ML17228B449

Cycle 9 Startup Physics Testing Rept.

ML17228B449
Person / Time
Site:	Saint Lucie
Issue date:	03/14/1996
From:	Klein R, Martin L, Wachtel P FLORIDA POWER & LIGHT CO.
To:
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ML17228B448	List: ML17228B447 ML17228B449
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NUDOCS 9604090121
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STARTUP PHYSICS TESTING REPORT 9604090i21 96040i PDR ADDCK 05000389 P PDR

ST. I UCIE UNIT 2, CYCLE 9 STARTUP PHYSICS TESTING REPORT

St. Lucie Unit 2, Cycle 9 Startup Physics Testing Report Author Date ~ 9/

Patricia . Wachtel Reactor Engineering, St. Lucie Plant Reviewed Date ay M. K ein Reactor Engineering, St. Lucie Plant Reviewed

+ ~Q Leo A. Martin Nuclear Fuel, JPN Approved Date William L. Parks Reactor Engineering Supervisor St. Lucie Plant

St. Lucie Unit 2, Cycle 9 Startup Physics Testing Report Table f ntents Qecfjiig ~ae I Introduction II Cycle 9 Fuel Design

. III CEA Drop Time Testing IV Approach to Criticality V Zero Power Physics Testing VI Power Ascension Program VII Summary VIII References f 'e i e u e Title 8 Cycle 9 Core Loading Pattern 9 Inverse Count Ratio Plot - Channel 1 9 Inverse Count Ratio Plot - Channel 2 10 Power Distribution - 25% Power 11 Power Distribution - 50% Power 12 Power Distribution - 80% Power 13 Power Distribution - 100% Power

.i t fTa les Table m er Titte 14 Cycle 9 Reload Sub-Batch ID 15 Approach to Criticality 15 CEA Group Worth Summary

St. I ucie Unit 2, Cycle 9 Startup Physics Testing Report L ~td The purpose of this report is to provide a description of the fuel design, core load and to summarize the startup physics testing performed at St. Lucie Unit 2 following the cycle 9 refueling.

Startup physics testing verifies that the models used in the safety analysis adequately predict the as-built core and that certain Technical Specifications are met. The major parts of this testing program include:

1) Initial criticality following refueling,

2) Zero power physics testing and

3) Power ascension testing.

II. cle uel e i n The cycle 9 reload consists entirely of fuel manufactured by ABB Combustion Engineering (ABB/CE). The 217 assemblies of the cycle 9 core are comprised of 84 fresh Region L assemblies, 80 once burned Region K assemblies, and 53 twice burned Region J assemblies. Table 1 provides enrichment information for the cycle 9 reload sub-batches.

The mechanical design for the fresh fuel Region L assemblies differs from Regions J and K in the following ways:

1) Gadolinia burnable absorbers are used in Region L in lieu of the Alumina - Boron Carbide burnable absorbers used in Regions J and K. The mechanical design features of the gadolinium poison rods are identical to that of the fuel rods, and

2) A change from tungsten inert gas to laser welded zircaloy intermediate spacer grids was employed for Region L.

The entire cycle 9 fuel load, Regions J, K, and L, consists of the debris resistant fuel assembly design. This design has long fuel rod lower end caps which provide protection against debris induced fretting in the lower end-fitting region.

The cycle 9 core map is represented in Figure 1. The assembly serial numbers and control element assembly (CEA) serial numbers are given for each core location. The fuel is arranged in a low leakage pattern with no significant differences between the cycle 8 loading pattern. Twenty

St. Lucie Vnit 2, Cycle 9 Startup Physics Testing Report four twice-irradiated Region J assemblies, sixteen once-irradiated Region K assemblies, and eight fresh Region L assemblies were placed on the core periphery and the remaining irradiated and fresh fuel was loaded inboard.

III. E r 'me e tin 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 2.69 seconds with maximum and minimum times of 2.83 seconds and 2.53 seconds, respectively. All drop times were within the requirements of Technical Specification 3.1.3.4 and the reload PC/M 112-295 (Reference 5).

IV. r ach t riti ali The approach to criticality involved diluting from a non-critical boron concentration of 1749 ppm a predicted critical boron concentration of 1496 ppm. Inverse count rate ratio (ICRR) plots to were maintained during the dilution process using startup channels 1 and 2. Refer to Figures 2 and 3 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 9, was achieved on January 1, 1996 at 0328 with CEA group 5 at 61 inches withdrawn and all other CEAs at the all-rods-out (ARO) position. The actual critical concentration was observed to be 1506 ppm.

V. er wer Ph ic Te tin To ensure that the operating characteristics of the cycle 9 core were consistent with the design models, the following tests were performed:

1) Reactivity Computer Checkout,

2) All Rods Out Critical Boron Concentration,

3) Isothermal Temperature Coefficient Measurement and

4) CEA Group Rod Worth Measurements.

St. Lucie Unit 2, Cycle 9 Startup Physics Testing Report Proper operation of the reactivity computer was verified through the performance of two tests. In the first, reactor power was elevated suf5ciently 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 ascertained the 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 in the reload PC/M 112-295 (Reference 5). Satisfactory agreement was obtained.

