ML20064H062

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Startup Test Rept for Cycle 5
ML20064H062
Person / Time
Site: Millstone Dominion icon.png
Issue date: 03/07/1994
From: Miller D
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-94-155, NUDOCS 9403170143
Download: ML20064H062 (14)
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Text

Rope Ferry Rd. (Route 156), Wcterford, Ur 06385 s

)gy .Nordicast Nuclear Energy stone Nocie,r po ,r stauon Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385-0128 (203) 447-1791 Fax (203) 444-4277 The Northeast Utihtica System March 7, 1994 MP-94-155 Docket No. 50-423 Re: Technical Specification 6.9.1.1 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Millstone Nuclear Power Station. Un t f mJ Start-Up Test Reoort for Cycle 5 Millstone Unit No. 3 entered Mode 1 on November 5,1993 and the Cycle 5 startup test program was completed on December 13,1993, following its refueling outage. As required by the Millstone Unit No. 3 Technical Specifications, Section 6.9.1.1, Northeast Nuclear Energy Company hereby submits the attached Millstone Unit No. 3 Start-Up Test Report.

Should you have any questions related to this submittal, please contact Ms. Kimberley Lincoln of Millstone Unit 3 Technical Support, at (203) 444-5284.

Very truly yours, NORTHEAST NUCLEAR ENERG COMP NY N

Donald B. Miller, Jr.

Senior Vice President - Millstone Station DBM/kml Attachment cc: T. T. Martin, Region i Administrator P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1,2, and 3 V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 1

170028 ow n arv i w pN, I 9403170143 940307 PDR ADDCK 05000423 P. PDR

Docket No. 50 423 MILLSTONE NUCLEAR POWER STATION UNIT NO. 3 STARTUP TEST REPORT CYCLE 5 March 1994 f

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Page 2 of 13 INDEX 1,

SUMMARY

3

2. INTRODUCTION 3
3. LOW POWER PHYSICS TESTING RESULTS 3 3.1 Critical Boron Concentrations 3 3.2 Isothermal / Moderator Temperature Coefficients 4 3.3 Control Rod Reactivity Woith Measurements 5
4. POWER ASCENSION TESTING RESULTS 5 4.1 Power Peaking and Tilt Measurements 5 4.2 Boron Measurements 6 4.3 Doppler Only Power Coefficient 6 4.4 RCS Flow 7 4.5 Power Distribution 7
5. REFERENCES 8

Page 3 of 13

1.

SUMMARY

Low Power Physics Testing and Power Ascension Testing for Millstone 3, Cycle 5 identified no unusual situations or anomalies. All parameters were determined to be within their acceptance criteria. All Technical Specification limits were met.

2. INTRODUCTION The Millstone 3, Cycle 5 fuel reload was completed on September 11,1993. The attached core map (Figure 1) shows the final core configuration. Eighty-four (84) new fuel assemblies were inserted into the core. Major changes from the Millstone 3, Cycle 4 core design are:
  • Addition of 90 thimble plugs, such that all but four unrodded locations contain thimble plugs
  • Replacement of all four Reactor Coolant Pumps, resulting in a reduction of roughly 2% in core flow
  • Increase in number of Vantage SH fuel assemblies to 172 of 193, with 30 of the new assemblies containing Zirlo clad and grids, and 48 of the new assemblies containing Zirlo clad with rotated Zirc 4 grids for vortex shedding on the baffles Subsequent operational and testing milestones were completed as follows:

Initial Criticality October 30,1993 Low Power Physics Testing completed October 31,1993 Main Turbine On-Line November 7,1993 30% Power Testing completed November 7,1993 75% Power Testing completed November 11,1993 100% Power Testing completed December 13,1993 Cycle 5 operation is with 193 Westinghouse manufactured fuel assemblies. The Safety Analysis is provided by Westinghouso.

3. LOW POWER PHYSICS TESTING RESULIS Low Power Physics Testing was performed in accordance with ANSI 19.6.1, at a power level of <5 x 10 2% power to avoid nuclear fuel heating effects.

3.1 Critical Boron Concentrations Critical Boron Concentration was measured at two different Rod Control

Page 4 of 13

, Cluster Assembly (RCCA) configurations; at All Rods Out (ARO) and with

RCCA Control Banks D, C, B and A inserted.

