ML20211G050

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Rev 0 to NF-908.03, Brunswick Unit 2,Cycle 14 Neutronics Startup Rept
ML20211G050
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 08/31/1999
From: Parker S, Thomas R, Westermark H
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20211F993 List:
References
NF-908.03-01, NF-908.03-R00, NUDOCS 9908310139
Download: ML20211G050 (10)
v • d • e


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l CP&L Nuclear Fuels Managenrnt & Safety Analysis Section File: NF-908 03 il2Cl4 Neutronics Startup Report Page I of lo, Revision 0 1

BRUNSWICK UNIT 2, CYCLE 14 NEUTRONICS STARTUP REPORT August 1999 1

Prepared by: 42( !/c frac,s P - H 8 u -+f Stacy L. Parker Reviewed by: I ,/,// f/g 9

[ ' Roger l[homas, J6 /

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Reviewed by: W' O N4Yd" /k/[hh/nauftK.

Hans Westermark Approved by: 9-zy-t*

' George E. Smith Superintendent, BWR Fuel Analysis NAFuels\PROJEC1W2CIMiartup Test ReportW2Cl4 Neutronics Startup TesReport. doe 9908310139 990825 PDR ADOCK 03000324 ,

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CP&L Nuclear Fuels M.vugement & safety Analysis sectan File: NF-908.03 if 2Cl4 Neutronies startup Report Page 2 of 10. Revision 0 I.0 Introduction This repon summarizes observed data from the initial Brunswick Unit 2, Cycle 14 (B2Cl4) startup tests. The Cycle 14 core represents the third reload of the GE13 fuel type in Unit 2. Four Siemens ATRIUM-10 Lead Qualification Assemblies (LQAs) were also loaded into the B2C14 core.

Pursuant to the requirements of Section 13.4.2.1 of the BSEP 1 & 2 Updated FSAR, a summary report of plant startup and power escalation testing shall be submitted to the NRC should any one of four conditions occur. Condition (3) applies:

(3): " installation of fuel that has a different design or has been manufactured by a different fuel supplier."

This report shall include results of neutronics related startup tests following core reloading as described in the UFSAR.

2.0 UFSAR Section 14.4.1. Item 1: Core Loadinst Verification A Core Loading Pattern Verification was performed per BNP Engineering Procedure ENP-24.13,. " Core Verification." The core was verified to be loaded in accordance with the B2Cl4 Full Core Loading Pattern.

3.0 UFSAR Section 14.4.1. Item 2: TIP Operability and Core Power Symmetry

a. TIP Uncertainty A TIP uncertainty determination was completed according to BNP Engineering Procedure OPT-50.3,"Tip Reproducibility and Uncertainty Determination." The acceptance

. criterion for this test requires the TIP Total Noise Uncertainty to be s 7.1%. The measured uncertainty was 2.1%, thus - eting the criteria.

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CP&L Nuclear Fuels Management & Safety Analysis Section File: NF-908.03 l B2Cl4 Neutronics Startup Report Page 3 of 10. Resision 0 3.0 UFSAR Section 14.4.1. Item 2: TIP Operability and Core Power Symmetry (continued)

b. Core Power Symmetry Core power symmetry is indirectly verified via the standard traversing in-core probe (TIP) uncertainty measurement performed per OPT-50.3, described in Section 3.0.a.

Direct power symmetry measurement utilizing computed bundle powers is no longer

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performed at Brunswick with the improved POWERPLEX core monitoring system.

POWERPLEX methodology does not require core symmetry. Therefore, the Core Power Symmetry Test was replaced by a more appropriate Bundle Power Analysis. The test results and acceptance criteria are provided in item (c) below. l I

c. Bundle Power Analysis BNP Engineering procedure 0FT-50.0," Reactor Engineering Refueling Outage Testing,"

was revised to replace the Core Power Symmetry Test with a Bundle Power Analysis. j This analysis compares the MICROBURN-B design code's calculation of predicted {

bundle powers to the plant process computer's measured bundle powers. The comparison l must verify that the absolute difference between measured and predicted bundle powers f' meets the acceptance criterion of $ 8.64%. Bundles located in peripheral control cells or uncontrolled peripheral locations are excluded.

The acceptance criterion was met with the maximum absolute difference measured as 5.68%.

