L-92-246, Cycle 7 Startup Physics Testing Rept. W/

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Cycle 7 Startup Physics Testing Rept. W/
ML17227A587
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 09/01/1992
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-92-246, NUDOCS 9209110100
Download: ML17227A587 (17)


Text

DOCKET 0 05000335

~CCFXXaAmO OmaxSUnox oaMQXS 'nom SvSrzM REGULATE(Y INFORNATION DISTRIBUTI SYSTEM (R IDS)

ACCESSION, NBR: 9209110100 DOC. DATE: 92/09/01 NOTARIZED:

NO FACIAL:50-335=-St.

Lucie Plant>.Unit 1> Florida Poeer h Light Co.

AUTH. NANE AUTHOR AFFILIATION SAGER'. A.

Florida Pacer Sc Light Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

"St Lucie'-Unit 2. Cycle 7 Startup Physics Testing Rept."

W/

920'F01 ltr.

DISTRIBUTION CODE:

ZEESD COPIES RECEIVED: LTR

~ ENCL J SIZE: /~

TITLE: Startup Report/Refueling Report (per Tech Specs),

NOTES:

REC IP IENT, ID CODE/NAKE PD2-2 LA NORRISz J INTERNAL: ACRS NRR CHATTERTON EG 02 h

EXTERNAL:

NRC PDR COPIES

,LTTR ENCL 1

0 2

2 5

5 1

1 1

REC IP IENT ID CODE/MANE PD2-2 PD-AEOD/DSP/TPAB NUDOCS-ABSTRACT RQN2 FILE 01 NSI C COPIES LTTR ENCL 1

1 1

1 A

A NOTE TO ALL RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.

ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR ib ENCL 15

P.O. Box 128, Ft. Pierce, FL 34954-0128 FPL September 1,

1992 L-92-246 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 Re:

St. Lucie Unit 2 Docket 50-335 St. Lucie Unit 2, Cycle 7

Startu Ph sics Testin Re ort In accordance with St.

Lucie Unit 2

Technical Specification 6.9.1.1, the attached Unit 2 Cycle 7 Startup Physics Testing Report is being submitted.

Should you have any questions, please contact us.

Very truly yours, D. A.

er Vice sident St. Lucre Plant DAS:JJB:kw cc:

Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant DAS/PSL 4770-92 9209110100 920901 PDR ADOCK 05000335 P

PDR an FPL Group company pg6 l

)

St. Lucie Unit 2, Cycle 7 Startup Physics Testing Report

St. Lucie Unit 2, Cycle 7 Author Bobbi Torres Reactor Engineering, St. Lucie Plant Reviewed

~vuJ~I t 'C4'oDQ Walter D. Mead, jr Reactor Engineering, St. Lucie Plant Reviewed

~

Jimmie Ferryman Nuclear Fuel, JPN Approved Erwin J. Wunderlich Reactor Engineering Supervisor St. Lucie Plant Page 2 of 15

St. Lucie Unit 2, Cycle 7 Table of ContentsSection I

H III IV V

VI VII

~Pa e 4

4 5

5 6

6 7

Title Introduction Cycle 7 Fuel Design Approach to Criticality Zero Power Physics Testing Power Ascension Program Summary References List of Fi es Fi re No.

Titles 1

2 3

4a 4b 5

6 7

8 9

9 10 10 11 12 13 Cycle 7 Core Loading Pattern Inverse Count Ratio Plot-Channel B

Inverse Count Ratio Plot-Channel D

Inverse Count Ratio Plot-Channel 1

Inverse Count Ratio Plot-Channel 2

Power Distribution-25% Power Power Distribution-50% Power Power Distribution-100% Power List of Tables Table No.

Title 1

2 3

14 14 15 Cycle 7 Reload Sub-Batch ID Approach to Criticality CEA Group Worth Summary Page 3 of 15

St. Lucie Unit 2, Cycle 7 I.

Introduction The purpose of this report is to provide a description of the fuel design and core load, and to summarize the startup physics testing performed at St. Lucie Unit 2 following the Cycle 7 refueling.

Startup physics testing verifies key core parameters are as predicted.