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The Critical Boron Concentration (CBC) measured with Control Bank D at 197 steps was 2246 ppm. Adjusted to All Rods Out, the CBC was 2254 ppm.

Therefore, Measured CBC at BOL HZP-ARO = 2254 ppm Predicted CBC at BOL-HZP-ARO = 2267 com Difference = 13 ppm The Acceptance Criteria is 150 ppm.

! Acceptance Criteria met? Yes The Critical Boron Concentration (CBC) measured with Control Banks D, C, B, inserted and A at 16 steps was 1720 ppm. Adjusted to All Rods in (ARI), the CBC was 1721 ppm.

Measured CBC at BOL-HZP ARO = 2254 ppm
Measured CBC at BOL-HZP-ARI = j]21 ppm

. Difference = 533 ppm The predicted Critical Baron Concentration for Control Banks A, B, C and D inserted is 1733 ppm, therefore the difference is:

i Predicted CBC at BOL-HZP-ARO = 2267 ppm 1 Predicted CBC at BOL-HZP-ARI = 1733 Dom Difference a 534 ppm Therefore, the difference between the predicted and measured values is:

Predicted Difference in ARO and ARI CBCs = 534 ppm Measured Difference in ARO and ARI CBCs =

J33 DDm Difference = 1 ppm The Acceptance Criterla is150 ppm l Acceptance Criteria met? Yes

. 3.2 1sothermal/ Moderator Temperature Coefficients The Isotnermal Temperature Coefficient wa.s measured with all RCCA banks

, withdrawn (ARO). The Moderator Temperature Coefficient was then calculated.

ARO ITC Measurement: i i i b The measured ITC value with Control Bank D at 196 steps, an average RCS temperature of 5540F, and an RCS Boron Concentration of 2252 ppm, was

! 1.29 pcmFF.

Page 5 of 13 Comparing the mea *,ured ITC to the predicted ITC yields:

Measured ITC at BOL, ARO = 1.29 pcmPF Predicted ITC at BOL, ARO =

1.05 ocmFE Ditference = 024 pcmFF The Acceptance Criteria is +1.05 pcmFF 12 pcmFF Acceptance Criteria met? Yes All Rods Out MTC Determination The MTC was calculated by subtracting the design Doppler Temperature Coefficient ( 1.78 pcmFF) from the ARO ITC. In addition to comparing the measured MTC to the predicted value, it was required to verify that the Technical Specification MTC limit of MTC < +5 pcmFF at ARO, HZP was met.

Calculating the MTC yields:

1.29 pcmFF - (-1.78 pcmFF) = 3.07 pcmFF Comparing the measured MTC to the predicted MTC yields:

Calculated MTC at BOL, ARO = 3.07 pcmFF Predicted MTC at BOL, ARO = 2.80 pcmFF -

Technical Specification Acceptance Criteria is MTC < +5 pcmFF Acceptance Criteria met? Yes 3.3 Control Rod Reactivity Worth Measurements Reactivity worth measurements were performed individually on Contrul Banks D, C, B, and A. The results of the measurements were:

Individual Bank Worth Measurements (by dilution)

Measured Predicted Delta  % Difference a

Q_anh Worths (ocm) Worths (ocm) (M-P) ((M-P)/El Control D 552 553 -1 -0.2 Control C 870 854 16 1.9 Control B 710 731 21 -2.9 Control A 1418 1368 50 3.7 Total 3550 3506 44 -1,3 The Acceptance Criteria for the Total Worth of the Control Banks inserted is110% of the predicted total worth. The Acceptance Criteria for any individual Control Bank is the greater of either1100 pcm or 115% of

I Page 6 of 13 the predicted Bank worth.

Acceptance Criteria met 7 Yes Measurement of Control Rod Reactivity Worth also verified the Technical Specification Surveillance requirements for SHUTDOWN MARGIN, which require that at least 1.3% reactivity (1300 pcm) exists below the zero power rod insertion limit.

4. POWER ASCENSION TESTING RESULTS 4.1 Power Peakina and Tilt Measurements Flux Maps were performed to determine incore power distribution and tilt.

