L-2008-052, Cycle 17 Reactor Startup Physics Testing Report

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Cycle 17 Reactor Startup Physics Testing Report
ML080950523
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 03/26/2008
From: Johnston G
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2008-052
Download: ML080950523 (35)
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0 Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 March 26, 2008 iFPL L-2008-052 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 2 Docket No. 50-389 Cycle 17 Startup Report Pursuant to St. Lucie Unit 2 Technical Specification (TS) 6.9.1.1, Florida Power & Light Company (FPL) is submitting the Cycle 17 Startup Report. This report is required due to the replacement of the steam generators and the implementation of Startup Test Activity Reduction (STAR).

Please contact us if there are any questions regarding this submittal.

Very truly yours, Gordon L. Johnston Site Vice President

(

St. Lucie Plant GLJ/KWF Attachment M/a&

an FPL Group company

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 1 of 34 ST. LUCIE UNIT 2, CYCLE 17 REACTOR STARTUP PHYSICS TESTING REPORT

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 2 of 34 Table of Contents Section Title Pane I Introduction 4 II Cycle 17 Fuel Design 5 III CEA Drop Time Testing 6 IV Approach to Criticality 7 V Zero Power Physics Testing 8 VI Power Ascension Program 9 VII Steam Generator Testing 10 VIII Summary 12 IX References 13 List of Appendices Appendix Title . Page A Summary of Implementation on the First Application of STAR for St. Lucie Unit 2, Cycle 17 26 List of Figures Figure Title Page 1 Cycle 17 Core Loading Pattern 14 2 Inverse Count Ratio Plot- Channel C 15 3 Inverse Count Ratio Plot- Channel D 15 4 Inverse Count Ratio Plot- Channel 1 16 5 Inverse Count Ratio Plot- Channel 2 16 6 Power Distribution Comparison with Design - 30% Power 17 7 Power Distribution Comparison with Design - 45% Power 18 8 Power Distribution Comparison with Design - 98% Power 19 9 Average RSG Differential Pressure 20 10 Rx Vessel Differential Pressure vs. Power 21 11 RCS Temperature vs. Power 22 12 Tavg/Tref vs. Power 23

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 3 of 34 Table of Contents (cont)

List of Tables Table Title Paae 1 Cycle 17 Reload Sub-Batch ID 24 2 Approach to Criticality 25 3 Comparison of Key Parameters 27 4 Summary of Tests Performed for Cycle 17 28

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 4 of 34 I. Introduction The purpose of this report is to provide a description of the fuel design and core load, and to summarize the startup testing performed at St. Lucie Unit 2 following the Cycle 17 refueling.

The startup testing verifies that key core and plant parameters are as predicted. The major parts of this testing program include:

1) Initial criticality following refueling,
2) Zero power physics testing,
3) Power ascension testing, and,
4) Replacement Steam Generator Testing.

This Cycle 17 Startup Report is being submitted in accordance with Technical Specification 6.9.1.1 due to the replacement of the original steam generators during the refueling outage, which may have significantly altered the thermal and/or hydraulic performance of the unit.

The test data collected during startup and summarized in this report indicates that although key thermal-hydraulic parameters exhibited some changes there was no significant impact to the performance of the unit. The test data satisfied all acceptance criteriaand demonstrated conformance to predicted performance.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 5 of 34 II.' Cycle 17 Fuel Design The Cycle 17 reload consists entirely of fuel manufactured by Westinghouse. The primary

.design change to the core for Cycle 17 is the replacement of 77 irradiated fuel assemblies (4 Region P assemblies, 73 Region S assemblies) with 72 fresh fuel assemblies (Region X), and 5 irradiated Region S fuel assemblies from the spent fuel pool. The fuel in the Cycle 17 core is arranged in a low leakage pattern. The mechanical design of Region X fuel is essentially the same as that of Region U fuel, and consists of Value-AddedTM fuel pellets and Guardian GridTM design, first introduced in Cycle 11. The only significant difference is that Region X incorporates the use of ZIRLOTM cladding.

The safety analysis of this design was performed by Westinghouse and by FPL using NRC approved methodologies. The core design and the generation of physics inputs to safety are performed by FPL using the Westinghouse physics methodology.

The Cycle 17 reload is based on the Westinghouse WCAP-9272, Westinghouse Reload Safety Evaluation Methodology, first introduced in Cycle 15 for St. Lucie Unit 2. This approach uses a checklist format to assess cycle-specific core design and plant parameters for compliance with the existing safety analysis.

The Cycle 17 core map is represented in Figure 1. The assembly serial numbers and Control Element Assembly (CEA) serial numbers are given for each core location.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 6 of 34 III. CEA Drop Time Testin2 Following the core reload and prior to the approach to criticality, CEA drop time testing was performed. The objective of this test is to measure the time of insertion from the fully withdrawn position (upper electrical limit) to the 90% inserted position under hot, full flow conditions. The average CEA drop time was found to be 2.91 seconds with maximum and minimum times of 3.02 seconds and 2.74 seconds, respectively (Reference 7). All drop times were within the 3.1 second requirement of Technical Specification 3.1.3.4 and within the safety analysis requirements supporting the reload PC/M 07004, "St. Lucie Unit 2 Cycle 17 Reload,"

requirements (Reference 6).

St. Lucie Unit 2 L-2008-052 Docket No. 50-3 89 Attachment Cycle 17 Startup Report Page 7 of 34 IV. Approach to Criticality The approach to criticality involved diluting from a non-critical boron concentration of 1830 ppm to a predicted critical boron concentration of 1623 ppm. Inverse Count Rate Ratio (ICRR) plots were maintained during the dilution process using wide range channels C and D, and startup channels 1 and 2. Refer to Figures 2 through 5 for ICRR information. Table 2 summarizes the dilution rates and times, as well as beginning and ending boron concentrations.

Initial criticality for St. Lucie Unit 2, Cycle 17, was achieved on January 4, 2008 at 0204 hours0.00236 days <br />0.0567 hours <br />3.373016e-4 weeks <br />7.7622e-5 months <br /> with CEA group 5 at 112 inches withdrawn and all other CEAs at the All-Rods-Out (ARO) position. The actual critical concentration was measured to be 1623 ppm (Reference 1).

