ML20198T296
| ML20198T296 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/24/1997 |
| From: | Labelle D, Siphers J, Thomas R CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20198T294 | List: |
| References | |
| B2C13, B2C13-R, B2C13-R00, NUDOCS 9801270025 | |
| Download: ML20198T296 (11) | |
Text
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ENCLOSURE 1 BRUNSW1CK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324/ LICENSE NOS. DPR-62 CYCLE 13 STARTUP REPORT 5
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P BRUNSWICK UNIT 2, CYCLE 13 NEUTRONICS STARTUP REPORT t,.
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BRUNSWICK UNIT 2, CYCLE 13 NEUTRONICS STARTUP REPORT November 1997 Prepared by: _
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Roger L. Thpas, Jr.
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O2 97 John T Siphers I '
Superintendent, BWR Fuel Analysis t
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1.0 lotroductinn i
This report summarires observed data from the initial Brunswick Unit 2, Cycle 13 (B2Cl3) stanup tests. The Cycle 13 core represents the second reload of the GE13 fuel type in Unit 2. For Cycle 13, core rated thermal power is being increased from 2436 to 2558 M Wt.
Pursuant to the requirements of Section 6 9.1.1 of the Unit 2 Technical Speci0 cations, a summary report of plant startup and power escalation testing shall be submitted to the -
NRC should any one of four conditions occur. Conditions (2) and (4) <ipply:
(2):
" amendment to the licen.,e involving a planned increase in power level",
and i
(4):
"niodifications that may have signincantly altered the nn&ar, thermal, or hydraulic perfonnance of the plant."
This repon shall include results of neutronics related startup tests following core i
reloading as de*.cribed in the UFSAR. This report is not inten&d as a stand alone document, but will be included with the power up. rate startup report for Cycle 13.
2.0 UFS AR Section 14.4.1. ltem 1: Core 1,oadinn Veri 0 cation A Core L
'ng Pattern Verification was performed per BNP Engineering Procedure ENP 24.1 Core Verincation." The core was verified to be loaded in accordance with the Recomi. nded Full Core Loading Pattern.
3.0 UFS AR Section 14.4.1. Item 2: TlP Ooerability and Core Power Symmetry a.
TIP Uncenainty -
A TIP uncenainty 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 57.1%. The measured uncertainty was 2.66%, thus meeting the criteria.
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i ci'AL Nutlear l'ucle Manaren,ent & &alcty Analysis Seruon file' NFV4 03 ft2Cl1 Neuttunkt startup krpwt Page 3 of 10. Reunion 0 3.0 UFS AP Section 14 4.1. Item 2: TIP Oncrability and Core Power Symmetry (cont...)
)
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 bun.lle powers is no longer performed at Isrunswick with the improved POWERPLEX core monitoring syrtem.
POWERPLEX methodology does not require core symmetry. Therefore, the Core Power Symmetry Test was replaced by a more appropriate Predicted Verses Measured Bundh Power Test. The test results and acceptance criteria are provided in c tv Iow.
c.
Predicted Versus Measured Ilundle Powers llNP Engineering procedure Olrr 50.0," Reactor Engineering Refueling Outage Testing,"
was revised to replace the Core Power Symmetry Test (115% symmetric bundle power agreement acceptance criterion) with a Predicted Versus Measured llundle Powers test.
This test compares the MICRollURN H design code's calculation of predicted bundle powers to the plant process computer's ?acasured bundle powers. The comparison must verify that the absolute difference between measured and predicted bundle powers meets the acceptance criterion of 58Mk. Ilundles hicated in peripheral control cells or uncontrolled peripheral locctions are excluded.
The acceptance criteria was met with the maximum absolute difference measured as 4.64 %
4.0 UFSAR Section 14.4.1. Item 3: Control Rod Mobility Cretrol rod mobility is verified by two tests: friction testing and scram timing. The results of these tests 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 olrr-901, the reactor was observed to remain suberitical during the withdrawal of the most reactive rod in llNP Fuel llandling Procedure OFil 11, " Refueling."
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b.
Scram Time Testing Scram Time Testing was performed for each control rod prior to exceeding 40% power per ilNP Engince.ing Procedure OPT-14.2.1," Single Rod Scam insertion Times Test" The acceptance criteria for this test are found in Technical Specifications 3.1.3.2,3.1.3.3, and 3.1.3.4. The maximum 90% insertion time was measured as 2.906 seconds meeting the 57.0 seconds acceptance criteria of Technical Specification 3.1.3.2. Acceptance criteria for the Core Average Scram Insertion and Maximum Average 2x2 Scram insertion times were also met as illustrated in Attachment 1.
