ML20112C648

Cycle 5 Startup Physics Test Rept

ML20112C648
Person / Time
Site:	Beaver Valley
Issue date:	01/31/1985
From:	Jones T DUQUESNE LIGHT CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 8503220057
Download: ML20112C648 (10)

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Beaver Valley Power Station Unit No. 1 CYCLE 5 STARTUP PHYSICS TEST REPORT f

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BEAVER VALLEY POWER STATION Cycle 5 Startup Test Report INTRODUCTION:

This ' report describes the .startup test program applicable for the Cycle 5 reload core design verification and incore/excore cross-calibration for Beaver Valley Power Station, Unit I. This testing program consisted of the following measurements:

1. Control rod drop time measurements

2. Critical boron concentration measurements

3. Control rod bank worth measurements

4. Temperature coef ficient measurements

5. Reactivity computer checks

6. Incore/Excore cross-calibration 7.. Startup power distribution measurements using the incore flux mapping system.

The results of these startup tests are summarized in this report and comparisons are made to predicted design values' and applicable BVPS Technical Specification requirements.

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[* Beaver Valley Power Station Cycle 5 Startup Test Report TEST SUMMARIES:

BVT 1.1 - 1.1.1 Control Rod Drop Time Measurements.

PURPOSE The purpose of this test was to determine a drop time for each full-length Rod Cluster Assembly with the RCS in Hot Standby, T avg > 541 F, and full reactor coolant system flow.

TEST DESCRIPTION:

A single RCCA Bank is withdrawn to the full-out position (228 steps). A visicorder is connected to the detector primary coil and test leads are t he n - inserted . at the stationary gripper coil jacks in the power cabinets.

- The RCCA blown fuse indicator and moving coil fuse are removed. After the visicorder is turned ON, an assembly is dropped by pulling the stationary gripper fuse out. Each of the 48 rod cluster assemblies is tested in this manner and the drop times determined from the visicorder traces.

RESULTS:

The drop times of all 48 rods were well within the BVPS Technical Specification requirement of < 2.2 seconds, _ with the slowest time being 1.44 seconds for rod B-6 at hot full RCS flow.

BVT 1.5 - 2.2.1 Initial Approach to Criticality PURPOSE:

The purpose of this test was to (1) achieve initial criticality;(2) determine the point at which nuclear heat occurs and establish the zero power physics testing decade; (3) verify the proper calibration of the reactivity computer.

TEST DESCRIPTION' Initial conditions were es tablished with the shutdown banks fully withdrawn, control banks fully inserted, boron concentration 1940 ppm, RCS h temperature at 547'F and RCS pressure at 2235 psig.

L l The control banks were withdrawn in 50 step intervals until control bank D I reached 160 steps. An inverse count rate ratio (ICRR) was taken at each

!~ interval. During control rod withdrawal, the ICRR dropped from 1.0 to f approximately 0.41.

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,' Beaver Valley Power Station Cycle 5 Startup Test Report Dilution to criticality was then commenced at approximately 1000 pcm/hr.

Again, ICRR was monitored and plotted at 20 minute intervals. At 0200 on January 2, 1985 after 12,400 gallons had been added criticality was achieved.

Following the recording of criticality data, nuclear heat. Nuclearheatoccurredat7.4x10gowerwasincreasedtoward amps as indicated on the reactivity computer. The zero power physics testing decade (ZPPTD) was set from 3 x 10-9 amps to 3 x 10-8 amps on the reactivity computer.

Flux was then reduced to the lower end of the ZPPTD in preparation for the reactivity computer operational checkout. Positive reactivity insertions of 25 pcm, 32 pcm, and 45 pcm were made with the reactor doubling times being measured for each. The results were checked against Westinghouse design criteria.

RESULTS:

The all rods out (ARO) critical boron concentration corrected for rod position was calculated to be 1566.5 ppm. The acceptance criteria _was 1525

+ 50 ppm. Thus the measured value was within the acceptance criteria.

The ZPPTD was set at 3 x 10-9 amps to 3 x 10-8 amps based on a mearured nuclear heat point of 7.4 x 10-7 amps.

All the test runs for the reactivity computer showed good agreement with design data. The errors for the three test cases were 1.82%, 0.25%, and 1.22%, all well within the 4% acceptance criteria.

BVT 1.5 - 2.2.2 Core Design Check Test -

PURPOSE:

The purpose of this test was to verify the reactor core design data between 0 and 100 percent power, and to perform the incore/excore cross-calibration prior to 75% reactor power.

TEST DESCRIPTION:

The test was divided into three parts. Section A covered zero power physics tests. These tests included boron endpoint measurements, boron dilution worth measurement of the reference bank (CBB), rod swap bank worths, and isothermal temperature coef ficient measureme nt s . Core power anomalies were also checked at this time by performing an ARO zero power full-core flux map.

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Beaver Valley Power Station Cycle 5 Startup Test Report Section B involved incore/excore cross-calibration prior to exceeding 75%

of rated thermal power. This involved performing BVT 1.3 - 2.2.3 Nuclear Power Range Calibration, in which a series of flux maps are run at various axial effsets. The flux maps were also examined to ensure that the measured peaking factors were within their applicable Technical Specification limits .

Section C required a full-core flux map to be run at 100% power to serve as a calibration check for the incore/excore calibration and to verify that the measured peaking factors were within the power distribution limits of applicable Technical Specifications.

RESULTS:

Boron Endpoints The all rods out (ARD) critical boron concentration was measured to be 1576 ppm. This value was 1 ppm outside the acceptance criteria of 1525 1 50 ppm. Westinghouse was contacted and responded that the 50 ppm criteria was considered a design review criteria and that there were no safety or technical specification implications. Hence the plant could proceed to Mode 1.

