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{{#Wiki_filter:OC1084-0011-NL02 ATTACHMENT Consumers Power Company Palisades Plant -Docket 50-255 PHYSICS TESTING REPORT FOR CYCLE 6 START-UP October 1984 20 Pages Section 1 Section 2 Section 3 Section 4 Section 5 Section 6 Section 7 Section 8 Section 9 TABLE OF CONTENTS Introduction ARO HZP Critical Boron Concentration Regulating Rod Bank Worths -No Overlap Regulating Rod Bank Worths in Overlap Sequence Symmetric Rod Worths Moderator Temperatur*e Coefficient ARO and Regulating Banks In Reciprocal Soluble Boron Worth Power Distribution Conclusion References MI1084-0235A-TC01 Page No. 1 2 3 8 10 14 15 16 18 19 1 SECTION 1 -INTRODUCTION This report presents the results of low power and power physics testing per-formed at the beginning of Cycle 6 at the Palisades Nuclear Power Plant and is identical in format to the Cycle 5 report. The following approved proce-dures were used for the testing: Special No. Title T-141, Revision 1 Low Power Test Program for a New Palisades Core T-142, Revision 1 .Base Power *Level Selection T-143, Revision 1 Zero Pbwer Isothermal Temperature Coefficient Measurement T-144, Revision 1 Zero Power Rod Worth Measurements
{{#Wiki_filter:ATTACHMENT Consumers Power Company Palisades Plant - Docket 50-255 PHYSICS TESTING REPORT FOR CYCLE 6 START-UP October 1984 20 Pages OC1084-0011-NL02
.. T-145, Revision 1 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 com-puter 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
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 Temperatur*e Coefficient ARO and        14 Regulating Banks In Section 7      Reciprocal Soluble Boron Worth                    15 Section 8      Power Distribution                                16 Section 9      Conclusion                                        18 References                                        19 MI1084-0235A-TC01
 
1 SECTION 1 - INTRODUCTION This report presents the results of low power and power physics testing per-formed at the beginning of Cycle 6 at the Palisades Nuclear Power Plant and is identical in format to the Cycle 5 report. The following approved proce-dures were used for the testing:
Special  T~st No.                                Title T-141, Revision 1          Low Power Test Program for a New Palisades Core T-142, Revision 1        .Base Power *Level Selection T-143, Revision 1          Zero Pbwer Isothermal Temperature Coefficient Measurement T-144, Revision 1          Zero Power Rod Worth Measurements T-145, Revision 1
                        ..      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 com-puter 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  S~quence
: 4. Symmetric Rod Worths S. Moderator Temperature Coefficient ARO and Regulating Banks In
: 6. Reciprocal Soluble Boron Worth
: 7. Power Distribution MI1084-0235A-TC01
 
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 conf~guration. 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  bo~on 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

Revision as of 19:52, 21 October 2019

Physics Testing Rept for Cycle 6 Startup.
ML18051B103
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/31/1984
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051B102 List:
References
NUDOCS 8411060386
Download: ML18051B103 (21)


Text

ATTACHMENT Consumers Power Company Palisades Plant - Docket 50-255 PHYSICS TESTING REPORT FOR CYCLE 6 START-UP October 1984 20 Pages OC1084-0011-NL02

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 Temperatur*e Coefficient ARO and 14 Regulating Banks In Section 7 Reciprocal Soluble Boron Worth 15 Section 8 Power Distribution 16 Section 9 Conclusion 18 References 19 MI1084-0235A-TC01

1 SECTION 1 - INTRODUCTION This report presents the results of low power and power physics testing per-formed at the beginning of Cycle 6 at the Palisades Nuclear Power Plant and is identical in format to the Cycle 5 report. The following approved proce-dures were used for the testing:

Special T~st No. Title T-141, Revision 1 Low Power Test Program for a New Palisades Core T-142, Revision 1 .Base Power *Level Selection T-143, Revision 1 Zero Pbwer Isothermal Temperature Coefficient Measurement T-144, Revision 1 Zero Power Rod Worth Measurements T-145, Revision 1

.. 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 com-puter 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 S~quence
4. Symmetric Rod Worths S. Moderator Temperature Coefficient ARO and Regulating Banks In
6. Reciprocal Soluble Boron Worth
7. Power Distribution MI1084-0235A-TC01

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 conf~guration. 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 bo~on 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 1246 ppm 1271 ppm 25 ppm Review criterion - Measured value within 70 ppm of predicted Acceptance Criterion - None MI1084-0235A-TC01

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, 50 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 'YAp Predicted 'YAp  % Deviation 'YAp Deviation 4 .353 .398 -11.3 -.045 3 .937 .874 7.2 .063 2 .446 .469 - 4.9 -.023 1 1.408 1.395 0.93 .013 4+3+2+1 3.144 3.136 0.26 Eeview Criterion - Individual rod banks within 15% or 0.15'}'.,D.p of predicted value, whichever is greater Acceptance Criterion - Sum of regulating banks within 10% of prediction MI1084-0235A-TC01

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SECTION 4 - REGULATING ROD BANKS WORTH IN OVERLAP SEQUENCE The sequential worth of regulating rod banks was measured by borating the pri-mary 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 presented 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 r

Measured 'YoLip Predicted '}'Ap  % Difference 3.122 3.136 -0.45 Review Criterion - None Acceptance Criterion - Sum of regulating banks with 10% of prediction MI1084-023SA-TC01

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10 SECTION 5 - SYMMETRIC ROD WORTHS The testing of syrrunetric rods consisted of inserting one rod in a symmetric group while withdrawing a second rod in the same symmetric group and repeat-ing this sequence for all rods in a symmetric group. This process was per-formed for all syrrunetric groups. Table 4 presents the  % deviation of rod worths in a symmetric group from the group average worth. The review crite-rion was not met in 5 of 7 rod groups and, as displayed in Figure 6, there is a tilt indicated in the direction of the primary coolant system hot legs.

