25
. | VERMONT Y AN KME NUCLEAR POWER CORPORATION * J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING OFFICE ' 1671 WORCESTER ROAD FRAMINGH AM, M ASSACH USETTS o1701 TELEPHONE 017 872-5100 United States Nuclear Regulatory Commission 8 D Washington, D. C. 20555 Atten tion : Office of Nuclear Reactor Regulation Mr. D. B. Vassallo, Chief f Operating Reactors Branch #2 ' - ', Division of Licensing Q Il References: (a) License No. DPR-28 (Docket No. 50-271), Vermont ee . (b) Telecon, W. L. Brooks (NRC) to S. P. Schultz (VY),'b @ Februa ry if,,1982. (c) D. M. VerPlanck, " Methods for the Analysis of Boiling Water Reactors Steady State Core Physics," YAEC-1238, March,1981. (d) E. E. Pilat, " Methods for the Analysis of Boiling Water Reactors Lattice Physics," YAEC-1232, December, 1980. Subject : Submittal of Additional Information Regarding SIMULATE Code Verification: Xenon Transient Predictive Capability In Reference (b), W. L. Brooks of your staff reques ted further informa tion regarding the verifica tion of the SIMULATE code. Specifically, it was requested that a demons tration of the xenon transient predictive capability of the code be provided. Steady state core physics models of Vermont Yankee Cycles 1-7 are demons tra ted in Reference (c). The model used for Vermont Yankee is replicated without substantive change and is demonstrated again in Reference (c) for Quad Cities 1, Cycles 1 and 2. The capability to calculate core performance accurately during xenon transients is mentioned but not demons tra ted in this report. The attached analysis, performed with the licensing model, demonstrates substantial capability to follow the core performance during xenon transients. According to W. L. Brooks , this information will complete that required for the review of the s teady state core physics and lattice physics analysis methodologies (References (c) and (d)). We trus t you will find this information satisfactory; however, should you desire additional information, please contact us . Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION $ R. L. Smith ! 8203310345 820326 PDR ADOCK 05000271 P PDR

VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 1: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

.

| VERMONT Y AN KME NUCLEAR POWER CORPORATION*

J scvcNTY scvcn onovc sTRtcr2.C.2.1

RUTLAND, VEftMONT 05701 FVY 82-31REPLY TO:

ENGINEERING OFFICE' 1671 WORCESTER ROAD

FRAMINGH AM, M ASSACH USETTS o1701TELEPHONE 017 872-5100

United States Nuclear Regulatory Commission 8 DWashington, D. C. 20555

Atten tion : Office of Nuclear Reactor RegulationMr. D. B. Vassallo, Chief fOperating Reactors Branch #2 '-

',Division of LicensingQ Il

References: (a) License No. DPR-28 (Docket No. 50-271), Vermont ee .(b) Telecon, W. L. Brooks (NRC) to S. P. Schultz (VY),'b @

Februa ry if,,1982.(c) D. M. VerPlanck, " Methods for the Analysis of Boiling Water

Reactors Steady State Core Physics," YAEC-1238, March,1981.(d) E. E. Pilat, " Methods for the Analysis of Boiling Water

Reactors Lattice Physics," YAEC-1232, December, 1980.

Subject : Submittal of Additional Information Regarding SIMULATE CodeVerification: Xenon Transient Predictive Capability

In Reference (b), W. L. Brooks of your staff reques ted furtherinforma tion regarding the verifica tion of the SIMULATE code. Specifically, itwas requested that a demons tration of the xenon transient predictivecapability of the code be provided.

Steady state core physics models of Vermont Yankee Cycles 1-7 are

demons tra ted in Reference (c). The model used for Vermont Yankee isreplicated without substantive change and is demonstrated again inReference (c) for Quad Cities 1, Cycles 1 and 2. The capability to calculatecore performance accurately during xenon transients is mentioned but notdemons tra ted in this report. The attached analysis, performed with thelicensing model, demonstrates substantial capability to follow the coreperformance during xenon transients.