The measurement of the all-rods-out critical boron concentration was performed. The measured value was 1561 ppm which compared favorably with the design value of 1547 ppm. This was within the acceptance limits of+ 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 0.56 pcm/'F which fell well within the acceptance criteria of+ 2.0 pcm/'F of the design MTC of -0.044 pcm/'F (corrected). Additionally, this satisfies the Unit 2 Technical Specification which states that the MTC shall be less positive than 5.0 pcm/'F.

The final section of interest for zero power physics testing is in the measurement of CEA group worths. Rod worth measurements were performed using the rod swap methodology. This method involves exchanging the reference group, which is measured by the 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 applies to the measurements made:

1) The measured value of each test group is within+ 15% or + 100 pcm of the design CEA worths, whichever is greater, and

2) The measure 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.

e cni nPro ra During power ascension, the fixed incore detector system is utilized to verify that the core is loaded properly and that there are no abnormalities occurring in various core parameters (core peaking factors, linear heat rate, and tilt) for power plateaus at 25%, 50%, 80% and greater than 98%

St. Lucie Unit 2, Cycle 9 Startup Physics Testing Report rated thermal power. Additionally, calorimetric, nuclear, and hT power calibrations were performed at each of the plateaus prior to advancing reactor power to the next higher level. A summary of the results of the flux maps at each power level is provided in Figures 4, 5, 6, and 7.

VII. $ ummaig All measurement to prediction acceptance criteria were met and compliance with the applicable Unit 2 Technical Specifications was satisfactory.

I) "InitialCriticality, Pre-Operational Procedure 2-3200088, Revision 10.

2) "Reload Starlup Physics Testing, Pre-Operational Procedure 3200091, Revision 7.

3) "Reactor Engineering Power Ascension Program, "Pre-Operational Procedure 3200092, Revision 9.

4) St. Lucie Unit 2 Technical Specifications.

5) St. Lucie Unit 2, Cycle 9 Fuel Reload PC/M 112-295.

St. Lucie Unit 2, Cycle 9 Startup Physics Testing Report FIGURE 1 CYCLE 9 CORE LOADING PATTERN P M K H Y X W V T S R N L J ~ F E D C B A Krl J21 J31 K88 21 L01'2P L2lf K24 L3f K1P LO P 20 101 K48 K1f K3l L8f KOS L3f 19 8 17 J62 L1f L1f 18 201 113 L2f K48 Let J1 P LS? K77 L6f f7 74 1e 25 76 LOf K18 Lrf K68 K2f K67 Lrf J12 L9f K4P 16 52 5 75 72 K28 Lrf J2s K5g Lsf K48 Lef 15 12 21 71 K7R K78 14 J13 L4Z K58 Lrf Lef 13 20 78 J23 12 K28 K1f J10 0

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~ St. Lucie Unit 2, Cycle 9 ~

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11

~ St. Lucio Unit 2, Cycle 9 ~

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RMS Oaviation: 2.5%

Max Deviation: 9.3%

The tncore detection system Is operable per Aooendbc A RMS devlltlon should be loss than or equal to 6 IV/, and meet the requlremonts of *7.7 If performed at the 26 anti Sd percent power test ptlteaus durtng the powei ascension test program.

EI 12

~ St. Lucio Unit 2, Cycle 9 ~

Startup Physics Testing Report FIGURE 7 POiVER DISTRIBUTION COMPARISON iVITHDESIGN - 100% POPOVER MeoeootL (KCCRT/bNTATO Dcdct:

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Max Deviatfon: 8A%

The fncore dtIOCdon system Is operable por Appendix A RMS devlatlon should be less than or equal fo 6.4756 and meet the requlremenls of 4.7.1 If performed af the 26 and Sa percenl powlr test plateaus durlnf) Ihe power ascension test prof)ran@

13

St. Lucie Unit 2, Cycle 9 Startup Physics Testing Report Table 1 Cycle 9 Reload Sub-Batch ID Sub-Batch Number of Assemblies Enrichment 4.30 4.30/2.30 L/ 4.30/2.30 LX 48 4.30/2.30 LY 16 4.30/2.30 12 4.10 3.60 3.60 32 3.60 16 3.60 4.10 20 4.10 16 3.70 17 3.70 14

St. Lucie Unit 2, Cycle 9 Startup Physics Testing Report Table 2 Approach to Criticality Dilution Rate Initial Boron Final Boron Dilution Time Concentration Concentration (minutes) 132 gpm 1749 1671 30 88 gpm 1671 1532 60 44 gpm 1532 1506 30 Table 3 CEA Group Worth Summary CEA Group Measured Worth Design

• Worth Percent Difference (pcm) (pcm)

Reference Group 1992 1947 -2.3 1481 1451 -2.0 1,2 1641 1581 -3.7 3,4,5 1783 1665 -6.6 Total 6897 6644 -3.7

• Reference 5.

Percent difference = (Design/Measured) - 1 x 100 15