Text

Cycle 4 Startup Test Rept
	ML19340B629
Person / Time
Site:	FitzPatrick
Issue date:	11/07/1980
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
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ML19340B628	List: ML19340B627; ML19340B629;
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	NUDOCS 8011110492
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-CYCLE 4 STARTUP TEST REPORT E

Cycle 4 operations commenced August 8, 1980 with the withdrawal of the fi rs t control rod. The startup test program was conducted from July 18, 1980 through October 25, 1980, in accordance with Reactor Analyst Procedure (RAP) 7.1.17,. titled Refuel Startup Program, Revision 3

When reference is made to values of core thermal power and core flow, these are nominal values rather than exact percentages.

CONTROL ROD ORIVE TESTS Control rod drive coupling checks were satisfactorily completed on August 17, 1980.

In addition, the insert and withdrawal times for rods i

were checked and_ adjusted as required.

1 Prior to reaching.40% rated core thermal power, control rod scram time testing was conducted in accordance with RAP 7 310 titled Control Rod Scram Time' Evaluation, Revision ~3 This test requires that each control rod be scrammed from position 48 (full out) with reactor pressure

> 950 psig. The results of these tests are tabulated below.

Results:

Average of Control Rod Notch Position Technical Specification 137 Rods Observed (Seconds)

(Seconds) 46 0.338 0.312 38 0.923 0.719 24-1.992 1.452 04 3 554 2.569 The average of the scram insertion times for the three fastest i

operable control rods 'for all groups of four control rods a in two-1 -two array were less than the maximum allowed by the technical specifications.

80.11110

. N

SHUTDOWN M ARGIN DEMONSTRATION A shutdown margin (SDM) demonstration was performed August 8, 1980 in accordance with Reactor Analyst. Procedure 7 3 9 Revision 2.

The required SDM was 0.38% a k + R + temperature defect.

The fuel vendor has calculated that the value of R is 0.15%. After calculating the temperature defect and uncertainty, the required SDM was determined to be 0.78% ak.

Sufficient control rods were withdrawn to demonstrate a SDM cf 0.80% a k.

The calculated SDM based on the in-sequence critical dati. was 1.69%.

INSEQUENCE CRITICAL Based on data supplied by the fuel vendor, the first critical was estimated to be notch 10 of the eleventh rod of group 2 with a reactor water temperature of 145 F.

The at ual data was group 2, rod 14, notch 08, reactor water temperature 155 F, period 89 seconds, indicating good agreement between predicted and actual data.

REACTIVITY ANOMALY CHECK A comparison of the expected and actual control rod density was performed at 100% core thermal power (CTP) and 100% rated core flow.

The control rod inventory was 418 notches which was in close agreement.

with the predicted value of 421 notches. The 1% reactivity boundaries were 80 to 720 notches.

POWER DISTRIBUTION MEASUREMENTS Core power distribution was monitored throughout the startup using the process computer.

Following significant changes in control rod pattern and power level, a complete power distribution measurement was '

performed using the Traversing in-core Probe (TIP) system.

Core parameters were maintained within technical specification limits.

TIP REPRODUCIBILITY Four successive traces were run in the common channel for each TIP mach ine. Computer reduction of the data calculated a random noise of 1.46% and a total uncertainty of 3.14%, well below the 8.7% assumed by the vendor in the statistical analysis performed for the licensing topical report (NEDG-24011-P-A)'for the reload fuel application.

l l

L CORE POWER SYMMETRY Core ' power symmetry was : checked at 25%, 50%, 75% and 100% CTP.

-Mirror symmetricLfuel assemblies checked at 100% CTP and 100% core-f flow using the. process computer indicate a maximum difference of less l

than 10%.

i

. CORE LOAD NG_.

A copy of the final core loading is attached as Figure 1.

Irradiated fuel returned to the core -is' designated EA or LJ5 or LJ6 or LJB. There were 160 new fuel assemblies, designated LJM,:(136 bundles with 2.82 w/o U-235, 24 bundles with 2.65 w/o~U-235) loaded during the refueling outage.

