B15368, Startup Test Rept Cycle 6

Startup Test Rept Cycle 6

ML20092J385
Person / Time
Site:	Millstone
Issue date:	09/30/1995
From:	Miller D NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B15368, NUDOCS 9509220099
Download: ML20092J385 (14)

Text

-

1

"') Northeast 107 seiden street. neriin, cT 06037 s, .,,,,, m 3,, ,

y Utilities System P.O. Box 270 Ilartford, CT 06141-0270 (203) 665-5000

+

' September 12, 1995 Docket No. 50-423 B15368 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Start-Up Test Report for Cvele 6 Millstone Unit No. 3 entered Mode 1 on June 6, 1995, and the Cycle 6 startup test program was completed on June 23, 1995, 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 Mr. Jeffrey Camp of Millstone Unit 3 Technical Support, at (860) 447-1791, extension 6076.

Very truly yours, NORTHEAST NUCLEAR EN GY COMPANY f

f DIN DIl D. B. Millef, Jr.

Senior Vice President - Millstone Attachment cc: T. T. Martin, Region I Administrator V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 k).$Ob23 I

osam arv. im 9509220099 950930 l ,I gDR ADDCK 05000423 t/

PDR

, 4, .

1 .

. Docket No. 50-423 i

4 i 1 4

4 i 4

i

,i . i V

-l l .i 1' MILLSTONE NUCLEAR POWER STATION

UNIT NO. 3 '

STARTUP TEST REPORT .  !

' CYCLE 6 j 4 ,

a i-d a r

i i

Is ,

i t .j i

September 1995 -

i F

h t- i 6

A -

4

[

t I

I

+

t-9 8 4

I

Page 2 of 13 LNDEX P

1.

SUMMARY

3

2. INTRODUCTION 3

3. LOW POWER PHYSICS TESTING RESULTS 4 3.1 Critical Boron Concentrations 4

• 3.2 Isothermal / Moderator Temperature Coefficients 5 3.3 Control Rod Reactivity Worth Measurements 6  ;

4. POWER ASCENSION TESTING RESULTS 6 4.1 Power Peaking and Tilt Measurements 6 4.2 Boron Measurements 7 4.3 Doppler Only Power Coefficient 7 4.4 Reactor Coolant System Flow 8 4.5 Power Distribution 8

5. REFERENCES 8 I

_ _ . _ . . _ . _ . - _ . - - . . . _ _ . _ _ _ _ _ _ _ . . = _ _ ._ _ _ . _ _ _

i 4 . Page 3 of 13 e

' 1.

SUMMARY

Low Power Physics Testing and Power Ascension Testing for Millstone 3, Cycle 6

- identified no unusual situations or anomalies. All parameters were determined to be within their acceptance criteria. All Technical Specification limits were met.  ;

b

2. INTRODUCTION The Millstone 3, Cycle 6 fuel reload was completed on May 19,1995. The attached core loading pattem (Figure 1) shows the final core configuration. ' Eighty-four (84) new ,

Region 8 fuel assemblies were inserted into the core. Major changes from the Millstone

- 3, Cycle 5 core design are: ,

• Addition of 2 thimble plugs and 2 new unactivated secondary source assemblies such that all locations contain an insert. Also, the locations of the two activated secondary

sources was changed.

• Decrease the number of Vantage EH fuct assemblies from 172 to 168. Vantage SH

! fuel assemblies are Region 6,7 and 8. Region 4 fuel assemblies were loaded on the core periphery where Region 6 fuel assemblies would normally have gone. This is because there were insufficient numbers of Region 6 fuel assemblies available with rotated grids to put on the core periphery.

• 1 leaking fuel rod in a Region 7 fuel assembly was replaced with a stainless steel filler

rod.

• 1 top nozzle was replaced on a fresh Region 8 fuel assembly due to a manufacturing <

problem identified prior to fuel loading.

Subsequent operational and testing milestones were completed as follows:

initial Criticality June 3,1995 l Low Power Physics Testing completed June 6,1995 Main Turbine On-Line June 7,1995 30% Power Testing completed June 7,1995 1

j 75% PowerTesting completed June 10,1995 ,

4 1

100% Power Testing completed June 23,1993 Cycle 6 operation is with 193 Westinghouse manufactured fuel assemblies. The

Safety Analysis is provided by Westinghouse.

