W3F1-2002-0064, Ses Startup and Power Escalation Report for Cycle 12

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Ses Startup and Power Escalation Report for Cycle 12
ML021990702
Person / Time
Site: Waterford Entergy icon.png
Issue date: 07/12/2002
From: Peters K
Entergy Nuclear South, Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
A4.05, W3F1-2002-0064
Download: ML021990702 (20)
v • d • e


Text

Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70066 e Tel 504 739 6440 Fax 504 739 6698 kpeters@entergy.com Ken Peters Director, Nuclear Safety Assurance Waterford 3 W3F1-2002-0064 A4.05 PR July 12, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Startup and Power Escalation Report for Cycle 12 Gentlemen:

In accordance with Waterford 3 Technical Specification 6.9.1, Entergy is submitting the attached summary report for plant startup and power escalation testing for Waterford 3's Cycle 12 operation. Waterford 3 resumed commercial power operation on April 17, 2002 following the completion of refueling outage 11. As part of the refueling outage scope, the part-length Control Element Assemblies (CEAs) were replaced with full-length CEAs, four peripheral CEAs were removed, minor fuel mechanical design changes were made, and core thermal power was uprated from 3390 MWt to 3441 MWt in accordance with Appendix K of 10CFR50.

This letter does not contain any commitments. Should you have questions regarding this letter, please contact Mike Brandon at (504) 739-6254.

Very truly yours, Director, Nuclear Safety Assurance KJP/GCS/cbh Attachment cc: E.W. Merschoff (NRC Region IV), N. Kalyanam (NRC-NRR),

J. Smith, N.S. Reynolds, NRC Resident Inspectors Office (

ATTACHMENT TO LETTER W3F1-2002-0064 WATERFORD 3'S STARTUP AND POWER ESCALATION REPORT FOR CYCLE 12

TABLE OF CONTENTS Page 1.0 INTRO D UC TION ............................................................................... 2 2.0 REACTOR CORE DESCRIPTION .................................................... 2 3.0 LOW POWER PHYSICS TESTING .................................................. 5 3.1 Initial C riticality ...................................................................... .. 5 3.2 Critical Boron Concentration Measurement ............................ 5 3.3 Isothermal Temperature Coefficient Measurement ................ 5 3.4 CEA Group Worth Measurement ............................................ 6 4.0 POWER ASCENSION TESTING ...................................................... 7 4.1 Fuel Symmetry Verification .................................................... 7 4.2 Core Power Distribution Measurement ................................... 7 5.0 OPERATIONAL TESTING ............................................................... 9 5.1 Isothermal Temperature Coefficient Measurement ................. 9 6.0 C O N C LU S IO N S ............................................................................... 10 7.0 REFER EN C ES ................................................................................. 10 8.0 FIGURES Figure 1 Waterford 3 Original (Cycle 11) CEA Group Configuration ............................................................ 11 Figure 2 Waterford 3 Cycle 12 Revised CEA Group C onfiguration ............................................................. 12 Figure 3 Waterford 3 Cycle 12 Enrichment Zoning Pattern for B atch U Fuel ............................................................... 13 Figure 4 CECOR Results for Fuel Symmetry Verification ...... 14 Figure 5 GETARP Results at 68% Power with Westinghouse P redictions ................................................................. 15 Figure 6 GETARP Results at 100% Power with Westinghouse P redictions ................................................................. 17 1

1.0 INTRODUCTION

This report summarizes the results of the Waterford Steam Electric Station-3 (WSES-3) Cycle 12 startup physics test program, as it pertains to replacement of Part Length Control Element Assemblies (CEAs) with Full Length CEAs, removal of four peripheral 4-element CEAs, introduction of an inconel top grid in 36 of 92 fuel assemblies, and core thermal power uprate per Appendix K of 1.5%.

This program included pre-critical tests as well as those conducted during low power physics testing (LPPT), power ascension and at full power. While all tests performed as a part of this program were completed satisfactorily, not all test results are included in this summary. Only the tests deemed necessary to demonstrate acceptance of the measured core physics parameters were included.

The objectives of these tests were to demonstrate that, during reactor operation, the measured core physics parameters would be within the assumptions of the FSAR accident analyses and within the limitations of the plant technical specifications, as well as to verify the nuclear design calculations. It was also the intent of these tests to demonstrate adequate conservatism in the Cycle 12 core performance with respect to the WSES-3 FSAR, Technical Specifications, Cycle 12 Core Operating Limits Report (COLR), and Cycle 12 Reload Analysis Report.

