ML17227A587
| ML17227A587 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| 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
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ACCESSION, NBR: 9209110100 DOC. DATE: 92/09/01 NOTARIZED: NO DOCKET 0 FACIAL: 50-335=-St. Lucie Plant> .Unit 1> Florida Poeer h Light Co. 05000335 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, COPIES REC IP IENT COPIES ID CODE/NAKE ,LTTR ENCL ID CODE/MANE LTTR ENCL PD2-2 LA 0 PD2-2 PD- '
1 NORRISz J 2 2 A INTERNAL: ACRS 5 5 AEOD/DSP/TPAB 1 NRR CHATTERTON 1 1 NUDOCS-ABSTRACT 1 1 h
EG 02 1 RQN2 FILE 01 1 EXTERNAL: NRC PDR NSI C A
NOTE TO ALL RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
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TOTAL NUMBER OF COPIES REQUIRED: LTTR ib ENCL 15
P.O. Box 128, Ft. Pierce, FL 34954-0128 September 1, 1992 FPL 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 pg6l
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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 Contents Section ~Pa e Title I 4 Introduction H 4 Cycle 7 Fuel Design III 5 Approach to Criticality IV 5 Zero Power Physics Testing V 6 Power Ascension Program VI 6 Summary VII 7 References List of Fi es Fi re No. Titles 1 8 Cycle 7 Core Loading Pattern 2 9 Inverse Count Ratio Plot- Channel B 3 9 Inverse Count Ratio Plot- Channel D 4a 10 Inverse Count Ratio Plot- Channel 1 4b 10 Inverse Count Ratio Plot- Channel 2 5 11 Power Distribution- 25% Power 6 12 Power Distribution- 50% Power 7 13 Power Distribution- 100% Power List of Tables Table No. Title 1 14 Cycle 7 Reload Sub-Batch ID 2 14 Approach to Criticality 3 15 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 Criticality following reload,
- 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-flow conditions. 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 B and D and startup channels 1 and 2. Refer to Figures 2 through 4B for range'hannels 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 All Rods 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) All Rods 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 G F E D C 8 A H14 21 G64 H52 H02 J01 J19 H12 100 101 20 G73 J05 J21 J31 G30 J15 G72 8 102 103 17 G78 J37 '67 G74 J47 H37 J11 G69 18 45 49 202 J13 H66 J41 G11 G16 J59 H63 H34 J07 G65 74 16 61 76 79 17 G20 J45 J49 G44 53 J51 H55 G19 H49 28 7 39 3 H10 J29 J57 H73 H06 H75 G48 J43 G53 J23 104 ~ 48 203 21 204 71 105 15 G10 J17 H25 J33 H41 J65 G18 J67 H31 J55 G05 J27 J03 W4 65 38 62 10 66 11 "18 18 2
G26 G79 H60 H72 H07 H08 H71 H59 G70 G27 G31 205 78 56 24 42 206 11 H15 H17 0
J04 H24 J28 G12 J56 H32 J66 H42 J62 G13 J34 J18 41 '14 12 107 69 18 59 G07 G08 8
J24 J44 G61 H76 H05 H30 H74 G62 J58 G47 J30 108 1 207 109 208 32 110 J40 J52 J64 H70 J54 J50 J46 G33 H48 58 15 70 111 112 33 H67 H58 J42 H65 H39 J14 G37 57 113 114 115 36 J12 J48 G39 G75 J26 J38 H36 J10 G71 209 37 116 117 210 G77 J16 J32 G17 J22 G76 31 118 211 119 2
121 122 G15 H19 H13 G14 D ASSEMBLY ID INSERT ID Page 8 of 15
'la<<u 'm<< ~ <<<< * ~ <<<<LM<<<<'<<<<<<<< 'w<<~<<<<
St, Lucie Unit 2, Cycle 7 FIGURE 2 WIDERANGE CHANNEL "B" BORON DILUTION Cb <<130 Ca+NO Rye Neo+
1.0 0.9 0.9 08 0.8 0.7 0.7 0.6 0.6 tt 0.5 0.5 O
0.4 0.4 09 0.3 02 0.2 0.1 0.1 0 0 Gallons FIGURE 3 Diluted WIDE RANGE CHANNEL "D" BORON DILUTION ~
Cb <<100 Ch<<50 4l 1.0 1.0 0.9 0.9 0.8 0.8 0.7 0.7 0.6 0.6 tt-0.5 0.5 D
0.4 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 i
~ upas 1.0 0.9 0.9 0$ 08 0.7 0.7 0.6 0.6
~0.5 0.5 O
OA 0.4 0.3 0.3 0.2 0.2 0.1 0.1 0 0 Gallons FIGURE 48 Diluted
,STARTUP CHANNEL "2" BORON DILLON Cb+1$ 0 Cb+ SO Cb W M I 1.0 1.0 0.9 0.9 08 0.8 0.7 0.7 0.6 0.6 tt-0.5 0.5 O