St. Lucie Unit 2 L-2008-052 Docket No. 50-3 89 Attachment Cycle 17 Startup Report Page 8 of 34 V. Zero Power Physics Testin2 To ensure that the operating characteristics of the Cycle 17 core were consistent with the design predictions, the following tests were performed:

1) Reactivity Computer Checkout;
2) All Rods Out Critical Boron Concentration; and,
3) Isothermal Temperature Coefficient Measurement Proper operation of the reactivity computer is ensured by performing the "Reactivity Computer Checkout." This part of the testing determines the appropriate testing range and checks that reactivity changes are being correctly calculated by the reactivity computer's internal algorithms.

The testing range is selected such that the signal to noise ratio is maximized and that testing is performed below the point of adding nuclear heat. The reactivity calculation is checked by performing a positive and negative reactor period test through respective introduction of a known amount of positive and negative reactivity. The results of the reactivity computer checkout were compared to the appropriate predictions supplied in the reload PC/M 07004 (Reference 6). Satisfactory agreement was obtained.

The measurement of the all-rods-out (ARO) critical boron concentration was performed. The measured value was 1627 ppm which compared favorably with the design value of 1628 ppm (Reference 2). This Was within the acceptance limits of+ 50 PPM.

The measurement of the isothermal temperature coefficient was performed and the resulting Moderator Temperature Coefficient (MTC) was derived. The MTC was determined to be 1.279 pcm/°F which fell well within the acceptance criteria of+ 2.0 pcm!°F of the design MTC of 1.63 pcm/°F. This complies with Unit 2 Technical Specification 3.1.1.4 requirements that the maximum upper limit shall be +5 pcm/°F at <70% of Rated Thermal Power.

Rod worth measurements were not performed due to the implementation of the Startup Test Activity Reduction (STAR) program (Reference 9). Appendix A contains further information on the implementation of STAR for Unit 2 Cycle 17.

All acceptance criteria were met.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 9 of 34 VI. Power Ascension Program During power ascension, the fixed incore detector system is utilized to verify that the core is loaded properly and there are no abnormalities occurring in various core parameters (core peaking factors, linear heat rate, and tilt) for power plateaus at 30%, 45%, and greater than 98%

rated thermal power.

A summary of the flux maps at the 30%, 45% and 98% power levels is provided in Figures 6, 7 and 8. These flux maps are used for comparing the measured power distribution with the predicted power distribution. For the purposes of power ascension, the acceptance criteria require the Root Mean Square (RMS) value of the power deviation to be less than or equal to 5%. The individual assembly powers should be within 10% of the predicted power for assembly powers greater than or equal to 0.9 (30% and 98% plateaus). In addition, for the 30% plateau the Relative Power Density (RPD) should be within 0.1 RPD units of predicted for assembly powers less than or equal to 0.9. These criteria were satisfied.

Additionally, calorimetric, nuclear, and delta T power calibrations were performed at each power plateau prior to advancing reactor power to the next higher level specified by procedure.

A determination of RCS flow by calorimetric parameters (Reference 8) was performed and the measured result of 404,128 gpm met the minimum acceptance criteria of 349,500 gpm (Technical Specification required flow of 335,000 gpm + uncertainties).

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report. Page 10 of 34 VII. Steam Generator Testin2 The Unit 2 Original Steam Generators (OSG) were replaced with new, equivalent steam generators supplied by AREVA, during the 2007 Steam Generator (SG) and Replacement and Refueling Outage. As a result of the steam generator replacement, return to service testing was performed.

The return to service testing comprised two discreet types of testing: post work testing and performance testing. Testing of many of the individual components impacted by the installation of the Replacement Steam Generators (RSGs) was performed and documented under the Post Maintenance program. Performance testing which required integrated plant conditions was performed using existing plant procedures, or specialized test procedures detailed in 2-PTP-35, "Unit 2 Cycle 17 Return to Service Testing and Performance Verification".

There were no adverse conditions identified during the performance of 2-PTP-35 affecting the thermal and hydraulic behavior of the reactor core. Performance of the RSGs was monitored throughout the power ascension. The data was reviewed at each power plateau and compared with design predictions, which were summarized in 2-PTP-35. The power plateaus were chosen to align with the normal power ascension procedure.

Figure 9 displays the measured primary side differential pressure at the power plateaus. As illustrated on the graph the average differential pressure decreased with rising power due the effects of decreasing fluid density with power. Reactor Vessel differential pressure was monitored throughout the power ascension and is shown on Figure 10. This parameter was used to estimate the RCS flow in Mode 3. Values for the measured and predicted differential pressures are provided in Table VII-1 below. Based on the various instrument uncertainties (e.g., RCS flow measurement uncertainty is +/-14,500 gpm) and accuracy of the analytical model, the differences are considered reasonable and the results acceptable.

Table VII-1: Differential Pressures for the SG and Reactor Vessel (Based on 100% Power, 1355 MWt per SG)

Parameter Measured Value Predicted Value SG Differential Pressure 20.5 psid to 23.5 psid @ 27.6 psid @ measured measured flow of flow of 402,814 gpm 404,128 gpm Reactor Vessel Differential Pressure 47 psid @ measured flow 45.05 psid @ measured of 404,128 gpm flow of 409,193 gpm Figure 11 shows the RCS temperatures at the various power levels. TCold was maintained per procedures to approximately 549°F (actual measured was -548.34°F). The measured THor and consequently AT were higher than predicted due to the effects of Hot Leg Stratification Factor (HLSF), which was determined to be approximately 5°F at 1006/o power.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 11 of 34 The parameters TAvg, TRef and predicted TAvg are plotted on Figure 12. The Average Temperature, (TAvg), based on primary temperature instruments and TRef, which is derived from turbine first stage pressure, are used as indication of primary to secondary power mismatch. At 100% power the predicted TAvg was 572.26°F, the measured TAvg was 575.8°F, and the measured TRef was 575.7°F. The measured values were reasonable compared to the predicted value taking into account the effect of HLSF. Also, with TAvg and TRef being within 0.1 *F of each other there was no indication of a primary to secondary power mismatch and the results are documented as acceptable.

The RCS low flow reactor trip is derived from SG differential pressure instrumentation.