2.0 REACTOR CORE DESCRIPTION The WSES-3 core originally contained 91 Control Element Assemblies (CEAs),

of which 83 were full length, full strength and eight (commonly referred to as PLRs) were part length containing only a part length poison column. Of the 83 full length CEAs, 79 were standard five-element design and 4 were four-element CEAs, not possessing a center poison rod or finger. The four-element CEAs each spanned two fuel assemblies at the core periphery's major axes and were assigned to Shutdown Bank A. The four-element CEAs were commonly referred to as 4-Finger CEAs and/or Mini-Dual CEAs. The original purpose of the PLRs was to provide control of axial power distribution, particularly in the event of axial xenon oscillations. The original purpose of the 4 four-element CEAs was to provide additional scram worth, particularly for the steam-line break event.

At the end of Cycle 11, during the RF1 1 refueling outage, the 4 four-element CEAs were removed from the core and the 8 part length CEAs were replaced with standard full length, five-element design CEAs. Commencing with Cycle 12, the WSES-3 core will have a total of 87 CEAs, all of the standard full-length five element design.

2

As part of the Part Length Rod Replacement effort, the CEA bank configurations and Power Dependent Insertion Limits (PDILs) were also modified. The eight (8)

Part-Length CEAs comprising the original part-length CEA banks were replaced with full-length, full strength CEAs as previously discussed and reassigned to Shutdown Bank A. Four (4) full-length CEAs from Shutdown Bank A were reassigned to Bank P. Therefore, as a result of Part Length Rod Replacement and 4-element CEA removal, Shutdown Bank A consists of 18 standard full strength CEAs and Bank P consists of 4 standard full length, full strength CEAs.

See Figure 1 and 2 for additional information.

The smaller reconfigured full length, full strength Bank P along with the unmodified Regulating CEA Bank 6 will provide ample control of axial power distribution and axial xenon oscillations. The contribution of the 4 four-element CEAs, located on the core periphery, to scram worth has diminished for recent core designs that employ low leakage fuel management strategies. Therefore, the net effect on scram worth of removing the four-element CEAs and replacing the PLRs with full length CEAs is a neutral to small increase in scram worth.

A total of 92 new Batch U fuel assemblies were loaded with fuel rod enrichments of 4.17 and 4.57 w/% U-235. 2.1 w/% erbia as a burnable absorber is included in some of the 4.17 w/% U-235 fuel rods. In addition, 49 Batch S and 76 Batch T assemblies were loaded into the Cycle 12 core. See Figure 3 for additional enrichment information.

With the exceptions discussed below, the mechanical design of the Waterford Batch U and Batch T reload fuel bundle assemblies are identical. The mechanical design bases have not changed since the original fuel design.

The following features/processes have changed for Batch U fuel assemblies.

These changes were the result of the transition of manufacturing operations from Hematite, Missouri, to Columbia, South Carolina.

End caps were Tungsten Inert Gas (TIG) welded rather than magnetic force welded. This resulted in the following changes:

  • The upper and lower end cap lengths and geometries have changed.
  • The plenum spring design changed.
  • The alumina spacer disc was removed from the bottom of the pellet stack.
  • Void volume increased.
  • Pellet stack was lowered.
  • The fuel rod was pressurized with helium fill gas through a small hole in the upper end cap after the upper end cap was welded to the tube. The rod was not evacuated prior to its pressurization, so air at approximately one atmosphere of pressure stayed in the rod.
  • Deflashing of the end cap weld is no longer required.

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  • A slight crown (0.004 inches maximum, radial) was produced in the end cap weld region.

"* Pellet marking was eliminated.

"* Dimensions/tolerances of the stack length and plenum have changed.

There were also changes to the Batch U design that were not related to fuel fabrication transition that relate to the grid cage assembly and its components.

These changes are generic and being incorporated into all new batches of fuel and do not affect the functional requirements of the fuel.

"* The fabrication process for the Zircaloy coil material that is used to fabricate fuel assembly grids was revised to eliminate the final buffing operation.

"* The lower end fitting drawing was revised to reflect the use of a different technique for the inspection of the positioning of the Guardian grid to ensure that the Guardian grid springs engage the groove on the lower end caps of the rods.

"* The grid cage assembly drawing was revised to make the wording of the requirements for the perpendicularity between the spacer grids and guide tubes consistent across all contracts.

To provide increased margin to grid-to-rod fretting, thirty-two of the Batch U fuel assemblies have an Inconel top spacer grid replacing the Zircaloy grid used on the remaining sixty fuel assemblies. Other than this Inconel top spacer grid and its attachment feature (split sleeve), these assemblies will be identical to the rest of the reload batch.