According to W. L. Brooks , this information will complete that requiredfor the review of the s teady state core physics and lattice physics analysismethodologies (References (c) and (d)). We trus t you will find thisinformation satisfactory; however, should you desire additional information,please contact us .

Very truly yours,

VERMONT YANKEE NUCLEAR POWER CORPORATION

$R. L. Smith

!8203310345 820326PDR ADOCK 05000271P PDR

Page 2: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

I

.

.

Attache nt 1

Simulation of Three Preconditioning Passesin Vermnt Yankee Cycle 3

%

Page 3: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

.

.

.

Contents

Page'1.0 Introduction and Purpose 1

2.0 Description of the Analysis 1.

3.0 Analys'is Results and Conclusions 1

List of Ffgures

A.1 Percent of Core Power Versus Percent of Core Flow 3

A.2 Calculated K-effective Versus Elapsed Time 4

A.3 Percent of Core Flow Versus Elapsed Time 5

A.4 Percent of Core Power Ver' sus Elapsed Time 6

A.5 Control Rod Notches Inserted Versus Elapsed Time 7

A.6 Calculated Inlet Subcooling Versus Elapsed Time 8

A.7 Comparison of Total Peaking Factor 9

A.8 Core Average Axial Tip Traces (Calibration 69) 10

A.9 Core Average Axial Tip Traces (Calibration 71) 11

A.10 Core Average Axial Tip Traces (Calibration 74) 12

A.11 Individual Tip Traces (Calibration 69) 13

A.12 Individual Tip Traces (Calibration 71) 14

A.13 Individual Tip Traces (Calibration 74) 15 j

A.14 Xenon Number Density and Calculated Eigenvalue,,

Versus Elapsed Time 16

A.15 Iodine Number Density Versus Elapsed Time 17

A.16 Ratio of Calculated Transient Xenon Density to

Approximate Equilibrium Density Versus Elapsed Time 18

A.17 Axial Symmetric Offset of the Core Average Xenon

Number Density Versus Elapsed Time 19

List of Tables

.

A.1 SIMULATE Statepoints in Preconditioning Pass 1 20

A.2- SIMULATE Statepoints in Preconditioning Pass 2 21

A.3 SIMULATE Statepoints in Preconditioning Pass 3 22

.

Page 4: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

. _ _. . ___ _ ___ _ . .

.

t .

Simulation of Three Preconditioning Passes in Vermont Yankee Cycle 3

:1.0 Introduction and Purpose

j The purpose of this calculation was to determine the accuracy of the VermontYankee SIMULATE model as described in YAEC-1238 for application in a complete;

1 ascent to power..

2.0 Description of the Analysis

Operating data statepoints were selected from the period 2/19/75 to 3/14/75,4

1- early in Cycle 3. Cycle 3 was composed almost entirely of new fuel, thus any, effects of fuel burnup distribution are essentially eliminated.

An hourly operating history for the 13 day period was extracted from processcomputer printout. From this history, the major features were identified, ;

yielding 38 statepoints for SIMULATE spatial calculations. To provide,

improved accuracy in the integration of the xenon equations, two SliWLATEprogram optione were selected: 1) core power was varied linearly between the'

statepoints using 15 minute flux renormalization subintervals and 2) the'

'

integration was redone internally using the average of the beginning- andend-of-step spatial flux distributions.,

The data set provides an integral test of the several factors affectingSIMULATE's calculated eigenvalue and power distribution *

o core powero core flowo core heat balance -

'o control rod patterno transient xenon

i

Included in the data set are five flow-induced power increase ramps performed4

for fuel preconditioning; four rapid core flow power reductions; and threemajor rod pattern changes. Demonstrations of the xenon transient capabilityoccur following the rapid core flow power reductions.

3.0 Analysis Results and Conclusions'

Power distribution accuracy is demonstrated by comparis6n to three complete'

TIP data sets: Calibrations 69, 71, and 74. . Alse. for every case the process. computer ana SIMULATE total peaking factors are compared.

