L-96-265, Startup Physics Testing Rept

Startup Physics Testing Rept

ML17229A086
Person / Time
Site:	Saint Lucie
Issue date:	10/18/1996
From:	Klein R, Mead W, Ofarrill C FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-96-265, NUDOCS 9610240215
Download: ML17229A086 (23)

Text

CATEGORY 1 REGULAT INFORMATION DISTRIBUTIONtSTEM (RIDE)

V ACCESSION NBR:9610240215 DOC.DATE: 96/10/18 NOTARIZED:

NO FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co.

AUTH.NAME AUTHOR AFFILIATION MEAD,W.D.

Florida Power 6 Light Co.

KLEIN,R.M; Florida Power

& Light Co.

O'FARRILL,C.G.

Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION DOCKET t 05000335

SUBJECT:

"Startup Physics Testing Rept." W/961018 ltr.

DISTRIBUTION CODE:

A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

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NOTE TO ALL "RZDS" 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 CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 13 ENCL 12

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pp Florida Power &Light Company, P.O. Box 128, Fort Pierce, FL 34954-0128 October 18, 1996 L-96-265 10 CFR 50.36 U.

S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 Re:

St. Lucie Unit 1 Docket 50-335 Pursuant to St. Lucie Unit 1.Technical Specification 6.9.1.1, the enclosed summary report of Cycle 14 plant startup and power escalation testing 'is hereby submitted.

Should you have any questions, please contact us.

Very truly yours, J.

A. Stall Vice President St. Lucie Plant JAS/RLD

Enclosure:

St. Lucie Unit 1, Cycle 14, Startup Physics Testing Report (Approved October 16, 1996) cc:

Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 96f0240215

'rr61018 I

,PDR 'i ADDCK 05000335 P

PDR an FPL Group company

ST. LVCIEUNIT 1, CYCLE 14 STARTUP PHYSICS TESTING REPORT

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St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report Author Walter D. Mead, Jr.

Reactor Engineering, St. Lucie Plant Date Reviewed Ray M.

ein Reactor Engineering, St. Lucie Plant Date 0 /4 Approved Carl G. O'Farrill Reactor Engineering Supervisor St. Lucie Plant

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St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report Ta leof n ents

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II III IV V

VI VII VIII Introduction Cycle 14 Fuel Design CEA Drop Time Testing Approach to Criticality Zero Power Physics Testing Power Ascension Program Summary References Li fFi ure F~i

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1 2

3 4

5 6

9 10 11 12 13 14 Cycle 14 Core Loading Pattern Inverse Count Ratio Plot-Channel B Inverse Count Ratio Plot-Channel D Power Distribution - 25% Power Power Distribution - 50% Power Power Distribution - 98% Power 15 16 16 Cycle 14 Reload Sub-Batch ID Approach to Criticality CEA Group Worth Summary

St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report I.

Introduction The purpose ofthis report is to provide a description ofthe fuel design and core load and to summarize the startup physics testing performed at St. Lucie Unit 1 followingthe cycle 14 refueling outage.

The Startup physics testing verifies that key core parameters are as predicted.

The major parts ofthis testing program include:

1) Initial criticalityfollowingrefueling,

2) Zero power physics testing, and

3) Power ascension testing.

This Cycle 14 Startup Report is being submitted in accordance with Technical Specification 6.9.1.1 because the significant number ofsteam generator tubes plugged during the refueling outage may have significantly altered the nuclear, thermal, or hydraulic performance ofthe unit.

However, 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 nuclear, thermal, or hydraulic performance ofthe unit.

II.

cle 4FuelDe i n The cycle 14 reload consists entirely offuel manufactured by Siemens Power Corporation (SPC).

The 217 assemblies ofthe cycle 14 core are comprised offuel from three batches.

Ofthese, 88 are fresh assemblies (batch T), 84 are once-burned assemblies (batch S) consisting of76 natural uranium blanket assemblies and 8 Vessel Fluence Reduction Assemblies (VFRAs), and 45 are twice-burned assemblies from batch R. Table 1 provides enrichment information for the cycle 14 reload sub-batches.