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3.0 LOW POWER PHYSICS TESTING 3.1 Initial Criticality Following Refuel 11, initial criticality was achieved by boron dilution. The initial RCS boron concentration is required to be greater than the predicted All Rods Out (ARO) Critical Boron Concentration (CBC) by an amount worth 1.5%Ap. An estimated CBC is calculated for ARO and CEA Group P at 75 inches withdrawn. All Shutdown and Regulating CEA Groups are withdrawn to their upper electrical limits. Group P is withdrawn to 75 inches and dilution is commenced. For Cycle 12, the estimated CBC was calculated to be 1994 ppm. Criticality was achieved with a CBC of 1974 ppm and Group P at 75 inches withdrawn which was within the procedural allowance of + 100 ppm.

3.2 Critical Boron Concentration Measurement The purpose of this test is to verify the critical boron concentration for the ARO CEA configuration of the startup test predictions. Initially, CEAs are ARO except for CEA Group P at greater than 130 inches withdrawn.

Three stable RCS boron samples are averaged to estimate the rodded CBC. Group P is withdrawn to the upper group stop and the residual worth is measured using a reactivity meter. The rodded CBC is then corrected using the Group P residual worth. The measured ARO CBC for Cycle 12 was 2016 ppm. The predicted ARO CBC for Cycle 12 was 2025 ppm. The acceptance criteria for Cycle 12 measured ARO CBC was +

113 ppm. This acceptance criteria was met with actual ARO CBC being 9 ppm less than predicted.

3.3 Isothermal Temperature Coefficient Measurement The Isothermal Temperature Coefficient (ITC) is estimated by measuring changes in reactivity associated with RCS temperature changes. The RCS average temperature is decreased by approximately 50F and the reactivity change is measured using a reactivity meter. The temperature is then returned to 545 0 F and the reactivity change is again measured.

The Moderator Temperature Coefficient (MTC) is then calculated by subtracting the predicted Fuel Temperature Coefficient (FTC) from the measured average ITC. Additional calculations include MTC linear extrapolations to both 70% and 100% power.

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The acceptance criteria requires, per WSES-3 Technical Specification 3.1.1.3, that the MTC be less positive than +0.5 x 10' Ap/deg F at zero power and within the limits of the COLR. This requires that the MTC be less positive than 0.0 x 1 0 -4Ap/deg F at > 70% power, more negative than

-0.2 x 1 0 A Ap/deg F at 100% power, and less negative than -4.0 x 10-4 Ap/deg F at any power. Also, the measured average ITC must agree with predictions to within +/-0.3 x 10-4 Ap/deg F. All acceptance criteria were met and are summarized in Table 3.3-1.

Table 3.3-1 WSES-3 ITC/MTC Measurement Results*

Measured** ABB-CE Acceptance Predicted Criteria ITC -0.124 -0.0257 +0.3 MTC (0%) +0.036 +0.134 -4.0<MTC<+0.5 MTC (70%) -0.125 NA -4.0<MTC<0.0 MTC(100%) -0.824 NA -4.0<MTC<-0.2

  • All values are xl10.
    • MTC values at 70% and 100% are extrapolated.

3.4 CEA Group Worth Measurement The purpose of this test is to determine the worth of selected CEA groups.

Initially, CEAs are ARO except for Group P at greater than 130 inches withdrawn. Shutdown Bank B was designated as the reference group.

First, the reactivity of the reference group was measured using a reactivity meter and dilution to compensate for the reactivity addition. Then all other CEA groups were measured using CEA exchanges and the reactivity computer.

The acceptance criteria demands that the measured worth of the Reference Group is within +/-10% of the predicted worth, the measured worth of each CEA measurement group is within +/-0.10%Ap or +/-15%

(whichever is larger) of the predicted CEA group worth, and the total measured CEA group worth is within +/-10% of the predicted total CEA group worth. All acceptance criteria were met and are summarized in Table 3.4-1.

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Table 3.4-1 WSES-3 CEA Group Worth Measurement Results Group(s) Measured Predicted Measured Acceptance Inserted Worth* Worth Error Criteria

(%Ap) (%Ap) (%) Satisfied?

B 1.732 1.778 -2.604 Yes 2 &3 0.934 0.932 +0.172 Yes 1 &6 &P 1.000 1.039 -3.760 Yes 4 &5 1.100 1.153 -4.600 Yes A 1.630 1.631 -0.060 Yes Total 6.396 6.534 -2.112 Yes

  • After correction to adjust for test conditions.

4.0 POWER ASCENSION TESTING 4.1 Fuel Symmetry Verification Prior to exceeding 30% full power, fuel symmetry verification must be performed to ensure that no detectable fuel misloadings are present.

Assembly power data is obtained by executing CECOR, a computer code used to construct three dimensional assembly and peak pin power distributions from incore detector signals. Each instrumented assembly power is compared with the average of its symmetric group and a percent difference is calculated. The acceptance criterion states that this difference must be less than or equal to 10%. The largest percent difference from average observed was approximately 3.2%. See Figure 4 for CECOR output.