Power distribution comparisons demonstrate:

o Accuracy over normal range of core power and flow. -

:o Proper treatment of control rod effects.-

o Power distribution accuracy during xenon transients.

1

-1-

. - .- , . - . - - .- , -. -

Page 5: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

.

.

Eigenvalue graphs demons trate:

o Inaccurate modelling below 50% power, coincident with major rodpattern changes.

'

Accurate eigenvalue prediction elsewhere (0.99781,0,0009).o

|Xenon transient accuracy is demonstrated at the rapid core flow-powerreductions in passes 2 and 3, where rod pattern changes are minor:

o Cases 19 - 24 (hours 134 - 165)o Cases 28 - 33 (hours 197 - 245)o Cases 35 - 38 (hours 269 - 327)

During the above cases, the predicted eigenvalue deviates from the average

(0.9978) by no more than 10.0013. This eigenvalue deviation corresponds to adeviation of 2-3% of total core power - which is a useful level of predictivea ccura cy .

Figures 1 through 17 and Tables 1 through 3 which present the analysis ares el f-explana tory.

d

4

-2-

m-

Page 6: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 7: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

*.

.

VERMONT YANKEE PRECONDITIONING PASSES IN CYCLE 3ORTR FROM 2/19/75 THROUGH 3/04/75 (CASES V125-127)

m m

.hh.' CALCULRTED K-EFFECTIVE

e eT 5- 57o oa r a

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AVG .9980 .0015 (WITHOUT POINT 1)= 2k.00 4'O.00 8'O.00 1'20.00 1'60 00 2'00 00 2'40.00 2'80.00 3'20.00 3'80.00 40h.00

ELRPSED TIME - HOURS

FIGURE A.2

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

Page 8: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 9: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 10: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 11: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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VERMONT YANKEE PRECONDITIONING PASSES IN CYCLE 3DATA FROM 2/19/7S THROUGH 3/04/7S (CASES V12S-127)

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ELAPSED TIME - HOURS

FIGURE A.6

- , - _ ..

Page 12: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 13: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

- -. _ .

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CORE RVERAGE RXIRL TIP TRRCES 81/04/22.VERMONT CYCLE.3 R1 STRRTUP-7TH STEP 02/21/75 1643 CRL 69

8b-

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CORE EXPOSURE % POWER % FLOW K-EFFECTIVE JOB NRME1.569 55 1 87 7 .99802 SIOV124

FIGURE A.8

- - _ . _ . .- ~_ . - . , _ , _ _ _ . . . _ . - _ _. _._ _ . - _

Page 14: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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CORE AVERAGE AXIAL TIP TRACES 81/04/22.VERMONT CYCLE 3 Al STARTUP-12TH STEP 02/22/75 2137 CAL 71

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BOTTOM OF CORE-

CORE EXPOSURE % POWER % FLOW K-EFFECTIVE JOB NAME1.584 64.3 63 1 .99666 SIOV125

FIGURE A.9

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

Page 15: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ .-- .

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CORE AVERRGE RXIRL TIP TRACES 81/04/22VERMONT CYCLE 3 Al STARTUP STEP 35 03/04/75 0954 CRL 74

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iBOTTOM OF CORE

CORE EXPOSURE % POWER % FLOW K-EFFECTIVE' JOB NRME1 750 99 7 99 7 99910 SIOV126

FIGURE A.10

. _ _ . _ - _ _ _ _ _ , - . . - _ . _ . . _ _ _ . . _ . _ _ . _ _ _ _ - _ - - _ _ - -

Page 16: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 18: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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FIGURE A.13

. . _ - _ _ _ _ _ _ _ _

Page 19: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 22: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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Page 23: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

'.

TABLE A.1

' .

SIMULATE STATEPOINTS IN PRECONDITIONING PASS 1

.

