ML082060060
| ML082060060 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 07/16/2008 |
| From: | Wilson M Dominion Energy Kewaunee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 08-0380 | |
| Download: ML082060060 (15) | |
Text
Dominion Energy Kewaunee, Inc.
6Dominiono N490 Highway 42, Kewaunee, WI 54216-9511 JUL 16 2008 ATTN: Document Control Desk Serial No. 08-0380 U. S. Nuclear Regulatory Commission LIC/JG/R0 Washington, DC 20555-0001 Docket No.: 50-305 License No.: DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION CYCLE 29 STARTUP REPORT In accordance with Technical Specification 6.9.a.1, Startup Report, attached is the Kewaunee Power Station Cycle 29 Startup Report. Rod drop times were inadvertently omitted from the Startup Report and are provided separately as attachment 2 to this letter.
If you have questions or require additional information, please feel free to contact Mr. J. F. Helfenberger at 920-388-8294.
Very truly yours, Mic el J. Wilson Dire'ctor Safety and Licensing Kewaunee Power Station Attachments
- 1. Cycle 29 Startup Report
- 2. Cycle 29 Startup Report, Rod Drop Times Commitments made by this letter: NONE
Serial No. 08-0380 Page 2 of 2 cc:
Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. P. S. Tam Sr. Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station
Serial No. 08-0380 ATTACHMENT 1 CYCLE 29 STARTUP REPORT KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Page 1 Table of Contents Paqe 1.0 S U M M A RY...........................................................................................
2
2.0 INTRODUCTION
2 3.0 FUEL DESIGN....................................................................................
2 4.0 LOW POWER PHYSICS TESTING....................................................
2 4.1 Critical Boron Concentration....................................................
3 4.2 Moderator Temperature Coefficient.........................................
3 4.3 Control Rod Reactivity Worth Measurements.......................... 3 5.0 POWER ASCENSION TESTING.........................................................
4 5.1 Power Distribution, Power Peaking and Tilt Measurements......... 4 5.2 Reactor Coolant System Flow Measurement...........................
6
6.0 REFERENCES
6 7.0 FIG U R ES.............................................................................................
6 Page 2 1.0
SUMMARY
Low Power Physics Testing and Power Ascension Testing for Kewaunee Cycle 29 identified no unusual core response or reactivity anomalies. All measured core parameters were determined to be within their acceptance criteria. All Technical Specification surveillance requirements were met.
2.0 INTRODUCTION
The Kewaunee Cycle 29 fuel reload was completed on April 27, 2008. The attached core map (Figure 1) shows the final core configuration. Cycle 29 uses a low leakage loading pattern consisting of 45 new Region 31 fuel assemblies, 44 Region 30 once-burned fuel assemblies, and 32 Region 29 twice-burned fuel assemblies.
Subsequent operational and testing milestones were completed as follows:
Initial Criticality May 08, 2008 Low Power Physics Testing completed May 09, 2008 Main Turbine Online May 09, 2008 30% Power Testing completed on May 10, 2008 50% Power Testing completed on May 11,2008 100% Power Testing completed on May 16, 2008 3.0 FUEL DESIGN All fuel assemblies in Cycle 29 are of the Westinghouse 14x14 422V+ assembly design. There are 45 fresh Region 31 assemblies with 20 of the assemblies (Region 31A) being enriched to 4.00 weight percent Uranium-235 (w/o U235) and contain various loadings of 1.25x IFBA rods. The remaining 25 assemblies (Region 31 B) are enriched to 4.40 weight percent Uranium-235 (w/o U23) with 9 of the assemblies containing various loadings of 1.25x IFBA rods. All assemblies in the core contain six inches of axial blankets at the top and bottom enriched to 2.60 w/o U235. The axial blankets are annular pellets with the exception that solid pellets are used in all fuel rods containing gad.
4.0 LOW POWER PHYSICS TESTING The low power physics testing program for Cycle 29 (Reference 6.1) was completed using the FTI Reactivity Measurement and Analysis System (RMAS). Note that RMAS v.6 was used for KEW29 Startup Physics Testing. This program consisted of the following:
Critical Boron Endpoint measurements for All Rods Out (ARO),
Moderator/Isothermal Temperature Coefficient measurements, and Control and Page 3 Shutdown Bank Worth measurements. Low power physics testing was performed at a power level below the point of nuclear heat to avoid nuclear heating reactivity feedback effects.