0.4 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) UNIT 2 SNAPSHOT ID A062692.DAT POWER LEVEL EXPOSURE .32EFPH CEA POSITION 122 BORON CONC. 1426 PPM 0.7440 0.6870 DESIGN:
0.0570 DATASOURCE~F2 4 1.2660 0.8990 POWER LEVEL~2 1.2460 0.8550 EXPOSURE EFPH CEA POSITION 122 0.0200 3 0.0440 1.1700 1.2390 1.2740 1.1090 1.2040 1.2620 0.0610 0.0350 3 0.0120 1.3780 1.0990 1.3720 1.1890 1.3650 1.0340 1.3530 1.1780 0.0130 0.0650 2 0.0190 0.0110 2 1.1780 1.2260 1.3830 1.1150 1.1240 1.1650 1.2000 1.3640 1.0730 1.0740 0.0130 0.0260 2 0.0190 2 0.0420 2 0.0500 1.1820 ~
1.1570 1.3190 1 1410
~ 1.3720 0.8930 1.2160 1.1740 1.3300 1.1030 1.3490 0.8270
-0.0340 1 -0.0170 1 -0.0110 0.0380 1 0.0230 1 0.0660 1 0.3830 1.0400 0.8540 1.3050 1.1960 0.8830 0.3680 1.0630 0.8310 1.3110 1.1680 0.8180 0.0150 8 -0.0230 9 0.0230 1 -0.0060 1 0.0280 0.0650 0.2680 0.5310 0.8800 1.2370 0.8060 0.2530 0.4990 0.8590 1.2430 0.7500 0.0150 3 0.0320 0.0210 5 -0.0060 0.0560 0.3310 0.5410 MEASURED RMS DEVIATION 3,5189 , 0.3060 0.5040 DESIGN 0.0250 1 .0.0370 DELTA Page 11 of 15
St. Lucie Unit 2, Cycle 7 FIGURE 6 POWER DISTRIBuTION COMPARISION.WITH DESIGN AT 50% POWER MEASURE: (CECOR/INPAX) UNIT 2 SNAPSHOT ID g C062892.DAT EXPOSURE 9.32 EFPH 0.7440 BORON CONC. 1302 0.7340 0.0100 DESIGN: 1.2650 0.8980 DATA SOURCF: F2-92-054 1.2750 0.8940 EXPOSURE 10.00 EFPH -0.0100 3 0.0040 CEA POSITION 122 " 1.1650 1.2350 1.2720 BORON CONC 1309 1.1490 1.2300 1.2820 1 3 -0.0100 1.3680 1.0890 1.3660 1.1850 1.3630 1.0580 1.3650 1.1990 0.0050 0.0310 2 0.0010 -0.0140 2 1.1670 1.2150 1.3740 , 1.1090 1.1200 1.1600 1.1980 1.3570 1.0860 1.0970 0.0070 0.0170 2 0.0170 2 0.0230 2 0.0230 1.1760 1.1440 1.3090 1.1320 1.3670 0.8870 1.1920 1.1560 1.3070 1.0990 1.3380 0.8490
-0.0160 1 -0.0120 1 0.0020 0.0330 1 0.0290 1 0.0380 1 0.3790 1.0330 0.8460 1.2950 1.1860 0.8760 0.3740 1.0440 0.8300 1.2790 1.1520 0.8350 8 -.11 9 1 . 1 1 0.0340 0.0410 0.2710 0.5260 0.8700 1.2250 0.7930 MEASURED 0.2620 0.5070 0.8440 1.2050 0.7520 DESIGN 0.0090 8 0.0190 0.0260 5 0.0200 0.0410 DELTA 0.3260 0.5340 RMS DEVIATION~ 2 4743 0.3100 0.5090 0.0160 1 0.0250 2 Page 12 of 15
0 ~
St. Lucie Unit 2, Cycle 7 I
FIGURE 7 POWER DISTRIBUTIONCOMPARISION WITH DESIGN AT 100% POWER MEASURE: (CECOR/INPAX) UNIT 2 SNAPSHOT ID g A070392.DAT EXPOSURE 108 EFPH 0.7600 BORON CONC. 1060 0.6870 0.0730 3 DESIGN: 1.2820 0.9110 DATA SOURCE: F2 92 p54 1.2460 0.8550 POWER LEVEL 1pp o 0.0360 3 0.0560 EXPOSURE 1.1740 1.2470 1.2890 CEA POSITION ARO 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 1.3720 1.1100 1.1270 1.1650 1.2000 1.3640 1.0730 1.0740
-0.0100 0.0070 2 2 7 2 1.1630 1.1200 1.2930 1.1200 1.3640 0.9010 1.2160 ~
1.1740 1.3300 1.1030 1.3490 0.8270 1 -.54 1 -. 7 1 1 1 1 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 0.5180 0.8460 1.2080 0.7850 0.2530 0.4990 0.8590 1.2430 0.7500 ~KEY 0.0250 3 0.0190 -0.0130 6 -0.0350 0.0350 MEASURED 0.3190 0.5260 DESIGN RMS DEVIATION 3 7848 0.3060 0.5040 DELTA 1 1 0.0220 2 Page 13 of 15
St. Luoie Unit 2, Cycie 7 1hble 1 Cycle 7 Reload Sub-batch ID Sub-Batch ¹ of Assemb Ennch.
6 16'0 4.00 Gk 4.00 6/, 25 4.00/3.60 GX 12: 3.60 H 12 4.20 H* 8 4.20/3.80 H/ 32 3.80 HX 24 3.80 J 20 4.10 J/ 16 3.70 JX 32 3.70 .
Table 2 Agxoach to CrMcality Mution Rate Init. Boron Conc. Final Boron Conc. Dilution Tim,(min) 132 gpm 1744 ppm 1637 ppm 45 88 gpm 1637 ppm 1537 ppm 49 1537 ppm 1437 ppm 51 Page 14 of 15
St. Lucie Unit 2, Cycle 7 Table 3 CEA Group Worth Summary CEA Group Measured Design * % Diff.
Worth m Worth m Ref. Grp. 2079 2085 +.3%
1,2 1810 1851 +2.3%
3,4,5 1538 1555 +1.1%
A 1735 1773 +2.2%
Total 7162 7264 +1.4%
% Diff= (D/M-1)100 Reference 3 Page 15 of 15