4.2 Core Power Distribution Measurement The purpose of this test is to verify that selected measured core power distribution parameters agree with the predicted core power distribution parameters at both the 68% and 100% power levels. These parameters include the measured radial power distribution, axial power distribution, planar radial peaking factor (FY), integrated radial peaking factor (Fr), core average axial peaking factor (F,), and three-dimensional (3-D) power peaking factor (Fq).

A snapshot is taken and CECOR executed to obtain assembly power data. The comparisons were made using the GETARP program and the results are shown in Figures 5 and 6, and summarized in Tables 4.2-1 and 4.2-2.

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The acceptance criteria states that for the measured radial power distribution, the total Root Mean Square (RMS) error between measured and predicted relative power densities for all assemblies must be less than 5%. Also, for each assembly with a predicted relative power density less than 0.9, the percent difference between measured and predicted must be less than 15%. For those assemblies with predicted relative power densities greater than or equal to 0.9, the percent difference between measured and predicted must be less than 10%. For the axial power distribution, the RMS error between measured and predicted relative power densities must be less than 5%. Additionally, for all four peaking factors, measured and predicted values must agree to within

+/-10%. All acceptance criteria were met at both the 68% and 100% power levels and are summarized in Tables 4.2-1 and 4.2-2.

Table 4.2-1 WSES-3 Cycle 12 68% Core Power Distribution Results Westinghouse Measured  % Acceptance Predicted

  • Difference Criteria Radial RMS NA 1.42 NA <5%

Axial RMS NA 2.67 NA <5%

Fxy 1.5500 1.5921 +2.71 +5%

Fr 1.5300 1.5143 -1.03 +5%

FZ 1.1900 1.1541 -3.02 +5%

Fq 1.8200 1.7684 -2.83 +/-5%

  • RMS values in %.

Table 4.2-2 WSES-3 Cycle 12 100% Core Power Distribution Results Westinghouse Measured  % Acceptance Predicted

  • Difference Criteria Radial RMS NA 1.45 NA <5%

Axial RMS NA 3.00 NA <5%

Fxy 1.5400 1.5785 +2.50 +5%

Fr 1.5300 1.5424 +0.81 +5%

Fz 1.1800 1.1486 -2.66 +/-5%

Fq 1.8000 1.7710 -1.61 +5%

  • RMS values in %.

8

5.0 OPERATIONAL TESTING 5.1 Isothermal Temperature Coefficient Measurement Prior to reaching 40 EFPD core burnup, an additional ITC/MTC test must be conducted to verify compliance with Technical Specification and COLR requirements. Initially, power is reduced to 93% to allow temperature fluctuations necessary for the test. In a process similar to the Low Power Physics Testing ITC Measurement, RCS temperature is increased and decreased by approximately 80F and the power change is measured.

This process is repeated 3 additional times to obtain sufficient data to determine an average rate of change of power with temperature. This value is multiplied by a predicted Power Coefficient to arrive at an average ITC.

The MTC is then calculated by subtracting the predicted FTC from the measured average ITC. Additional calculations include MTC linear extrapolations to 70% and 100% at the current burnup and an extrapolation to 100% power at the end of cycle (EOC).

The acceptance criteria demands that, for any core burnup, the MTC be less positive than 0.0 x 10-4 Ap/deg F at > 70% power, more negative than

-0.2 x 10-4 Ap/deg F at 100% power, and less negative than -4.0 x 10-4 Ap/deg F at any power. Also, the measured average ITC must agree with predictions to within +/-0.5 x 104 Ap/deg F. All acceptance criteria were met and are summarized in Table 5.1-1.

Table 5.1-1 WSES-3 ITC/MTC Measurement Results*

Measured** Predicted Acceptance Criteria ITC -0.904 -0.987 +/-0.5 MTC (70%) -0.480 NA -4.0<MTC<0.0 MTC(1 00%) -0.837 NA -4.0<MTC<-0.2 EOC MTC (100%) -2.833 NA -4.0<MTC<-0.2

  • All values are x10-4.
    • MTC values at 70%, 100% and EOC 100% are extrapolated.

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6.0 CONCLUSION

S Based upon the successful completion of all required startup tests, specifically those described above, and the proximity of core physics parameters to predicted values, it is concluded that the measured core parameters verify the Cycle 12 nuclear design calculations and demonstrate adequate conservatism with respect to the limits and requirements of the FSAR and technical specifications, respectively.