The new fuel was of the P8 x 8 R design with an active fuel' length of 150-inches and received 100 mil channels.-

+

Figures 2a - 2d show the approximate irradiated bundle average l

exposure following refueling. A zero indicates a new fuel assembly.

The new fuel assemblies contain burnable poison in the form of GdO. The concentration and location is proprietary to the fuel vendor.

3 Figure 3 shows the rod sequence control system (RSCS) designations i

for the A and B rod withdrawal sequences.

During the refueling operation, each fuel move was checked by an individual, other than the" operator performing the move, and verified independently by a third individual.

Two lines of communication were established between the refuel bridge and the control room. -Following 4

loading, a core verification was conducted.(and video-taped and examined later by quality assurance personnel) to verify the correct placement t

and orientation of each assembly.

ADDITIONAL TESTS 1.

Tests were performed in accordance with RAP 7.1.17 and F-ST-5C to verify that.there is approximately one decade overlap between the

,~

source range. monitor and intermediate range monitor (IRM) systems, and between the'IRM and average ' power range monitor (APRM) systems.

2.

Reactor core isolation _ cooling and.high pressure coolant injection flow rate tests were performed in accordance with F-ST-24C and F-ST-4B and demonstrated compliance with the technical specifications.

3 Both the rod worth minimizer and rod sequence control system functioned

[

properly.during the startup ' test program.

4.

Since some TIP tubing were replaced, t' e TIP alignment and logic h

limits were ' checked and adjusted as required.

5 New computer. software was installed during the outage. -Extensive testing was performed prior-to and during the startup in accordance-with the' vendor's recommendations.

6.

The APRM system was 'calibrat3d to core thermal power and satisfactorily tracked power. changes.

7

. Heat balances were calculated manually and used to verify the process computer calculations.

8.

Process computer calculations of fuel assembly parameters, maximum average planar ' linear heat generation rate, minimum critical power ratto, and maximum fraction limiting power density compared satisfactorily with results obtained using of f-line computer calculations.

9 RAP 7.3.18, " Pressure Regulator Tests," was perforned satisfactorily when it was verified that an induced pressure transient of 10 psi was contro113d by the electro-hydraulic control system pressure regulator.

11 addition, trans fer f rom the primary to back-up pressure regulator was demonstrated following a simulated failure of the primary regulator.

I 10.

RAP 7.3.7, " Core Flow Evaluation and Indication Calibration," was performed at 75%, 89% and 96% CTP.

The res01ts of the September 12, 1980 tests at 96% CTP showed a calculated core flow of 72.2 Mlb/hr while the indicated. core flow was 77.1 Mlb/lir.

After adjustment of the amplifier gains, the calibration was repeated September 16, 1980. Calculated core flow was 75.3 M1b/hr with an indicated core flow of 76.4 M1b/hr.