4.1 Critical Boron Concentration The critical boron concentration was measured for the All Rods Out configuration. The measured values include corrections to account for differences between the measured critical rod configuration and the ARO configuration.
The acceptance criteria of +50 ppm was met for the ARO configuration.
Critical Boron Endpoint Results Measured Predicted M-P Acceptance Criteria (ppm)
(ppm)
(ppm)
(ppm)
All Rods Out (ARO) 2393 2396
-3
+ 50 4.2 Moderator Temperature Coefficient Isothermal Temperature Coefficient (ITC) data was measured near All Rods Out conditions. Controlled heat-ups and cool-downs were performed and the reactivity change was measured. These measurements were then averaged to determine the measured ITC. They were then compared to the design predictions, which were adjusted to measured conditions. The review criteria of +3 pcm/°F of the predictions were met.
The Moderator Temperature Coefficient (MTC) of 1.699 pcmfF was determined by subtracting the design Doppler Temperature Coefficient (-1.721 pcm/PF) from the measured Isothermal Temperature Coefficient of -0.022 pcm/tF. The Technical Specification Limit of MTC < +5.0 pcm/?F at ARO Hot Zero Power (HZP) was met.
Isothermal/Moderator Temperature Coefficient Results Measured Predicted M-P Acceptance Criteria (pcm/F)F
) (p/F)
(pcm/0F)
(pcm/fF)
ARO ITC
-0.022
-0.280 0.258 N/A ARO MTC 1.699 1.442 NA MTC < +5.0 4.3 Control Rod Reactivity Worth Measurements The integral reactivity worths of all RCCA Control and Shutdown Banks were measured using the rod swap technique (Reference 6.2). The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were Page 4 recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 29, Control Bank C was used as the reference bank.
The acceptance criteria are as follows: The measured worth of the Reference Bank be within +10% of the predicted worth; the worth of a test bank be within +15% of the predicted worth for banks > 600 pcm: the worth of a test bank be within 100 pcm of the predicted worth for banks < 600 pcm; the sum of the measured worths of all banks is within +10% of the sum of the predicted worths.
Control Bank Integral Worth Results PERCENT MEASURED PREDICTED M-P DIFFERENCE (%)
BANK WORTH (PCM)
WORTH (PCM)
(pcm)
(M-P)/P X 100 A
801 816
-15
-1.8 B
636 599 37 6.2 C
880 864 16 1.9 D
786 790
-4
-0.5 SA 651 635 16 2.5 SB 653 635 18 2.8 Total 4407 4339 68 1.6 The measured results of the individual bank worths and the total control bank worth showed excellent agreement with the predicted values. All individual and total worth acceptance criteria were met.
5.0 POWER ASCENSION TESTING 5.1 Power Distribution, Power Peaking and Tilt Measurements The core power distribution was measured through the performance of a series of flux maps during the power ascension in accordance with Reference 6.3. The results from the flux maps were used to verify compliance with the power distribution Technical Specifications.
A summary of the Measured Axial Flux Difference (AFD) and INCORE Tilt for the flux maps performed during the power ascension is provided below. Additional tables provide comparisons of the most limiting measured Heat Flux Hot Channel Factor (F0) and Nuclear Enthalpy Rise Hot Channel Factor (FAh), including uncertainties, to their respective limits from each of the flux maps performed during the power ascension.
The most limiting Fa is based on margin to the limit which varies as a function of core height.
Page 5 As can be seen from the data presented, all Technical Specification limits were met and no abnormalities in core power distribution were observed during power ascension.
Measured Axial Flux Difference and INCORE Tilt Power Burnup Rod Axial INCORE Tilt
(%RTP)
(MWD/MTU)
Position Offset (steps)
(%)
27.1 3.5 151 0.748 1.019 49.6 17.3 187 5.792 1.011 99.6 193 225 2.549 1.003 Comparison of Measured Fo to Fa RTP limit Power Burnup FoHI P steady Powe (L
Measured F0 state limityMargin to Limit
-(%RTP)
(MWD/MTU) state limit 27.1 3.5 2.379 5.000 52.42 %
49.6 17.3 2.194 5.000 56.12%
99.6 193 2.020 2.510 19.53 %
Comparison of Measured F&h to FAh limit Power Burnup
(%RTP)
(MWD/MTU)
Measured F~h F~h limit Margin to Limit 27.1 3.5 1.599 2.072 22.82%
49.6 17.3 1.553 1.957 20.66%
99.6 193 1.505 1.702 11.57%
Presented in Figures 2, 3 and 4 are measured Power Distribution Maps showing percent difference from the predicted power for the 30%, 50%, and 100% power plateaus. From this data it can be seen that there is good agreement between the measured and predicted assembly powers.