7.0 REFERENCES

7.1 WSES-3 Technical Specifications 7.2 WSES-3 Cycle 12 Core Operating Limits Report (COLR) 7.3 WSES-3 Final Safety Analysis Report (FSAR) 7.4 Waterford 3 Cycle 12 Reload Analysis Report 7.5 WSES-3 Procedure NE-002-002, Variable Tavg Test 7.6 WSES-3 Procedure NE-002-003, Post-Refueling Startup Testing Controlling Document 7.7 WSES-3 Procedure NE-002-030, Initial Criticality 7.8 WSES-3 Procedure NE-002-040, CEA Group Worth Measurement 7.9 WSES-3 Procedure NE-002-050, Critical Boron Concentration Measurement 7.10 WSES-3 Procedure NE-002-060, Isothermal Temperature Coefficient Measurement 7.11 WSES-3 Procedure NE-002-110, Fuel Symmetry Verification 7.12 WSES-3 Procedure NE-002-140, Core Power Distribution Measurement 10

Figure 1 Waterford 3 Original (Cycle 11) CEA Group Configuration I7 1Q 111 12 113 5 8 2 IV 2 1" 12 113 II 16 18 19 20 121 22 123 1 24 14 15i 17 3 4 3 25 26 1 + 27-4'-- 28 + - I "U - t1 I1

+ I 1

SA B B A 1 65 46 47 41' 19 s5 s 38 39 B 40 41 5 42 43 P 4 6 P __5 __B m i 54 5 5 57 S8 a9 60 fill 2 63

  • 64 as 67 A A B B A A 88 69 70 71 72 73 1 74  ? 76 7 7m 79 80 41 82 83 3 P 4 1 4 P 3 85 86 87 88 8s 90 91 92 93 94 as 96 97 98 99 100 2 B B A B B 2110 102 103 104 105 106 107 108 109 140 ill 112 113 114 l5 11ie A 4 6 1 2 117 719 120 121 122 123 124 i125 in 14427 128 16 129 130
6. 131 4

132 133 I

2 138 ... 137 "

B 138... 39 140 B 141 142 143 A

144 145 46 B 147 t48 B 149 ISO 2

3 1P I_ 4 1 4 P 3 151 IS2 153 154 155 156 157 158 1 160 161 162 183 164 15 A A B B A A 166 167 1l8 18m 170 171 172 173 174 175 176 177 178 179 180 B 5 P 6 P 5 B 19 181 1 14 6 193 162 1 ,113 A B 187 BA 0 191 192 1

194 11 1196 11973 19 N 4 2 1 [02 203 204 IB r3 r 4 1 "3 I'jB 205 126 213 2 2 207 2J8 29 1210 2 1212 1

214 1 215 A - Shutdown Group A B - Shutdown Group B 1 - Regulating Group 1 2 - Regulating Group 2 3 - Regulating Group 3 4 - Regulating Group 4 5 - Regulating Group 5 6 - Regulating Group 6 P -Group P 11

Figure 2 Waterford 3 Cycle 12 Revised CEA Group Configuration 5 5 1rr2vri4 8

2 9 10 2

11 12 113 i i5 116 P7 4a in 4*

  • 20
  • 4 31 22 B 124 IBI 3 4 3 1BI I -,

CC 4! 9 0 1E 9T I 31 33 F IA F B B "Al35 I6 37 to B 5 A 6 A 5 B SO 5ks 5e A P B 10 B u 62 - 3 P A fm8 5 6 "1 3 A 4 1 4 A 3 8 6 87 89 N 91 92 93 94 95 9B 969 B 99 II3 2 BB B

A B B 2 12 13 104 106 1071 lug 109 110 1 112 *113 114 115 lie 1

4 9 " 1 1 1 6 1 2 1 6 4 1122 1 i3 124 125 1215 127 128 129 I3 N 13 1 132 133 2 I IV B138 I 140 B 14 12 4 144 A 145 146 B 147 148 B 149 ISO 2 135 3 A 4 1 4 A 3 153 1" 1e 1 e' 59 .0 161 16 2 163 16 4 1 65 A P B B P A 166 17 166 169 170 171 172 173 174 175 17- I i78 1179 180

_5 A 6 A 5 B 181 151 1 A B BA 1 193 IL4 1 95 r[ F 1201 20 lB 204 BI 31 4 1' 1B I1 - I

?U* 1400 212 213 207 a2 l08 209 l 2 14O 11

- £- A -,= a -,, lW2 A - Shutdown Group A B - Shutdown Group B 1 - Regulating Group 1 2 - Regulating Group 2 3 - Regulating Group 3 4 - Regulating Group 4 5 - Regulating Group 5 6 - Regulating Group 6 P - Group P 12

