC 1227 1240 13 ppm

• Acceptance Criteria is +/- 50 ppm

3.4 Rod Worth 0 .

m Most Reactive Bank

~

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 as the boron (Rod) worth of the Bank (Table 3.4.1). The differential and integral worth of control bank C was measured and plotted (Figure 4, page 10).

TABLE 3.4.1: ROD WORTH (ppm)

MEASURED WESTINGHOUSE CBC 149 165 3.5 Rod Worth cm 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.

TABLE 3.5.1: ROD WORTH (pcm)

Measured W~ti ff ~Oitl i 'I Diff CBD2 844.6 848 + 3.4 + 0.40 C BC'371.0 1427 + 56.0 + 4.09 CBB2 450 8 447 -3.8 -0.84 CBA2 1127.8 1131 + 3.2 + 0.28 SBA2 1201.4 1206 + 4.6 + 0.38 SBBi 1023.6 1079 + 55.4 + 5.41 Total'019.2 6138 + 118.8 + 1.97 The acceptance criteria for rod worth measurements are:

~ Reference bank within +/- 10% of design, and 2 Individual bankswithin +/-15% or +/-100 pcm of design, whichever is greater, and 3 Sum of all measured banks within +/- 10% of design.

FIGURE 4 HOT ZERO POWER DIFFERENTIALAND INTEGRAL BANK C WORTH VS.

BANK POSITION

- Op. o20 I.5 UNIT' gN)TQ, CYCLE 12 CYCLE: XII EXPOSURE: 0.0 MWD/MTU igloo l 400 o +CA1 5 P:

BANK: CBC y tokay pc~ l3 BANK POSITIONS OUT IN MOVING llDD SBA Qx Q 0 E <~O lD SBB Qx Q 0 q 'V CBA Px Q 0 SOD l

0 CBB Px Q 0 0

3 CBC 0 0 Qx

'1 O CBD Px Q 0

~ c i -

p TEST METHOD iil i DILUTION

~ r Qx BORATION 0

~

I'D QO 4P lO SO le laO l'lO I4O l~ GOO St,cps Hit,kcLraw~

3.6 Tem erature oefficient The isothermal and moderator temperature coefficients were determined using Appendix B in Operating Procedure 0204.5, Nuclear Design Check Tests During Startup Sequence After Refueling. The values determined for this testing sequence are presented on Tables 3.6.1 and 3.6.2 below:

TABLE 3.6.1: ISOTHERMALTEMPERATURE COEFICIENT (pcm/0F)

RODS MEASURED1 WESTINGHOUSE DIFF*

D/197 -2.73 -2.0 + 0.73

• Acceptance Criteria is +/- 2 pcm/0F of design.

TABLE 3.6.2: MODERATOR TEMPERATURE COEFFICIENT (pcm/0F)

RODS MEASURED'* WESTINGHOUSE2 DIFF D/197 -1.03 -0.614 + 0.416

• Acceptance Criteria is (+ 5 pcm/oF.

1 This is the average of one heat up and one cool down measurement.

> This value has been adjusted for boron and temperature sensitivity.

3.7. HZP Differential Boron Worth The Hot Zero Power (HZP) Differential Boron worth was measured using Control Bank C, which had a bank worth of 1371 pcm. The value obtained for this test is presented on Table 3.7..1. k.

TABLE 3.7.1: HZP DIFFERENTIAL BORON WORTH (pcm/ppm)

MEASURED WESTINGHOUSE  % DIFF*

9.2 8.63 -6.2

• Acceptance criteria is < +/- 15%.