The measurements of these parameters, including uncertainty, were:

HEAT FLUX HOT CHANNEL FACTOR - FQ(Z)

Above Midooint Peak Below Mido._o1n. t Peak -

Measured FQ(Z) Measured FQ(Z) Max Incore Power Level FQ(Z) Limit FQ(Z) Limit Tilt 30 % 1.985 3.791 1.290 3.436 .1.008 75% 1.884 2.521 1.356 2.284 1.007 90 % 1.971 2.272 1.418 1.929 1.007 10- 2.028 2.112 1.665 1.877 1.011 Ns t LAR ENTHALPY RISE HOT CHANNEL FACTOR - FNDH Power Level Measured FNDH FNDH Limit 30% 1.52 1.98 75 % 1.48 1.76 00 % 1.46 1.69 100% 1.47 1.64 4.2 Boron Measurements At 100% power,2073 MWD /MTU, Control Bank D at 222 steps and Equilibrium Xenon, the measured RCS Boron Concentration, Cg, was 1561 ppm.

Measured Cg, adjusted to ARO = 1561 ppm Predicted C 3at 100%_ power, ARO, 2073 MWD /MTU Equilibrium Xenon = 1581 com Difference = -20 ppm ,

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Page 7 of 13 Subsequent RCS Boron measurements made at 100% power,2308 MWD /MTU, Control Bank D at 223 steps and equilibrium xenon, yielded the following results:

Measured Ce

= 1568 ppm Predicted Cs at 100% power, ARO, 2308 MWD /MTU, Equilibrium Xenon = 1592 Dom Difference = -24 ppm The Acceptance Criteria is i 159 ppm (t 1000 pcm)

Acceptance Criteria met? Yes 4.3 QQooler Only Power Coefficient A Doppler Only Power Coefficient verification factor (PCm) was calculated at 100% power and compared to the predicted Doppler Only Power Coefficient verification factor (PCp). Measurements were taken at an average power of 98.9%, an average RCS temperature of 586.1oF, and an RCS boron concen-tration of 1586 ppm.

Average Calculated value, PCm ' = 1.397 Fo/%

Predicted value, [PCpl = 0.931 F0/%

Difference = 0.486 F*/%

The Acceptance Criteria is an absolute difference of <0.5 F0/% between PCmand PCp.

Acceptance Criteria met? Yes 4.4 RCS Flow The measured RCS fk y at 75% power was 388,902 GPM.

The Acceptance Criterir., per Millstone 3 Technical Specifications, is that RCS flow must be greater than 387,480 GPM prior to exceeding 75% power.

Acceptance Criteria met? Yes RCS flow was remeasured at 100% power as further verification of acceptable flow. Measured RCS flow at 100% powerwas 391,522 GPM.

The Acceptance Criteria is that RCS flow, adjusted for venturl fouling, must be greater than 387,867 GPM.

Acceptance Criteria met? Yes Total RCS flow decreased from the previous cycle due to the replacement of the reactor coolant pumps and the reinstallation of the thimble plugs, however RCS flow remained above the Technical Specification minimum value.

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4.5 Power Distribution

- Power Distribution maps are shown for 30%,75%,90% and 100% power conditions in Figures 2,3,4 and 5. The agreement between the measurements and the predictions is good.

The Acceptance Criteria is that all locations are within 110% of the predicted value Acceptance Criteria met? Yes 1

5. REFERENCES 1

5.1 in-Service Test 3-93-010, Cycle 5 Low Power Physics Tests 5.2 in-Service Test 3-93-013, Cycle 5 Power Ascension Tests 5.3 Westinghouse Nuclear Design Report - Cycle 5 (WCAP 13804) 5.4 ANSl/ANS - 19.6.1 (1985) Reload Startup Physics Tests For Pressurized Water Reactors

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l Page 9 of 13 Figure 1  ;

1 Core Loading Pattern Millstone Unit 3 - Cycle 5 R P W M D C B A i L. K. J. H. C. F. I. 1 SB 7 7 5B 7 7 58 E59 C03 C08 E39 C10 C35 E7 0 I

5B 7 7 7 (B 6A 68 7 7 7 58 E72 C22 C31 G34 F60 F21 F59 C36 G42 G24 E56 j 58  ? 6B 68 7 6A EB 6A 7 68 68 7 5B l 3

E62 017 F51 F75 C47 F31 F47 F05 C59 F7 8 F67 G02 E71 7 6B 6B 1 6A 7 68 7 (A 7 68 69 7 j C25 F62 F38 G62 F17 G72 F80 C73 F30 C46 F43 F63 C26 5B 7 68 7 6A 7 6B 7 6B 7 6A 7 63 7 SB