The major parts of this testing program are:

.1) Initial Criticalityfollowingreload,

2) Zero Power Physics Testing,

~ Reactivity Computer Checkout

~ ARO Boron Concentration

~ CEA Worth Measurements

3) Power Ascension Testing.

~ Fuel Assembly loading verification

~

25% Power Relative Power Distribution

~

50% Power Relative Power Distribution

~

100% Power Relative Power Distribution 0,

C cle7Fuel Desi The Cycle 7 reload consists of 68 fresh fuel assemblies (Region J), 76 once burned assemblies (Region H) and 73 twice burned assemblies (Region G). Table 1 provides enrichment information for the Cycle 7 reload sub-batches.

The mechanical design for the fresh. fuel assemblies, Region J, is nearly the same as for Region H fuel (Cycle 6); the only mechanical difference is that region J has four crimp holes instead of two, as in previous cycles, to secure the upper end fitting posts to the guide tubes.

The Region J fuel assemblies use the debris resistant fuel assembly (DRFA) design, making the entire Cycle 7 fuel load of debris resistant fuel assemblies.

The Cycle 7 core map is represented in Figure 1. The assembly serial numbers and Control Element Assembly (CEA) serial numbers are given for each core location. Cycle 7 employs a low-leakage design. Twenty-four twice-irradiated region G assemblies and twenty-four once irradiated region H fuel assemblies are placed on the core periphery and the fresh fuel, Region J, is loaded inboard.

Following the fuel shuffle and prior to the approach to criticality, CEA drop time testing was performed.

The objective of this test was to measure the time of insertion from the fully-withdrawn position (UEL) to the 90% inserted position

~

under hot, full-flowconditions.

The average CEA drop time was found to be 2.77 seconds with maximum and minimum times of 2.92 seconds and 2.62 seconds Page 4 of 15

St. Lucie Unit 2, Cycle 7 respectively.

All drop times were within the requirements of Technical Specifications 3.1.3.4 (i.e. less than or equal to 3.1 seconds).

III. A roach to Criticali The approach to criticality involved diluting from a non-critical boron concentration of 1744 ppm to a predicted critical boron concentration of 1487 ppm.

The actual critical concentration was observed to be 1476 ppm, Inverse countrate ratio (ICRR) plots were maintained during the dilution process using wide range'hannels B and D and startup channels 1 and 2.

Refer to Figures 2 through 4B for ICRR information.

Table 2 summarizes'the dilution rates and times, as -well as beginning and ending boron concentrations.

Initial criticality for St. Lucie Vnit 2, Cycle 7 was achieved on June 24, 1992 at 0300 with CEA group 5 at 60 inches withdrawn and all other CEA's at the AllRods Out (ARO) position.

IV. Zero Power Ph sics Testin The major tests performed for the startup of Cycle 7 were the following:

1) Reactivity Computer Checkout
2) AllRods Out Critical Boron Concentration
3) Isothermal Temperature Coefficient Measurement,
4) CEA Group Rod Worth Measurements The tests above were performed in accordance with approved procedures.

Proper operation of the Reactivity Computer is verified through the performance of two tests. In the first, reactor power is elevated sufficiently high to ensure maximum sensitivity of the reactivity measuring system and at the same time preserve adequate margin to the point of adding heat.

The second test ascertains response to a known value of positive or negative reactivity by measuring the values of positive or negative reactor periods that result.

The results of the Reactivity Computer checkout were compared to the appropriate predictions supplied by the fuel vendor. Satisfactory agreement was obtained.

The All Rod's Out Critical Boron concentration was performed.

The measured value was 1513.67 ppm which compared favorably with the design value Page 5of15

St. Lucie Unit 2, Cycle 7 of 1524 ppm. This was within the acceptance limits of 2 100 ppm.

The measurement of the Isothermal Temperature Coefficient was performed and the resulting Moderator Temperature Coefficient (MTC) was obtained.

The MTC was determined to be 0.94 pcm/'F which fell well within the acceptance criteria of 2 3.0 pcm/'F of the design MTC of 1.19 pcm/'F (corrected)..This agreed favorably with the Unit 2 Technical Specification 3.1.1.4 which states the MTC shall

,be less positive than 5.0 pcm/'F.

