ML18143A832

Physics Measurements of Cycle III

ML18143A832
Person / Time
Site:	Ginna
Issue date:	12/28/1972
From:	Amish K Rochester Gas & Electric Corp
To:	O'Leary J US Atomic Energy Commission (AEC)
References
Download: ML18143A832 (19)

Text

AEC DZo "BCTZON FOR PART

. 0 DOCKET MATZSILL TEMPORARY FOIWi CONTROL No l

\\

n FX FROM: Rochester Gas 5 Electric

.'orporation Rochester, N.Y.

Keith W.. Amish DATE OF DOC:

DATE REC'D nZMO TO ~

."Mr. John P. O'eary CLASS<'

PROP INFO 12-28-72 ORIG 1 signed INPUT 1-2-73 CC mo cYs REc'D

&iiT AZC PDR SERT LOCAL PDR DOCiKT NO:

50-244 DESCRIPTION; Ltr trans the following:

ENCLOSURES:

REPORT-on Physics Measurements on Cycle III at the Ginna Station.....'1 cy encl rec'd)

PLAhg ~S.

Ginna P'lant FOR ACTION INFORMATION DL 1- "73 BUTLEz(r,)

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S9 EAST AVENUE, ROCHESTER, N.Y. %68+ 14'649 KEITH W. AMISH SENIOR VICE PRESIDENT KLKCTRICAND STEAM December 28, 1972 Mr. John P. O'eary, Director Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C. 20545 TELEPHONE AREA CODE T51 546 2700 g}

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Subject:

Physics Measurements of Cycle III R. E. Ginna Nuclear Power Plant Unit No.

1 Docket 50-244

Dear Mr. 0,

'Leary:

As required by the Ginna Unit No.

1 Technical Specifications, para-graph 6. 6.4, attached herewith is a description of the measured values and comparisons with design predictions and specifications for the designated Cycle III. There was generally good agreement between the measured and predicted values.

Very t ly yours, eith W. Amish Attachment xc:

Mr. J. P. O'Reilly IlpCKgpp Ups 0

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PHYSICS MEASUREMENTS CYCLE III Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant Unit No.

1 Docket 50-244 December 22, 1972

l

REPORT OF PHYSICS MEASUREMENTS ON CYCLE 'III

'T GXNNA STATION ABSTRACT:

This report is a description of the operating conditions or characteristics and a comparison with design predictions and specifications, as required by Technical Specifications 6.6.Q.

The Ginna Nuclear Station Cycle III Physics Testing Pxogram was conducted over the period of November 8, 1972 to December 2,

1972.

The majority of measure-ments were made during the period of November 8,'972 to November 15, 1972.

The period of November 16, 1972 to November 25,'1972 was required to increase power from 75% to 100% of 1266 K<t at a rate of 3% pex day, 1.0 SM'1MARY OF FUEL LOADING AND TESTING

'he Cycle IXI fuel loading pattern was loaded as designed duxing the refueling outage of October - November, 1972.

Figure 1 is the Cycle III loading pattern, as loaded.

There was generally good agreement between the measured and predicted II values.

These values are presented as part of Section 3'f this report.

The time required to complete the entire test program was 25 days.

This length of time was due to limiting power increases and performing the power coefficient measurement by a powex reduction.

Maximum power increase rate was 3% per hour until. 75% of per day from 75% to 100% of 1266 0Ãt.

The 1266 Kft was reached and 3%

power coefficient measure-ment requix'es a fast rate of change, which can only be achieved by power reduction.

If

2 ~ 0 PHYSICS TESTING PROGRAM The physics testing program consisted of measurements made at zero

power, (power was increased to 3% of 1266 hat for incore flux maps),

incore flux maps at 25%,

50%,

75%,

and 100% of 1266 Mft, calibration of axial offset at 960 Mft, and power coefficient measurement at 1266 The measurements made at zero power included:

1.

Isothermal Temperature Coefficient 2.

Differential Boron Worth 3.

Boron End Points 4.

Control Rod Bank "C" and "D" Differential Worth The condition.of the core during power escalation was verified by reduction of Incore Flux Map data.

The calibration of the Axial Offset was accomplished by use of Incore Flux Maps and Part Length Rods.

The power coefficient measurement was made by reducing power after 1266 MNt was reached.

~

3 ~ 0 ZERO POWER PHYSICS MEASUREMENTS The reactivity computer, which provides an on-line solution of the point model neutron kinetics equations, was used for all core reactivity measurements, Power Range Channel N-41 was placed in the trip mode and its'ignal supplied to the reactivity computer.

The reactivity computer was verified b'y comparing its'esults to a corresponding reactor period.

The combination of the reactivity measurements from the reactivity computer and changes made in Control Rod Position, Temperature, and Boron concentration produce the reactivity coefficients.

3.1 ISOTHERMAL TEMPERATURE COEFFICIENT The Isothermal Temperature Coefficient was measured with all rods out, Bank "D" inserted, and Banks "C" and "D" inserted.

The results are given in Table 3.1, 3 ~ 2 DIFFERENTIAL BORON WORTH The Boron Concentration was varied as Control Rod Banks "D" and "C" wex'e inserted and removed from the core at zero power.

The change in boron concentration was monitored by 20 minute samplin'g during these periods.

The results of these data are presented in Table 3.2.

3 ~ 3 'ORON ENDPOINTS The boron endpoints were measured with all x'ods out, Bank "D" inserted and Banks "C" and "D" inserted.

The'esulting boron endpoints compared to predicted values are presented in Table 3. 3.

3.4 BANKS "C" AND "D" DIFFERENTIAL WORTH The differential worth of Control Rod Banks "C" and "D" w'ere measured using their normal insertion sequence.

The resulting curves are shown on Figures 2 and 3.

