ML19343B113

Core 12 Physics Test for Yankee Rowe

ML19343B113
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1975
From:	Autio H, Ebert M, Henderson T YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19343B112	List: ML19343B111 ML19343B113
References
YAEC-1097, YAEC-109731, NUDOCS 8012040430
Download: ML19343B113 (20)

Text

--

hr D-Ei S.

i CORE XII PHYSICS TEST FOR YANKEE ROWE T. K. HENDERSON DECEMBER 1975 I

I 6

e.

Prepared.by

% MJ,

Reviewed by d.

Reactor Enginee.r j

Approved by

[

Mk f

l Plant Superintendent i

Yankee Atomic Electric Company Star Route Rowe, Massachuse,tts 01367 i

0 r

8012040 9 0 l

l l

(:'

TABLE OF CONTENTS Page List of Figures and Tables lii I.

Introduction

'l II.

Summary of Results 3

III.

Discussion of Results 4

A.

Rod Drop Times 4

B.

Control Rod Group' Worths 5

C.

Ejected Rod Worths 5

D.

Dropped Rod Worths 6

l' E.

Boron Worth 6

j F." Moderator Temperature Coefficient.

6 G.

Power Plus Xenon Worth 7

j I

I H.

Power Distribution 7

4 i

l 1

i 6

e i

11

=

(-

(..

l LIST OF TABLES AND FIGURES

~

iI Table Page I.

Neutron Fractions 2

II.

Summary of Results 3

}

III.

Control Rod Drop Times 4

I l

Figure 5

i 1

Core XII Fuel Locations 8

2 Control Rod Groups 9

i e.

3 Group A Worth' 10 4

Group B' Worth 11 j

5 Ej ected' Rod Worths 12 i

l 6

Dropped Rod Worths 13 i

7 Boron Worth 14 8

Moderator Temperature Coefficient 15 9

Thermocouple Correction Factors 16 l

1 1

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t i

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3 I.

Introduction

'l l

The intent of physics testing is to measure and record the various parameters which are characteristic of a particular j

core.

These parameters are used as a basis for routine plant l

i operation.

They also serve to verify the nuclear design

[

calculations used in analyzing plant transients and accidents.

l 2

t Records are made by intentionally varying one core parameter and measuring its response or the response of another.

Variable parameters include reactivity, time, boron-10 concentra-tion, temperatures and rod position.

The desired correlations I

include inverse boron, temperature and rod worths in units of reactivity, rod drops in time and temperatures relative to each other.

Plant chemists provided boron concentration measurements 4

by manual titra.tions.

Multiple samplings and repeated titrations provid6d a good degree of reliability in the boron data.

Time, temperature and rod po,sitions were measured with calibrated timing device ~, thermocouples and the plant Honeywell Visicorder s

Model 906B.

Reactivity was measured wi.th the plant's Westinghouse

{

Solid State Reactivity Computer.

The reactivity computer is a hard wired analog computer simulating the differential Inhour Equation.

Delayed neutron fractions for Core XII were computed by Westboro Nuclear Services Division (NSD) and programmed into the analog.

(See Table I).

i A series of tests during and after physics testing verified that the NSD delayed neutron fractions matched Core XII and provided proof that the re~ activity computer was operating with a high degree of accuracy.

D 4

1

.2

(.[..

TABLE I

'b=

~

4 9

YR CORE XII HZP, BOL, 534F, 2145 PPM DNF

~

I FRACTION EFFECTIVE LAMBDA.

GROUP BETA BAR FRACTION (SEC)-1 i

1

.00019566

.00019331

.01250 2

.00137237

.00135868

.03057 i

3

.00125687

.00124338

.11438 4

4

.00257440

.00254496

.30760 5

.00087122

.00086292 1.15667 6

.00031363

.00031088 3.04555 BETA EFFECTIVE =.006514 BETA BAR =.006584 I BAR =

.9894 PROMPT NEUTRON LIFETIME = 18.08 MICROSECONDS' STARTUP RATE PERIOD REACTIVITY (DECADES / MIN.)