CASE

1 VERMONT CYCLE 3 BEGIN STARTUP OF A1 SEQUENCE O2/19/75 17362 VERMONT CYCLE 3 STARTUP STEP 1A 02/19/75 22163 VERMONT CYCLE 3 3A1 STARTUP-2ND STEP O2/19/75 23074 VERMONT CYCLE 3 A1 STARTUP-3RD STEP O2/2C/75 07575 VERMONT CYCLE 3 A1 STARTUP-4TH STEP O2/20/75 15526 VERMONT CYCLE 3 Al STARTUP-5TH STEP O2/20/75 23567 VERMONT CYCLE 3 Al STARTUP-6TH STEP O2/21/75 08328 VERMONT CYCLF ,Al STARTUP-7TH STEP O2/21/75 1643 CAL 699 VERMONT CYC'J. J Al STARTUP-8TH STEP O2/21/75 2344to VERMONT CYCLE 3 Al STARTUP-9TH STEP O2/22/75 075411 VERMONT CYCLE 3 Al STARTUP-10TH STEP O2/22/75 1432

[a CASE HOURS K-EFF NOTCHES SUBCOOLING % POWER % FLOW EXPOSURE PEAK

o1 23.100 1.01547 1712.000 13.239 7.512 35.688 1.552 2.199'2 27.760 1.00244 1516.000 24.797 21.090 38.229 1.552 2.085

3 35.520 .99634 1296.000 32.121 31.143 39.688 1.555 2.684

4 37.450 1.00081 970.000 34.025 40.164 46.375 1.555 3.128

5 45.367 1.00025 902.000 30.218 44.996 58.354 1.558 3.107

6 53.433 .99943 902.000 27.185 47.297 68.771 1.562 2.954

7 62.033 .99902 902.000 23.655 48.031 77.417 1.565 2.885

8 70.217 .99802 870.000 21.494 55.146 87.667 1.569 2.728

9 77.233 .99661 870.000 20.911 57.664 91.396 1.573 2.734

10 85.400 .99607 870.000 19.924 57.392 93.875 1.577 2.741

11 91.920 .99595 670.000 19.747 56.525 93.750 1.581 2.750

,

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Page 24: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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TABLE A.2

SIMULATE STATEPOINTS IN PRECONDITIONING PASS 2

.

CASE

12 VERMONT CYCLE 3 Al STARTUP STEP 11 02/22/75 152113 VERMONT CYCLE 3 Al STARTUP-STEP 11A 02/22/75 200014 VERMONT CYCLE 3 At STARTUP-12TH STEP O2/22/75 2137 CAL 71'

15 VERMONT CYCLE 3 Al STARTUP STEP 12A 2/23/75 000016 VERMONT CYCLE 3 Al STARTUP-13TH STEP O2/23/75 082217 VERMONT CYCLE 3 Al STARTUP-14TH STEP O2/23/75 162018 VERMONT CYCLE 3 A1 STARTUP-15TH STEP O2/24/75 0017*

19 VERMONT CYCLE 3 A1 STARTUP-16TH STEP O2/24/75 0912 ROD BLOCK20 VERMONT CYCLE 3 Al STARTUP-17TH STEP O2/24/75 105321 VERMONT CYCLE 3 Al STARTUP-18TH STEP O2/24/75 155222 VERMONT CYCLE 3 Al STARTUP-19TH STEP O2/24/75 235923 VERMONT CYCLE 3 Al STARTUP-20TH STEP O2/25/75 075324 VERMONT CYCLE 3 Al STARTUP-21ST STEP O2/25/75 155525 VERMONT CYCLE 3 Al STARTUP-22ND STEP O2/25/75 234426 VERMONT CYCLE 3 At STARTUP-23RD STEP O2/26/75 0817