Figure 3 Waterford 3 Cycle 12 Enrichment Zoning Pattern for Batch U Fuel LLJ I I I RI m*41 q!/

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48 -Erbium 60 -Erbium 72 - Erbium r -+

" I F-P- I I m jr p

  • iP. p pP, ri u

-Low Enrichment w/

n - High Enrichment Erbium I - Low Enrichment 13

Figure 4 CECOR Results for Fuel Symmetry Verification GLOBAL TILT OF INSTRUMENT IN EACH OCTANT SYMMETRIC GROUP SUMMED OVER ALL LEVELS FORMAT OF ASSEMBLY IN CORE MAP ASSEMBLY NUMBER - DETECTOR NUMBER POWER IN INSTRUMENTED ASSEMBLIES AVERAGE POWER IN OCTANT SYMMETRIC GROUP PERCENT DIFFERENCE FROM SYMMETRIC AVG 1-00 2-00 3-00 4-00

.000 .000 .000 .000

.000 .000 .000 .000

.000 .000 .000 .000 5-01 6-00 7-02 8-00 9-03 10-00 11-04 12-00 13-05

.265 .000 .746 .000 1.733 .000 .746 .000 .276

.268 .000 .754 .000 1.733 .000 .754 .000 .268

-. 967 .000 -. 968 .000 .000 .000 -1.049 .000 3.194 14-00 15-00 16-00 17-00 18-00 19-00 20-00 21-00 22-00 23-00 24-00

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 25-06 26-00 27-07 28-00 29-08 30-00 31-09 32-00 33-10 34-00 35-11 36-00 37-12

.310 .000 1.683 .000 1.919 .000 .000 .000 1.896 .000 1.690 .000 .317

.314 .000 1.693 .000 1.916 .000 .000 .000 1.916 .000 1.693 .000 .314

-1.403 .000 -. 595 .000 .159 .000 .000 .000 -1.013 .000 -. 154 .000 .925 38-00 39-00 40-00 41-00 42-00 43-00 44-00 45-00 46-00 47-00 48-00 49-00 50-00 51-00 52-00

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 53-00 54-13 55-00 56-14 57-00 58-15 59-00 60-16 61-00 62-17 63-00 64-18 65-00 66-19 67-00

.000 1.565 .000 1.844 .000 1.840 .000 1.823 .000 1.875 .000 1.865 .000 1.555 .000

.000 1.562 .000 1.862 .000 1.862 .000 1.825 .000 1.862 .000 1.862 .000 1.562 .000

.000 .185 .000 -. 966 .000 -1.185 .000 -. 107 .000 .653 .000 .173 .000 -. 477 .000 68-00 69-00 70-00 71-00 72-00 73-00 74-00 75-00 76-00 77-00 78-00 79-00 80-00 81-00 82-00

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 83-20 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 84-21

.285 .281

.285 85-00 86-22 87-00 88-23 89-00 90-24 91-00 92-25 93-00 94-26 95-00 96-27 97-00 98-28 99-00 .285

-. 011 .000 1.795 .000 1.889 .000 1.784 .000 1.171 .000 1.762 .000 1.862 .000 1.802 .000 -1.394

.000 1.800 .000 1.869 .000 1.780 .000 1.171 .000 1.780 .000 1.869 .000 1.800 .000 100-00 .000 -. 307 .000 1.062 .000 .249 .000 .000 .000 -. 988 .000 -. 388 .000 .077 .000 101-00

.000 .000

.000 102-00 103-00 104-00 105-00 106-00 107-00 108-00 109-00 110-00 111-00 112-00 113-00 114-00 115-00 116-00 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 117-00 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 118-00

.000 .000

.000 119-00 120-29 121-00 122-30 123-00 124-31 125-00 126-32 127-00 128-33 129-00 130-34 131-00 132-35 133-00 .000

.000 .000 1.810 .000 1.858 .000 1.798 .000 .000 .000 1.776 .000 1.868 .000 1.795 .000 .000

.000 1.800 .000 1.869 .000 1.780 .000 .000 .000 1.780 .000 1.869 .000 1.800 .000 134-36 .000 .533 .000 -. 592 .000 .982 .000 .000 .000 -. 243 .000 -. 082 .000 -. 303 .000 135-37

.289 .286

.285 136-00 137-00 138-00 139-00 140-00 141-00 142-00 143-00 144-00 145-00 146-00 147-00 148-00 149-00 150-00 .285 1.266 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .139

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 151-00 152-38 153-00 154-39 155-00 156-40 157-00 158-41 159-00 160-42 161-00 162-43 163-00 164-44 165-00

.000 1.560 .000 1.873 .000 1.889 .000 1.827 .000 1.845 .000 1.866 .000 1.569 .000