(SEC.)

(PERCENT)

.100 260.6

.0272

.500 52.1

.0985 1.000 26.1

.1528 l

2.606 10.0

.2495 l

Core XII is loaded with 40 new Zircaloy clad fuel assemblies around the perimeter of the core (see Figure I).

36 partially burned Zircaloy assemblies make up the middle.

24 control rods divided in four groups are arranged per l

Figure 2.

2 l

L

= = -

=-

II Summary of Results 9

Table II summarizes the medsured parameters.

Predicted values from the Yankee Rowe Technical Specifications are provided for comparis_on.

s TABLE II Measured Worth Predicted Worth Test

(% AK/K)

(% 4 K/K)

Group A (differential) 1.15 1.12 B (differential) 2.62 2.79 C (integral) 1.41 a 1.96 D not measured 5.21 Total 11.08 Ejected Rod 7

.58

.646 11

.62 Dropped Rod 7

.26 11

.25 Inverse Baron 6 2000 PPM) 148.3 158 Just Critical Boron 2258 2145 Power Plus Xenon 3.18 8 70% Power i

Moderator Temperature Coefficient (x 10-4)

CB Measured hfIC Corrected MIC Predicted MIC 2250

.349

.345

.28 2091

.686

.536

.47 1930

.954

.714

. 68 1730 1.323

.939

.95

• Note that Group C is a drop measured worth useable only for I

an order of magnitude.

v 3

l

(Ex-bEc III.

Discussion of Results A.

Control Rod Drop Time C mtrol rod dro'p times measure the interval from the moment power to the control rod latching mechanism is to the moment each control rod reaches the bottom of cut the core.

Drop times are measured with Tave at 250*F and then with Tave at 530*F.

An oscillograph provides a permanent record.

The average drop time at 250*F was 1.89 seconds and at 530*F, 1.62 seconds.

This represents a small improvement over previous tests.

Table III details the individual drop times.

Just prior to the drop test, an operability check was performed by moving each group in turn from 0" to 90" to 0" and verifying control rod movement by the rod position indicators.

TABLE III Control Rod Drop Times Control Rod Drop Time - Seconds 250*F 530*F 1

1.97 1.77 2

1,85 1.73 3

1.88 1.61 4

1.79 1.74 5

1.76 1.54 6

l.75 1.56 7

1.78 1.58 8

1.83 1.58 9

1.79 1.56 10 1.78 1.56 11 1.79 l.48 12

~1.78 1.54 13 1.82 1.74 14 1.82 1.52 4

C...

(--

Control Rod Drop Times Centrol Rod Drop Time - Seconds 250*F 530*F 15 1.80 1.50 16 2.03 1.53 17 1.91 1.62

~

18 2.25 1.56

~

19 2.03 1.59 20

• 2.27 1.61 21 1.90 1.84 22 1.88 1.68 23 1.89

• 1.86 24~

1.98 1.60 Average 1.89 1.62 Highest B.

Control Rod Group Worths Differential worths of groups A and B were measured at 530*F.

The technique used a constant dilution rate ( % 15-20 gpm).

The reactivity change due to the

,ilution was balanced by inserting control rods at intervals d

l which allowed the reactivity to vary from plus to winus 10 pcm AK/K.

The effect was to create a saw toothed graphi-cal measurement of differential group worth.

The results are depicted in figures 3 and 4.

I i

Integral worths of groups A, B and C were measured by simply dropping the respective group from a 90* inch, just critical position.

Results are off by as much as 28%

but do provide an order of magnitude feeling for the group worth.

C.

Ej ected Rod Worths The ej ected' rod condition is defined as a single control rod forced out and held out of the core by coolant i.'

flow following a complete severance of a control rod j

housing.

i 5

(=_-

k

~

Four ej ected rod conditions were evaluated using the two highest worth rods in group A and in group B.

Their worths are plotted in figure 5.

The technique used is similar to group worth measuremen,ts.