Page 6 5.2 Reactor Coolant System Flow Measurement The Reactor Coolant Flow rate was determined in accordance with Reference 6.3 using a secondary calorimetric heat balance for each loop using the steam generators as the control volumes.
Steam generator blowdown was not isolated during the data acquisition period. The measured reactor coolant flow met the Technical Specification Limit of > 178,000 gpm and the more limiting COLR value of > 186,000 gpm.
Reactor Coolant System Flow Results Measured Flow Acceptance Criteria Flow Limit (ppm)
(gpm1 186m0 194321 186000
> 186000
6.0 REFERENCES
6.1 NF-KW-RET-002, "Low Power Physics Test" 6.2 Westinghouse Electric Corporation, "Rod Exchange Technique for Rod Worth Measurement" and "Rod Worth Verification Tests Utilizing RCC Bank Interchange."
6.3 NF-KW-RET-008 "Power Escalation Tests" 7.0 FIGURES Pag~e 1
Core Loading Pattern................................................................
7 2
INCORE Power Distribution - 27.1%......................................
8 3
INCORE Power Distribution - 49.6%......................................
9 4
INCORE Power Distribution - 99.6%......................................
10 Page 7 FIGURE 1 CORE LOADING PATTERN KEWAUNEE - CYCLE 29 1
2 3
4 5
6 7:'
8 9
10 11 12 13 2% 1 29A 298 G93 G87 I G59 29A G63 29A G77 31B 31A 31B 29A 29A J73 J51 J76 G75 G51 29A 318 29A 29A 31 B 31B J88 31A 30.
31A 31B 31B J57 H
181 IJ60 IJg0 J84 29A 29A 318 31A 301 30 30 30 30 31A 31B 29A G60 J85 J62 H71 H83 H75-H85 IH72 J68 J72 G61 A
B C
D E
F G
H 29A G80 31B 30 J91 H68 30 H94 30 31A 30 130 30 H53 I J69 I H57 H84 H70 31B 29A J92 I G79 1800 29B 31B 31A 30 30 30 30 30 30 30 31A 31B 29B G89 J86 J56 H80 H64 H66 H65 H59 H54 H93 J70 J74 G94 29A 31A 30 30 31A 30 31B 30 31A 30 30 31A 29A G66 J52 H89 H76 J58 H51 J95 H56 J65 H77 H82 J53 G62 298 31B 31A 30 30 30 30 30 30 30 31A 31B 29B G90..
J81 J66 1188 H61 H52 1-160 H62 H55 H87 J63 J82 G88 29A G72 31 B J93 30 H74 30 H79 30 31A 30 30 30 H58 IJ64 IH63 IHg0 IH69 31B 29A J87 IG85 I
H5 J64 H63H9 9
87-8 29A 31B 31A 30 30 30 30 30 31A 31B 29A G54 J79 J59 H73 H86 IH78 H92 H67 J61 J80 G65 29A G74 31B J75 31 B J94 31A 30 31A 31B 31B J55 H91 I J67 I J89 J77 29A G73 14 J
K L
M 29A G56 29A G84 318 31A 31B 29A 29A J71 J54 I J83 I G78 G53 298 G392 29A G352 900 298 (391 LEGEND REGION ASSEMBUES ENRICHMENT Region Identifier Fuel Assembly Identifier 29A 29B 30 31A 31B 24 8
44 20 25 4.60 4.94 4.96 4.00 4.40 Page 8 FIGURE 2 INCORE Power Distribution - 27.1%
KEWAUNEE - CYCLE 29 1
2 3
4 5
6 7,
8 9
10 11 12 13 0.299 2.5 1.M308.21.86 0.3121 0.541 013081
-0.1 12.5 Nx2.7 1.082 0.8 1.066; 0.9 0.531 0.316 0
50.6 1.3 1.130 2.1 1.314 3.4 1.230 2.6 1.193 2.0 (41I.2 1 1.124 1.5 0.312 1.!