4 i-l i

_ _ _ ._._ _ .__ _ _ _ _ - _ . . _ _ _ _ . . _ _ _ . _ _ . . _m

, j

\

\

Page 4 of 13

3. LOW POWER PHYSICS TESTING RESULTS I l

j Low Power Physics Testing was performed at a power level of <5 x 10% power to i

avoid nuclear fuel heating effects. l J

j- 3.1 Cntical Boron Concentrations l Critical Boron Concentration (CBC) was measured at two different Rod Control j Cluster Assembly (RCCA) configurations; at All Rods Out (ARO) and with i j RCCA Control Banks D, C, B and A inserted. l The CBC measured with Control Bank D at 204 steps was 2178 ppm. Adjusted to All Rods Out, the CBC was 2181 ppm. j i . 1 Therefore, j j

f Measured CBC at BOL-HZP-ARO = 2181 ppm l j Predicted CBC at BOL-HZP-ARO = 2193 Dom

Difference = 12 ppm  !

J l The Acceptance Criteria isi 75 ppm.  !

Acceptance Criteria met? Yes I t

i The CBC measured with Control Banks D, C, B, inserted and A at 28 steps was i 1644 ppm. Adjusted to All Rods in (ARI), the CBC was 1648 ppm.

I The predicted CBC for Control Banks A, B, C and D inserted is 1658 ppm, therefore the difference is; i

Predicted CBC at BOL-HZP-ARI = 1658 ppm Measured CBC at BOL-HZP-ARI = 1648 con 1 1 Difference = 10 ppm j The Acceptance Criteria is175 ppm

Acceptance Criteria met? Yes ]

$ Measured CBC at BOL-HZP-ARO = 2181 ppm i Measured CBC at BOL-HZP-ARI = 1648 Dom

Difference = 533 ppm Predicted CBC at BOL-HZP-ARO = 2193 ppm Predicted CBC at BOL-HZP-ARI = 1658 ppm Difference = 535 ppm i

}

m.v -a - - -w .,

4 Page 5 of 13 Therefore, the difference between the predicted and measured values is:

l

. Predicted Difference in ARO and ARI CBCs = 535 ppm 1 Measured Difference in ARO and ARI CBCs = 533 Dom Difference = 2 ppm There is no acceptance criteria on this value.

3.2 Isothermal / Moderator Temocrature Coefficients The isothermal Temperature Coefficient (lTC) was measured with all RCCA banks withdrawn (ARO). The Moderator Temperature Coefficient (MTC) was then calculated.

ARO ITC Measurement:

The measured ITC value with Control Bank D at 204 steps, an average Reactor Coolant System (RCS) temperature of 556 F, and an RCS Boron Concentration of 2178 ppm, was-0.0921 pcmFF. 1 Comparing the measured ITC to the predicted ITC yields:

Measured ITC at BOL, ARO = -0.0921 pcmFF  :

' Predicted ITC at BOL, ARO = -0.01 ocmFE 4

Difference = 0.0821 pcmFF The Acceptance Criteria is -0.01 pcmFF 12 pcmFF Acceptance Criteria met? Yes All Rods Out MTC Determination The MTC was calculated by subtracting the design Doppler Temperature Coefficient (-1.74 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:

-0.0921 pcmFF - (-1.74 pcmFF) = 1.6479 pcmFF Comparing the measured MTC to the predicted MTC yields:

Calculated MTC at BOL, ARO = 1.6479 pcmFF Predicted MTC at BOL, ARO = 1.72 pcmFF Technical Specification Acceptance Criteria is MTC < +5 pcmFF Acceptance Criteria met? Yes

4 .

Pa9e 6 of 13 f

' 3.3 Control Rod Reactivity Worth Measurements Reactivity worth measurements were performed Individually on Control Banks l D, C, B, and A. The results of the measurements were:

Jndividual Bank Worth Measurements (by dilution)

Measured Predicted Delta  % Difference  ;

Hank Worths (ocm) Worths (ocm) (EE) ((M-P)/P)

Control D 472 483 -11 -2.3 i Control C 1121 1108 13 1.2 .i Control B 712 740 -28 -3.8 l Control A 1059 1039 20 1.9 Total 3364 3370 6 0.18

]

The Acceptance Criteria for the Total Worth of the Control Banks inserted is110 % of the predicted total worth. The Acceptance Criteria for any i Individual Control Bank is the greater of either1100 pcm or115% of l the predicted Bank worth.

