Text

Physics Testing Rept for Cycle 5 Start-up.
	ML18047A292
Person / Time
Site:	Palisades
Issue date:	04/14/1982
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
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ML18047A291	List: ML18047A290; ML18047A292;
References
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CONSUMERS POWER COMPANY PALISADES PLANT - 50~255 PHYSICS TESTING REPORT FOR CYCLE 5 START-UP MARCH 1982 April 14, 1982

TABLE OF CONTENTS Page No.

Section 1 Introduction 1 Section 2 ARO HZP Critical Boron Concentration 2 Section 3 Regulating Rod Bank Worths - No Overlap 3 Section 4 Regulating Rod Bank Worths in Overlap Sequence 8 Section 5 Symmetric Rod Worths 10 Section 6 Moderator Tzmperature Coefficient ARO and 13 Regulating Banks In Section 7 Reciprocal Soluble Boron Worth 14 Section 8 Power Distribution 15 Section 9 Conclusion 19 References 20

1 SECTION 1 - INTRODUCTION This report presents the results of low power and power physics testing performed at the beginning of Cycle 5 at the Palisades Nuclear Power Plant. The following approved procedures were used for the testing:

Special Test No. Title T-141 Low Power Test Program for Palisades Core 5 T-142 Base Power Level Selection T-143 Zero Power Isothermal Temperature Coefficient Measurement' T-144 Zero Power Rod Worth Measurements T-145 Zero Power Symmetry Check Results presented in this report were obtained from the performance of the

.above tests -except the power distribution data which came from the INCA computer output. Measured results were compared to predicted results (see Reference 1) to ascertain whether or not review and acceptance criteria were violated (see Reference 2). Sections 2 through 7 of this report contain the test results with each section covering a particular test result.

The results presented are:

1. ARO HZP Critical Boron Concentration

2. Regulating Rod Bank Worths, No Overlap

3. Regulating Rod Bank Worths in Overlap Sequence

4. Symmetric Rod Worths

5. Moderator Temperature Coefficient ARO and Regulating Banks In

6. Reciprocal Soluble Boron Worth

7. Power Distribution

2 SECTION 2 - ARO HZP CRITICAL BORON CONCENTRATION The all rods out (ARO) hot.zero power (HZP) critical boron concentration was determined by obtaining a boron concentration with Gr 4 rods at approximately the ARO configuration. The residual worth of Group 4 was then measured on the reactivity computer and this was correlated to a change in boron concen-tration via the reciprocal boron worth. The boron concentration with Gr 4 at approximately the ARO configuration was added to the residual worth boron concentration and this result is presented below. Review and acceptance criteria. were not exceeded.

TABLE 1 Results of ARO HZP Critical Boron Concentration Measured Predicted Difference 1295 ppm 1320 ppm 25 ppm Review criterion - Measured value within 70 ppm of predicted Acceptance Criterion - None

3 SECTION 3 - REGULATING ROD BANK WORTHS - NO OVERLAP The worths of the regulating rod banks were measured by diluting the primary coolant system at a constant rate, 4o gpm, and trading positive reactivity due to the dilution with negative reactivity due to rod insertion.

The rods were inserted in the manual group mode in the order 4, 3, 2, 1.

Results are presented in Table 2 and as can be seen review and acceptance criteria .. were not exceeded. Figures 1 - 4 present graphs of the measured integral rod worths.

TABLE 2 Results of Regulating Rod Bank Worths - No Overlap Group Measured %Lip Predicted %Lip %Deviation %Lip Deviation 4 .421 .444 -5.2 -.023 3 .909 .883 2.9 .026 2 .473 .565 -16.3 -.092 1 1.424 1.488 -4.3 -.064 4+3+2+1 3.227 3.380 -4.6 Review Criterion - Individual rod banks within 15% or 0 .15% tl.p of predicted Value, whichever is greater Acceptance Criterion - Sum of regulating banks within 10% of prediction

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8 SECTION 4 - REGULATING ROD BANKS WORTH IN OVERLAP SEQUENCE The sequential worth of regulating rod banks was measured by borating the primary coolant system at a constant rate, 5 gpm, and trading negative reactivity due to boration with positive reactivity due to withdrawal of the rods. Results are presentBd in Table 3. Figure 5 displays a graph of the measured integral rod worth in sequential mode. Review and acceptance criteria were not exceeded.