4 1.
1,37 8
1.306 1.M, 1.238 1oll11 0.31 0.1 0.2 2.1 2.9 1.8 1.7 1.1 0.4
-0.4 A
B C
D E
F G
H 1.274 0.2 1.362 3.4 1.402 3.5 11278 2.0 1.287 1.2 1.370 1.1 1.276 0.4 0.527
-0.1 0.294 1.069 1.203 1.360 1.2 1.260 1.235
.2 1.260 1323 1.189 1 0.288 0.9 1.1 0.6 1.3 1
2.7 2.2 0.5
-1.2
-0.8
-1.
-1.2 0.32 1T.08b 1.180 1.9 1.268
'1.2i 1.294 1.206 1L.23 12311
.5
-1,1 0.8 1.3 0.6
-0.2
-2.8
-1.
-1.6
-1 1.0541 1.335 1.253 1.227 1.207 1.21 1.
1r.31Z 1.164 1.036 0.284
-0.5
-0.4
-0.1 0.0
-0.2
-2.2
-2.7
-2.0
-2.4 0.521 1.270 1-307I34ý 1.282 T.23r 1.236 1.317 1
-2
- 12 0.517 I
0.310 1('4 1.225 1.320 1.334 1.260 1-.3 1.279 1.215 1.086 (
-0.6
-1.5
-1
- 2.
-0.7
-2.0 0.437
-0.6 1.265
-0.5 1-218 1.8 1.138
-2.7 1.174
-2.1 1.244
-2.1 1.087
-1.8 0.424
-3.6
.0.6
-3.6 9~
9* -
I ~9
-1w, J K
L M
0.524
-0.7 1.015 1.032
-4.0
-3.7 1.032
-2.6
(~51A 0.306
-2.0 v-1-2.I 0
0-279
-4.3
-3.0 E]
Measured Power Percent Difference (M-P)/P D Measured Location Page 9 FIGURE 3 INCORE Power Distribution - 49.6%
KEWAUNEE - CYCLE 29 1
2 3
4 5
6 7
8 9
10 11 12 13
-j.-30, 2.3 031 0.339 2.3 0.5
.14.
.1
- 4. -
0.3071 0.538 jIr{10* 1.111 1.0781 0.5281 0.311
-0.5 2.2 k, 2A.
1.0 0.3
- 10. 1 0.6 4~I~411 I
-1 (6.43N 1.109 1.295 Y,-o.sA 0.6 1 1.9 1.236 1.6 1.263 1.7 22N 1.28N 1.112 V.
ý,.A -A0.7 K
0.311 1.110 1.223
.32 1.354 1.30 1.349 1.308 1.219 1.106 0.312 0.6 0.6 0.6 1.6 1.0 0.4 0.2 0.3 1.1 I
I I
A B
C D
E F
G H
(~. 53~
K1.7 1.293 1.7 1.315 1.0 1.352 1.3 Q52~125~ 1257 1.328
-0.5 1.279 0.6 0o537 1.9 0.300 1.098 1.228 1.337
.25 1.215 1.192 1l.20* 1.230 1.321 1.214 0.301 2.2 2.2 1.3 0.0 0.6 0.3
-0.5
-0.9
-0.2 2.5 0.343
.11 1.254 1.238
.1 1.259 1.181 1.22 1.259 -.
1.111
.34 1.8 1.0
.1
-0.2
-0.7
-0.6
-1.
-1.8 1.0 1.092 1.2 1.328 1.226 1.197 1.179 1.1 1.233 (.31 1.184 1.072 0.303 S
1.4
-0.4 0.8 09
-0.8
-1.6
-1.6
-2.3
-0.2 3.0 0.530 1.274 0.6 0.2 1.295
-0,4 1.2391
-1.1
-1Z 1.9 1-2.8
-2.6
_-1.*
-1.2 I
0.308( f105 1.212 1.296 1.3221 1.253 1.30 1.249 1.194 1.090K
-0.1
-0.4
-0.5
-2.3
-3.9
-1.9
-1.2 0.435 Cl.i00 0.0 KO.Q.
1.27211.220 0.0 1 0.6 1.199 1.202 1.257 1.119 0.432
-3.5 1 -1.2
-1.1i1 1.5 1 -0.7 I ~
4-4
~ -
I ~4 J K
L M
304 0.527 0.0 1.095 1.9 1.122 2.0 1.095 1.7 t©.53 0.313 1.5 4.