.000 1.562 .000 1.862 .000 1.862 .000 1.825 .000 1.862 .000 1.862 .000 1.562 .000

.000 -. 152 .000 .589 .000 1.447 .000 .107 .000 -. 915 .000 .204 .000 .444 .000 166-00 167-00 168-00 169-00 170-00 171-00 172-00 173-00 174-00 175-00 176-00 177-00 178-00 179-00 180-00

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 181-45 182-00 183-46 184-00 185-47 186-00 187-48 188-00 189-49 190-00 191-50 192-00 193-51

.316 .000 1.688 .000 1.902 .000 1.900 .000 1.946 .000 1.710 .000 .313

.314 .000 1.693 .000 1.916 .000 1.900 .000 1.916 .000 1.693 .000 .314

.717 .000 -. 280 .000 -. 720 .000 .000 .000 1.574 .000 1.028 .000 -. 239 194-00 195-00 196-00 197-00 198-00 199-00 200-00 201-00 202-00 203-00 204-00

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000

.000 .000 .000 .000 .000 .000 .000 .000 .000 .000 .000 205-52 206-00 207-53 208-00 209-54 210-00 211-55 212-00 213-56

.270 .000 .749 .000 .000 .000 .774 .000 .260

.268 .000 .754 .000 .000 .000 .754 .000 .268

.746 .000 -. 636 .000 .000 .000 2.653 .000 -2.973 214-00 215-00 216-00 217-00

.000 .000 .000 .000

.000 .000 .000 .000

.000 .000 .000 .000 14

Figure 5 GETARP Results at 68% Power with Westinghouse Predictions W1 06696 on April 19, 2002 RELATIVE RADIAL POWER DISTRIBUTION COMPARISON

--- + + ......--- +--------+-------- +-..-+

PREDICTED ;  ; .210; .335; .334; .209; (MEAS.-PREDICTED)

MEASURED  ; .233; .366; .366; .233;  % DIFFERENCE =------ ---------- X 100.0

% DIFFER ;  ; 10.95; 9.30; 9.44; 11.41; PREDICTED

-- - - + +

- --- -+ ... - .. ++ ... ---------

.. ...- +.. ... +- .. ..--. ..---- +-. .+- . -+

.193; .367; .549; 1.109; 1.238; 1.106; .543; .350; .201;

.201; .387; .560; 1.122; 1.269; 1.121; .562; .367; .210; 4.21; 5.49; 2.06; 1.16; 2.47; 1.36; 3.42; 4.84; 4.53;

+-......+..-....+....-..+.....-.+......-+......-+......-+..-..+..-.+..-.+..-.+

.243; .661; 1.154; 1.244; 1.328; 1.119; 1.325; 1.239; 1.149; .663; .244;

.262; .668; 1.152; 1.240; 1.326; 1.126; 1.322; 1.232; 1.146; .670; .263;

8.00; 1.00; -. 18; -. 34; -. 17; .59; -. 26; -. 56; -. 23; 1.08; 7.82;

+-------------------- ------ +I------ + -. .+--- +- --------- + -------- - - - ------+-------------

.244; .635; 1.253; 1.183; 1.395; 1.145; 1.374; 1.144; 1.393; 1.183; 1.255; .635; .243;

.240; .640; 1.247; 1.169; 1.405; 1.153; 1.380; 1.146; 1.390; 1.170; 1.251; .642; .244;

-1.65; .77; -. 44; -1.18; .71; .67; .47; .15; -. 21; -1.07; -. 35; 1.16; .48;

+--------+-....+.-...+--+.- - +--+ ---- -- +

I+ -. + -. +. +I ......- + -......- +.....---+-.....-.+

.201; .663; 1.255; 1.149; 1.388; 1.224; 1.404; 1.154; 1.404; 1.223; 1.390; 1.149; 1.253; .661; .193;

.217; .666; 1.243; 1.135; 1.375; 1.219; 1.403; 1.155; 1.402; 1.221; 1.381; 1.140; 1.245; .666; .211; 7.77; .44; -. 96; -1.21; -. 94; -. 44; -. 09; .07; -. 13; -. 14; -. 65; -. 77; -. 67; .70; 9.24;

+ -- -+ - + .- + .. .. I+

+- --....