The final section of interest for low power physics testing is in the measurement of CEA Group Rod Worths.

Rod worth measurements were performed using the Rod Swap methodology.

This method'involves exchanging the reference group (measur'ed by Boration Dilution Technique) with each of the remaining test groups.

A comparison of the measured and design CEA reactivity worths is provided in Table 3.

The following acceptance criteria apply to the measurements made:

1) The measured value of each test group is within 215% or 2100 pcm of the design CEA worths, whichever is greater.

2)

The measured worth of the Reference Group, and the total worth for all the CEA groups measured is within %10% of the total design worth.

All acceptance criteria were met in that the Reference Group measure worth was within 210% design worth and each test group was within %15% or 2100 pcm design worth, V. Power Ascension Pro am During Power Ascension, the fixed incore detector system is utilized to verify that the fuel is loaded properly and there are no abnormalities occurring in the various core parameters (core peaking factors, LHR, and Tilt) for power plateaus at 25%, 50%, and >98% rated thermal power.

Calorimetric, Nuclear, and bT power calibrations were performed at each of the plateaus prior to advancing reactor power to the next higher power level.

A summary of the results of the flux maps at each power level is provided 'in Figures 5, 6, and 7.

VI.~S Compliance with the applicable Technical Specifications was satisfactory.

Page 6 of 15

St. Lucie Unit 2, Cycle 7 VII.References

1) Reload Startup Physics Testing," Pre-Operational Number 3200091, Revision 0.
2) St, Lucie Unit 2 Technical Specifications"
3) "St. Lucie Unit 2, Cycle 7 Fuel Reload PC/M-067-292E.
4) "Initial Criticality," Pre-Operational Test Procedure Number 2-3200088, Revision 3.

Page 7 of 15

St. Lucie Unit 2, Cycle 7 Figure 1

Unlt2, Cycle 7 Revision 1

P M

K H

Y X

IN V

T 5

R N

H14 G

F E

D C

8 A

21 G64 H52 H02 J01 100 J19 101 H12 20 G78 J13 74 G73 J05 8

H66 16 J21 102 J37 '67 45 J41 61 G11 G74 G16 J31 103 J59 76 G30 J47 49 H63 J15 17 H37 G72 J11 202 H34 G69 J07 79 G65 18 17 H10 G20 J29 104 J45 28 J57

~ 48 J49 7

G44 H73 203 53 39 H06 21 H75 204 J51 3

G48 H55 J43 71 G53 G19 H49 J23 105 15 G10 18 H15 G07 J17 65 J04 41 H25 G26 205 H24 J24 108 J33 38 G79 J28

'14 H60 78 G12 J44 1

H72 J56 12 G61 H41 H07 56 H32 H76 207 J65 62 H05 109 J66 107 H30 H08 24 H42 H74 208 G18 J67 H31 J55 10 H71 J62 69 G62 G05 H59 42 G13 J58 32 J27 66 G70 J34 18 G47 G27 206 J30 110 J03 11 G31 J18 59 W4 "18 2

H17 11 0

G08 8

J40 58 J52 15 J64 70 H70 J54 111 J50 112 J46 33 G33 H48 J12 209 G77 H67 57 J16 31 J48 37 G39 J32 118 121 H58 113 G75 G17 211 J26 116 2

122 J42 114 J22 119 J38 117 H65 115 H36 H39 J10 210 G76 J14 36 G71 G37 G15 H19 H13 G14 D

ASSEMBLYID INSERT ID Page 8 of 15

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St, Lucie Unit 2, Cycle 7 FIGURE 2 WIDERANGE CHANNEL "B" BORON DILUTION Cb <<130 Rye Ca+NO Neo+

1.0 0.9 0.9 08 0.8 0.7 0.7 0.6 0.6 tt 0.5 O

0.4 0.5 0.4 09 0.3 02 0.2 0.1 0.1 0

0 FIGURE 3 WIDERANGE CHANNEL "D" BORON DILUTION~

Gallons Diluted 1.0 Cb <<100 Ch<<50 4l 1.0 0.9 0.9 0.8 0.8 0.7 0.7 0.6 0.6 tt-0.5 D