0.299 1.9 0.299 1.7 FZ Measured Power Percent Difference (M-P)/P D Measured Location Page 10 FIGURE 4 INCORE Power Distribution - 99.6%
KEWAUNEE - CYCLE 29 1
2 3
4 5
6 7
8 9
10 11 12 13 0.3 0380.359 0.3
-0.7 Y. -
9-I~9-w.
0.320
-0.6 0.547 0.3 r(.09-)
\\.O.
1.1181 1.0871 0.5441 0.326
-0.4
-0.1 1 -0.2 1 1.2 w
94 4
6-I 6
I 1.089 0.3 1.257 0.7 1.221 0.1 1.291
-0.2 T.22a 1.100 1.3 t 451%
0.323 1.091 11.191 r1.2&j 1.325 1.28 1.323 1.2781 1.1951 1.090 0.326 0.3 0.4 0.3 N 0.3
-0.
0.0 0.1 0.5 0.4 1A A
B C
D E
F G
H 6'55N 1.264 1.31 0
1.316 (06
.22A
- 1.
1.3 0.4 0,A
\\0.
1.232 1.235 1.303
-0.4 1.256 0.6 0.557 2.1
-0.1
-0.6 0.318 1.102 1.221 1.318 1.2 1.200 1.185 v1. 1.218 1.309 1.220 11 0.322 1.0 1.2 0.4
-0.5 \\.
0.0 0.0
-0.
-0.7
-0.9 0.1 1\\.
2.1 0.361 l'1.12* 1.296 1.28iý 1.226
.11 1.246 1.174 1.21 1.263 1l.28ý 1.134
-0.3 \\
0.2
-0.
-0.6
-0.
-0.6
-0.8
-1.
-1.8 \\0.
1.0
.31 1.092 1.22 1.315 1.218 1.188 1.171 V1 1.219
.32
-0.
~ 0.1
-0.4
-0.8
-11.0
-1.1
- 1.
-1.8
-1.
-1.4 10.5 2.0 0.544
-0.3 1.252 0.3 1.272
-0.2 ri.296)
ý, J J))
1.227
-1.2
ý1,2.
1.212
ý-.2
-1.2 1.286
-1.8 1.257 V1.242 0.549
-1.5 N-K.S 0.7 0.322
, O 1.18811.27511.3081i.271 130 1
21 1,
105 0.1 0.0 1-0.1 1-1.2 1-1.2 I
-1.01 0.2 1 0.8 TO?-
9 9~~
J K
0.448 0.8 1.263 1.2 1.226 0.8 1.281
-1.0 1.230 0.9 1.261 1.0 1.117 2.9 0.450 1.2 02 I1.$.~7 0.331 0.55211.107 1.1
-1.7 1.141 1.6 1.116 2.3 0.331 L
2...
D.320 1.5 r6-36ý S142 0.322 2.2 M
LI Measured Power Percent Difference (M-P)/P D
Measured Location
Serial No. 08-0380 ATTACHMENT 2 CYCLE 29 STARTUP REPORT CYCLE 29 STARTUP REPORT ROD DROP TIMES KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
I I! I
. i i" Serial No. 08-0380 Page 1 of 1 Kewaunee Power Station Cycle 29 Startup Report Rod Drop Times May 2008 RCCA Bank and Group RCCA Core Location Time from Start to Dash Pot (seconds)
F-2 1.271 B-8 1.310 Control Bank Al B-8 1.286 H-12 1.286 L-6 1.310 B-6 1.245 Control Bank A2 F-12 1.272 L-8 1.239 H-2 1.278 F-6 1.305 Control Bank B1 F-8 1.317 H-8 1.297 H-6 1.311 C-7 1.316 Control Bank D1 G-11 1.235 K-7 1.305 G-3 1.256 Shutdown Bank Al E-3 1.299 1-11 1.312 Shutdown Bank A2 C-9 1.348 K-5 1.348 C-5 1.266 Shutdown BankB1 E-11 1.272 K-9 1.234 1-3 1.307 Control Bank C D-10 1.281 J-4 1.288 D-4 1.259 Control Bank C2 G-7 1.359 J-10 1.281 Note: All rods met rod drop time criterion of no greater than 1.8 seconds.