ML20086A570

Cycle 9 Startup Physics Test Rept

ML20086A570
Person / Time
Site:	Beaver Valley
Issue date:	11/05/1991
From:	Mclain D, Moul D, Noonan T DUQUESNE LIGHT CO.
To:
Shared Package
ML20086A569	List: ML20086A565 ML20086A570
References
NUDOCS 9111190239
Download: ML20086A570 (13)

Text

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DUQUESNE LIGTP COMPANY BEAVER VALIEi POWER STATIO1 UNIT 1 CYCLE 9 c

STAR'IUP PHYSICS TESP REIORT Prepared by: . f. 4is Reviewed by: . -~

D.A.Mml T. G. a Reactor Engineer Plant Perfonnance Director Raviewed by: M//M l Approved W

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D. G. McLain T. P. Noonan Technical Service Kmager General Manager Nuclear Operatiorts l

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9111190239 911103 PDR. ADOCK 05000334 P FDR

4 BFAVER VALLEY POWER STATIQ1 Cycle 9 Startun Test Report INIRODUCTIGE Daaver Valley Unit 1 was shutdown on April 12, 1991 for its Eighth Refueling Outage. During the outage, 72 of 157 fuel assemblics were replaced with_ a split batr31: 20 fuel ar e lies of 3.60 w/o enrichment airl 52 fuel assemblics of 4.00 w/a enrichment. 'Ihe fresh fuel rods are based on the Vantage 55! design with natural uranium in the top and bottcan six inches.

Ascamblics with Intayral Fbel Burnable Absorbers (IFBA) have arrangem3nts of 80, 104, or 128 rods with boride-coated pellets in the central 120 inches.- A region of unpoisoned fuel six inches in lergth is found between the natural tr:anium and the boride-coated fuel in these IFBA fuel assemblies. Ca pared to the IFDA in Cycle 8, tne B-10 loading for Cycle 9 has bcci increased from 1.57 ng/in to 2.35 ng/in.

'Ihis report describes the startup test program applicable for the cycle 9 reload core design verification for BVP3, Unit 1. 'Ih.t. testing program consisted of the following measurements conductcd frani .Tuly 3,1991 through -

August 7, 1991:

1. Control rod drop time

2. Initial criticality

3. Boron endpoints

4. Control bank worths

5. 'Ibmperature coefficicnt

6. Reactivity conputer checks

7. 30% power symmetry check

8. Incore/Excore cr:ss-calibration

9. Power distribution measurements at 60% and 100% reactor power.

'Ihe results of these startup tests are summarized in this report and comparisons are nude- to predicted design values and applicable BV 3 Technical Specification Requirements.

PAGh 1 OF 12

Beaver Valley Power Station Cycle 9 Startup Test Report TEST SLM MRIES:

1BVP 1.1.1_"Qontrol Rod Droo Tine Measuremnts" PURPOSE:

The purpose of this test was to detcrmine a drop tim for each full-length Rod Cluster Assembly with the RCS in Hot Standby, Tavg 2: 541*F, and full RCS flow.

TEST DESCRIPTION:

A sirgle RCCA Bank is withdrawn to the full-out position 031 steps' 2 .

visicorder is connected to the detector primary coil and test.13 ads are dicn inserted at the stationary gripper coil jacks in the power cabinets. The RCCA blown fuse irdicator and movire coil fuse are removed. After the '.isicorder ir turned ON, an assembly is dropped by pullirg the stationary gripper fuse out.

Each of the 48 rod cluster assemblies are tested in this manner and the drop times are determined fram the start of stationary gripper voltage decay to darhpot entry oi. the visimrder traces.

RESULTS:

The test was performed on July 3, 1991. The drop times of all 48 rods were well within the BVPS Technical Specification Requirement of < 2.7 ch , with slowest time beirg 1.33 seconds for rod B-6 at hot full RCS flow. Figure 1 rhows the drop times for each rod.

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Beaver Valley Power Station Cycle 9 Startup 7bst Report 1BVT 2.2.1. " Initial Aroroach to Criticality" PURIOSE:

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 7bsting Band (ZPPIB); (3) verify the proper calibration of the reactivity caputer.

TEST DESCRIPTION:

Initial conditions wera established with shutdown banks fully withdrawn, control banks fully inse.rted, RCS boron concentration of 2008 ppm, RCS terperature at 547'F and RCS pressure at 2239 psig on July 17, 1991 at 09:11.

The control banks are witMrawn in 50 step intervals until control Bank D reached 160 steps. An Inverse Count Rate Ratio (ICRR) was taken at each interval. Durirg control rod withdrawal, the ICRR dropped from 1.0 to 0.46.