TABLE 3 Results of Regulating Rod Bank Worths in Overlap Sequence Measured %6p Predicted %6p %Difference 3.224 3.380 -4.6 Review Criterion - None Acceptance Criterion - Sum of regulating banks within 10% of prediction

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I 10 SECTION 5 - SYMMETRIC ROD WORTHS The testing of SYlllIIletric rods consisted of inserting one rod in a SYlllIIletric group while withdrawing a second rod in the same SYlllIIletric group and repeating this sequence for all rods in a SYlllIIletric group. This process was performed for all symmetric groups. Table 4 presents the %deviation of rod worths in a symmetric group from the group average worth. This is also displayed in Figure 6 in which a slight tilt is observed. No significant tilt was observed at power (see Section 8). Review and acceptance criteria were not exceeded.

TABLE 4 Results of SYlllIIletric Rod Worths Group* A Outer Rods Rod No. % Deviation from Group Average 1 -5.27 2 -6.18 3 - .36 4 -5.45 9 3.27 10 0.00 11 8.00 12 6.55 Group A Inner Rods Rod No. %Deviation from Group Average 5 -1.87 6 1.17 7 -1.96 8 2.64

11 Group B Rods Rod No. %Deviation from Group Average 13 -5.36 14 -5.78 15 - .38 16 -2.38 17 2.45 18 .31 19 7.08 20 4.o4 Group 1 Rods Rod No. %Deviation from Group Average 21 -5.29 22 -5.44 23 - .59 24 74 25 .44 26 .29 27 8.82 28 7.21 Group 2 Rods Rod No. %Deviation from Group Average 29 -2.20 30 -3.73 31 3,39 32 2.55 Group 3 Outer Rods Rod No. %Deviation from Group Average 33 -7.05 34 .32 36 -1.71 37 8.58 Grou:;:i 4 Rods Rod No. %Deviation from Group Average 38 -2.64 39 -6.45 40 5.97 41 3.10 Review Criterion - Each individual rod within 10% of the symmetric group average Acceptance Criterion - Each individual rod within 20% of the symmetric group average.

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13 SECTION 6 - MODERATOR TEMPERATURE COEFFICIENT ARO AND REGULATING BANKS IN The moderator temperature coefficient (MTC) was determined at essentially the all rods out 1 ARO;configuration and the configuration with the regulating groups inserted. The MTC was determined by observing reactivity changes on the reactivity computer while cooling or heating the primary coolant system. From the reactivity and temperature changes, an isothermal temperature coefficient (ITC) was determined from which the MTC was extracted using the relationship ITC = MTC + doppler. The doppler coefficient can be found in Reference 1 and has a value of -1.55 X 10- 5 lip/°F. The MTC determined for the ARO case was extrapolated to full power using the techni~ue given in Reference 3. Results from the MTC measurements are given in Table 5 and as can be seen, review and acceptance criteria were not exceeded.

TABLE 5 Results of MTC Measurements Measured Value Rod Position Measured Predicted Difference Extra12olated to Full Pwr ARO 2.9ox10-5tip/°F 2.50xl0- 5lip/°F .40xl0=~lip/°F (-4.67+/-1) xl0 7 5lip!°F Reg groups in -4.36x1Q-5lip/°F -5. 2ox10-5 lip /°F .84xl0 lip/°F Review Criterion - Measured value within 5xl0- 5lip/°F of the predicted value.

Acceptance Criterion - Measured value between 5xl0- 5lip/°F and -35xl0- 5lip/°F when extrapolated to full power

..... 14 SECTION 7 - RECIPROCAL SOLU13LE BORON WORTH The reciprocal soluble boron worth was determined from the boron concentration at two end points and the reactivity difference between the end points. The end points used in this test were all rods out and regulating groups inserted.

Results of the reciprocal soluble boron worth are given in Table 6. Review &

acceptance criteria . were not exceeded.