Differential pressure data is collected in Mode 3. The low flow trip setpoints were determined and implemented based on the Mode 3 differential pressure data. The Hot Zero Power flow rate of approximately 406,000 gpm calculated in Mode 3 determined that the low flow trip setpoints were set to cover a range of SG differential pressures of 20.0 psid to 28.5 psid as specified in 2-PTP-35.

At the 98% plateau, the RCS flow was determined as 404,128 gpm (202,064 gpm per SG) at a SG differential pressure of approximately 23 psid per SG. AREVA determined the best estimate primary flow to be 201,407 gpm per SG with a pressure loss along the tubes of 27.60 psid at this predicted flow rate. Considering the calculational uncertainties as well as the instrument uncertainties for both the flow measurement (i.e., +/--14,500 gpm) and the differential pressure measurements, the calculated and measured values are within the measurement uncertainty and are considered acceptable.

In accordance with Technical Specification Table 3.2-2, the measured RCS flow rate (after accounting for uncertainties) is required to be > 335,000 gpm and less than the PCM 05137 maximum design flow of 431,000 gpm. Accounting for a measurement uncertainty of 14,500 gpm, the actual RCS flow is between 389,628 gpm and 418,628 gpm. Therefore, the minimum flow requirement is met and the design flow rate is not exceeded.

BlowdoWn testing was performed in accordance with NOP-23.02. The acceptance criterion for the blowdown test is to achieve a blowdown rate of 1% (5.9 x 104 lb/hr/SG) of steam flow or meeting the maximum capacity of the system. As a blowdown capacity of 5.9 x 104 lb/hr/SG was achieved during the test the blowdown capacity measurement was documented as acceptable. In addition, there was no detectable primary to secondary leakage as verified by testing and by Chemistry daily sampling results.

As described above, RSG performance tests that could impact the thermal and hydraulic behavior of the reactor core, performed per RSG Return to Service procedure, were completed and it was concluded that there were no adverse impacts to the thermal and hydraulic behavior of the reactor core as a result of the installation of RSGs at St. Lucie Unit 2.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 12 of 34 VIII. Summary Compliance with the applicable Unit 2 Technical Specifications was satisfactory. The acceptance criteria for all the startup testing parameters were met.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 13 of 34 IX. References

1) "Unit 2 Initial Criticality FollowingRefueling, " Pre-Operational Procedure 2-3200088, Rev.

27.

2) , "Reload Startup Physics Testing, "Pre-Operational Procedure 3200091, Rev. 27
3) "Reactor Engineering Power Ascension Program," Pre-Operational Procedure 3200092, Rev. 33.
4) St. Lucie Unit 2 Technical Specifications.
5) Engineering Evaluation PSL-ENG-SEMJ-08-01 1, "St. Lucie Unit 2 Replacement Steam GeneratorReturn to Service Summary Report, " Revision 0, February 2008.
6) St. Lucie Unit 2 Cycle 17 Reload PC/M #07004, Rev 1.
7) "Periodic Rod Drop Time and CEA Position Functional Test," Operating Procedure 2-0110054, Rev. 26C.
8) "RCS Flow Determination by Calorimetric," Operating Procedure 2-012005 1, Rev. 16A.
9) WCAP- 16011-P-A, Rev. 0, "Startup Test Activity Reduction Program," February 2005.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 14 of 34 FIGURE 1 CYCLE 17 CORE LOADING PATTERN P M K H y R N L *J *G F E D C B A x w v T S U17I I I*A

' I I I 21 U25 T65 T40 X51 X02 X54 T3,9 T69 U24

-** ...... * ... -;... .. 20 145 106 X62 T38 T28 I I T23 T37 X56 X66 U10 U66 U20 X68 X62 T38 T28 -.. .19 121 110 210 104 65 U2 -4.-I-+-I-4.-I-4.-I-4.-4-4.-4 121 U22 U37 U03 65 X46 --

T21 T21 X45 Xll XII U08 U43 X34 U22 X36 U37 U03 X16 T2.7jj- ----- --....18 205 50 137 139 49 200 U23 T42 X18 U48 T05 X27 T71 U54 T55 X28 T08 U47 X10 T36 U31 42 115 132 111 133 45 38 T58 X63 U06 T07 X37 T09 U56 T01 U65 T16 X42 T19 U05 X50 T63 -. 1------ 16 102 48 61 117 142 114 T41 X69 U40 X31 T11 U53 X12 T47 X22 U60 T06 X23 U38 X70 T29 15 120 135 203 57 204 130 108 X64 U34 X43 T59 U50 X19 T52 X04 T45 X20 U68 T72 X33 U12 X52

-13 58 143 59 54 56 136 146 . ..12 X05 U59 U55 T02 T51 X06 S78 X07 T50 T03 U52 U62 -. 11 202 103 39 113 124 126 209 T62

-10 X59T61 U57 X15 T49 X08 T48 X17 U49 T56 X35 U8 X60 9

8 144 35 119 125 138 23 T34 X71 U39 X09 T13 U61 X26 T46 X14 U58 T12 X13 U44 X65 T31 7 68 129 207 122 208 24 41 766 X57 U01 T14 X40 T20 U63 T04 U67 T18 X41 T17 U07 X58 T68 101 105 100 116 66 62 U29 T35 X30 U46 T15 X29 T70 U64 T60 X25 T10 U45 X32 T33 U30 36 112 134 37 131 123 127 T26 X47 X24 U02 U41 X38 U16 X39 U42 U04 X21 X48 T25 206 46 140 141 109 211 T24 T43 X53 X72 U14 U51 U26 X67 X55 T30 T22 118 70 201 71 107 U32 T67 T32 X49 X03 X61 T44 T64 U33 76 128 U15I 54I S12 55IU 28 Assembly Serial #-- [--

Insert Serial #-I ##-

St. Lucie Unit 2 L-2008-052 Docket No: 50-389 Attachment Cycle 17 Startup Report Page 15 of 34 Figure 2. Wide Range Channel C Boron Dilution 0.9 HM114M1 0.8 0.7 0.6 20.4 M 0.3 0.2 12 0.1 0.0 - -