4.0 UFSAR Section 14.4.1. Item 3: Control Rod Mobility Control rod mobility is verified by two tests: friction testing and scram timing. The results of these tes'.s and their acceptance criteria are described below,

a. Friction Testing Friction Testing was performed prior to startup per BNP Engineering Procedure OPT-90.2," Friction Testing of Control Rods." Control rods were verified to complete full travel without excessive binding or friction. In a pre-requisite to OPT-90.2, the reactor was observed to remain suberitical during the withdrawal of the most reactive rod in BNP Fuel Handling Procedure OFH-11," Refueling."

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CP&L Nuetear Fuch Management & safety Analysis Section File NF-903 03 p2Cl4 Neutronics startup Report Page 4 of 10. Revision 0 4.0 UFSAR Section 14.4.1. Item 3: Control Rod Mobility (continued)

b. Scram Time Testing Scram Time Testing was performed for each control rod prior to exceeding 40% power per BNP Engineering Procedure OPT-14.2.1," Single Rod Scam Insertion Times Test."

The acceptance criteria for this test are found in Technical Specification 3.1.4. All control rods had a scram time of s 7.0 seconds and thus were considered operable in accordance with Technical Specification 3.1.3. None of the rods were designated as

" slow"in accordance with Technical Specification 3.1.4. The maximum measured 5%,

20%,50%, and 90% insertion times are given in Attachment 1 of this report.

The average 20% insertion time measured from the low power testing was 0.843 seconds, thus meeting the ODYN Option B time requirement of s 0.861 seconds.

ODYN Option B MCPR limits were therefore installed following the test.

5.0 UFS AR Section 14.4.1, Item 4: Reactivity Testine Reactivity Testing consists of a shutdown margin measurement, reactivity anomaly check, and measured critical kerr comparison to predicted values. The results of these tests are provided below with the acceptance criteria.

a. Shutdown Margin Shutdown margin measurements were performed per BNP Engineering Procedure OPT-14.3.1,"Insequence Critical Shutdown Margin Calculation." The initial BOC shutdown margin was measured as 1.117% Ak compared to a predicted value of 1.89% Ak, an absolute difference of 0.773% Ak. The acceptance criterion for minimum shutdown margin is defined in Technical Specification 3.1.1.1, which requires the shutdown margin be 2 0.38% Ak during the entire cycle. To calculate the minimum shutdown margin for the cycle, the maximum predicted decrease in shutdown margin )

over the cycle relative to BOC,0.508% Ak (R), was subtracted from the BOC measured .

I shutdown margin. This resulted in an inferred minimum shutdown margin for Cycle 14 of 0.609% Ak. Therefore, the acceptance criterion is met.

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  • ' l CP&L Nuclear Fuels Management & Safety Analysis Section File: NF.908.03 B2Cl4 Neutronics Startup Report Page 5 of 10, Revision 0 l

5.0 UFSAR Section 14.4.1. Item 4: Reactivity Testing (continued)

b. Reactivity Anomaly A reactivity anomaly test was performed at near rated (2553.2 MWt or 99.8%) conditions

- per BNP Engineering Procedure OPT-14.5.2," Reactivity Anomaly Check." The acceptance criteria is defined by Technical Specification 3.1.2, which requires that the reactivity difference between monitored and predicted core ken be within il% Ak. The measured and predicted values for kenwere 1.0021 and 1.0029, respectively, a difference of-0.08% Ak. This is well within the 1% Ak requirement.

c. Cold Critical Eigenvalue (ken)

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The measured BOC cold critical ken was inferred as 0.99982 by nodal simulator code calculations with actual critical conditions as input. The predicted BOC cold critical ken was 1.00350 giving a measured vs. predicted difference of-0.368% Ak. Therefore, the acceptanca criterion requiring agreement within il% Ak is met.

6.0 Additional Testine Results As a matter of course, key testing and checks beyond those specified in the UFSAR are performed during initial startup and power ascension. These " standard" tests are described in items (a) and (b) below.