The average 20% inseition time measured from the low power testing was 0.817 seconds, thus meeting the ODYN Opilon il time requirement of 50.850 seconds. ODYN Option il 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 Ken comparison to predicted values. The results of these tests a c provided below with the acceptance criteria.
a.
Shutdown Margin Shutdown margin measurements were performed per 11NP Engineering Procedure OPT-14.3.1,"Insequence Critical Shutdown Margin Calculation." Th:imtial 130C shutdown margin was mecsured as 1.364% Ak/k compared to a predicted value of 1.222% Ak/k, an absolute difference of 0.142% Ak/k. The acceptance criterion for minimum shutdown margin is defined in Technical Specification 3.1.1, which requires the shutdown margin be 2 0.38% Ak/k for the entire cycle. To calculate the minimum shutdown margin for the cycle, the maximum predicted decrease in shutdown margin over the cycle relative to IlOC,-0.131% Ak/k (R), was applied to the 130C measured shutdown margin. This resulted m an inferred minimum shutdown margin for Cycle 13 of 1.233% Ak/k. Therefore, the acceptance criterion is met.
b.
Cold Critical Eigenvalue (Kn)
The measured cold critical Kn was inferred as 1.00399,,
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calculations with actual critical conditions as input. The predicted cold critical La was 1.00388 giving a measured vs. predicted diff:rence of-0.011% Ak/k. Therefore, the acceptance criterion requiring agreement within il% Ak/k is met.
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c.
Reactivity Anomaly A reactivity anomaly test was performed at near rated (2401.1 MWt or 93.9%) conditions per BNP Engineerirq Prcredum OPT.14.5.2," Reactivity Anomaly Check." The acceptance criteria Mermed by Technical Specification 3.1.2 which requires the scactivity difference between actual and predicted core K<rr net exceed il% Ak/k. The measured and predicted values for K,n were 1.0024 and 1.002, respectively, an absolute difference of 0.04% Ak/k. well within the il% Ak/k requirement.
6.0 Additional Testine Results ~
As a matter of course, key testing and checks beyond those specified in the UFS AR are performed during initM startup and power ascension. These " standard" tests are described in items a. and b. below, a.
Core Monitoring Software Comparisons to Design Code Thermal limits casulated 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.
Ilot Full Power Eigenvalue After establishing a sustained period of full power (2558 MWt) equilibrium operation, the design and core follow Ilot Full Power Eigenvalues (Ken) are compared. At 507 MWD /MT the core follow K,n was calculated as 1.0009 and the design Ken is 1.0016.
The difference between the core, follow and design values is +0.066% Ak/k which is well within the 11% Ak/k reactivity anomaly requirements.
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CPA1.Natrar Iwii Maragtnrnt & safety Atulpa sertmn file NfWW 01 il2Cl 3 Newitonia startup Repri Parc 6 of 10, Reuimn 0 7.0 Siimmary Evaluation of the 13runswick Unit 2, Cycle 13 startup data concludes the core has been loaded properly and is operating as expected at the uprate power of 2558 MWt. The startup and initial operating conditions and parameters compare well to predictions. Core thermal peaking design predictic ns and measured peaking comparisons met the startup acceptance criteria. The 110C shutdown margin demonstration indicates adequate shutdown margin will exist throughout il2Cl3. All prescribed and additional tests met their acceptance criteria.
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CPAL Nmicat I'vels Manarcarent & Safety Atulym $cctumn l'ile; NF4K4 03 182C13 Neuttimics Startup Regust Page 7 of 10. Revnion 0 Attachment I to the H2Cl3 Startup Report Results of Control Rod Scram Time Testine Core Average Scram insertion Time i
Technical Specification 3.1.3.3 Insertion Position / Notch Tech Spec I,imit Average Measured (sec)
Insertion Time p(sec) 5%
46 0.358 0.301 20%
36 1.096 3.817 50%
26 1.8(O 1.352 90 %
6 3.419 2.507 Maximum Average 2x2 Scram insertion Time Technical Specification 3.1.3.4 Insertion Position / Notch Tech Spec I.imit Average Measured (sec)
Insertion Time (sec) 5%
46 0.379 0.316 20 %
36 1.162 0.859 50%
26 1.971 1.423 90 %
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e CTAL Nalear rurie Marweenent & Safety Arialysis $cctu n Fde: NF W4 03 Il2Cl3 Neutronics $tanup neport Page 8 of 10. Restsion 0 to the H2Cl3 Startup Report Core Monitorine Software Comparisons to Deslan Cmle Medium Power Testing Plateau 70.6% CMWT,970CT24,17:53:19,35 MWD /MTU Thennal Limit POWERPLEX MICRODURN B Difference Ac. ptance On Line Design Code Criteria Monitoring MFLCPR 0.748 0.761 0.013 i0.15 MAPRAT 0.770 0.786 0.016 10.15 MFLPD 0.559 0.571 0.012 i0.15 liigh Power Testing Plateau 93.9% CMWT,970CT26,00:31:38,64 MWD /MTU Thennal Limit POWERPLEX MICRODURN B Difference Acceptance On Line Design Code Criteria Monitoring MFLCPR 0.786 0.791 0.005 10.10 MAPRAT 0.873 0.904 0.031 10.10 MFLPD 0.725 0.749 0.024 10.10 l
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CPAL Nudcar fuels Manapenent & Safety Analph Section nk: NF.908 On 142C11 Neumanca startup Report Pape 9 of 10. Retision 0
. to the B2C13 Startup Report (cont...)