0 1000 2000 3000 4000 5000 6000 7000 8000 9000

.Gallons Diluted Figure 3. Wide Range Channel D Boron Dilution 1.0 0.9 0.8 0.7 0.6zZ r0.5 20.4MT 0.3 0.1 0.0 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 Gallons Diluted

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 16 of 34 Figure 4. Startup Channel 1 Boron Dilution 1.0 - -- -

0.9 0.8 19Em -f-0.7 0.6 0.5 2 0.4 9 ý-g- n 0.3 0.22 0.0 0.1 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 Gallons Diluted Figure 5. Startup Channel 2 Boron Dilution 1.0-0.9 0.8 0.7 0.6 1 H

S0.5

~~HIM 0.3 0.2 0.1 0.0 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 Gallons Diluted

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 17 of 34 Figure 6 POWER DISTRIBUTION COMPARISON WITH DESIGN - 30% POWER A.eosured: BEACON Design:

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.0,00 0,00 4.,020 00 .00 4.030 A.020 4.00 -0,420

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The inore detnotion system is operable per Appendix 1, RMS deviation shoutd be less than or equal to 5.0% and meet the requirements of 4.7.1 if performed at the 25 and 98 peroent power test plateaus during the power ascension Key-test program.

Box #

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 18 of 34 Figure 7 POWER DISTRIBUTION COMPARISON WITH DESIGN - 45% POWER Measured: BEACON Design:

Source 4? -0005084935*3 PCM7004.R1 Exposure 7.12 - 162 a N CEAPosition 23 13- 0~. 217, 216 L 21 2N 0 T S 1 000 1106 0

-.. 000

- .2.7 II.

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" 3 12 1 1 210 1209 ý208 1207 12. 12.

.20 .40

'no 0.620 1.170 1.40 1.90 0.2 0.420 0-zi8 4.010 1 .010 4.010 0.00 0.00 -().o1 4.010 -(.010 0.000

.* * :_

  • n10 1s _1* _In Z04 0.340 0.350

-2.9'.010 203 7.620 1(30

.1.6 202 1.29 1.200

-0.0 I20 1.250

.250 10., 0.

200 1.220 1220 0.0 199 1320 1-320 00 10 1.230 1.220 0.8 1297 2.260 1.250 0.8 296 1.200 2.200 0.0 19"t 0.620 0.630

-1.6 294 040 0.350

.2.9 c

193 192. 1 92 20 209 280 187 186 185 184 123 182 262 0.340 1.120 2.200 2270 .230 2.2.29 0.20 1.300 1.230 1.270 2.240 1 .232 0.340 0.350 1.130 1.240 2.260 2.220 2.280 1.280 1 .280 2.220 1.260 2.240 1.230 0.390 0.010 .0.20 0.000 0.020 0.020 0.010 0.010 0.020 0.010 0.010 0.000 0.000 0.020 1080 279 178 277 176 175 174 173 272 271 170 269 200 167 266

.211 0.620 1.2,K) 13"0 .190 .3]0 .9130 1:,170 0.980  ;.310 1.190 :3]90 M.4 *.620 2118 0.200 0.630 1.240 2.310 2.270 1.290 0.960 2.250 0.960 1.290 1.170 1300 1.2,0 0.630 0.280 0.000 0.010 0.000 0.010 0.020 0.020 0.020 0.020 0.020 0.020 0.020 0.010 0.000 A0.010 0.000 0.0 -1.6 0.0 0.7 .7 2.5 2.0 1.7 0.0 1.5 2,7 0.7 0.0 -0.6 0.0 165 164 163 162 261 260 519 I5M 257 156 505 154 153 152 151 0.420 2.200 2.200 2.200 1.320 .230 1.440 0.120 2.230 0.230 2300 1.280 1.20 1.200 0410 0.420 1.200 2.260 2.270 1.200 .220 2.220 2.100 2.220 2.20 2.290 1.270 2.20 1.200 0.420 0.020 0.000 0.020 0.020 0.020 0.010 0.020 0.020 0.010 0.010 0.010 0.020 0.020 0.000 0.000

.2.4 .0 1.6 [,7 .5 uo.9 1,6 1.8 '0. 0.9 0.8 o.8 0.8 0.0 0 150 149 140 147 046 245 144 143 142 141 040 139 230 037 236 0.610 1.260 0.230 0310 1.130 1.270 1.270 0.970 2.270 2.260 2.120 1300 2.230 2.250 0.620 0.620 2.250 1-220 2.0 1.020 1.250 1.260 0.970 1.260 2.290 2.120 1.200 0.220 0.259 0.620

-0.010 n.8 0.010 o.8 0.010 t.5 0.020 0.9 0.010 .m60.020 0.s 0.010 0.0 0.000 0.8 0.010 0.110.010 0.0 0.000 (I.8 0.010 o.0 0.001 0.0 0.000 "* -0.010 *

-4.6 D350 20 109 034(

7 00 209 100 120 006 1022 21 233 2.100 132 1.230 2.0 131 10 13 0.260 22 2.22 0 211

.970 0 1.250 07 2.250 0.260 2120 2.050 .280 2210 2.230

-2.9-0.020 2.20 12320 .100 0.250 1.220 0.97 02 0.740 1.250 0.97 22.0 2.960 1.2.0 1.220 2.270 -.0.372 7

118 -0.020 0.010 0.010 0.020 0.012 0.000 0.000 0.000 0.000 .0.020 0.000 0.010 0 0.0 0.00 -0.010 1.410 A.010 116~~ ] 1 2 1 ~ ;110 109 108 107 0 0 1003 00:370 0.060 1.220 .2190 0.970

-2.5 17240 12320 2.200 0.650

_1.0 1.2 19.70 090 1.260 0.250 0.00 2.290 2.0 1 1.010 26 2.260 2.0 1.220 0.960 2.00 1.280 2.230

.220 2.270 0.00 2.7 Jul 16 -0.010 150 0.000 974 0.010 ;03 0.020 95 0.020 94 0.020 931 0. 0.0 92 00 9 0.000 0 0.to 0 0.00 8 0.01 809.2 0.000 0.010 -0.010

.0'9 0.0 0.0 0.9 00 0.0. 0.0 0 0.0 0.0 0 0.0 00.. .0.0 0.8 .7. 83 o 50 0.370 0.380

.1M0 20 0.290 2.970 1 127021.000 2.7 02 10.60 0 1.26 20 1.970 2.290 2.200 0.670 03.00.020 1.170 1.290 2.20 2.960 1.220 1.250 2.60 0. .000 2.260 1.220 .960 1.2.220 2.60 2.