I

a. Core Monitoring Software Comparisons to Design Code I

Thermal limits calculated by the online POWERPLEX Core Monitoring Software System were compared to those calculated by the MICROBURN-B design code at medium and high power levels. The results of these comparisons and the POWERPLEX statepoints are provided as Attachment 2. The acceptance criteria specified in OPT-50.0 require the two codes' thermal limits agree within 0.15 for medium power testing and 0.10 for high power testing. The acceptance criteria were met.

b. Hot Full Power Eigenvalue After establishing a sustained period of full power (2558 MWt) equilibrium operation, the t design and core follow Hot Full Power Eigenvalues (ken) are compared. At 142.6 MWD /MT the' core follow ken was calculated as 1.00055 and the design ken is 1.00282.

The difference between the design and core follow values is -0.227% Ak which is within the 1% Ak reactivity anomaly requirements.

N:\ Fuels \ PROJECT \B2Cl4\startup Test Report \B2Cl4 Neutronies startup TesReport. doc

CP&L Nucleu Fuels Management & safety Analysis Section File: NF-908.03 B2Cl4 Neutronics startup Report Page 6 of 10. Revision 0 7.0 - Summary Evaluation of the Brunswick Unit 2, Cycle 14 startup data concludes the core has been loaded properly and is operating as expected. The startup and initial operating conditions and parameters compare well to predictions. Core thermal peaking design predictions and measured peaking comparisons met the startup acceptance criteria. The BOC shutdown margin demonstration indicates adequate shutdown margin will exist throughout B2Cl4. All prescribed and additional tests met their acceptance criteria.

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l CP&L Nuclear Fuels Management & Safety Analysis Secnon File: NF-908 0.1 B2Cl4 Neutronics Startup Report Page 7 of 10. Resision 0 Attachment I to the B2C14 Startup Report Results of Control Rod Scram Time Testing Alaximum SIcasured Scram Insertion Time Technical Specification 3.1.4 Insertion Position / Notch Tech Spec Limit Slaximum hieasured (seconds) Insertion Time (seconds) 5% 46 0.440 0.352

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1 20 % 36 1.080 1.035 l 50 % 26 1.830 1.720 l

90 % 6 3.350 3.158 l

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CP&L Nuclear Fuels Management & Safety Analysis Section File: NF.903 03

,H2Cl4 Neutronics Startup Report Page 8 of 10. Revision 0 Attachment 2 to the B2C14 Startup Report Core Monitorine Software Comparisons to Design Code Medium Power Testing Plateau 58.6?c CMWT,99MAY26,11.15.12,29 MWD /MTU Thermal Limit POWERPLEX MICROBURN-B Absolute Acceptance On-Line Design Code Difference Criteria Monitoring MFLCPR 0.802 0.790 0.012 < 0.15 MAPRAT 0.684 0.671 0.013 < 0.15 MFLPD 0.496 0.535 0.039 < 0.15 High Power Testing Plateau 100.0?e CMWT,99MAY27,07.53.33,46 MWD /MTU Thermal Limit POWERPLEX MICROBURN-B Absolute Acceptance On-Line Design Code D fference Criteria Monitoring MFLCPR 0.921 0.929 0.008 < 0.10 MAPRAT 0.922 0.973 0.051 < 0.10 MFLPD 0.939 0.987 0.(M8 < 0.10 i

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CP&L Nuclear Fuels Management & Safety Analysis Section File: NF.908.03 B2Cl4 Neutronics Startup Report Page 9 of 10. Resision 0 Attachment 2 to the B2C14 Startup Report (continued)

Medium Power Testing Plateau Statepoint Report BRUNSWICK-2 WK-9922 99MAY26-11.15.12 13744 MWD /MTU TRIGR= USER REV=FEB97 CORE PERFORMANCE LOG --- LONG EDIT B2Cl4 BOC TO EOFPC-2't05 MWD /MT ODYNB POW DEP MCPR CALCULATION TYPE : NORMAL CONVERGENCE . TIGHT SYMMETRY 4 FULL CTP CALCULATION HEAT BALANCE CYCLE 14 STATE CONDITIONS FLOW RATES CORE PARAMETERS NUCLEAR LIMITS LOCATION GMWE 474.89 WT 43.5 CMEQ 0.2798 P-PCS -3.40 39-40-05 CMWT 1497.8 (58.6%) WTGUB 41.60 CAEQ 0.1406 FCBB 1.869 PR 996.4 PSIA WTFLAG 2 CAQA 0.0832 CMPF 2.563 27-30-15 DHS 25.90 WFW 6.01 CAVF 0.4508 CMFLCPR 0.802- 23-28 WT 43.52 (56.5%) WD 18.24 CAPD 30.2249 P=1.558 F=1.365 CRD 0.117 RWL 186.7387 CMAPRAT 0.684 19-28-14 CYCEXP 29 MWD /MTU ERATIO 0.98 CDLP 7.3837 P=0.783 F=0.839 MEASURED / CALCULATED LPRM READINGS DPCC 12.2886 CMFLPD 0.496 27-30-15 AVG: 11.01% MAX: 34.04% KEFF 1.0015 CMFLEX 0.662 31-02-05 LOCATION 1 2 3 4 5 6 7 8 9 10 11 12 AXIAL REL POWER 0.55 1.25 1.36 1.30 1.22 1.18 1.17 1.12 1.04 0.86 0.66 0.30 REGION REL POWER 0.91 0.98 0.91 1.00 1.29 1.02 0.91 0.99 0.92 RING REL POWER 1.25 1.38 1.19 1.11 1.00 1.04 0.78 APRM GAFS 0.98 0.99 0.99 1.00 0.99 1.00