A small dilution rate was used and the highest worth rod in the group is used to compensate for the reactivity change.

The graphical results can be evaluated to measure worth.

A different technique is used to measure the second highest ej ecte'd rod worth.

The second highest worth rod is inserted as the highest worth rod is with-drawn.

This is done in steps which vary reactivity from plus to minus 10 pcm AK/K.

D.

Dropped Rod Worths The dropped rod condition is defined a.s a single control rod dropping into the core while the rest remain withdrawn.

Two group B dropped rod conditions were evaluate?

using the dilution balance and rod swap techniques described above.

The results are shown in figure 6.

E.

Boron Worth i

The various differential rod worth measurements also provided boron worth data points (See_ Figure 7) in the range of 1750 to 2250 ppm boron.

From these data points the inverse boron worth is evaluated for the range.

Figure 7 shows inverse boron worth as measured.

F.

Moderator Temperature Coefficient (MTC) l The moderator tempera,ture coefficient is measured

. at various boron concentrations.

Rods are moved to compen-sate for the boron concentration changes instead of the burn-up compensation during normal operation.

Consequently the measured MTC must be corrected for rod insertion.

This can be seen in Figure 8.

6

(

(-

.=

MTC is' measured as the slope of a line produced by an X-i plotter with reactivity fed to the ordinate and temperature into the abscissa.

Temperature was varied from 527*~to 530*F and back several times for each boron concentration.

Boron was varied from 1730 to 2250 ppm.

G.

Power Plus Xenon Worth

.An integral measurement of the combined worths of power and Xenon was made by comparing hot Zero power conditions to hot 70% power.

The A boron concentration worth plus the A temperature worth yields the combined power and Xenon worth.

For this test the change was from 2258 ppm boron, 530 F at Zero power to 1800 ppm, 514*F at 70% power.

~

H.

Power Distribution Power distribution was evaluated after stabilizing at 70% power using the incore instrumentation. 'Results verified that the reactor plant is operating within Tech-nical Specification limits.

9 9

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L OCATIONS - BO b-

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FUEL N

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YANKEE ROWE CONTROL ROD GROUPS A

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A - Group "A"

B - Group "B"

C - Group "C" D - Group "D" Figure 2~-

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Least Squares Fit Yields:

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THERMOCOUPLE CORRECTION FACTORS CORE XII, BOL op A

B C

D E

F G

H J

K t

. Thermocouple 1

2 d

Correction

+.4 0

3 4

5

+.3

+.1

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7 8

9 20 3

+.5

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10 11 12 13 14

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10 Thermocouple r6'adings are normalized to their average at hot, zero power conditions.

Figure 9

'WFcnu 195 U.S. NUCLE AR REGULATORY COPAMISSION DOCKET NUM DE R

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50-29 1

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" """2""

, NRC DISTRIBUTION FOR PART 50 DOCKET M ATERI AL,

To.

FROM:

Yankee Atom 1C t.lec. CO.

DATE OF DOCUMENT g*3*g*g*g*

Westborough. Mass.

p_ ;_7g J.L. French DATE RECEtVED

? 12 76 OLETTER C N OTORIZ E D PROP INPUT FORM NUMBER OF CCPIES RECEtVED OoRIGINAL hNC LASSIFIE D OCOPY 33 DESCRIPTION ENCLOSU RE Startup Report entitled " Core XIII Physics Tes t" W/ Enclosures (33 Cys. Received)

AC_ KNOWLEDGED Z~~~

' " " ~ " -

DO NOT REMOVE

.y

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=_

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PLANT NAME:

Yankee Rowe SAFETY FOR ACTIONANFORMATION ENVIRO N

'-D-/0

- ASSIGNSD AD.

ASSIGNED AD :

1. ERANCE CHIEF :

Purole BRANCH CHIEF :

~

PROJECT MANAGER:

PROJECT MANAGER :

4IC. As3T. :

Sheppard LIC. ASST. :

p INTERNAL DISTRIBUTION

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