0.020 0.000 92 00 0.000 In 79 0.020 78 0.020 0.020 76 0.000 79 0.0we 4 0.000 2 7 0.000 0.000 72900.010 70 0.010 69 0.000 60 .. 020 03510 -oo J

-0.69 .0 0.8 0 .8 0 0.8 0.0 0.0 0.0 0.8 0.0 0.8 0.0 0.0 -1.6 2-340 2_340 62 61 s 679 63 277 76 75 74 73 72 71 70 59 M J 0.000 0.420 1.200 2.270 2.280 2.30 21.230 1.270 010 1.20 12.20 200 0.18300 1.230 :2.00 1610 0.610 2.200 2.260 2.270 2.20 .220 1.260 2.970 1.260 1.250 1.120 1.290 2.260 0.200 0.620 0-.we o0.020 0.020 0.00 0.020 0.020 O.OLO o0.oo 0.020 0o.o 0.02 0.000 0.00 0oowI -,0010 50 . 0.0 00s8 009 09 0.0 0.0 0.0 0.0 0.0 00 0.0 00 .04 27 1 4 0 *5 7 0, 4* 44 43 2,42. ..

1.201.90 70 80190 1.1"0 1.0 1.I10 1.23 120 I 300 1.180 1.2?0 1.2100 0:40 o:.'A10 n.o 0.00

.201)

.0 A.010 1.260 0.8 omolo 1.170 u.s o.010

1.2" u.

0.010 1.120 0.9 O.OLO I.220 0.8 0.010 1.110 ono omoo 1.220 u.,

omoto0 1.120 0.0 o.000 1.20 0.,

0.010 1.170 1.,

O.OLO 1.26()

0.8 o~l ~

1.200 0.0 moo0.010

).410

.2A

.200 .620 .230 2.380 2.280 2.300 0.970 2.060 .70 I20 2.170 2310 20 .620 0.260 0.200 0.630 1.240 1.380 1.170 L.290 0.960 2.150 0.We 2.200 1.170 0.380 2.240 0.630 .280 0.000 0.010 -0.020 0.000 0.010 0.020 0.010 0.000 0.020 of 0 0w -4.020 '0.020 0.000.

3. 1.6 JAS 0.0 1.8 ,00 1.0 0.9 1.0 0.0 " 1.0 10.0 As8 l6 o.0 07 20 35 34 33 32 32 0 29 120 27 2 25 0.340 1.110 1.230 0.260 10.220 2.200 2.200 1.20 1.210 1.260 2230 1.020 )340 0.350 1.130 1.240 2.20.0 1.220 2.280 0.200 1.280 1.220 0260 1.240 0.230 0350

.o" -0.00`020 4.01007 0.000 I 0.000 0000 0.000 . 0.000 .0.010 0.000 -0.000 -0. 20 -0 010 24 23 22 201 0 12 18 27 16 15 14 0.350 0.630 7.200 1.250 1.220 21.320 1.220 1.250 2.200 0.630 0.350

.00 .00 1 .010

- .10",ol 0.000 4..01 0 -().020 1:* .020 10 .020 .1

____ F' +' 4.' 4' 4' 4' F F F' F--'

13 22 22 16 20 9 s8 7

).270 40 0.610 1.170 1.220 1.5 *.0 .00 10.270 7.2870 0.420 0.620 0.100 1.240 1.270 0.620 0.410 0.282

-0.020 A.0.0 0.010 -. 020 -. 02.020 .020 .020 -0.020 -0.020 0340 0.400 0.370 0.330 0350

ý4 1.410 10'" 12 0101080 0.340ot

-2.9 25 .2. .ý3.04 RMS Deviation: 1.03%

The incore detection system is operable per Appendix 1, RMS deviation should be less than or equal to 5.0% and meet the requirements of 4.7.1 if performed at the 25 and 98 percent power test plateaus during the power ascension Ke0-0 test program.

  • 4 St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 19 of 34 Figure 8 POWER DISTRIBUTION COMPARISON WITH DESIGN - 98% POWER Measured: BEACON

-Soure -O10ýO C -2I0 ' . oPC

-0704oR /

Powr 1.0. 915 300 %

N Expo-o CEAPosiion.. ~

25. 2 3EP1 :

'V~

4 CP

" oI I _, I ... I .

0.300 0.39 0.42 0.36 V

0.280 213 0.290

.0.00 0.410 211 0.420

-0.00 060 1211 0.620

-0.00 0.0 230 1.160

.0.01 0

.2.6

.20 205 1.220

.010

.2.4 weS

.0 r

1.370

  • .0.10

.2.9 0.620 J70.620 0.00 1206 20 0.420 0.000 0.290 1205 0.295 0.000 D

204 203 202 120t 00 1299 19 1.97 396 195 194 c Ii 030O 0.620 I3.0 L230 11.210 1330o 3.230 1.230 1.180 0.630 039 0.360 0.630 1.180 1,230 1,200 0 1.230 1.230 3.30 0,630 0.30 0.10 -.0.00 .0.030 0.000 0.030 0.010 o.0.0 0.000 0.0o0 0.0 0.000 i . 21 i