  • ' * *
  • THE 10 MOST LIMITING BUNDLES * * * * *
  • FLCPR LOC CPR LIMIT APRAT LOC APLHGR LIMIT FLPD LOC LPD LIMIT 0.802 23-28 1.943 1.558 0.684 19-28-14 6.21 9.08 0.496 27-30-15 7.14 14.40 0.801 25-24 1.944 1.558 0.683 27-34-14 6.20 9.08 0.495 29-28-15 7.13 14.40 0.786 29-32 1.981 1.558 0.641 27-30-15 5.25 8.19 0.490 19-28-15 7.05 14.40 0.784 31-30 1.988 1.558 0.639 23-28-15 5.23 8.19 0.489 27-34-15 7.04 14.40 0.776 21-28 2.007 1.558 0.631 23-32-15 5.16 8.19 0.488 23-32-15 7.03 14.40 0.775 27-22 2.011 1.558 0.630 27-32-15 5.71 9.06 0.487 21-30-15 7.01 14.40 0.744 31-32 2.094 1.558 0.630 27-36-14 5.12 8.12 0.484 41-40-05 6.97 14.40 0.735 29-34 2.121 1.558 0.628 21-30-15 5.15 8.19 0.483 37-40-05 6.96 14.40 0.729 33-30 2.137 1.558 0.628 31-28-15 5.69 9.05 0.482 39-42-05 6.95 14.40 0.709 19-28 2.197 1.558 0.628 17-26-14 5.11 8.14 0.481 39-38-05 6.93 14.40 4 ASSYS W LIMITS > 1 l FLCPR 0 l APRAT 0 l FLPD 0
                  • NUCLEAR LIMITS BY REGION *********

7 8 9 0.656 15-40 0.688 29-36 0.674 37-40 0.478 11-40-05 0.465 29-40-05 0.484 41-40-05 0.601 11-40-05 0.630 27-36-14 0.609 41-40-05

...____.......___+--__..______._____.+_. ____ ....____.

4 5 6 **********

0.677 17-24 0.802 23-28 0.682 39-30

  • j 0.470 05-30-05 0.496 27-30-15 0.477 45-32-05
  • l 0.628 17-26-14 0.684 19-28-14 0.625 35-28-14
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..............___+______. _... __ __.+..___. _____ __.. ********** 1 1 2 3 l 0.655 13-16 0.673 23-18 0.661 37-14 j 0.479 11-14-05 0.457 23-14-05 0.477 37-14-05 5 0.602 11-14-05 0.622 25-18-14 0.601 37-14-05 l I

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CP&L Nudear Fuels Management & Safety Analysis Section File: NF-%8 03 U2Cl4 Neutronics Startup Report Page 10 of 10, Revision 0 i .