The entire cycle 14 fuel load, batches R, S, and T, consist ofthe debris resistant fuel assembly design. This design has long fuel rod lower end caps which provides protection against debris induced fretting in the lower end-fitting region.

The cycle 14 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 from the cycle 13 loading pattern. Twenty four twice-irradiated batch R assemblies were placed on the core periphery with the VFRAs occupying the the corner positions ofeach dog-ear.

The remaining irradiated and fresh fuel was loaded inboard.

St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report III.

EA Dro Time Testin Following the core reload and prior to the approach to criticality, CEA drop time testing was performed. The objective ofthis test is to measure the time ofinsertion from the fullywithdrawn position (upper electrical limit)to the 90% inserted position under hot, fullflowconditions. The average CEA drop time was found to be 2.21 seconds with maximum and minimum times of 2.39 seconds and 2.1 seconds, respectively. Alldrop times were within the requirements of technical specification 3.1.3.4 and the reload PC/M 054-196 (Reference 5).

IV. A roach to riticali The approach to criticalityinvolved diluting from a non-critical boron concentration of 1820 ppm to a predicted critical boron concentration of 1503 ppm. Inverse countrate 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 2 summarizes the dilution rates and times, as well as beginning and ending boron concentrations.

Initialcriticalityfor St. Lucie Unit 1, Cycle 14, was achieved on July 23, 1996 at 1722 with CEA group 7 at 60 inches withdrawn and all other CEAs at the all-rods-out (ARO) position. The actual critical concentration was observed to be 1476 ppm. A calculation ofpost-criticality conditions variance showed the actual critical conditions to be within 224 pcm ofpredicted.

This satisfied the criteria that predicted conditions should be within 1000 pcm ofthe observed condition.

V.

Zero P wer Ph ic Te tin To ensure that the operating charateristics ofthe cycle 14 core were consistent with the design predictions, the followingtests were performed:

1) Reactivity Computer Checkout,

2) Dual CEDM Symmetry Test,

3) AllRods Out Critical Boron Concentration,

St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report and

4) Isothermal Temperature Coefficient Measurement,

5) CEA Group Rod Worth Measurements.

Proper operation of the reactivity computer was verified through the performance oftwo tests.

In the first, reactor power was elevated sufficiently high to ensure maximum sensitivity ofthe reactivity measuring system and at the same time preserve adequate margin to the point ofadding heat. The second test ascertains the response to a known value ofpositive or negative reactivity by measuring the values ofpositive or negative reactor periods that result. The results ofthe reactivity computer checkout were compared to the appropriate predictions supplied in the reload PC/M 056-194 (Reference 5). Satisfactory agreement was obtained.

Verification ofproper CEA latching is confirmed throught the use ofa CEA symmetry test for those groups which contain dual CEAs (shutdown banks AHAB). The prescribed acceptance criteria is that the reactivity measured for each dual CEA shall be within+15.0 pcm ofthe average reactivity measured for the entire group. There were no unlatched CEAs for either group.

The measurement ofthe all-rods-out (ARO) critical boron concentration was performed. The measured value was 1519 ppm which compared favorably with the design value of 1545 ppm.

This was within the acceptance limits of+ 100 ppm.

The measurement ofthe isothermal temperature coefficient was performed and the resulting moderator temperature coefficient (MTC) was obtained.

The MTC was determined to be 2.458 pcm/'F which fell well within the acceptance criteria of+ 2.0 pcm/'F ofthe design MTC of 2.716 pcm/'F (corrected).

This satisfies the Unit 1 Technical Specification which states that the MTC shall be less positive than 5.0 pcm/'F.

The final section ofinterest for zero power physics testing is in the measurement ofCEA 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 ofthe remaining test groups. A comparison ofthe measured and design CEA reactivity worths is provided in Table 3. The following acceptance criteria applies to the measurements made:

1) The measured value ofeach test group, or Supergroup measured, is within+15% or

+100 pcm ofits corresponding design CEA worths, whichever is greater;

and,

2) The measure worth ofthe reference group and the total worth for all the CEA groups measured is within+ 10% ofthe total design worth.

St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report Allacceptance criteria were met.