S 193 389 18S 387 186 385 384 133 132 I83 91.3 1.220

.9122 1.250 1.210 .200 !AS0 3.280 1.220 1.250 3.220 1.120 0350 0350 1.120 1.220 1.250 1.230 1.2"0 1.380 3.270 1.210 1.200 3.220 1.120 0.360 0.00 ,OlOI 0.000 0.000 0.00. 0.010 0.00o 0.030 0.0L0 0.0oo 0.000 0.000 ,0.0 In 10 179 175 177 376 175 174 303 172 131 370 369 365 167 166 0.290 0.630 1.220 1360 3.370 .300 0."00 1.370 0."00 3.00 .170 330 3.220 0.630 0.290 0.290 0.630 1.220 1.350 3.360 3.280 0.550 .150 0.000 .1280 1.170 350 1.230 0.630 0.29" 0.000 0.0 00 0.010 0.030 0.020 o.oo0 0.030 0.000 0.020 0.000 0.030 0.000 o.o00 0.000 00.0 .0 .0 0.7 0.9 1. 00 09 0.0 1.5 0.0 0.7 0.0 0 0.0 165 16" 163 162 161 130 359 30 157 156 355 154 353 152 151 0.420 3.200 3.300 3.330 3.300 1."90 3.250 .130 1.240 3.140 3300 1.170 1.2t50 1S0 0.410 0.420 0 3.80 3.250 3.170 .290 1.1330 1.30 1.2 .2 30 3.290 1.160 1.250 3.350 0.420 0.000 0.010 0.010 0.020 0.020 0.010 0.020 0.010 0,010 0.010 0.010 0.010 0.000 0.000 4.010 0.0 0. 0 0.5 2.5 09j 1. .6 0.9 0. 0.9 0.8 0.9 0.0 0.0 .7.4 150 149 148 147 146 145 344 343 342 141 340 139 138 137 336 0.620 1.240 1.220 3.300 3.240 3.290 1.290 3.000 3290 3.250 1.340 3.290 3.230 1.230 0.630 0.620 3.230 3.210 1 .210 3.130 3.270 3.200 0.990 1.250 3.270 3.130 3.250 3.230 1.230 0.620 0.000 0.030 0.010 0.020 0+010 0.020 0.010 0.030 0.03 0 30 0 0 0.0 0.000 0.000 4.010 135 0.0 0 .8 1 1 16 .8 1.0 0. 0+ 0.8 0.0 0.0 .3.6 0350 1 034 0 1 0360 333 132 33 3129 230 128 127 026 325 124 123 122a 22 120 119 3.94 0.350 I A

9010 3.160 3.210 n.280 0.950 3.250 1.29" 1.030 3290 3.030 1.200 3.240 0.000 .250 1.200 1.350 170 3.210 .1270 0.000 1.230 1.280 1.030 1.290 .030 1.2n0 3.230 0.980 0370 3.290 1.360 .2.9 0.010 o0.o00 0.010 0,010 0.020 o.010 o.o00 0.000 o.ooo 0.000 0.010 o.o00 0.010 0.000 0 .0.0 117

-.09 0.0 Ox I.O 1.6 08 .O 0. 00 0.0 0o. 0.0 o.S 00 .0.9 340 5'0

(),20

-8.020 236 330 334 203 312 I11 330 109 08 107 306 105 104 103 102 0.390 3.230 3.300 2.380 1.370 130 1.000 3.290 0.75 .290 0.990 3.130 1.160 1.300 1.300 1.210 3.220O :300 1.080 1.360 3.320 0.990 3.200 0780 .290 0.990 1.120 3.150 1.3s0 3300 1.220 - .6.

. 0 0.000 0c.3oo0 0.030 0.010 0.010 0.o00 0.000 0.000 0.000 O.O03 0.000 0.000 0.000 .0.0 101 IOO

-.0 0.0 0.0 0.9 fl.9 1.0 10 . 00o lO 0.0 0.9 0.0 3.0 0.0 .0.8 0.350 0.410 3 9 00 97 5 96 94 93 92 9' 90 9 80 37 06 85 0.420 1

1.200 3.20 0.00 1.240 1290  :.030 .290 3.030 1.280 .2.40 0.00 1.280 3.200 1.160

.2.6 s30 1.270 0.'0 1.230 1.230 3.030 329 030 1.280 1.230 0."00 1.270 1.210 1.170 -2.4 9 -0.010 oo 0.000 O lO. 01 0.

o o 0.0 0 O.l3O 0.000 0.000 . 0.00 o.0 0o.010 o0.00 0.010 0.000 A.o0o0 0.0 0.8 " 0.0 0.8 08* 00 0.0 00 0.0 0.3 0.5 0.8 0.0 .0,5.-.......

O.34O 13w 0.35O01 03 00 S2 79 78 77 76 75 74 73 72 71 70 69 65 A.380 0.610 1.230 3.210 1.300 3 .340 1.280 1.290" .950 ,280 1.280 1.340 3.300 1.220 1,240 0620 ,.96 0,620 1.230 3.210 1.280 1,130 1.270 1.280 0.590 3280 3.270 .;330 1.280 1.210 3.230 0.620

.0 o ooo 0.000 0.000 0.020 0.010 0.010 0.020 0.000 0.000 0.030 0.010 0.020 0.0D0 0.010 0.000

.1.6 0 0.0 1.5 0.9 0.8 0,8 0,0 o 00 7.8 0+9 1.5 0.8 0.8 8.0 67 60 65 64 63 62 61 "0 59 58 07 56 55 54 53 0.430 13180 1.250 3.270 13010 3 3.240 3230 .240 3.130 12.0 2.370 1.250 3.080 0.420 0.420 1 1380 1.250 3.160 3.290 1.130 1.230 3.320 1.230 3.130 1.290 1,170 1.250 3.100 0.420

. 0 0 0.0000 0.000 0.0 10 0.030 0.030 0.010 0.0 10 0.030 0.000 0.000 0.000 0. 0

.0000 0.000

-2.4 0 0 00 0.5 0.8 09L908 05 08 0.0 0.0 0 ,0 0.0 0.0 .0 52 51 1541 47 6 45.44 43 42 40 .0. 39 0.290 0.630 3.220 3.5 70 3.290 . .00 3.1 6000 1.2"0 3.360 .350 33 0.620 0.290 0.29000 .630 3.2233 3.350 3.370 3.280 0.000 3.160 0.0 3.280 3.360 1.350 3.230*M 0.630 0.290 0:20.000 o ~~ ~ ~

0 0 .000 .0 oO 0 0.00 0 .000 mi 0

0.0 I[.0.03 Mooo 10.0 0.0 o0ooo

. 0.0 ~ 0.000 0.000 o.olo

. 0.03 0

0.33o 0.0 o 0+0 0.00

. .0.030.0.