0.4 0.5 OA 09 0.3 0.2 0.2 0.1 0.1 0

0 Gallons Diluted Page 9 of 15

St. Lucie Unit 2, Cycle 7 FIGURE 4A STAR'IVP CIIANNEL"I" BORON DILUTION cb+1sO uzgzs Cb+ 00

~iupas 1.0 0.9 0.9 0$

08 0.7 0.7 0.6 0.6

~0.5 O

OA 0.5 0.4 0.3 0.3 0.2 0.2 0.1 0.1 0

0 1.0 Cb+1$ 0 W

FIGURE 48

,STARTUP CHANNEL "2" BORON DILLON Cb+ SO M

Gallons Diluted CbI 1.0 0.9 0.9 08 0.8 0.7 0.7 0.6 0.6 tt-0.5 O

0.4 0.5 0.4 0.3 0.3 0.2 0.2 0.1 0.1 0

0 Qellons Diluted Page 10 of 15

St. Lucie unit 2, Cycle 7

, FIGURE 5 POWER DISTRIBUTIONCOMPARISION WITH DESIGN AT 25% POWER MEASURE: (CECOR/INPAX)

SNAPSHOT ID A062692.DAT POWER LEVEL EXPOSURE

.32EFPH CEA POSITION 122 BORON CONC.

1426 PPM DESIGN:

DATASOURCE~F2 4 POWER LEVEL~2 EXPOSURE EFPH CEA POSITION 122 1.3780 1.3650 0.0130 1.1780 1.2260 1.1650 1.2000 0.0130 0.0260 2

1.2660 1.2460 0.0200 3

1.1700 1.2390 1.1090 1.2040 0.0610 0.0350 3

1.0990 1.3720 1.0340 1.3530 0.0650 2

0.0190 1.3830 1.1150 1.3640 1.0730 0.0190 2

0.0420 2

UNIT 2 0.7440 0.6870 0.0570 0.8990 0.8550 0.0440 1.2740 1.2620 0.0120 1.1890 1.1780 0.0110 2

1.1240 1.0740 0.0500 1.1820 1.2160

-0.0340 1

0.3830 0.3680 0.0150 8

~

1.1570 1.3190 1.1740 1.3300

-0.0170 1

-0.0110 1.0400 0.8540 1.0630 0.8310

-0.0230 9

0.0230 1

1 ~1410 1.3720 1.1030 1.3490 0.0380 1

0.0230 1

1.3050 1.1960 1.3110 1.1680

-0.0060 1

0.0280 0.8930 0.8270 0.0660 1

0.8830 0.8180 0.0650 0.2680 0.2530 0.0150 3

0.5310 0.4990 0.0320 0.8800 0.8590 0.0210 5

1.2370 1.2430

-0.0060 0.8060 0.7500 0.0560 RMS DEVIATION 3,5189 0.3310 0.5410

, 0.3060 0.5040 0.0250 1.0.0370 MEASURED DESIGN DELTA Page 11 of 15

St. Lucie Unit 2, Cycle 7 FIGURE 6 POWER DISTRIBuTIONCOMPARISION.WITHDESIGN AT50% POWER MEASURE: (CECOR/INPAX)

SNAPSHOT IDg C062892.DAT EXPOSURE 9.32 EFPH BORON CONC.

1302 DESIGN:

DATASOURCF:

F2-92-054 EXPOSURE 10.00 EFPH CEA POSITION 122 "