11

4.0 SHUTDOWN MAR The Shutdown Margin was calculated prior to power escalation to verify adequate shutdown capability. For this calculation the total of the design rod worths (minus the most reactive stuck rod) were reduced by 10%. The results show adequate shutdown margin at BOL and EOL. The following is a summary of the data used*:

TABLE 4.1: UNIT 3 CYCLE XII SHUTDOWN DATA BOL EOL Contro!Rod Worth %h All Rods Inserted Less Worst Stuck Rod 7.07 6.45 (I) Less 10% 6.36 5.81 Control Rod Re uirements %A Reactivity Defects (Doppler, T>>g, Void, Redistribution) 2.05 2.85 Rod Insertion Allowance 0.60 0.50 (2) Total Requirements 2.65 3.35 Shutdown Margin (I) - (2) %bp 3.71 2.46 Required Shutdown Margin (%bp) 1.00 1.77

• Source: WCAP -12538 5.0 POWER DISTRIBUTION MAPS The core was mapped using incore instrumentation for power levels of 30%,

50% and 100%. A summary of the results are presented on pages 13 through15.

12

t FLORIDA POWER AND LIGHT ~%!PANY TURKEY POINT PLANT OPERATING

SUMMARY

U~ 3 MEASURED ASSEMBLY POWER AND PERCENT DIFF. TD EXPECTED POWER r A 8 C 0 E F H J K 1 M N P R NORTH I 0.233) 0.249) 0.242)

)

+

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I -0.2) 0.9) 2.0] 2.0 ) 2. 1) 0.8) -4. 1) 14

+

0.360) 0.945) 1.268) 1.346) 1. 243) 1. 305) 1.215) 0.907) 0.350)

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+ r + + + + + +

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+ + + + + + + + + + +

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) 5.3) 3.4) 0.0) 0.2) -0.5] -0.2) 0.0) 1.2) 1. 7) -1. 'I ) -2.8) -1.4) -1.0) 1.6) 5,6) 8

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ROD POSITION Location INCORE TILT

~in Ste N

SBA 228 Map No. PM3XH1 SBB Poster ..... 3096 CBA 228 Axial Offset 7.324%

0.9975 1.0245 CBB 228 Max p N . ~ . 1.5272 ha 0.9983 0.9796 CBC 228 CBD 174 Max p N ... 2.0666

t FLORIDA POWER AND LIGHT ~PANY TURKEY POINT PLANT UM 3 OPERATING

SUMMARY

MEaSUREO aSSEM81.v POwER aNO PERCENT DIFF. TO EXPECTED POwER 0 E F G H K M N P R a 8 C NORTH 0.2521 0.260) 0 '38]

5.21 2.3) -0.41 +

15

+

) 0.347) 0,8101 1.140) 0.795) 1.0761 0.759) 0.325)

) 1.7) 3.8) 5.91 2.01 0,01 -2.71 -4.6) 14 t + + + + + +

) 0. 3561 0.971) 1. 2651 1.337) I. 2481 1. 285) I 1911 0.907) 0.3631

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+ e e + e +

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) 2.9) 2. 71 3.01 -2. 71 3. 31 -3. I ) -1.3) '1.2) 2.0) -3.5) -1. 6) 2. 2) 2.1) 10

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0.258) 0.796) 1.271) 218) 0 978) I 296) 1. 150) '0.833] I . 142) 1.233) 0.934) 1.212) 1.258] 0.796] 0.253)

2. 11 -0.'ll -0.9) 0.81 - I . 21

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I 0.8) 0.9) 1.9) -1.5) -2.7 I -2.21 -3.0) -5.3) -0.7) 1.0) 8

+ + + + +

) 0.243) 1.091) 1.3071 1. 216) I 2881 ~ 233) 1.057) 'I. 165) 1.047) 1. 185) I 2341 1.235) ~ '1.3441 1.092) 0.2381 0.8) 0.71 0. 11 -2.4) 0.41 0.9) 0.9) -0.1] -1.9) -3.1) -3.9] -0.9) 3.0) 0.9) -1.2) 7

+ + + e + + + + + + +

) 0.762) 1.234) 1.275) 1.267) I 351) 1.233 1.305) 1. 225) I 291 ) 1.236) 1,260) ~ 1,277) 0.806) 0.'ll 0.41 1