.SA .6".0.10

-10 ). 0.0 o.0 o

17 36 35 34 33 12 33 30 29 28 27 26 25

o. so IAN1 1.210 3.240 1.220 1280 1.170 1.270 1.2330 3.240 1.210 1.100 0340 0.360 1.120 1.220 1.250 1.210 3.270 1.180 1.270 3.230 3.220 1.200 1.20 10.350

" OlO -A.010 -o.010 -.0.00 0.000 0.030 .0.0 0.03o 1..01101.20.0 .0.00 -.0.2 -0.00

0. .~'4, 0.0 41 . 4, _0710 4"' -0.

I'..

29 ,9 24 23 22 23 20 39 18 37 16 15 14 0.340 0.620 1.170 1.230 1.200 1.200 1.390 1.2"0 1.160 0.620 0.340 0.350 0.630 1.280 3.230 1.210 3.300 3.200 3.230 3.180 0.630 0.360

-0I00

,0 . 0A.O .00 0. .000 4.0 .0.010 -. 00 -().020 0.020 1 l.010 .0.020 13 12 1,10 7 ,

0.410 2.610 3.350 L.200 1.130 O.sno 60.410 0.290 0,620 1.370 L.220 0.620 0.420 AM42

-0.010 ..- 0'010 -0.020i 4O.030 -0.020 .24-o'OI 3 -0.010

.1.7 17 .77 0.30O

ý4 0.350 130.420 10.400 0.39 2`1 10.370 0.350 0.340

ý504.020 -o.020 -.01

'",0 1

.2.9 .5. .54 .2 9 RMS Deviation: 0.96%

The incore detection system is operable per Appendix 1, RMS deviation should be less than or equal to 5.0% and neet the requirements of 4.7.1 if performed at the 25 and 98 percent power test plateaus during the power ascension KDy.

test program.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 20 of 34 Figure 9 Average RSG Differential Pressure 23.6 23.4 23.2 23.0

£0 0.

0~~ 22.8 C,

U, 22.6 22.4 22.2 22.0 0 10 20 30 40 50 60 70 80 90 100 Power, %

St. Lucie Unit 2 L-2008-052 Docket No. 50-3 89 Attachment Cycle 17 Startup Report Page 21 of 34 Figure 10 Rx Vessel Differential Pressure vs. Power 49.0 48.5 PD1-1124Z 48.0 X 47.5 Q,47.0" "

"6 Average RX Vessel Differential Pressure 46.5 -

  • PD1-1 124X 46.0 -

45.5 -

PDI-1 124W 45.0 44.5 30 40 50 60 70 80 90 100 Power, %

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 22 of 34 Figure 11 RCS Temperature vs. Power 610 600 590 580 LI.

5 70 E

560 550 540 530 30 40 50 60 70 80 90 100 Power, %

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 23 of 34 Figure 12 Tavg/Tref vs. Power 600 590 580 570 Tav

.LL 560

" 550 Tavg Predicte 540 530 520 510 500 0 20 40 60 80 100 120 Power, %

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 24 of 34 Table 1 Cycle 17 Reload Sub-Batch ID*

Sub-Batch Number of Assemblies S4 4 S5 1 TI 20 T2 8 T3 16 T4 8 T5 20 Ul 8 U2 28 U3 8 U4 4 U5 20 X1 8 X2 24 X3 12 X4 4 X5 16 X6 8

  • Reference 6

St. Lucie Unit 2 L-2008-052 Docket No. 50-3 89 Attachment Cycle 17 Startup Report Page 25 of 34 Table 2 Approach to Criticality Dilution Rate Initial Boron Final Boron Approximate Dilution Concentration (ppm) Concentration (ppm) Time (minutes) 132 gpm 1830 1787 20 88 gpm 1787 1661 62 44.gpm 1661 1623 96

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 26 of 34 Appendix A Summary of Implementation on the First Application of STAR for St. Lucie Unit 2, Cycle 17

Background

The St. Lucie Unit 2, Cycle 17 startup from refueling successfully utilized the Startup Test Activity Reduction (STAR) Program in accordance with Westinghouse Topical Report, WCAP-16011-P-A, Rev. 0 (Reference A-i). This was the first application of the STAR Program at St.

Lucie Unit 2. The current implementation eliminates the CEA worth measurement only and there is no change to the MTC testing requirements. The conditions and limitations of the NRC safety evaluation for the STAR Program topical report (Reference A-1) requires that "each licensee using STAR to submit a summary report following the first application, either successful or not, of STAR to its plant. The report should (a) identify the core design method used, (b) compare the measured and calculated values and the differences between these values to the corresponding core design method uncertainties and (c) show compliance with the STAR applicability requirements. If the application of STAR is unsuccessful, identify the reasons why the STAR application failed."

This summary report provides the NRC with the required information specified in the Conditions and Limitations section of the NRC safety evaluation for the STAR topical report.

Core Design Method Used The core design method used for St. Lucie Unit 2 Cycle 17 reload core was the PHOENIX-P/ANC code design package described in Reference A-2. The CASMO-4/SIMULATE-3 (CS) code package described in Reference A-3 was used for the alternate method calculations.

Cycle 17 STAR Program Test Results (Comparison of Measured and Calculated Values)

A comparison of the last measured cycle values (Cycle 16) and the corresponding calculated values for the key physics parameters is provided in Table 3 along with the design method/analysis uncertainties.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 27 of 34 Table 3: Comparison of Key Parameters Parameter Measured Predicted Safety Analysis / Within Criteria?

(Cycle 16) (Cycle 16) Design Method Uncertainty BOC HZP CBC 1570 1567 100 ppm (minimum) Yes BOC HZP CEA WORTH 1513.49 1528.00 15% Yes (Bank B)

BOC HZP CEA WORTH 1433.63 1415.00 15% Yes (Bank 1/3/5)

BOC HZP CEA WORTH 1354.64 1299.00 15% Yes (Bank 2/4)

BOC HZP CEA WORTH 1696.70 1690.00 15% Yes (Bank A)

BOC HZP CEA WORTH 5998.47 5932.00 10% Yes (Total)

BOC HZP ITC -0.864 -1.301 1.8 pcm/°F Yes Power Distribution (RMS, 2.46 +5.00%

  • Yes 30%)

Power Distribution (RMS, 1.56 +5.00%

  • Yes 45%)

Power Distribution (RMS, 1.37 +/-5.00%

  • Yes 98%)
  • Procedural limit based on guidance in ANSI Standard 19.6.1 1997.