BORON CONC 1309 1.3680 1.3630 0.0050 1.1670 1.2150 1.1600 1.1980 0.0070 0.0170 2

1.1760 1.1440 1.3090 1.1920 1.1560 1.3070

-0.0160 1

-0.0120 1

0.0020 1.1650 1.1490 1

1.0890 1.0580 0.0310 2

1.3740 1.3570 0.0170 2

1.1320 1.0990 0.0330 1

UNIT 2 0.7440 0.7340 0.0100 1.2650 0.8980 1.2750 0.8940

-0.0100 3

0.0040 1.2350 1.2720 1.2300 1.2820 3

-0.0100 1.3660 1.1850 1.3650 1.1990 0.0010

-0.0140 2

, 1.1090 1.1200 1.0860 1.0970 0.0230 2

0.0230 1.3670 0.8870 1.3380 0.8490 0.0290 1

0.0380 1

0.3790 1.0330 0.3740 1.0440 8 -.11 9

0.8460 0.8300 1

1.2950 1.2790 1

1 1.1860 0.8760 1.1520 0.8350 0.0340 0.0410 0.2710 0.2620 0.0090 8

0.5260 0.5070 0.0190 0.8700 0.8440 0.0260 5

1.2250 1.2050 0.0200 0.7930 0.7520 0.0410 MEASURED DESIGN DELTA RMS DEVIATION~

2 4743 0.3260 0.3100 0.0160 1

0.5340 0.5090 0.0250 2

Page 12 of 15

0

~

St. Lucie Unit 2, Cycle 7 I

FIGURE 7 POWER DISTRIBUTIONCOMPARISION WITH DESIGN AT100% POWER MEASURE: (CECOR/INPAX)

SNAPSHOT IDg A070392.DAT EXPOSURE 108 EFPH BORON CONC.

1060 DESIGN:

DATASOURCE:

F2 92 p54 POWER LEVEL 1pp o EXPOSURE CEA POSITION ARO UNIT 2 0.7600 0.6870 0.0730 3

1.2820 0.9110 1.2460 0.8550 0.0360 3

0.0560 1.1740 1.2470 1.2890 1.1090 1.2040 1.2620 0.0650 0.0430 3

0.0270 1.3680 1.0950 1.3780 1.1980 1.3650 1.0340 1.3530 1.1780 0.0030 0.0610 2

0.0250 0.0200 2

1.1550 1.2070 1.1650 1.2000

-0.0100 0.0070 2

1.1630 1.1200 1.2930 1.2160

~

1.1740 1.3300 1 -.54 1 -.

7 1.3720 1.3640 2

1.1200 1.1030 1

1 1.1100 1.0730 7

2 1.3640 1.3490 1

1 1.1270 1.0740 0.9010 0.8270 74 1

, 0.3740 1.0210 0.8340 1.2780 1.1750 0.8700 0.3680 1.0630 0.8310 1.3110 1.1680 0.8180 0.0060 8

-0.0420 9

0.0030 1

-P.P33P 1

0.0070 0.0520 0.2780 0.2530 0.0250 3

RMS DEVIATION 3 7848 0.5180 0.4990 0.0190 0.8460 0.8590 1.2080 1.2430

-0.0130 6

-0.0350 0.7850 0.7500 0.0350 0.3190 0.5260 0.3060 0.5040 1

1 0.0220 2

~KEY MEASURED DESIGN DELTA Page 13 of 15

St. Luoie Unit 2, Cycie 7 1hble 1 Cycle 7 Reload Sub-batch ID Sub-Batch

¹ ofAssemb Ennch.

6 Gk 6/,

GX HH*

H/

HX J

J/

JX 16'0 25 12:

12 8

32 24 20 16 32 4.00 4.00 4.00/3.60 3.60 4.20 4.20/3.80 3.80 3.80 4.10 3.70 3.70.

Mution Rate 132 gpm 88 gpm 1744 ppm 1637 ppm 1637 ppm 1537 ppm 45 49 Table 2 Agxoach to CrMcality Init.Boron Conc.

Final Boron Conc.

DilutionTim,(min) 1537 ppm 1437 ppm 51 Page 14 of 15

St. Lucie Unit 2, Cycle 7 Table 3 CEA Group Worth Summary CEAGroup Measured Worth m

Design

  • Worth m

% Diff.

Ref. Grp.

1,2 3,4,5 A

2079 1810 1538 1735 2085 1851 1555 1773

+.3%

+2.3%

+1.1%

+2.2%

Total 7162 7264

+1.4%

% Diff= (D/M-1)100 Reference 3 Page 15 of 15