1 27 VERMONT CYCLE 3 Al STARTUP-24TH STEP O2/26/75 1542VERMONT CYCLE 3 A1 STARTUP-25TH STEP O2/26/75 2356I 28

UHOURS K-EFF NOTCHES SUBCOOLING % POWER % FLOW EXPOSURE PEAKs

9'2.846 .99983 870.000 31.063 31.191 41.292 1.581 2.904

97.500 .99648 690.000 39.100 43.992 41.558 1.583 2.474

14 99.130 .99666 642.000 35.579 64.289 .63.142 1.584 2.313

15 101.520 .99880 658.000 34.076 60.497 63.517 1.585 2.425

16 109.867 .99913- 658.000 31.898 62.471 69.563 1.589 2.476

17 117.833 .99820 658.000 29.149 65.729 77.063 1.594 2.509

18 125.800 .99752 658.000 27.055 68.250 83.208 1.599 2.487

19 134.720 .99735 658.000 24.589 71.171 90.683 1.605 2.459

20 136.400 .99881 658.000 34.752 49.253 52.558 1.605 2.549

21 141.380 .99772 658.000 29.366 59.520 72.688 1.608 2.509

22 149.500 .99846 658.000 29.906 60.946 72.521 1.612 2.515

23 157.400 .99809 653.000 28.384 65.190 78.354 1.617 2.509

24 165.400 .99752 658.000 26.198 69.457 85.646 1.622 2.478

25 172.500 . 99', 41 650.000 24.370 71.926 91.417 1.627 2.459

26 181.800 .99707 658.000 22.714 74.186 96.896 1.633 2.436

27 109.200 .99689 658.000 21.767 75.304 100.000 1.638 2.422

28 197.450 .99702 658.000 21.468 74.583 100.375 1.643 2.418

4,

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -

Page 25: VERMONT Y AN KME NUCLEAR POWER CORPORATION J. * | VERMONT Y AN KME NUCLEAR POWER CORPORATION J scvcNTY scvcn onovc sTRtcr 2.C.2.1 RUTLAND, VEftMONT 05701 FVY 82-31 REPLY TO: ENGINEERING

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TABLE A.3

'

SIMULATE STATEPOINTS IN PRECONDITIONING PASS 3-

.

CASE

29 VERMONT CYCLE 3 Al STARTUP STEP 26 02/27/75 015930 VERMONT CYCLE 3'A1 STARTUP STEP 27 02/27/75 050731 VERMONT CYCLE 3 Al STARTUP STEP 28 02/27/75 072432 VERMONT CYCLE 3 At STARTUP STEP 29 02/28/75 000033 VERMONT CYCLE 3 Al STARTUP STEP 30 023/01/75 000034 VERMONT CYCLE 3 Al STARTUP STEP 31 03/01/75 120035 VERMONT CYCLE 3 Al STARTUP STEP 32 03/02/75 000036 VERMONT CYCLE 3 At STARTUP STEP 33 03/02/75 012537 VERMONT CYCLE 3 Al STARTUP STEP 34 03/02/75 050038 VERMONT CYCLE 3 Al STARTUP STEP 35 03/04/75 0954 CAL 74

e ibJ iy HOURS K-EFF NOTCHES SUBCOOLING % POWER % FLOW EXPOSURE PEAK

29 199.500 .99785 658.000 37.846 40.163 40.558 1.644 2.64830 202.640 .99632 528.000 38.607 71.375 61.725 1.646 2.08631 204.920 .99698 488.000 39.741 74.998 61.958 1.647 2.12032 221.520 .99802 488.000 35.365 81.959 .73.725 1.659 2.131.

33 245.520 .99785 488.000 28.910 90.282 90.750 1.679 2.09534 257.520 .99801 488.000 26.101 94.456 99.333 1.689 2.06235 .269.520 .99796 488.000 26.269 93.258 98.292 1.699 2.05736 270.530 .99919 488.000 35.839 72.359 67.792 1.699 2.15637 274.520 .99720 462.000 33.733 87.289 79.292 1.703 2.06738 327.420 .99910 462.000 27.092 99.674 99.667 1.750 1.991

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