ML17229B044

Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr

ML17229B044
Person / Time
Site:	Saint Lucie
Issue date:	03/02/1999
From:	Klein R, Stall J FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-99-059, L-99-59, NUDOCS 9903110413
Download: ML17229B044 (28)

Text

CATEGORY 1 y.

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9903110413 DOC.DATE: 99/03/02 NOTARIZED: NO FACIL:50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co.

DOCKET 05000389 I

AUTH.NAY& . AUTHOR AFFILIATION KLEIN,R.M. Florida Power & Light Co.

STALL,J'.A. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"St Lucie,Unit 2,Cycle 11 Reactor Startup Physics Testing Rept." With 990304 ltr.

DISTRIBUTION CODE: IE26D COPIES RECEIVED:LTR TITLE: Startup Report/Refueling Report (per Tech Specs) 2 ENCL [ SIEE: Z I NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID, CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 PD 1 1 GLEAVES,W 1 1 INTERNAL: ACRS 1 1 CSEE 1. 1 NRR/DSSA/SRXB/B 1 1 RGN2 FILE 01 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROI DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8

Florida Power St Light Company,6351 S. Ocean Drive, Jensen Beach, FL 34957 March 4, 1999 L-99-059

@PI 10 CFR 50.36 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Re: St. Lucie Unit 2 Docket 50-389 P i in R Pursuant to St. Lucie Unit 2 Technical Specification 6.9.1.1, the enclosed summary report of plant startup and power escalation testing for Cycle 11 is hereby submitted.

Should you have any questions, please contact us.

Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/RLD II

Enclosure:

St. Lucie Unit 2, Cycle 11 Reactor Startup Physics Testing Report; March 2, 1999 CC: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 9903ii0413 990302 05000389' PDR ADOCK PDR an FPL Group company

~hurtle S'T<ARg'UgrP> XE'S'f"RE~Og<RX'

ST. LUCIE UNIT 2, CYCLE 11 REACTOR STARTUP PHYSICS TESTING REPORT Author Date .2 z Ray M.

React ngineering, S . Lucie Plant Reviewed Date Walter D. Mead Jr.

Reactor Engineering, St. Lucie Plant Reviewed Date Carl G. O'Farrill S ervisor of P Fu Engineering Approved C. Ashton Pell Reactor Engineering Supervisor, St. Lucie Plant

St. Lucie Unit 2, Cycle 11 Startup Physics Testing Report Table of Contents Section Title Pa e I Introduction 4 II Cycle 11 Fuel Design 5 III CEA Drop Time Testing 7 IV Approach to Criticality 8 V Zero Power Physics Testing 9 VI Power Ascension Program 10 VII Summary 11 VIII References 12 List of Fi ures Fi ure Title Pa e Cycle 11 Core Loading Pattern 13 Inverse Count Ratio Plot- Channel B 14 Inverse Count Ratio Plot- Channel D 14 Power Distribution - 25% Power 15 Power Distribution - 50% Power 16 Power Distribution - 98% Power 17

0 St. Lucie Unit 2, Cycle 11 Startup Physics Testing Report Table of Contents cont List of Tables Table Title Pa e 1 Approach to Criticality 18 2 CEA Group'Worth Summary 19

11 St. Lucie Unit 2, Cycle 11 Startup Physics Testing Report 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 11 refueling.

The Startup testing verifies 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, and

3) Power ascension testing.

This Cycle 11 Startup Report is being submitted in accordance with Technical Specification 6.9.1.1 because:

A. Fuel design changes were made, introducing the "Value Added" pellet, the Guardian Grid and consequently eliminating long lower end-caps The test data satisfied all acceptance criteria and demonstrated general conformance to predicted performance..

St. Lucie Unit 2, Cycle 11 Startup Physics Testing Report II. cle 11 Fuel Desi n The Cycle 11 reload consists entirely of fuel manufactured by Asea Brown Boveri Combustion Engineering (ABB-CE). The 217 assemblies of the Cycle 11 core are comprised of fuel from four batches. Of these, 64 are fresh batch N assemblies, 64 are once-burned batch M assemblies, 84 are twice-burned batch L assemblies and 5 are )hrice-burned batch K assemblies.