i

1 G8-C6-83 FIGURE 1 ISER/ISRBB FUEL SERIAL NUMBERS 1

EA EA EA EA EA EA EA EA EA EA 52 156 538 598 219 292 252 181 478 542 284 EA LJB LJM LJB LJM LJB LJB LJM LJB LJM LJB EA 59 293 378 476 381 456 319 358 459 498 452 386 236 EA EA EA LJB EA LJB EA LJB LJM LJM LJB EA LJB EA LJB EA EA EA 48 412 528 193 348 221 37? 213 411 585 565 397 270 389 179 334 223 543 519 EA LJB LJM LJB LJM LJB LJM LJD LJM LJ5 LJ5 LJM LJB LJM LJB LJN LJB LJM LJB EA 46 399 316 469 284 584 352 537 353 4?7 336 358 494 355 542 364 591 389 451 344 351 EA LJB LJB LJ6 LJB LJ5 LJM LJ5 LJB LJ6 ! JM LJM LJ6 LJB LJS LJM LJ5 LJB LJ6 LJB LJB EA 44 275 398 391 271 354 341 514 337 322 278 530 547 197 356 349 524 362 376 286 388 338 381 EA LJM LJ6 LJM LJ5 LJM LJ6 LJM LJ5 LJN LJ6 L I6 LJM LJ5 LJM LJ6 LJM LJ5 LJM LJ6 LJN EA 42 5366462 274 484 338 525 283 561 339 522 273 28b 583 365 582 297 563 357 573 287 458 492 EA LJB LJB LJ5 LJM LJ5 LJB LJ6 LJB EA LJM LJM EA LJB LJ6 LJB LJ5 LJM LJ5 LJB LJB EA 48 231 336 335 325 585 342 342 278 340 268 581 689 137 351 284 343 361 539 349 279 327.178-EA LJB LJM LJ5 LJM LJ5 LJN LJ5 LJN LJ5 LJM EA EA LJM LJ5 LJM LJ5 LJM LJ5 LJN LJ5 LJN LJB EA 38 152 391 558 335 554 326 559 333 528 344 556 247 226 578 355 598 354 562 343 546 352 598 359 165 EA LJB EA LJB LJM LJ6 LJB LJ5 LJM EA LJB EA LJM LJM EA LJB EA LJM LJ5 LJB LJ6 LJM LJB EA LJB EA 36 147 401 157 361 557 282 333 332 577 257 347 162 578 593 176 371 237 552 359 331 296 681 312 217 383 259 EA LJM LJB LJM LJ5 LJM LJ6 LJM EA LJM LJS LJM LJ5 LJ5 LJM LJ5 LJM EA LJM LJ6 LJM LJ5 LJM LJB LJM EA 34 583 471 382 475 327 495 277 564 189 548 338 518 328 345 599 358 545 735 559 291 555 346 535 395 467 489 EA LJB EA LJB LJB LJ5 LJB LJ5 LJB LJ5 LJB LJ6 LJB LJB LJ6 LJB LJ5 LJB LJS LJB LJ5 LJB LJB EA LJB EA 32 168 492 294 293 362 329 286 334 335 347 291 288 325 299 294 314 368 396 353 321 351 298 367 142 387 246 EA LJM LJB LJM LJ6 LJM EA LJM EA' LJM LJ6 LJN EA EA LJM LJ6 LJM EA LJN EA LJM LJ6 LJM LJB LJM EA 38 242 468 398 492 275 551 298 498 192 476 281 489 224 286 493 295 592 146 572 141 566 298 533 489 463 194 EA LJB LJM LJ6 LJM LJ6 LJM EA LJM LJ5 LJB EA LJ6 LJ6 EA LJB LJ5 LJM EA LJM LJ6 LJM LJ6 LJM LJB EA 28 271 392 593 272 579 279 569 286 516 331 383 244 276 289 214 329 348 499 158 526 293 667 285 511 337 273 EA LJB LJM LJ6 LJM LJ6 LJM EA LJM LJ6 LJB EA LJ6 LJ6 EA LJB LJ6 LJM EA LJM LJ6 LJM LJ6 LJM LJB EA 26 239 387 571 319 541 382 56s 245 548 246 297 225 366 319 188 318 263 598 171 488 31L 527 323 595 295 284 EA LJM LJB LJM LJ6 LJM EA LJM EA LJM LJ6 LJM EA EA LJM LJ6 LJM EA-LJM EA LJM LJ6 LJM LJB LJM EA 24 185 474 398 683 305 485 148 567 183 488 386 688 211 219 519 314 597 134 692 258 481 326 586 384 464 289 EA LJB LA LJB LJB LJS LJB LJ5 LJB LJS LJB LJ6 LJB LJB LJ6 LJB LJ6 LJB LJ6 LJB LJ6 LJB LJB EA LJB EA 22 186 496 269 373 298 374 319 372 368 356 315 381 278 283 315 324 251 366 268 287 249 384 285 218 394 175 EA LJN LJB LJM LJS LJM LJ6 LJM EA LJM LJ5 LJM LJ6 LJ6 LJM LJ6 LJM EA LJM LJ6 LJM LJ6 LJM LJB LJM EA 29 552 472 399 694 373 592 394 587 295 589 367 491 258 259 499 252 536 265 538 318 60s 267 568 412 457 5s7 EA LJB EA LJB LJM LJ6 LJB LJ5 LJM EA LJB EA LJM LJM EA LJB EA LJM LJ6 LJB LJ6 LJN LJB EA LJB EA 18 296 494 197 374 586 299 292 379 583 238 317 296 549 517 266 289 233 518 262 329 313 515 330 264 413 177 EA LJB LJM LJ6 LJM LJ6 LJM LJ5 LJM LJ5 LJM EF.