The comparison of measured to predicted values is given in Table 3.4.

3 ~ 5 ZERO POWER FLUX MAPS The proper fuel loading, design pow'er distribution, and hot channel factors were verified by Incore Flux Maps taken duxing zero power I

physics measurements.

The maps were taken with three diffexent con-trol rod configurations, all rods out, Control Rod Bank "D" inserted and Control Rod Banks "C" and "D" inserted.

These maps showed good agreement between the measured and predicted power in the measured assemblies.

4.0 VERIFICATION OF CORE CONDITION Flux maps were taken at 25%,

50%,

75%,

and 100% of 1266 MJ.

These maps were reduced and shown to be acceptable prior to any increase in If

.power.

5 ~ 0 CALIBRATION OF AXIAL OFFSET The power of the reactor was held at 960 K<t while three flux maps were taken.

The Axial Offset of the core was varied by means of the part length rods and maps were'aken at positive, negative and zero values.

Heat balances were calculated and the detector currents recorded ior each Axial Offset.

The Incore Flux Maps were reduced by the INCORE computer code providing the Axial Offset of the core.

This information was then extrapolated to full power to provide the setting for the Axial Offset protective circuitry.

Table F 1 presents the setpoints generated 'for the beginning of Core III.

6 0 PO[iER COEFFXCIENCE The Power coefficience could not be measured during the power increase due to the resCriction on the rate of change.

These values therefore, were measured using a power reduction of 1 percent per minute.

The-reductions were stopped every 20 percent of reduction for calorimetric purposes.

The preliminary results are given in table 6.1.

TABLE 3.1

~ TEMPERATURE COEFFICIENTS AT ZERO POWER 547 All rods out Bank "D" inserted Banks D and C inserted Measured cm/ F 0.0

- 2.4

'5 ~ 5 Predicted cm/ F

+ 1.3

+ 0.3

=- 1.8 Measured Boron m

1665 1565 1408 TABLE 3.2 DIFFERENTIAL BORON WORTH AT HZP

.DtC worth (ppm)

DtC worth (pcm)

CB 265 ppm ACB P Measured 114.7 (ppm/pcm)

Pred icted 116 (ppm/pcm)

TABLE 3.3 BORON ENDPOINTS AT HZP 5KASUREMENTS & PREDICTXONS BANK POSXTIONS ARO D inserted D & C inserted MEASURED 1675 ppm 1573 ppm 1410 ppm P RED IC TED 1585 ppm 1465 ppm 1305 ppm DIFF.

M-P

.90 ppm 108 ppm 105 ppm TABLE 3.4 S%1HARY AND COMPARISON OF MEASURED AND PREDICTED INTEGRAL CONTROL BANK WORTHS BANKS INSERTED BANK WORTH PCM)

MEASURED PREDICTED TOTAL BANK WORTHS (CPCM)

PRED ICTED MEASURED D and C

1030 1360 920 1390 1030.

2390 920 2310

TABLE 6.1 POWER COEFFICIENT VALUE

- 9.3 pcm/%

- -12,3 pcm/%

- 15.5 pcm/%

- 15.2 pcm/%

% OP 1266 M<

88.6%

69.1%

49.4%'0,9%

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TABLE 5.1 f b CALIBRATIOHAND SETPOihTS A<%LYSIS SHEET EXCORE DETECTOR INCORE 'OWER AXIAL LEVEL OFFSET

(~ii

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O/

FULL POWER I

TOP (W~)

I BOT (P~)

V-TOP (VOLTS)

V-BOT (VOLTS) gV (VOLTS) d,T PENALTY

( F)

RECORDER TOP (VOLTS)

RECORDER BOT (VOLTS)-

FLUX IiXDICAT

(/)

CH-41 CH-41 CH-41 CH-41 0%

+10%

-10%

+20%

1520 1520

~

1520 1520 100 100 100 100 248 267 229 287 393 374 413.

355 7.000 7.536 6.464 8.101 7.000 6.662 7.356 6.323

+0.874

-0.892

+1.778 4 '

4;0 0

+10

-10

+20 CH-41

-20%

1520 100 209 432 5.899 7.695

-1.796 11.4

-20 CH-42 0%

1520 100 273 412 7;000 7.000 0-4.0 4.0 CH-42 CH-42 CH-42 CH-42

-10%

1520

+20%

1520

-20%

1520

+10%

1520 100 100

100, 100 293 252 314 232 392 433 372 453

7. 513 6.462 8.053 5.949 6.660 7.357 6.320 7.697

+0.853

-0.895

+1.733 11.4

-1.748

. 11.4

+10

-10

+20

-20 CH-43 CH-43 CH-43 CH-43 0%

1520

-10%

1520

+20%

1520

+10%

1520 100 108 100 100 285 308 262 331 479 456 502

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433 7.000 7.565 6.435 8.129

7. 000 6.664 7.336 6.328

'0.901

>>0.901

+1.801 4.0 4.0

+10

-10

+20

0

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TABLE 5.1 f b CALIBRATIONAND SETPOINTS ANALYSIS SHEET EXCORE DETECTOR INCORE POWER AXIAL LEVEL OFFSET (YiAT) 0/

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RECORDER BOT (VOLTS)

FLUX IiXDICA'I

(%)

CH-43

-20%

1520 100 239 525 5.870 7.672

-1.802 11.4 CH-44 0%

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7.000

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1520 100 294 397 7.566 6.648

+0.918 0

+10 CH-44 CH-44 CH-44

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+20%

-20%

1520 1520 1520 100 100 100 250 440

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6.434 316 375 8.132 228 462 5.868 7.368 6.279 7.737

-0.934

+1.853

-1.869 0

11.4 11.4

-10

+20

-20