Attachment 2 to the B2C14 Startup Report (continued)

High Power Testing Plateau Statepoint Report BRUNSWICK-2 WK-9922 99MAY27-07.53.33 13761 brdD/ MTU TRIGR=1HR REV=FEB97 CORE PERFORMANCE LOG --- LONG EDIT l B2C14 BOC TO EOFPC-2205 MWD /Ftr ODYNB POW DEP MCPR CALCULATION TYPE : NORMAL CONVERGENCE . TIGHT SYMMETRY . FULL CTP CALCULATION t HEAT BALANCE CYCLE +

14 STATE CONDITIONS FLOW RATES CORE PARAMETERS NUCLEAR LIMITS LOCATION Gbf4E 844.10 WT 66.0 CMEQ 0.3293 P-PCS 0.39 27-36-05 CbrdT 2558.3(100.0%) WTSUB 66.38 CAEQ 0.1690 FCBB 2.303 PR 1043.8 PSIA WTFLAG 2 CAQA 0.1422 CMPF 2.840 29-32-04 DHS 23.79 WFW 11.01 CAVF 0.5060 CMFLCPR 0.921 29-32 WT 66.01 (85.7U WD 30.99 CAPD 51.6258 P=1.340 F=1.200 CRD 0.069 RWL 185.6996 CMAPRAT 0.922 21-28-04 CYCEXP 46 MWD /MTU ERATIO 0.98 CDLP 19.2829 P=1.000 F=1.000 MEASURED / CALCULATED LPRM READINGS DPCC 24.1238 CMFLPD 0.939 29-32-04 AVG: 6.394 MAX: 22.87% KEFF 1.0020 ~ CMFLEX 0.662 31-02-05 LOCATION 1 2 3 4 5 6 7 8 9 10 11 12 AXIAL REL POWER 0.56 1.24 1.34 1.34 1.37 1.32 1.23 1.10 0.95 0.73 0.55 0.26 REGION REL POWER 0.93 0.99 0.92 1.00 1.23 1.02 0.92 1.00 0.93 RING REL POWER 1.12 1.28 1.19 1.10 1.07 1.05 0.75 APRM GAFS 1.00 1.00 0.98 0.99 1.00 1.00

            • THE 10 MOST LIMITING BUNDLES ******

FLCPR LOC CPR LIMIT APRAT LOC APLHGR LIMIT FLPD LOC LPD LIMIT 0.921 29-32 1.455 1.340 0.922 21-28-04 10.56 11.46 0.939 29-32-04 13.52 14.40 0.918 31-30 1.460 1.340 0.921 25-32-04 10.50 11.40 0.935 31-30-04 13.46 14.40 0.911 27-30 1.471 1.340 0.917 29-32-04 9.59 10.46 0.918 23-28-04 13.22 14.40 0.910 29-28 1.473 1.340 0.913 31-30-04 9.55 10.46 0.917 27-24-04 13.20 14.40 0.894 37-40 1.499 1.340 0.899 25-34-04 10.36 11.52 0.892 29-34-04 12.85 14.40 0.891 39-38 1.503 1.340 0.896 23-28-04 9.38 10.46 0.882 33-30-04 12.70 14.40 0.890 29-34 1.506 1.340 0.895 27-24-04 9.36 10.46 0.836 21-28-03 12.03 14.40 0.887 25-32 1.511 1.340 0.892 19-26-04 10.27 11.52 0.830 27-22-03 11.96 14.40 0.885 39-34 1.515 1.340 0.871 29-34-04 9.11 10.46 0.824 29-36-05 11.86 14.40 0.884 31-28 1.517 1.340 0.864 31-32-04 10.17 11.77 0.815 25-34-03 11.74 14.40

  1. ASSYS W LIMITS > 1 l FLCPR 0 l APRAT 0 l FLPD 0
                  • NUCLEAR LIMI't S BY REGION * * * * * * * *
  • 7 8 9 0.873 15-40 0.866 33-40 0.894 37-40 0.763 15-40-10 0.824 29-36-05 0.778 37-40-10 0.790 17-42-10 0.829 33-42-10 0.813 41-36-10

..... .... ____..+.__.__..._____ ..__+_..______. ______

4 5 6 **********

0.856 13-20 0.921 29-32 0.885 39-34

  • 0.804 15-28-05 0.939 29-32-04 0.809 37-26-05
  • 0.838 11-20 0.922 21-28-04 0.846 41-34-10

. ___________ ...+...........__... __._________________ .......***

1 2 3 0.869 13-16 0.863 19-14 0.881 37-14 0.763 15-14-10 0.795 25-16-05 0.775 37-14-10 0.810 11-18-10 0.838 19-12-10 0.804 41-18-10 N:Wuels\ PROJECT \B2Cl#Startup Test Report \B2Cl4 Neutronics Startup TesReport. doc w _.

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