TABLE b Reciprocal Soluble Boron Worth Measured Predicted Difference 92.5ppm/%tip l00.6ppm/%tip -8.lppm/%tip Review Criterion - Within 15ppm/%tip of the predicted value.

Atteptance Criterion - Less than 125ppm/%tip.

15 SECTION 8 - POWER DISTRIBUTION Power distribution information was obtained from the computer routine INCA which uses incore detector readings to evaluate power distribution parameters.

The INCA program is routinely run and the computer run chosen for this report was one at 98% power and 224.5 MWD/MTU burnup. The information derived from the INCA output consisted of quadrant tilt, assembly power and assembly power RMS deviation. The assembly powers and assembly power RMS were compared to the predicted information supplied by Exxon in References 1 and 4. The predicted information was taken from a PDQ computer run at 100% power and 150 MWD/MTU burnup and an XTG computer run at 98% power and 150 MWD/MTU burnup.

Quadrant Tilt The INCA calculated quadrant tilt of .13% is well below the review criterion of 3%. Quadrant tilt did not have an acceptance criterion.

Assembly Power PDQ predicted assembly power, measured assembly power, and percent difference between the two are given in Figure 7, The review criterion was not met for the comparison shown in Figure 7, The bundle closest to the center of the core shows a difference between measured and PDQ predicted assembly power of 18.5%

which exceeded the criterion of 10%. The assemblies that exceed the review criterion are second cycle B 4

c p*oisoned assemblies.

An evaluation of the discrepancy was conducted. This evaluation entailed:

1. A review of the incore detection system.

2. A review of the INCA program.

3, A review by Exxon of their neutronics methodology.

4. A comparison of Consumers Power's XTG theorectical power distribution to the measured pcwer distribution of INCA.

16 Results of this evaluation indicated that there was a difficulty in Exxon's neutronics methodology for assemblies poisoned with B 4

c. Modifications were made in the modeling of B 4c and a reanalysis of the power distribution was performed. A revised comparison of measured and XTG pr~dicted assembly power is shown in Figure 8. This comparison meets the review criterion for assembly power. Similar corrections were made to the ENC PDQ calculation, but the improved power distribution still does not meet the review criterion with respect to the center assembly. As a result ENC has initiated a thorough investigation of their palisades PDQ model. This work has not been completed as of the date of this submittal.

Based on the revised XTG comparison and the agreement between XTG and INCA dUring cycle 4 we have concluded that the power distributions from INCA are accurate and that the core was loaded as intended. Additional supportive evidence for the above conclusion is that completely independent theorectical XTG calculations performed by Consumers Power Company meet the review criterion. Also, the Consumers Power XTG power distribution is in close agreement with Exxon's revised XTG.

Assembly Power RMS Deviation Assembly power RMS deviation calculated from the assembly powers is also displayed in Figures 7 and 8. The review criterion of 5% was slightly exceeded by the 5.2% result displayed in Figure 7. The RMS deviation for the revised XTG a~alysis is 3.40%, which is well within review criterion.

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r 19 SECTION 9 - CONCULSION Low power and power physics testing was conducted at the beginning of core 5 with the last test. finished on January 14, 1982. The testing determined and c_ompared to calculated results various core parameters such as:

1. Boron Concentrations

2. Rod Worths

3. Reciprocal Boron Worth

4. Moderator Temperature Coefficient

5. Assembly Power Review and acceptance criteria were met for all parameters except assembly power.

The assembly power anomaly was isolated to the neutronics methodology on B 4

c poisoned assemblies. This methodology is currently being updated.

l 20 REFERENCES

1. Palisades Cycle 5 Startup and Operations Report, XN-NF-81-68, Exxon Nuclear Company, September 1981.

2. Letter from Consumers Power, DPHoffman to Director Nuclear Reactor Regulation, Palisades Plant - Physics Test Program, October 31, 1979.

3. Palisades Plant Technical Specification, Section 3.12.

_4. Letter from JAUmbarger to DMKennedy, Palisades Cycle 5 XTG-INCA Comparison, March 22, 1982.

ML18047A292

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