Wes tinghouse the n recalculated the HZP, ARO critical boron concentration taking actual EOC-4, as built data and redistribution effects into ac count . The updated calculations yielded a predicted value of 1546 ppm 150 ppm. Thus, the 157 6 ppm measured value was within the updated acceptance criteria band.

The Control Bank B-in critical boron concentration was measured to be 1420 ppm, which was within the acceptance criteria of 1399 ppm + 15%.

Temperature Coef ficients The isothermal temperature coef ficient (lTC) and moderator temperature coef ficient (MTC) were measured at ARD, HZP conditions. The average measured ITC was determined to be -2.66 pcm/*F which was within the acceptance criteria of -2.1 1 3 pcm/*F. Subtracting the predicted design value of the doppler coef ficient (-2.0 pcm/*F) from the mesured ITC, the MTC was calculated to be -0.66 pcm/* F. This value for the MTC meets the requirements of BVPS Technical Specifications which requires the MTC to be between -50 pcm/*F and 0 pcm/* F.

Inverse Boron Worth The measured inverse boron worth was 0.117 ppm /pcm. This value was outside the acceptance criteria of 0.092 ppm /pcm f 15%. Utilizing the revised ARO critical boron of 1546 ppm, the acceptance criteria was 4

. Beaver Valley Power Station Cycle 5 Startup Test Report revised to 0.1078 ppm /pcm f 15%. Thus, the measured value was within the updated design value.

RCC Bank Worths The worth of the reference bank for rod swap,- CBB, was measured using boron dilution. Following the insertion of CBB, the worths of the remaining control and shu tdown banks were obtained relative to CBB.

The measured worth, predicted value, and percent difference for each RCC bank and total RCC worth are listed in Table I. All the measured values were within' the acceptance criteria for this test.

Reactivity Computer The reactivity computer was checked prior to low power physics testing, (LPPT), every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during testing, and at the conclusion of LPPT using the exponential generator. - In addition, the reactivity computer was' checked with the reactor following initial criticality. In all cases t he computer error was within the 4% acceptance criteria, with the highest measured error being 1.82%.

Low Power Full Core Flux Map A full-core flux _ map was taken at the ARO configuration to determine the initial flux distribution in the core during LPPT. Table II lists the values for quadrant power tilt , nuclear enthalpy hot channel factor (FN H), .and maximum deviation from predicted relative assembly powers.

Due to the slight core tilt measured during the HZP map, an additional map was performed at 50% power to reverify the core tilt. All- other measured values were within the zero power map acceptance criteria.

At Power Full Core Flux Maps Full core flux maps were. performed at 53%, 59% and 99% power to check

. core design predictions and applicable Technical Specifications for core peaking factors. The results from these maps were all well within the Technical Specifications for BVPS Unit I, as illustrated in Table II.

Incore/Excore Axial Of fset Calibration At 59% power, a full-core flux map and seven quarter-core flux maps were performed at various axial offsets to calibrate the exco re detectors in accordance with BVT 1.3 - 2.2.3, Nuclear Power Range Calibration. Upon reaching 100% power a full-core map was performed to check the incore/excore calibration. Due to the relatively high error found during this check (close to 3%), BVT 1.3 - 2.2.3 was performed 5

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-.- Beaver Valley Power Station

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Cycle 5 Startup Test Report again -at 100% reactor power. A full-core and six quarter-core flux maps were utilized to recalibrate the detectors at full power.

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TABLE I RCC BANK WORTHS RCC. Measured Predicted Error Acceptance Bank Value.(pcm) Value (pcm) (%) Criteria CBB* 1334.8 1363 -2.1 + 10%

I CBD 920.5 1004 +S.3 1 15%

CBC 996.6 992 .5 + 15%

CBA- 589.5 60 4 -2.4 + 15%

SBB 905.7 939 -3.5 + 15%

a SBA 1029.3 1089 -5.5 -+ 15%

4 TOTAL WORTH 5776.4 5991 -3.6 + 10%

• Reference Bank <

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FULL CORE FLUX MAPS ARO-HZP 50% Power 100% Power Acceptance CBD=187 steps Criteria ARO Quadrant Tilt 1.0208 1.0132 1.0040 < l.02 (Tech. Spec. is

< l.02 above 50% power)

Maximum D'eviation 8.8% 5.4% 4.2% 1 10% of Predicted for

, from Predicted Relative Power > .9

• • Y ' "*** 12.8% 5.1%

7.8% i 15% of Predicted for.

Relative Powers < .9

• 1.38 + .14 ARO-3ZP

.F Tech Spec.:

1.4456 1.3935 < 2.02 for HZP 4 1.5445 < l.77 for 534-

< l.55 for 994 Tech. Spec.:

y 2.3811 1.9195 1.7505 <'4.5124 for HZP Q

< 4.3262 for 534-

< 2.3474 for 99%

• Does not' include uncertainties

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'Af Telephone (412) 393-6000 Nuclear Group March 12, 1985 P.O. Box 4 Shippingport, PA 15077-0004 United States Nuclear Regulatory Commission Director of Nuclear Reactor Regulation ATTN: Mr. Steven A. Varga Operating Reactors Branch No.1 Division of Licensing Washington, D.C. 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 l Startup Physics Test Report Gentlemen:

Enclosed is the Cycle 5 Beaver Valley Startup Test Report, submitted in accordance with Technical Specification 6.9.1.3. The report provides a technical summary of the BVPS, Unit No. 1 Startup Testing Program. Comparisons are made to predicted design values and applicable Beaver Valley Power S tation Technical Specification requireme nts .

Very truly yours, o

T. . Jones, General Manager Nuclear Operations Unit Attachment cc: Mr. W. M. Troskoski, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C. 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company P. O. Box 26666 One James River Plaza Richmond, VA 23261 /

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