Acceptance Criteria met? Yes Measurement of Control Rod Reactivity Worth also verified the Technical i 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. i The measurements of these parameters, including uncertainty, were:

HEAT FLUX HOT CHANNEL FACTOR - FQ(Z)

Above Midooint Peak Below Midooint Peak l

Measured FQ(Z) Measured FQ(Z) Max Incore Power Level FQ(Z) Limit FQ(Z) Limit Tilt l l

30% 1.895 6.077 1.265 6.543 1.010 60% 1.684 3.061 1.507 3.296 1.005 75% 1.567 2.470 1.599 2.660 1.004 100 % 1.550 1.830 1.650 1.971 1.003 l

i Page 7 of 13 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FNDH Power Level Measured FNDH FNDH Limit 30 % 1.50 1.86 60% 1.48 1.72

' 75% 1.46 1,66 100 % 1.45 1.54 4.2 Boron Measurements At 100% power,1599 MWD /MTU, Control Bank D at 222 steps and Equilibrium Xenon, the measured RCS Boron Concentration, Cg, was 1632 ppm.

Measured Cg, adjusted to ARO = 1632 ppm Predicted Cgat 100% power, ARO, 1599 MWD /MTU, Equilibrium Xenon = 1633opm Difference = -1 ppm Subsequent RCS Boron measurements made at 100% power,2530 MWD /MTU, Control Bank D at 223 steps and equilibrium xenon, yielded the following results:

= 1673 ppm Measured Ce Predicted Cg at 100% power, ARO, 2530 MWD /MTU, Equilibrium Xenon = 1660 com Difference = -13 ppm The Acceptance Criteria is 1166 ppm (t 1000 pcm)

Acceptance Criteria met? Yes 4.3 Qpooler 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 99.0%, an average RCS temperature of 591.4 F, and an RCS Boron Concen-tration of 1586 ppm. (Note: average RCS temperature is not loop average but core average.)

Average Calculated value,lPCml = -1.08 0F/%

Predicted value, IPCpl = 935. Elh Difference = 0.23 0F/%

The Acceptance Criteria is an absolute difference of <0.5 0F/% between PCmand PCp.

Acceptance Criteria met? Yes

4

! Page 8 of 13

4.4 Reactor Coolant System Flow a

RCS flow was measured at 100% power as verification of acceptable

! flow. Measured RCS flow at 100% power was 391,358 GPM.

The Acceptance Criteria is that RCS flow, adjusted for venturl fouling, must be greater than 371,920 GPM.

Acceptance Criteria met? Yes 4.5 Power Distribution Power Distribution maps are shown for 30%,60%,75% 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 1

value.

- Acceptance Criteria met? Yes

5. REFERENCES 5.1 In-Service Test 3-95 001, Cycle 6 Low Power Physics Tests t

5.2 In-Service Test 3-95-019, Cycle 6 Power Ascension Tests 5.3 Westinghouse Nuclear Design Report - Cycle 6 (WCAP 14335) i 5.4 ANSI /ANS - 19.6.1 (1985) Reload Startup Physics Tests For Pressurized Water

, Readom L

l

f i *  !

, Figura 1 l . Core Imeding Patters i Page 9 of 13 Milletone Unit 3 - Cycle 6 i

) A P a a a o s 1

y { f F D C s A i

es as 7 7 7 es es 1

D7o Des oss oss oes D73 D6s i .a 7 e e e e e e e , ..

l 8 D7s ois son saa slo sie sia Es1 soa oos De4 1 as , . e , , e , , e e , de D7s oss s2o see old ont s8s o43 013 s71 sal o24 Deo l 7 e e 7 0 7 e 7 e 7 e e 7 j oos m36 aso oss sei see ass est uds odd see s27 0o7 1 as e e 7 7 e 7 7 7 e 7 7 e e es

