ML19257C641

Startup Test Rept,Cycle 7

ML19257C641
Person / Time
Site:	Vermont Yankee
Issue date:	01/18/1980
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML19257C639	List: ML19257C638 ML19257C641
References
NUDOCS 8001290531
Download: ML19257C641 (10)

Text

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STARTUP TEST REPORT VG MONT YANKEE CYCLE 7 INTRODUCTION:

Vermont Yankee Cycle 7 initial startup cormenced on November 3,1979 following a six week outage for annual refueling and maintenance related activities. Out of core wet sipping was performed on fourty-four (44) fuel assemblies discharged at the end of cycle 6A; one fuel assembly was found to be failed.

The core loading for cycle 7 consists of twenty (20) 8x8 (8D219) reinserts, 8 drilled and 12 not drilled, forty three (43) 8x8 (8D274) reconstituted assemblies from cycle 4, twenty-nine (29) 8x8 (8D274) additional assemblies from cycle 4, eighty-four (84) 8x8 (8D274) assemblies from cycle 5, thirty-six (36) 8x8 (8D274) assemblies from cycle 6, sixty (60) 8x8 (8DPB289) asse=blies from cycle 6, and ninety-six (96) non-irradiated (P8DPB289) prepressurized fuel assemblies. An as-loaded cycle 7 core map is included as Figure I. Details of the cycle 7 core loading are contained in the General Electric Document NEDE-25156 Aug. 1979, " Vermont Yankee Reload-6 Nuclear 7esign Report".

Shutdown margin testing was performed on October 13, 1979 and an In-Sequence Critical was performed on October 27, 1979 Startup commenced on November 3,1979 and steady-state full power conditions were reached on November 12, 1979 Control rod coupling verification and control rod scram testing were performed on November 20, 1979 through November 23, 1979.

The final core loading was verified by Yankee Atomic Electric Company and Vermont Yankee personnel on October 11, 1979 CORE VERIFICATION:

The final core loading was verified correct on October 11, 1979 Three separate criteria were checked.

1. Proper bundle orientation was verified by checking channel fastener orientation and assuring that fastener orientation agreed with that shown in Figure 3

2. Proper bundle seating was verified by following Vermont Yankee Procedure VYOP1411.

3 Proper bundle seating was 'terified by checking serial numbers of each bundle through the use of a video camere. This verification was recorded on video tape and was later independently reviewed and found to agree with the licensed core loading of Figure I.

PROCESS COMPUTER DATA CHECKS:

Process computer data shuffling checks were completed October 26, 1979 1829 032' 8 00 i29 0 S 3/

For the ten highest radial powers, the maximum overprediction was 3.5 percent while the maximum underprediction was 7.5 percent. The results of this cocparison are shown in Table 4.

TIP REPRODUCIBILITY AND TIP SYMMETRY:

TIP system reproducibility was checited in conjunction with the power distribution update performed on November 9, 1979 All three TIP system traces were reproducible within 5.05%

TIP sy= metry and total TIP uncertainty were calculated for three cets of reactor conditions. The total TIP uncertainties were calculated using the Yankee Atomic Electric code "TOTUNC". Two sets were actual plant data from power distribution updates done on November 6, 1979 (Case 442) and November 9, 1979 (Case 445). The third set of TIP data was a set of synthetic TIP traces (Case Syn 445) produced by a " SIMULATE" calculation at the same conditions as the power distribution update on November 9,1979 except that the control rods at positions 26-35 and 34-27, as well as their symmetric counterparts, were all set to position 28. These synthetic traces were pointwise adjusted by the ratios of the actual TIP traces of Case 445 to thc synthetic traces of Case Sym 445 to estimate the actual plant traces for an octant sym=etric rod pattern. TIP uncertainty results, as shown in Table 5, are well below the 8.7% criteria.

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TABLE I C0hTROL ROD SCRAM TIMES Scrs= #93 October 23, 1979 Mean Ti=e 7:

• Insertion 4.51% 23.34% 46.18% 87.84%

Measured Ti=e (sec) 0.329 0.850 1.379 2.471 T. S. L1=it (sec) 0.358 1.096 1.860 3.419 Maxi =um 87.S47. Insertion Time = 2.816 see T. S. L1=it = 5.00 see Slowes: 2x2 Arrav for

• Insertion 4.51* 23.34* 46.18% 87.84%

Measured T1=e (sec) 0.3533 0.8747 1.4347 2.5560 T. S. Limit (sec) 0.379 1.164 1.971 3.624

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TABLE 2 COMPARISC." 07 E'C'.E AND PROCESS COMPUTER Parameter Bucle Process Compute r MFLCPR 0.840 0.840 Location 13-18 13-13 MFLPD 0.730 0.731 Location 13-30-4 13-30-4 Peaking Factor 2.087 2.090 Location 31-30-4 31-30-4 MAPRAT 0.7138 0.716 Location 13-12-3 13~12-3 1827 035 _

TABLE 3 PO'E R DISTRISUTION MEASUREMENTS - CYCLE 7 STARTUP Date Power (*:) Core Flow (*) MFLPD L1=it MFLCPR Limit 11-3-79 14.41 30.60 0.235 1.0 0.270 1.0 11-

?? 33.75 0.317 1.0 0.427 1.0 11-4-79 26.45 33.42 0.317 1.0 0.417 1.0 11-4-79 52.36 41.94 0.522 1.0 0.718 1.0 11-5-79 52.29 42.04 0.590 1.0 0.713 1.0 11-5-79 56.46 42.02 0.596 1.0 0.767 1.0 11-6-79 66.54 47.15 0.686 1.0 0.53, 1.0 11-7-79 72.9^ 55.60 0.682 1.0 0.633 1.0 11-7-79 72.33 55.83 0.672 1.0 0.821 1.0 11-9-79 90.27 83.52 0.772 1.0 0.820 1.0 11-14-79 96.75 99.75 0.834 1.0 0.840 1.0 i821036

TA3LE 4 POWER DISTRIBUTION COMPARISON NOR".ALIZED AVE?aCZ .C'A' PCWZ2 D'STRIBUTION Node Simulate Plset  % Diff 1 0.97 0.85 + 14.1 2 1.23 1.14 + 7.9 3 1.17 1.12 + 4.5 4 1.08 1.03 + 4.9 5 1.26 1.02 + 3.9 6 1.11 1.08 + 2.8 7 1.13 1.09 + 3.7 8 1.09 1.11 - 1.8 9 1.05 1.10 - 4.5 10 0.95 1.08 - 12.0 11 0.74 0.89 - 16.9 12 0.42 0.50 - 16.0 TEN HIGHEST NORMALIZED RADIA' KELATIVE POWERS Location Simulate Plant  % Diff 27-30 1.366 1.418 - 3.7 29-24 1.385 1.336 + 3.5 29-28 1.373 1.435 - 4.3 29-30 1.321 1.344 - 1.7 29-32 1.288 1.352 - 4.7 31-26 1.271 1.307 - 2.8 31-28 1.309 1.369 - 4. 4 31-30 1.294 1.399 - 7.5 33-28 1.219 1.311 - 7.0 33-32 1.309 1.308 - 1.0 182'/ 037

TABLE 5 TOTAL TIP UNCERTAINTY Case Rod Pattern Dewer (%) Core Flew (%) % Uncert.

442 26 66.54 47.15 5.38 10 30 445 26 46 90.27 83 52 4.79 14 30 SYM 445 28 46 90.27 83.52 3.48 14 28

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