VI. P wer A cen ion Pro ram During power ascension, the fixed incore detector system is utilized to verify that the core is loaded properly and that there are no abnormalities occuring 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 shape annealing factor (SAF) test was performed in conjunction with the power ascension.

This test was necessitated by the replacement ofthe "B"Linear Range nuclear instrument channel detector.

A summary ofthe fluxmaps at the 25%, 45% and 98% power levels is provided in Figures 4, 5 Ec 6. These fluxmaps are used for comparing the measured power distribution with the predicted power distribution. For the purposes ofthe power ascension, the acceptance criteria requires the RMS value ofthe 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% ofthe predicted power (both) and the relative power density (RPD) should be within 0.1 RPD units ofpredicted for the 25%

power case. These criteria were satisfied.

When the unit reached 98% power, a calorimetric was performed in accordance with reference 6 for the purpose ofcalculating the RCS flowrate. The RCS flowrate was determined to have been reduced from 394,420 gpm (measured in cycle 13) to 374,674 gpm in cycle 14. This value of flowremains above the Technical Specification minimum of345,000 gpm.

Within seven effective fullpower days ofattaining the equilibrium value of 100% power, a hot fullpower (HFP) MTC test was performed by maintaining power constant and varying temperature.

The center CEA (7-1) was operated to permit compensation ofthe resulting reactivity changes.

The HFP MTC was measured to be -7.364 pcm/'F which was withinthe

+2.0 pcm/'F ofthe design value of-7.293 pcm/'F (corrected).

This test also verified compliance with Technical Specification 3.1.1.4 which requires the measured MTC be less negative than

-28.0 pcm/'F and less positive than+2.0 pcm/'F while thermal power is greater than 70%. The power coefficient was not measured.

VII. $ummary 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

St. Lucio Unit 1, Cycle 14 Startup Physics Testing Report nuclear, thermal, or hydraulic performance ofthe unit. Compliance with the applicable Unit 1 Technical Specifications was satisfactory and all acceptance criteria were met.

VIII.References 1)

"InitialCriticality," Pre-Operational Procedure 1-3200088, Revision 9.

2)

"Reload Startup Physics Testing, " Pre-Operational Procedure 3200091, Revision 6.

3)

"Reactor Engineering Power Ascension Program,"

Pre-Operational Procedure 3200092, Revisions 9%10.

4)

St. Lucie Unit 1 Technical Specifications.

5)

St. Lucie Unit 1, Cycle 14 Fuel Reload PC/M 054-196.

6)

"RCS Flow Determination By Calorimetric Procedure, " St. Lucie Unit 1 Operating Procedure 1-0120051, Revision 16.

I St. Lucie Unit 1 Figure 1 Cycle 14 Core Loading Pattern T

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4 ST. LUCIE UNIT 1, CYCLE 14 Startup Physics Testing Report Flguro 6 Power Distribution -98%

Pago:

unit p1~

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BEACON Source

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x uiawie cence eeffo S Oxk

St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report Table 1 Cycle 14 Reload Sub-Batch ID Sub-Batch Rl Sl S2 S3 S4 SS S6 S7 T3 T4 Number ofAssemblics 16 20 16 12 12 16 12 20 12 12 Enrichment 3.9 3.88 3.81 3.9 3.88 3.81 3.78 3.79 3.76 0.30 4.45 4.45 4.45 4.45 T5 36 4.45 15

St. Lucie Unit 1, Cycle 14 Startup Physics Testing Report Table 2 Approach to Critcality Dilution Rate 132 gpm 88 gpm 44 gpm InitialBoron Concentration NA 1818 1553 Final Boron Concentration 1553 1476 DilutionTime (minutes) 3 pumps not used 177 247 Table 3 CEA Group Worth Summary CKAGroup Reference Group A Measured Worth (pcm) 928.94 595.11 658.78 649.75 Design *Worth (pcm) 896.00 584.00 633.00 650.00 Percent Difference 3.55 1.87 3.91

-0.04 761.36 779.00

-2.32 B&6 749.00 788.00

-5.21 5&3 Total 859.30 5202.24 868.00 5198.00

-1.01 0.08

• Reference 5.

Percent difference = (Measured-Design)/(Measured)

• 100 16

F