) -2.5) -0.5) I . 7) 1.3) 3.2) 0.6) -2.8) -2.1) 1. I ) 3.0] 3.0) 6

+ + + + e + +

I 3311 I 0841 I 274] 1.3151 1.0151 1.322) 1.237) 1.049] 1.264) 0.977) 0.351)

)

e

)

0.332) 0.951)

-2.5)

+

0.3)

+

~

3 ') +

~

-0.9) 1.21

+

2.61

+

3.2) 3. I ) -1.81 -4. I ) -1.91

+ +

3.0)

+

3.0)

+

5

) 0.377) 0. 8671 1. 3031 I 312) 1.282) 1.304) 1.3461 1,295) 1.304) 0.843) 0.3621 I 0.4) 0.21 0.81 2.9) 2.7) 7.1) 7.8) 1.6) 0.9) -2.6] -4.6]

+ + + e + + +

) 0,378) 0.9571 1.273) 1.333) 1.3251 1.3991 1.294) 0.934] 0.366]

I -'I ~ 6) 0 '1 2.7) 2.8) 7.51 7.9) 4.4) -1.9) -4.6) e + + + + +

I 0.335) 0.803) 1. 1041 0 8421' ~ . 159) 0.843) 0.325]

) -1.6) 2.91 2.7) 8. I) 7.8) 8.1) -4.6) 2 er + + + + e + e +

I 0.2601 0.276) 0.260) ) MEa5 I I 8.61 8.7) 8.6) ) DIFF ) I

+ + + + +

ROD POSITION Location INCORE TILT Bank ~ie Ste Classification N

SBA 228 Map No. FM3XII2 SBB Power ...... 50%

CBA 228 Azial Offset 4e609%

1.0124 0.9951 CBB Max p N 4H

... 1.5205 1.0099 0.9826 CBC 228 Max F N ... 1.9725 CBD 179 14

i FLORIDA POWER AND LIGHT ~OMPANY TURKEY POINT PLANT OPERATING

SUMMARY

MEASUREO ASSEMSI.Y POWER ANO PERCENT Diff.

~

TO EXPECTED POWER 4

A 8 C E F G H J N P R NORTH 0.245) 0.2601 0.243) 3.9) 3.6) 3.2) 15 e + +

0.336) 0,788) 1. 111) 0.796) 1.083 0.773) 0.327) 1

1. I) 2.5) 4.0) 2.31 1.4) 0.5) -1.8 I 14

+ + + e I 0.365) 0.942) 1.240) 1.329) 1.262) 1,306) 1. 199) 0.911) 0.366]

I -1.8) 1.3) 1.31 1.6) -0. I) -0.2) -2. I ) -2.0) -1.7) 13

+ + e

) 0.361) 0.825) 1.270) I ~ 269) 1. 275) 1. 3331 I. 259) 1.225) 1.224) 0.8161 0.357)

-1.8) -1.9) 0.5) 0.6) -0. I) -0.81 1.4) -3.0) -3.1) -3.0) -2.81 12

+ + + + + e I 0.333) 0.9201 1.2371 1,073) 1.246) 1.2781 0.9981 1.274) 1.2241 1.040) 1.2231 0.901) 0.323)

I 0.1) -0.61 1,8) 0.0) 0 01 F 0,9) -1.2) 1.1) -1.8) -2.9) -2.9] -2.7) -2.8 I

+ + + + + + +

) 0. 786) I, 2281 1. 245) 1,241) 1.3151 1.214) 1.266) 1.209) 1.29'I) 1.211) 1. 225) 1. 1921 0.749)

) 1.9) 0. I ) -1.3) -0.6) -0 'l1 -0.2) -0.4) -0.5) -1.9) -2.91 -2.9) -2.7) -2.91 10

+ e + + e +

) 0. 2471 1.086) 1. 3'I I ) I 2401 1. 290) 1. 214) 1.086) 1. 190) 1.071 ) 1. 207)