The measured to predicted values for Cycle 16 were all within the acceptance criteria and design method/safety analysis uncertainties. This demonstrates compliance with Applicability Requirements of Table 3.4 for "Core Design", Items 1 and 2 in the STAR Topical.

Table 4 provides a summary of tests performed during the startup of the current Cycle 17.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 28 of 34 Table 4: Summary of Tests Performed for Cycle 17 TELST POWER ~~Location. . WithrinTst CEA Drop Tuie Slhutdown Test results located in Section III of this document. YES CEA*DropChar-acteristics Shutdown CEA coupling verified by CEA drop characteristics YES CBC HZP Test results located in Sections IV and V of this document. YES ITC ,. HZP Test results located in Section V of this document. YES MTC Surveillance HZP Test results located in Section V of this document. YES lincore FIlux Syiiinietiy Low (30%)~ Test results located in Section VI and Figure 4 of this document. YES In1core Powr iibutll Test results located in Section VI and Figure 5 of this document. YES Incore PoweirDistiibution HFP (98%)2b' Test results located in Section VI and Figure 6 of this document. YES ACBC HZP-HVP.I.FP The difference in boron concentration was within 21.0 ppm of prediction. YES

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 29 of 34 Compliance with STAR Applicability Requirements STAR Applicability Requirements are conditions that must be satisfied to use the STAR Program. The STAR Applicability Requirements are provided in Table 3-4 of Reference A-1 and provide assurance that the core can be operated as designed when used in conjunction with the proposed tests. The STAR Applicability Requirements involve the following areas:

  • Core Design

" Fabrication

" Refueling

" Startup Testing

" CEA Lifetime Conformance with the STAR Applicability Requirements is documented in accordance with plant processes and procedures. Demonstration of compliance with each of the STAR applicability requirements was documented in STAR Cycle Specific Startup Test Checklists that were completed during the core design and startup testing for Cycle 17. The completed STAR Cycle Specific Startup Test Checklists verify the applicability requirements of Reference A-1 are satisfied.

References A-1. WCAP- 16011-P-A, Rev. 0, "Startup Test Activity Reduction Program," February 2005.

A-2. WCAP- 11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988.

A-3. CASMO-4 Methodology, SSP-95/02 Revision 0, September 1995 & SIMULATE-3 Methodology, SSP-95/18 Revision 0, October 1995.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 30 of 34 Core Design Applicability Requirements The core design for Cycle 17 (cycle for STAR implementation) consists of the following:

  • A cycle length -of 16.1 EFPM

" An average enrichment of 3.83 w/o U-235

  • A maximum enrichment of 4.17 w/o U-235

" A reload of 72 fresh assemblies 0 A burnable absorber type of Gd 203

  • A 'CEA absorber type of B 4C
  • A low leakage fuel management scheme Requirements from Table 3.4, "Core Design" section (Pages 3-9 and 3-10) in WCAP-16011-P-A STAR Topical Requiremen Applicability Requirement t Satisfied Requirement Yes / No Core Design Item 1 See Table 3 YES Core Design Item 2 See Table 3 YES Core Design Item 3 (first bullet) Cycle Length YES Core Design Item 3 Average Enrichment YES (second bullet)

Core Design Item 3 Maximum Enrichment YES (second bullet)

Core Design Item 3 Fraction of Core Reloaded YES (third bullet)

Core Design Item 3 Fuel Type YES (fourth bullet)

Core Design Item 3 Burnable Absorber Type YES (fifth bullet)

Core Design Item 3 CEA Absorber Type YES (sixth bullet)

Core Design Item CoeDen Ite 3 Fuel Management YES (seventh bullet)

Core Design Item 4 CEA Worth Reconciliation YES -

(first bullet) Within 5%

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 31 of 34 CEA Lifetime Applicability Requirements Requirements from Table 3.4, "CEA Lifetime" section (Page 3-11) in WCAP-16011-P-A STAR Topical Requirement Applicability Requirement Satisfied Requirement Yes / No CEA Lifetime CEA lifetime requirements are consistent with the St. Lucie Unit 2 CEA lifetime management program/evaluation, which YES adheres to the STAR Topical criteria on CEA Lifetime?

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 32 of 34 Fabrication Applicability Requirements Requirements from Table 3.4, "Fabrication" section (Page 3-11) in WCAP-16011-P-A STAR Topical Requirement Satisfied Applicability Requirement Yes / No Requirement Fabrication Item FPL final core design/burnable absorber letter is in agreement La with the final manufacturing document to ensure STAR Topical YES Applicability Requirements Fabrication Item 1.a?

Fabrication Item The STAR Topical Applicability Requirements Fabrication 1.b, 1.c Items 1.b and L.c are consistent between FPL final core design/burnable absorber letter and the final manufacturing document (for each rod type)?.

Fabrication Item STAR Topical Fabrication Item 1.c (2) is consistent with the 1c (2) fuel design requirements (fuel assembly orientation)? YES Fabrication Item The STAR Topical Applicability Requirements Fabrication Item I.d for each fuel assembly is correct per the requirements of the 1d YES FPL final core design/burnable absorber letter?

Fabrication Items For new CEAs, is the final manufacturing document consistent 2.a, 2.b, 2.c, 2.d with the design specifications for STAR Topical Applicability YES Requirements Fabrication Items 2.a, 2.b, 2.c, and 2.d.

St. Lucie Unit 2 L-2008-052 Docket No. 50-389 Attachment Cycle 17 Startup Report Page 33 of 34 Refueling Applicability Requirements Requirements from Table 3.4, "Refueling" section (Page 3-11) in WCAP-16011-P-A STAR Topical Requirement Requirement Applicability Satisfied Requirement Yes / No Refueling Item 1 Core verification YES Refueling Item 2 CEA coupling YES

St. Lucie Unit 2 L-2008-052 Docket No. 50-3 89 Attachment Cycle 17 Startup Report Page 34 of 34 Startup Testing Applicability Requirements Requirements from Table 3.4, "Startup Testing" section (Page 3-11) in WCAP-16011-P-A The measured to predicted value for the ARO HZP CBC difference was < 10 ppm for Cycle 17.

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