The Region N assemblies consist of non-gadolinia fuel rods (4.1 to 4.45 w/o UQ35 enriched) and Gadolinia (UOz -GDg 03 )'bearing fuel rods (Gadolinia burnable absorber fuel rods, 4 or 8 w/o gadolinia homogeneously dispersed in a 2.2 to 2.55 w/o UQ35 enriched carrier).

The mechanical design of the Region N fuel assemblies differs from Regions M, L and K in the following ways:

1) The bottom grid is the laser welded "Guardian" grid. The Guardian grid incorporates debris stopping features. The other fuel batches employ TIG welded lower grids.

2) The fuel rod lower endcaps were changed from the long lower endcap design to a shorter design which works with the new Guardian grid. This effectively shifted the active fuel 1.14 inches down relative to the other fuel assembly regions.

3) The upper pellet stack spacer disc which separates the top fuel pellet &om the upper plenum spring was deleted.

4) The Plenum spring design was modified to accommodate the longer plenum size.

5) The fuel rod pellet diameter was increased by 0.0005 inches, pellet dish volume decreased by 69%, and the pellet theoretical density was.increased &om 95.25% to 95.4%.

6) The top spacer grid incorporates backup arches in all interior cells as opposed to only the peripheral cells of previous fuel assembly designs.

7) The upper end fitting flow and hold-down plates were slightly thickened'. The spring force was increased for the fuel assembly upper end fitting springs PC/M 98016 adressed the mechanical, thermal hydraulic and neutronic impact of the region N fuel design changes. Evaluations performed by FPL and ABB-CE found the operational impact of the fuel design changes to be acceptable. There was no safety impact due to the fuel design changes. Subsequent Low Power Physics, Power Ascension and Shape Annealing Factor (SAF) testing substantiated the conclusions of the evaluations.

St. Lucie Unit 2, Cycle 11 Startup Physics Testing Report II. cle 11 Fuel Desi n continued No fuel handling issues were noted due to the Region N fuel assembly upper end fitting changes mentioned above. The impact of the upper end fitting changes had been evaluated by FPL prior to the fuel receipt. This was accomplished by field testing an available Region N design upper end fitting with a PSL 2 new fuel grapple.

The entire Cycle 11 core consists of debris resistant fuel (long lower end-cap or Guardian grid).

The Cycle 11 loading pattern is similar to Cycle 10. Cycle 11 employs a low-leakage fuel management scheme'and is 90 degrees rotationally symmetric.

h The Cycle 11 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, Cycle 11 Startup Physics Testing Repor't III. CEA Dro Time Testin 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 2.29 seconds with maximum and minimum times of 2.92 seconds and 0.90 seconds, respectively. All drop times were within the 3.1 second maximum requirement of Technical Specification 3.1.3.4. 'In addition the CEA drop time distribution requirements for scram shape (average drop time <2.77 seconds and maximum drop time <3.07 seconds) specified in the reload PC/M 98016 (Reference 6) were satisfied.

St. Lucie Vnit 2, Cycle 11 Startup Physics Testing Report IV. A roach to Criticali The approach to criticality involved diluting from a sub-critical boron concentration of 1660 ppm to a predicted critical boron concentration of 1441 ppm. Inverse Count Rate ratio (ICRR) plots were maintained during the dilution process using wide range channels B and D. Refer to Figures 2 and 3 for ICRR information. Table 1 summarizes the dilution rates and times, as well as beginning and ending boron concentrations.

'nitial criticality for St. Lucie Unit 2, Cycle 11, was achieved on December 12, 1998 at 06:29 with CEA group 5 at 60 inches withdrawn and all other CEAs at the all-rods-out (ARO) position.

The actual critical concentration was observed to be 1473 ppm.

St.t ucie Unit 2, Cycle 11 Startup Physics Testing Report V. Zero Power Ph sics Testin To ensure that the operating characteristics of the Cycle 11 core were consistent with the design predictions, the following tests were performed:

1) Reactivity Computer Checkout;

2) AllRods Out Critical Boron Concentration;

3) Isothermal Temperature Coefficient Measurement; and

4) CEA Group Rod Worth Measurements.