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DRUNSWICE.2 WE 974) 970C724-17.$3.19 35 MWD /NTO 7880RelHR REVaMAY96 COPE PESFokMANCE LOG.. SHORT ED17 82C13 600 to EOC-220$ MWD /Mt DDYN4 POW DEP MCPR CALCULAt!ON TYPE : NORMAL C0FrVERGENCE T!GHT $YMMETRY s FU1.1.
Ctt CA14t/LATION i HEAT RALANCE C7CLE 4 13 i
STATE CtelD1710NS F14W PATE5 CORE PARAMETCks NUCLEAR LIM!?$ thCATION OMWE. 602.96 WT
$0.4 CMEQ 0.2827 P.PCs 0.1$ 11-26 08 CMWT 1806.9 t70.6%) WT8V8 $1.99 C' 'Q 0.1499 PC&B 1.954 1
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23.70 CAPD 36.4627 Pel.443 Fal.313
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RWL 188.7027 CMAPRAT
.0.770 11-26-08 CYCEXP-35 MWD /Miu ERAT!O 0.95 CDLP 10.6938 P.O.847 Fe0.900 NEABURE!VCALCULATED LPRM PEADINGs DPCC 15.1393 CMrLPD 0.l$9 09-28-06 AVQs $.Mt MAX:
18.194 FEFF 0.9996 CMrLEx 0.179 07 08-12 Locatitsi 1
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AX1AL REL POWER 0.52 1.16 1.29 1.30 1.26 1.25 1.19 1.10 1.00 0.85 0.71 0.36 RE010N REL POWER J,89 1.04 0.89 1.05 1.16 1.05 0.89 1.01 0.89 RING REL POWER 0.94 1.19 141$ 1.22 1.09 1.0S 0.71-J APRM QAPS 0.98 0.97 0.99 1.00 0.99 0.98
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$PUNsW1CE.2 WK 9744 9700726 00.31.30 44 MWD /MW TRIQR*U$tR REV*MAY96
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Copt FtkrORMAN02 000.. $HORT EDIT 82C11 80C TO E3C-220$ MWD /MT ODYNS POW DEP HCPR CA14'ULAT!UN TYPE a N9PMAL CONVER3t'NCE a T!GHT SYHMETRY FULL CTP CALCULAT1ON t HEAT BALANCR CYCLE :
13 STATE CVNDATIDNS PLOW RATES CORE PARAMETERS' NUCLEAR LIMITS LOCATION OMWE 411.10 WT 16.3 CMtQ 0.2463 P.PC8 D. t.0 19 36 10 CMWT 2401.1 (93.99) WTI:Ua 76.21 CAto 0.1364 PCam 2.067 PR 1021,0 P8IA WTFLAG 2 CADA 0.1382 CMPF 3.339 31 20 09 DH8 19.19 WrW 10.2$ CAVP 0.4309 CMrLCPp 0.186 31 20 WT 16.24 199.04) WD 34.50 CAPD 48.4511 Pel.330 rol.200 CBD 0.078 RWL 186.1076 CMAPRAT 0.073 11-20 09
(*YCEXP 64 MWD /MTI)
RRATIO 0.9% CDLP 23.0793 t.0.960 r=1.000 MEASUARD/CA1.Ct/ LATED LPRM RtADIN38 DPCC 24.9199 CMFLPD 0.72% 31 30 09 Avoi 3.964
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Ktrr 1.0024 CMPLEX 0.779 07 08 12 j
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