! D7e ses ass oss os7 sei ses es7 ovs use o7e oss ass ses Dse

~'

es e 7 e e 7 e 7 e 7 e e 7 e as

~

! g D62 sas aos uds see o23 udi o17 s76 o37 s74 566 ois see Die 1 7 e 7 7 7 e 7 e 7 8 7 7 7 e 7 oss mis oss oss a7s ses e47 sea seu

~'

s7 ofs osa eso sia o74 l

. 7 e e e 7 7 e 4. e 7 7 e e . 7

' so* -e j

eso s17 ado u7e ove not use Ds1 as son osa sta as7 sas oss 7 e 7 7 7 e 7 e 7 e 7 7 7 e

• 7 a

_s "'

e64 als os7 o7s oes s7s oss u?7 osi ses ee2 ois one nos 001 i

! as e 7 e e 7 e 7 e 7 e e 1 e as

~

! Dss uns oos us2 F34 o36 ses ois us7 o32 a47 ass ole ass D6e 5

es e e 1 7 e 7 7 7 e 1 7 e e as a - 11 I

D74 so? saa osa e7s s7o o71 o77 os4 aso oss oss s7s 501 D11 5

7 e e 7 e 7 e 7 e 7 e s 7 l ood als use eso saa oss nas osi use oss sss saa eso as 7 e . 7 7 . 7 7 e e 7 es i ,,

07 one ass saa ola oss ust est ett neo saa ont Det l

j es 7 e e e e e e e 7 as u l nos oss see ses s1s nas all ust son oos D77 '

I as as 7 7 7 as es

, is .'

l M6 M1 N6 odo M2 Ms M4 i i -

o*

j s mam l

• i

! a asexcu Desernsa

• Reconstituted Assembly

In rush AssausLY zonstzrscarzcer l l

! Region # Assemblies Enrichment 4A 1 3.5

4B 24 3.8 ,

l 7 84 4.4 '

! 8 84 4.8 i

l i I

a l

L. I

i Page 10 of 13 Figure 2 incore Power Distribution - 30%

Millstone Unit 3 - Cycle 6 R P N M L K J H 'G F E D C B A 1 273 363 499 536 493 351 263 2 238 618 988 1044 1242 1264 1223 1026 1034 663 249 3 251. 712 1082 1250 1293 1239 1333 1237 1301 1240 1122 709 241  !

4 663 1121 1105 1134 1317 1095 1214 1095 1285 1122 1097 1094 637 5 271 1052 1262 1143 1156 1336 1120 1059 1089 1279 1123 1118 1224 1034 270 6 352 1051 1343 1328 1330 1346 1315 1200 1271 12 % 1289 1314 1317 1052 359 7 495 1249 1263 1133 1131 1303 1111 1168 1101 1291 1116 1137 1255 1247 494 8 549 1289 1359 1251 1085 1208 1165 795 1166 1212 1087 1263 1359 1278 540 9 512 1269 1269 1121 1112 1285 1085 1156 1104 1299 1121 1125 1251 1249 505 10 365 1055 1363 1310 1307 1314 1267 1193 1281 1321 1305 1305 1304 1016 352 11 265 1014 1252 1128 1130 1299 1097 1061 1094 1288 1116 1111 1221 1012 265 12 634 1062 1099 1123 1303 1107 1226 1101 1289 1109 1082 1066 625 13 241 691 1084 1231 1306 1234 1322 1216 1278 1218 1101 703 238 14 243 631 1010 1026 1222 1241 1207 1016 1032 659 246 15 256 352 489 522 480 354 271 Legend: Measured Assembly Powers Scale: x 0.001

i Page 11 of 13 ,

Figure 3 Incore Power Distribution - 60%

Millstone Unit 3 - Cycle 6 h R P N M L K J H G F E D C B A ,

1 283 370 501 534 493 354 271 2 249 613 942 1017 1203 1218 1194 1013 1032 680 264 4