From Reference 4, the results of a detailed engineering review indicate there is a small core power tilt which was the primary reason for some of the periph-eral rods exceeding the review criteria. The tilt is most likely due to slightly different burnup characteristics across the core caused by a steam generator driven cold leg temperature difference.

The computer routine INCA confirms a tilt in the direction of the hot legs but of lower magnitude. The tilt is believed to be amplified in the symmetric rod worth test because of the very low power and the fact that the rod worth is proportional to the flux squared.

We have concluded that the core power tilt is low enough not to be of concern at power (see Section 8) and is not indicative of a core loading error.

MI1084-023SA-TC01

11 TABLE 4 Results of Symmetric Rod Worths Group A Outer Rods Rod No.  % Deviation. from Group Average 1 -11. 7 2 - 9.85 3 - 6.51 4 - 5.25 9 2.34 10 5.32 11 10.4 12 15 .3 Group A Inner Rods Rod No.  % Deviation from Group Average 5 - 5. 79 6 0.25 7 - 1.48 8 7.02 Group B Rods Rod No.  % Deviation from Group Average 13 - 6.70 14 - 6.91 9.74 15 -

16 - 6.48 17 0.60 18 3.86 19 12.2 20 1.3. 2 MI1084-0235A-TC01

12 Group 1 Rods Rod No.  % Deviation from Group Average 21 - 8.97 22 -12.0 23 - 7.23 24 - 4.44 25 26

- 1.14 2.00 27 15.4 28 16.4 Group 2 Rods Rod No.  % Deviation from Group Average 29 - 3.31 30 - 6.49 31 5.03 32 4.76 Group 3 Outer Rods

,* ..

Rod No.  % Deviation from Group Average

33. -11.0 34 - 3.80 36 - 1. 75 37 16.6 Group 4 Rods Rod No.  % Deviation from Group Average 38 - 8.20 39 - 8.38 40 *-6.33 41 10.2 Review Criterion - Each individual rod within 10% of the symmetric group average Acceptance Criterion - Each individual rod within 20% of the symmetric group average MI1084-0235A-TC01

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14 SECTION 6 - MODERATOR TEMPERATURE COEFFICIENT ARO AND REGULATING BANKS IN The moderator temperature coefficient (MTC) was determined at essentially the all rods out, 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 r~activity and temperature changes, an isothermal temperature co-efficient (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 -1.6Z x 10- 5 ~p/°F. The MTC determined for the ARO case was extrapolated to full power using the technique 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 Extrapolated to Full Pwr.

Rod Position Measured Predicted Difference and Equalibr{um Xenon ARO

-5 l.13x10_ ~p/°F 5 ~p/°F l.70xl0=;~p/°F .57xlo=;~p/°F (-6.35+/-1)xl0- 5 ~p/°F Reg groups in -5.54x10 -5.50x10 ~p/°F .04x10 ~p/°F 5

Review Criterion - Measured value within 5xl0- Kp/°F of the predicted value.

Acceptance Criterion - Measured value between 5xl0- 5 ~p/°F and -35xl0- ~p/°F 5

when extrapolated to full power.

MI1084-0235A-TC01

15 SECTION 7 - RECIPROCAL SOLUBLE 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 inserteti.

Results of the reciprocal soluble boron worth are given in Table 6. Review and acceptance criteria were not exceeded.

TABLE 6 Reciprocal Soluble Boron Worth Measured Predicted Difference 92.7 ppm/%llp 103.4 ppm/r.,llp -10.7 ppm/r.,llp Review Criterion - Within 15 ppm/~AP of the predicted value Acceptance Criterion - Less than 125 ppm/~AP MI1084-0235A-TC01

16 SECTION 8 - POWER DISTRIBUTION Power distribution iniormation 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 79% power~*: and 135. 9 tlWD/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 Rl'IS were compared to the predicted information supplied by Exxon in Reference 1. The predicted informa-tion was taken from a PDQ computer run at 100% power and 150 MWD/MTU burnup.

Quadrant Tilt The INCA calculated quadrant tilt of 0.50% 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 and acceptance criteria were not exceeded.

Assemblv Power RMS Deviation Assembly power RMS deviation calculated from the assembly powers is also dis-played in Figure 7 . . The RMS deviation of 4.7% was within the 5% review cri-terion.

  • Due to several forced outages since Cycle 6 start-up, full power has not yet been achieved and a supplementary report will be submitted per Reference 5 after reaching full power.

MI1084-0235A-TC01

46 0/'02

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18 SECTION 9 - CONCLUSION Low power and power physics testing was conducted at the beginning of cor~ 6 with the power distribution test at 79% finished on September 7, 1984. The testing determined and compared to calculated results various core parameters such as:

I. 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 symmetric rod worths. It has been determined that the symmetric rod worth test revealed a small core power tilt low enough not to be of concern at power and not indic-ative of a core loading error.

A supplementary report will be submitted for power distribution after reaching full power.

MII084-0235A-TC01

  • 19 REFERENCES
1. Palisades Cycle 6 Start-Up and Operations Report, XN-NF-83-81, Exxon Nuclear Company, September 1983.
2. Letter from Consumers Power, DPHoffman to Director Nuclear Reactor Regula-tion, Palisades Plant - Physics Test Program, October 31, 1979.
3. Palisades Plant Technical Specifications, Section 3.12.
4. Letter from TEHollowell to DVanDenBerg, Technical Review of Palisades Cycle 6 "Zero Power Symmetry Check" Test Results, September 28, 1984.
5. Palisades Plant Technical Specifications, Section 6.9.1.

MI1084-023SA-TC01