Dilution to criticality commcaced at 1050 at a rate of approximtely 750 pcm/hr. Again, the ICRR was monitored and plotted at 20 minute intervals. At 15:50 on July 17, 1991 after 11,150 gallons had been added, criticality was achieved. -

Following the reconiing of criticality data, flux was increased toward i

nuclear heat. Nuclear heat occurred at 8.6 x 10~7 arps as indicated on the reactivity computer strip chart recorder by increasing Tavg and/or an exponential decay of the reactivity trace.

A reactivity computer .cperational checkout was then performed using the reactor with positive reactivity insertions of 18.0 pcm, 27.5 pcm, and 49.5 pcm as indicated by the reactivity computer. The doubling times were also reasured

~dar the reactor period calculated. The calculated period was then input to the Westinghouse Nuclear Design Report camputer program which provided predicted reactivity values based on the reactor period. Predicted reactivity was campered to measured for each insertion. 1BVr 2.2.1 was completed at 19:48 on July 17, 1991.

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!- RESULTS:

The All Rods Out .(ARO) critical boron concentration corrected for rod l position was calculated to be 1655 ppm which was within the acceptance criteria I

range of 1637 to 1737 ppm.

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PAGE 3 OF 12

Beaver Valley Power station f

Cycle 9 Startup Test Report The Ze 8.6 x 10- p arpo Power Physica based 'Ibst Band on remainirg (ZPPIB) a decade wasthe below set at 9.4 x nuclear measured 10-9 ampo to 7 aqxt ard remaining a decade above the background heatire point of 8.6 xi current readiry of 9.4 x 10 gO amps on the power rarge detectors.

All the test runs for the reactivity computer were within the acceptance criteria of i 4%. The errors for the three test cases were 2.7%, 0.7% ard 2.0%.

PAGE 4 OF 12

- Beaver Valley Power Station Cycle 9 Startup Test Report 1EVP 2.2.2, " Core Desicrn Check Test" IUPJOSE:

The purpose of this test was to verify the reactor core design frca hct zero power to 100 percent reactor power, ard to perform the incore/excore cross-calibration.

TEST DESCRIPTION:

The test was divided into five parts:

Section A covered zero power physics tests. These tests included boron erdpoint measurements, boron dilution worth measurement of the reference bank (CBB), rod swap bank worths, differential baron worth, and an isothermal temperature coefficient measurement.

Section B involved verifying core symmetry and proper core loading by performing a full-core flux map prior to exceeding 30% reactor power.

Section C required a full-core flux map to to obtained prior to exceeding 75% reactor power to ensure the measured peaking factors were within their applicable Technical Specification Limits.

Section D required an incore/excore calibration between 50% and 90% of rated thermal power. This involved performing 1BVT 2.2.3, " Nuclear Power Range Calibration", in which a series of flux maps are run at various axial offsets.

Finally, Section E invclved performing a full-core flux map at 100% reactor power. This map served as a calibration check for the incore/excore calibration and verified that the power distribution limits of the Technical Specifications were not exceeded. ,

RESULTS:~

IloIon Endpoint:

The All Rods Out (ARC) critical boron concentration was measured to be 1647 ppm at 22:12 on July 17, 1991, which was within the acceptance criteria of 1637 to 1737 ppm.

The Control Bank B-in critical boron concentration was reasured to be 1356 ppn at 19:08 on July 18, 1991, which vm within the acceptance criteria of 1268 to 1716 ppm.

PAGE 5 OF 12

Beaver Valley Power Station Cycle 9 Startup Test Report ROC L%nk Worths:

The boron dilution reasurement of the reference bank for rod swap, CBB, was ccmpleted at 19:08 on July 18, 1991. Following the insertion of CBB, the worths of the remaining control and shutdown banks were obtained relative to CBB. The reasured worth, predicted worth, and percent difference for each RCC bank and total worth of all RCC banks are listed in Table 1. Figures 2 and 3 provide a graphical representation of differential and integral rod worth respectively for CBB. All montred values were within the accepWre criteria for this test as listed in Table 1.

Differential Epj:on Worth:

The measured differential boron worth was 7.42 pcm/ ppm. This value was within the acceptance criteria of 7.19 pcm/ ppm i 15%.

Tercerature Coefficient:

The ABO, HZP Isothermal Terporature Coefficient (IIC) was measured at 03:37 on July 18, 1991. The average ITC was determined to be -2.40 pcm/'F which was within the acceptance criteria of -3.52 3 pcm/'F.

Subtracting out the predicted design value of the doppler coefficient

(-1.93 pcm/ *F) from the measured l'IC, the MIC was calculated to be j -0.47 pcm/'F. This value meets the rcquirements of BVPS Technical l Specifications which rcquire the MIC to be between -50 pcm/*F and 0 pcm/'F. In l addition, tre station has in place procedures to ensure that a negative MIC is raintained throughout Cycle 9 core 41fe.

Reactivity Computer:

l The reactivity computer was checked prior to low Power Physics Testing (IPPT) , 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 conputer was checked using l

the reactor following initial criticality. In all cases, the computer error was within .the 4%-acceptance criteria, with the highest measured error being 2.7%.