~ 1. 268) 1.236) 1.2701 1.066] 0.246)

) 4.3) 1.1) -0.4) 2,6) 0.0) -0.5) 0.9) 0.0), -0.5) -1.1) -1.7) -2.9) -3.51 -0.8) 3.9) 9

+ + + + e + e

) 0.258) 0.805] 1.227) 1.312) 1.015) 1.3071 1. 203) 0.967) I . 216) 1. 281) 0.996) 1.307) 1.226) 0.7901 0.262)

) 2.4) 2.0) -3.8) -2.6) 0.3) 2.3) 1.01 1.81 2. I ) 0.3) -1.6] -2.9) -3.9] 0.1) 3 8] 8

+ + + +

)

1.4) 0.81 -0.6) -1.1) 1.4) 2 ')

0.240) 1.083) 1.308] 1.259) 1.308) 'I.2511 1.0991 1. 213) 1. 102) 1. 215)

2. I) 2.0) 2.4) -0.41

1. 264) 1.2391 '1.262) 1.0771 0.246)

-2.0) -2.6)

+ +

4.1) 0.21 3.9) 7

) 0. 776) 1. 232) 1. 266) 1. 261) 1. 360) 1. 248) 1. 2971 1. 232) 1.311) 1. 222) I . 238) I . 196) 0.803)

] 0.7) 0.5) 0.3) 1.0) 3.4) 2.6) 2.0) 1.3) -0.41 -2. I) -1.9) -2.4) 4. I) 6

+

) 0.335) 0.946) 1.2851 1.072) 1. 261) 1.3211 1.031] 1.296) 1.239) 1.055) 1.248) 0.910] 0.332)

) 0 7) 2. I) 2 0) 0 0) 1. 2] 2.5) 2.0] 0.5) -0.5) - 1.6) -0.9) - 1.7) -0.2)

+ + + + + + + +

) 0.377) 0.855) 1.278) 1.268) 1.282) 1.395] 1.292) 1,274) 1,282) 0.840) 0.367)

) 2.6) 1. 7) 1.2) 0,4) 0.4) 3.8) 1.3] 1.0) 1.5) -0. I) -0.2)

+ + + +

) 0.3841 0.954) 1.254] 1.327] '1.225) 1.359) 1.251) 0.936) 0.372)

I 3.0) 2.5) 2.4) 1.4) 3.0) 3.91 2.2) 0.6) -0. I ]

+ + + + + + + + +

I 0.346) 0.805) 1.079] 0.780) 1.068) 0.796) 0.332]

) 3.91 4.7] 1.0] 0.2) 0. I) 3.6) -0.2)

+ + + + + + +

0.247) 0.245) 0.242] ) MEA5 )

4.8] -2.2) 2.9) ) OI FF )

+ + +

ROD POSITION Location INCORE TILT Bank ~in Ste Classification N

SBA 228 Map No. PM3XII3 SBB 228 Power ...... 100%

CBA 228 Axial Oftset 2.31Z%

1.0131 1.0014 CBB 228 Max p N hH

... 1.48Z5 1.0007 0.9848 CBC 228 CBD 228 Max p N ... 1.Z533 15

6.0 CRITICAL BORON CENTRATION The critical boron concentration was calcualted by adjusting a measured boron concentration to the equilibrium hot full power, all rods out condition, as per Operating Procedure 1009.6, "Critical Boron Concentration-Full Power". For Unit 3 Cycle XII, this calculation was performed at 390 MWD/MTU.The following is a summary of the results in ppm.

TABLE 6.1:

SUMMARY

OF CRITICAL BORON CONCENTRATION (ppm)

MEASURED1 WESTINGHOUSE DIFF*

932 950 +18

• Acceptance Criteria is +/-50 ppm

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

29 ppm (Predicted HZP, ARO CB - Measured HZP, ARO CB).

16