~ '

E60 G43 F88 G81 Fil C52 FS2 G67 F71 G68 F01 C64 F76 G30 E55 7 7 7 6A 7 EB 68 4A 6B 6B 7 6A 1 7 7

~

G21 C44 G65 F24 c58 F77 F45 F14 F39 F87 G61 F13 G45 C32 C04 7 (B 6A 7 68 63 6A 7 6A 6B 6B 7 6A 68 7 I

~

013 F*2 F15 C71 F7 0 F41 F03 C57 F12 F44 F69 C54 F09 F64 G14 5B 6A 6B 68 7 6A 7 58 7 6A 7 68 65 6A 5B 9CC - e E43 F08 F46 F81 G78 F20 G76 E40 C70 F19 G84 F74 F37 F22 E35 7 6B 6A 7 68 63 6A 7 6A 68 EB 7 EA 68 7 i

~ '

C11 F56 F27 C69 F68 F48 F29 C66 F2B F34 F50 G75 F32 F58 012 7 7 7 6A 7 6B EB 6A 6B 6B 7 6A 7 7 7

~

01" C39 C53 F25 G80 F82 F40 F10 F35 F86 G51 F04 G60 C40 G09 5B 7 68 7 6A 7 68 7 EB 7 EA- 7 6B 7 5B Ef5 G37 FS3 G74 Foi G63 F53 Ci7 F54 C79 F23 G83 FG4 036 E61 7 63 6B 7 6A 7 EB 7 (A 7 68 EB -7 G27 F49 F36 C49 F02 CS2 F79 C49 Fis CSS F33 F66 C21 )

SB 7 68 68 7 6A 63 6A 7 6B 68 7 5B I 13 1 E69 001 F65 77 3 C50 F26 F42 F06 C56 F85 F61 C15 E76 i SW 7 7 7 6B EA 6B 7 7 7 5B 14-Esa C28 G33 C35 F16 r55 C29 G41 C23 E73 r._5_ 7 53 7 7 5B 7 7 5B 15 j E66 G06 G05 E34 G19 G18 E64 j 00 1

.E nto

'1 R R , RECION IDCCIF*ER

D :D : rVEL ASSDGLY IDFMIi! CATION Region # Assemblies Enrichment SB 21 4.5 6A 32 4.2 6B 56 4.5 7 84 4.4

l Page 10 of 13

-l 1

l Figure 2 i

I incore Power Distribution - 30%

Millstone Unit 3 - Cycle 5 l

i R P N M L K J H G F E D C B A I 353 775 710 413 709 785 363 2 301 674 %3 1161 874 720 871 1147 964 690 306 i

3 3N 894 935 1029 1251 957 977 957 1222 1013 947 900 3N l 4 684 938 1057 1277 1136 1307 .1141 1313 1123 1268 1054 940 678 5 362 %7 1015 1270 1168 1411 1290 1430 1288 1400 1160 1265 10I5 951 352 ,

l 6 802 1166 1232 1131 1409 1258 1385 1212 1392 1260 1411 1114 1221 1117 758 7 716 881 971 1328 1296 1377 1180 1324 1893 1391 12d2 1285 945 852 693 8 402 712 993 1155 1439 1203 1312 900 1331 1210 1424 1125 %5 711 412 9 690 862  % 7 1317 1282 1372 1175 1318 1173 1372 1273 13N 950 871 711  ;

l 10 748 1123 1236 1098 1366 1236 1381 12N 1365 1249 1402 1126 1229 1156 770 'j 11 345 941 980 1234 1130 1377 1278 1428 1280 1402 1160 1261 1002 952 350 l l

12 674 900 1025 1233 1100 1301 1139 1308 1127 1268 IN9 924 678 13 292 856 9N 987 1221 %2 989 964 1242 1027 944 895 302 14 291 665 940 1128 862 709 860 1153 972 697 307 15 348 758 695 403 694 768 357 Legend: Measured FoH Scale: x 0.001

l ..