30 Percent Power Symmetry Check:

A full-core flux map was performed on July _23, 1991 at approxir:ately 30%

reactor power with CBD at 175 steps to determine the initial flux distribution in the cnre. Table 2 lists the values for quadrant tilt and maxmum deviation fram predicted assembly powers for the 30% flux map. All measured values were l within the acceptance criteria for the test.

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l PAGE 6 OF 12

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Beaver Valley Power Station Cycle 9 Startup Test Report 60 Percellt Power Flux 330 ard Incore/Excore Calibratioj):

On July 31, 1991 1BVT 2 . 2 . '; , " Nuclear Power Range Calibration", was performed at approximately 60% pwer. One full-core and six quarter-core flux maps were obtained at various axial offsets to calibrate the excore detectors and verify core peakin; factors. S e results of the full-core flux map are shown in Table 2. All measured values were within the acceptance criteria.

We neasured Pxy corrected for uncertainties was 1.7845 for the 60% flux map. -

he Technical Specifications rcquire that this value be less than Fxy(RTP)

(1.79) arrl Fxy(LIM) (1.9323 for 60% power) . 21s rcquirement was met.

100 Percent Power Flux Map:

On August 7, 1991 a full-core flux map was performed at 100% power. mis map served as a check for the incero/excore calibration ard power distribution limits. Se measured Fxy including uncertainties was 1.7580 which was below Fxy (RTP) by 1.79% and FYy (LIM) by 1.91%. Se results of the map are shown in Table 2.-

he 100% flux map marked the completion of the reload startup test program for Beaver Valley Power Station, Unit 1, Cycle 9.

e PAGE 7 OF 12

'I 1 FIGURE 1 Unit 1 Cycle 9 HFF Rod Drops R P N M L K J H G F E D C B A 1

g 1.23 1.24 1.22 1.70 1.73 1.70 3 l 1.18 1.es l

1.68 1.68 4 14. ; 1.23 1.25 1.20 1,73 1.70 1.70 1.70 5 1.23 1.23 1.67 1,67 g 1.22 1.25 1.25 1.20 1.25 1.25 1.33 1 68 1.70 1.70 1.65 1.78 1.68 1.86

/ 1.22 1.24 1.22 1.22 1.70 1.68 1,66 1.68 g 1.25 1.20 1.20 1 30 1.76 1.72 1,68 1.78 9 1.20 1.2 s 1.24 1.20 1.65 1.6G 1.67 l 1.66 10 1.23 1.24 1.25 1.20 1.23 1.24 1.2 s 1.68, 1.77 1.76 1.67 1,70 1.06 g ,7 7

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11 1 1.2 s 1.24 1,69 1.69

-12 1.22 1.24 1.2 s 1.18 1.70 1.69 1,70 1.68 -

13 1.22 1.20 1.67 1 67 j j4 1.30 1.26 1.23 1.82 1.72 1.77 15 Average C:'op Time a 1.23 sec.

Fastest Drop Time = 1.18 sec.

Slowest Drop Time = 1.33 sec.

X.XX Breaker " Opening" to dashpot entry - sec.

X.XX Breaker " Opening" to dashpot bottom - sec.

l PAGE 8 0F 12 t

Beaver Valley Power Station Cycle 9 Startup Test Report l

TABLE 1 CONITOL ROD BANK iORIliS hmed Predicted Value Value Error Acceptance

- J!Mk (oc7n) (Dem)_ (%) Criteria CBD 1016.0 1061 -4.24 i 15%

f' y CBC 697.5 749 -6.88 i 15%

i I CBB

• 1356.0 1408 -3.69 10%

CBA 396.6 442 -10.27 1 15%

SBB 962.0 1000 -3.80 1 15% I I

SBA 875.8 936 -6.43 15% l

'Ibtal Worth 5303.9 5596 -5.22 1 10%

• Reference Bank for Rod Swap

a PAGE 9 OF 12

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e Beaver Valley Power Station Cycle 9 Startup Test Report TABLE 2 Iul CDRE FWX MAPS 30% Power 60% Power 100% Power CBD CBD CBD Acceptance Parameters 175 sters 190 stem 225_sters Criteria Quadrant 1.0142 1.0135 1.0113 5 1.02 for maps Tilt above 50%

Maximum Deviation 5.2% 3.7% -4.8% t 10% ior frun Predicted Predicted Relative Assembly Powers Pownr > .9 F delta H N/A 1.5933 1.5703 7bch Spec.:

< 1.8132 for 60%

< 1.6230 for 100%

Pxy N/A 1.7845 1.7580 Tech Spec.:

< 1.9323 for'60%

Fxy (IUP) = 1.79

< 1.7922 for 1004 Fxy (RTP) = 1.79 PAGS 12 OF 12