3 266 737 1092 1236 1286 1213 1297 1215 1301 1251 1152 733 251 4 673 1141 1225 1147 1280 10 % 1200 1094 1273 1150 1222 1116 647 5 277 1035 1245 1159 1156 1307 1119 1065 1091 1256 1120 1138 1237 1043 288 6 357 1025 1304 1300 1303 1312 1306 1205 1274 1276 1275 1299 1301 1049 377 7 488 11 % 1224 !!!8 1119 1287 1129 1211 1135 1298 1119 1140 1240 1233 509 8 544 1240 1318 1228 1078 '1202 1200 934 1217 1217 1088 1250 1334 1260 556 9 513 1228 1247 1114 1110 1278 1105 1197 1126 1289 1119 1120 1235 1243 524 10 -374 1034 1349 1284 1285 1291 1265 1196 1269'1294 1293 1292 1293 973 353 11 270 987 1229 1150 1138 1283 1095 1066 10 % 1282 1125 1136 1220 985 270 12 642 1059 1223 1146 1279 1099 1214 1099 1282 1121 1198 1075 630 13 253 706 1107 1238 1287 1215 1298 1197 1268 1210 1120 730 251 14 254 645 1004 1016 1197 1207 1177 1017 1031 673 262 15 265 366 498 527 486 371 284 Legend: Measured Assembly Powers Scale: x 0.001 i

Page 12 of 13 Figure 4 ,

incore Power Distribution - 75%

Millstone Unit 3- Cycle 6 l f

R P N M L. K J H G F E D C B A l 1 285 372 500 533 493 358 274 2 250 617 948 1024 1201 1215 1188 1009 1025 672 263 3 266 738 1088 1240 1279 1209 1293 1207 1277 1232 1138 731 253 ,

i 4 674 1140 1218 1150 1284 1095 1203 1091 1270 1140 1216 1113 648 5 281 1037 1243 1153 1156 1306 1121 1071 1098 1265 1125 1138 1228 1034 284 i

6 361 1028 1299 1297 1300 1317 1312 1214 1283 1285 1283 1292 1286 1038 371 '

7 491 1197 1218 1114 1118 12 % 1136 1223 1139 1304 1126 1135 1231 1220 504 8 541 1231 1305 .1226 1080 1216 1215 944 1223 1223 1094 1248 1327 1248 551 .

9 509 1219 1231 1113 1113 1286 1115 1207 1130 1295 1122 1121 1233 1235 519 10 373 1030 1326 1282 1282 1291 1273 1204 1279 1301 1295 1294 1289 978 355 11 273 998 1227 1147 1136 1283 1099 1071 1101 1285 1127 1138 1222 990 271 12 649 1066 1221 1143 1277 1097 1213 1098 1285 1127 1204 1088 636 13 255 710 1109 1236 1281 1204 1288 1191 1266 1217 1131 738 255 14 256 648 1009 1014 1190 1201 1174 1012 1036 681 266 15 268 365 496 525 486 368 285 l

Legend: Measured Assembly Powers Scale: x 0.001 i

l

)

I i

. i

~

, Page 13 of 13 Figure 5 Incore Power Distribution - 100%

Milktone Unit 3 - Cycle 8

! R P N M L K J H G F E D C B A 1 287 375 499 531 492 363 277 2 258 635 976 1032 1192 12 % 1181 1013 1025 668 267 3 269 744 1103' 1236 1261 1196 1279 11 % 1271 1225 1132 739 261 4 672 1138 1216 1145 1279 1085 11 % 1085 1271 1138 1213 1118 655 1

i 5 283 1037 1236 1147 1150 1299 1122 1075 1102 1269 1130 1137 1217 1025 281 l 6 367 1030 1288 1288 1295 1315 1318 1224 1289 1287 1285 1290 1278 1031 368 ,

7 4% 1193 1204 1106 1116 1301 1143 1235 1146 1307 1126 1130 1223 1211 498 8 536 1217 1288 1220 1081 1224 1225 955 1231 1229 1095 1245 1320 1240 544 i

l 9 504 1204 1209 1106 1113 1289 1121 1216 1143 1305 1123 1119 1225 1224 513 ,

i' 10 372 1027 1301 1280 1281 1291 1274 1209 1288 1312 1299 1298 1288 1001 364 11 278 1014 1229 1146 1134 1281 1097 1073 1104 1293 1132 1143 1225 1013 278 12 659 1091 1211 1135 1267 1091 1211 1097 1293 1134 1212 1106 653 1 13 261 727 1110 1221 1266 1193 1280 1188 1268 1218 1134 746 263 4

14 262 652 1006 1009 1182 1194 1171 1009 1034 680 269 15 272 366 494 524 486 368 284 Legend: Measured Assembly Powers Scale: x 0.001 6

P 1

i I