Page 11 of 13 Figure 3 Incore Power DistribuUon - 75%

- Millstone Unit 3 - Cycle 5 R P N M L K J H G F E D C B A I 364 753 697 411 711 784 374 2 325 703 %8 1114 855 710 866 1133 980 734 328 3 331 947 992 1043 1227 944 %I 946 1212 1045 1018 939 315 4 719 997 1199 1293 1118 1263 1114 1280 1116 1292 11 % 987 6%

5 370 978 1043 1301 1171 -1375 1250 1382 1253 1364 1138 1281 1042 %7 366 6 789 1147 1233 1127 1376 1224 1344 1192 1355 1225 1360 1096 1208 1107 765 7 710 873 %8 1291 1258 1343 1181 1338 1181 1346 1251 1250 937 846 697 8 408 711 978 1120 1383 1185 1337 1030 1338 1187 1381 1099 954 712 421 9 687 851 947 1278 1243 1343 1189 1344 1170 1336 1246 1274 944 862 714 10 735 1086 1203 1110 1353 1219 1359 1195 1343 1214 1360 1115 1214 1127 763 11 34 7 923 1023 1284 1140 1349 1242 1394 1258 1362 1168 12 % 1043 937 353 {

12 684 937 1171 1255 1087 1269 1126 1291 1118 1308 1203 982 689 13 312 893 948 997 1189 94 6 981 959 1222 1054 1016 948 318 14 311 685 935 1096 854 711 852 1117 973 729 328 15 350 743 688 407- 687 756 366 l Legend: Measured FM Scale: x 0.001

Page 12 of 13 Figure 4 Incore Power Distribution - 90%

Millstone Unit 3 - Cycle 5 R P N M L K J H G F E D C B A 1 363 765 707 419 712 781 373 2 325 702 966 1129 864 720 867 1129 972 721. 331 3 329 943 985 1041 1224 944 %3 947 1207 1034 1000 948 328 4 713 989 1192 1288 1111 1263 1105 1270 li15 1295 12N 994 710 5 370 972 1034 1290 1157 1356 1237 1468 1239 1365 i168 1299 1037 %2 362 6 789 1142 1221 1117 1358 1210 1332 1181 1342 1223 1375 1111 1209 1107 757 7 714 874 %3 1287 1246 1331 1168 1329 1178 1342 1242 1763 944 856 698 8 411 715 976 1120 1380 1179 1323 1026 1335 1182 1373 1105 965 722 423 9 691 855 950 1282 1243 1335 1175 1331 1165 1330 1239 1277 951 874 716 10 741 1095 1203 1097 1337 1206 1348 1186 1334 1220 1369 1122 1215 1830 766 11 353 940 1005 1271 1140 1347 1245 1380 1244 1369 1177 1306 INI 947 356 12 697 950 1168 1262 1093 1273 1114 1278 1123 1321 1218 999 707 13 316 9N 956 1010 1202 952 974 957 1228 1058 1013 959 331 14 315 690 938 1099 865 711 857 1137 981 727 334 15 352 746 692 409 695 770 369 Legend: Measured FL\H Scale: x 0.001

1 s

I Page 13 of 13 Figure 5 incore Power Distribution - 100%

s Millstone Unit 3 - Cycle 5 R P N M L K J H G F E D C B A 1

362 749 692 414 702 771 374 2 317 694 970 1131 858 715 865 1143 984 721 326 3

324 919 970 1034 1240 94 7 961 951 1235 1037 988 923 321 4

716 981 1195 1321 1123 1284 1102 1290 1116 1314 1191 977 705 5 371 983 1038 1316 1164 1375 1220 1369 1221 1372 1!$7 1311 1036 973 365 6

776 1149 1246 1123 1378 1191 1293 1150 1301 1195 1385 1109 1234 1121 752 7 700 869 %7 1305 1228 1293 1138 1324 1147 1307 1232 1283 950 857 694 8 409 715 978 1118 1380 1151 1323 1023 1335 1160 1384 1105 964 720 421 9 684 857 960 1298 1219 1292 1144 1312 1145 1303 1231 1303 960 872 706 10 740 1117 124I I144 1353 1183 1309 1163 1307 1208 1390 1132 1255 1148 761 11 357 956 1018 1298 1141 1360 1226 1390 1236 1383 1188 1341 1054 974 364 12 700 945 1168 1284 1096 1292 1117 1305 1129 1363 1227 989 711 13 314 889 947 1009 1224 952 974 962 1257 1062 1007 939 325 14 314 691 950 1113 855 711 857 1145 992 729 330 15 353 738 685 108 687 759 370 Legend: Measured F&i Scale: x 0.001 1

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