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 a positive and negative reactor period test through respective introduction of a known by'erforming 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 98016 (Reference 6).

Satisfactory agreement was obtained.

The measurement of the all-rods-out (ARO) critical boron concentration was performed. The measured value was 1524.9 ppm which compared favorably with the design value of 1491 ppm (Reference 2). 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 derived. The MTC was determined to be -1.630 pcm/'F which fell well within the acceptance criteria of + 2.0 pcm/'F. of the design MTC of

-1.938 pcm/'F (corrected). This satisfies Unit 2 Technical Specification 3.1.1.4 which states that the MTC shall be less positive than 5.0 pcm/;F when reactor power is less than or equal to 70%

rated thermal power.

Rod worth measurements were performed using the rod swap methodology. This method involves exchanging a 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 2. The following acceptance criteria apply to the measurements made:

1) The measured value of each test group, or supergroup measured, is within+15% or+100 pcm of its corresponding 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.

0 St. I ucie Unit 2, ~cle 11 Startup Physics Testing Report VI. Power Ascension Pro ram 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 25%, 50%, and greater than 98%

rated thermal power.

A summary of the flux maps at the 25%, 50% and 98% power levels is provided in figures 4, 5 8c

6. These flux maps are used for comparing the measured power distribution with the predicted power distribution. For the purposes of the power ascension, the acceptance criteria requires the RMS value of the power deviation be less than or equal to 5%. In addition, for the 25% and 98%

plateaus, the individual assembly powers should be within 10% of the predicted power (both) and the relative power density (RPD) should be within 0.1 RPD units of predicted for the 25%

power case. These criteria were satisfied.

A Shape Annealing Factor (reference 5) test was performed in conjunction with the power ascension (reference 3). This test was necessitated by the replacement of the Reactor Protection System Channel "D" the Linear Power Range Detector and the change in the active fuel stack height introduced with the Region N fuel. The measured Shape Annealing Factors were installed in the Linear Power Range Detector instrument circuits as required by the reload PC/M 98016 (Reference 6).

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.

10

St. Lucie Unit 2, Cycle 11 0

Startup Physics Testing Report VII. Summaru Compliance with the applicable Unit 2 Technical Specifications was satisfactory and all acceptance criteria were met.

11

St. Lucie Unit 2, Cycle 11 Startup Physics Testing Report VIII.References

1) "Initial Criticality, " Pre-Operational Procedure 2-3200088

2) "Reload Startup Physics Testing, " Pre-Operational Procedure 3200091

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

4) St. Lucie Unit 2 Technical Specifications.

5) "Shape Annealing Factor Test," Pre-Operational Test Procedure 3200093

6) St. Lucie Urit 2 Cycle 11 Reload PC/M 898016 12

St. Lucie Unit 2, Cycle 11 Startup Physics Testing Report FIGURE 1 CYCLE 11 CORE LOADINGPATTERN P M K H Y X W I

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St. Lucie Unit 2, Cycle il Startup Physics Testing Report FIGLRE 2. WIDE RANGE CHANNEL B BORON DILUTION 0.9 .

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I ucie Unit 2, Cycle 11 Startup Physics Testing Report I

Table 1 Approach.to Criticality Dilution Rate Initial Boron Final Boron Dilution Time Concentration Concentration (minutes) 132 gpm 1660 1591 ~

21 88 gpm 1591 1491 70 44 gpm 1491 1473 75 18

0 St. Lucie Unit 2, Cycle 11 0

Startup Physics Testing Report Table 2 CEA Group Worth Summary CEA Group Measured Worth Design

• Worth Percent Difference (pcm) (pcm)

Reference Group B 2140.69 2070.00 -3.30 .

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1427.65 1417 -0.75 1&2 1724.48 1691 -1.94 3,4&5 1762 1712 -2.84 Total 7054.84 6890 -2.34

• Reference 2 Percent difference = (Design-Measured)/(Measured) *100 19

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