EA LJM LJ6 LJM LJ6 LJM LJ6 LJM LJ6 LJN LJB EA 1

16 169 288 561 248 496 247 532 371 477 366 531 297 229 595 254 487 269 479 268 529 266 587 357 259 l

EA LJB LJB LJ6 LJM LJ5 LJB LJ6 LJB EA LJM LJM EA LJB LJ6 LJB LJ6 LJM LJ6 LJB LJB EA j

14 216 399 526 256 513 364 311 311 349 232 478 534 296 369 325 377 257 529 261 281 346 276 EA LJM LJ6 LJM LJ5 LJM LJ6 LJM LJ5 LJM LJ6 LJ6 LJN LJ6 LJN LJ6 LJM LJ6 LJM LJ6 LJM EA 12 493 453 398 483 368 695 298 594 369 576 367 322 553 255 589 312 588 256 482 321 466 512 EA LJB LJB LJ6 LJB LJ5 LJM LJ6 LJB LJ6 LJM LJM LJ6 LJB LJ6 LJM LJ6 LJB LJ6 LJB LJB EA

)

19 292 360 495 389 288 363 574 245 339 393 544 512 317 313 264 523 253 359 324 415 345 159 EA LJB LJM LJB LJM LJB LJM LJB LJM LJ6 LJ6 LJM LJB LJM LJB LJM LJB LJM LJB EA 98 419 296 454 355 686 282 596 378 618 244 265 575 294 596 332 486 363 461 375 313 EA EA EA LJB EA LJB EA LJB LJN LJN LJB EA LJB EA LJB EA EA EA 96 365 496 249 341'243 407 295 393 584 521 385 281 493 163 323 291 551 435 EA LJB LJM LJB LJM LJB LJB LJM LJB LJM lob EA I

94 278 396 455 388 473 372 328 465 392 468 498 198 EA EA EA EA EA EA EA EA EA EA 92 263 541 360 248 277 255 266 371 355 288 1

3 5

7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 n1 J

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________________1

R0D SEQUENCE CONTROL SYSTEM GROUP DESIGNATIONS A

A SEQUENCE 2

1 51 5

6 5

3 4

3 47 12 13 13 12 1

2 1

2 43 7

8 9

8 7

4 3

4

.y.

12 14 15 15 14 12 2

1 2

1 33 5

8 10 11

'to 8

l5 4

3 4

31 13 15 16 16 15 13!

1 2

27 6

9 11 10 11 9

6 3

4 3

4

'3 23 13 15 16 16 15 13 2

1 2

1 19 5

8 10 11 10 8

l5 3

4 3

15 12 14 15-15 14 12 1

2 1

2 11 7

8 8

7 4

3 4

07 12 13 13 12, 2

1 03 5

6 5

02 06 10 14 18 22 26 30 34 33 42 46 50 02 06 10 14 18 22 26 30 34 38 42 46 50 B SEQUENCE 1

2 1

51 5l 5

3 4

47 13 14 16 14 13 1

2 1

43 7

8 9

9 8

7 3

4 3

4 39 15 17 18 17 15 1

2 1

33 6

10 11 11 10 6

4 3

31 12 16 18 17 18 16 12 2

1 2

27 9

11 10 10 11 g

3 4

23 12 16 18 17 18 16 12 1

2 1

19 6

to 11 11 to 6

4 3

13 15 17 18 17 15 1

2 1

11 7

8 9

9 8

7 4

3 4

3 07 13 14 16 14 13 1

2 1

03 5

5 02 06 10 14 18 22 26 30 34 38 42 46 50 02 06 10 14 18 22 26 30 34 38 42 46 50 D

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Fig. 3

.

ML19340B629

Text

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