+ -......- +-......-+- ...... + ...... +.--

+...... ...... ..--- .+.- . - +

.350; 1.149; 1.183; 1.390; 1.160; 1.387; 1.158; 1.373; 1.159; 1.388; 1.160; 1.388; 1.183; 1.154; .367;

.373; 1.160; 1.167; 1.369; 1.152; 1.367; 1.148; 1.360; 1.150; 1.383; 1.157; 1.377; 1.168; 1.160; .392; 6.62; .92; -1.39; -1.54; -. 71; -1.47; -. 86; -. 95; -. 81; -. 34; -. 24; -. 78; -1.26; .51; 6.80;

+-......+..- ... +......- + ...... ...... ...... +......+...... .... .+...... -....- ... .. +......+.-----....-- +.- . . +

.543; 1.239; 1.393; 1.223; 1.388; 1.147; 1.345; 1.075; 1.351; 1.147; 1.387; 1.224; 1.395; 1.244; .549;

+-----  ; .566; 1.234; 1.379; 1.214; 1.382; 1.140; 1.328; 1.053; 1.330; 1.135; 1.376; 1.208; 1.377; 1.238; .572; ------ +

.209; 4.26; -. 42; -1.02; -. 73; -. 44; -. 61; -1.25; -2.01; -1.52; -1.06; -. 81; -1.31; -1.30; -. 48; 4.16; .210;

.216+------- +--......+.- ....- +...- - --. --------------------------- + ......- +-......-+.... ....-.-- - ---+ -- + -- +- + .216; 3.55; 1.106; 1.325; 1.144; 1.404; 1.159; 1.351; 1.131; .965; 1.131; 1.345; 1.158; 1.404; 1.145; 1.328; 1.109; 2.93;

+------; 1.104; 1.321; 1.145; 1.408; 1.155; 1.341; 1.111; .898; 1.102; 1.322; 1.144; 1.383; 1.139; 1.328; 1.106; ------ +

.334; -. 22; -. 28; .09; .25; -. 32; -. 75; -1.80; -6.91; -2.56; -1.75; -1.21; -1.48; -. 50; .00; -. 29; .335;

.357+. .. .+------------------------------..--.

+- - +- ...--...--.+ -- + ...--...----------------

+-+- .+-. . +.- . .+..-+ .357; 6.76; 1.238; 1.119; 1.374; 1.154; 1.373; 1.075; .965; .796; .965; 1.075; 1.373; 1.154; 1.374; 1.119; 1.238; 6.53;

+-------; 1.231; 1.118; 1.374; 1.154; 1.372; 1.078; .974; .807; .965; 1.067; 1.360; 1.145; 1.368; 1.115; 1.227; ------+

.335; -. 53; -. 08; .03; .04; -. 10; .29; .94; 1.43; .04; -. 72; -. 92; -. 75; -. 45; -. 32; -. 86; .334;

.359 ----------------------------------------------- +----------------------------------+-+- + - - + - + -- - -. .+-

-+ + .356; 7.09; 1.109; 1.328; 1.145; 1.404; 1.158; 1.345; 1.131; .965; 1.131; 1.351; 1.159; 1.404; 1.144; 1.325; 1.106; 6.48;

+-------; 1.111; 1.332; 1.141; 1.375; 1.149; 1.340; 1.132; .956; 1.122; 1.327; 1.143; 1.382; 1.137; 1.319; 1.101; ------

.210; .18; .34; -. 33; -2.06; -. 76; -. 39; .12; -. 96; -. 83; -1.77; -1.41; -1.59; -. 62; -. 42; -. 41; .209;

.221+ ------+ -..... + ...... ......--- .....--- ......-- -

+-----+- - +-......+.-

--. ....- + --. . +- ..-- + - .+- -. - + . + .216; 5.01; .549; 1.244; 1.395; 1.224; 1.387; 1.147; 1.351; 1.075; 1.345; 1.147; 1.388; 1.223; 1.393; 1.239; .543; 3.48;

+-....; .575; 1.241; 1.380; 1.210; 1.382; 1.146; 1.350; 1.072; 1.334; 1.134; 1.373; 1.205; 1.374; 1.233; .566; ----- +

4.65; -. 25; -1.08; -1.11; -. 39; -.11; -. 05; -. 25; -. 79; -1.16; -1.10; -1.48; -1.34; -. 47; 4.21;

+ -..... + ...... + -...... +......- +. ...--. + ... . +++-

+.. ... +. .. . .. ... . .. .+... .. +. ..----- +-...... +.....-.+

.367; 1.154; 1.183; 1.388; 1.160; 1.388; 1.159; 1.373; 1.158; 1.387; 1.160; 1.390; 1.183; 1.149; .350;

.393; 1.160; 1.171; 1.381; 1.158; 1.387; 1.155; 1.352; 1.145; 1.364; 1.149; 1.371; 1.169; 1.164; .375; 7.00; .51; -. 97; -. 47; -. 15; -. 07; -. 35; -1.51; -1.16; -1.65; -. 99; -1.40; -1.20; 1.29; 7.11;

+ .---- + ....-- .+...... ...- ..- ....---- +. .. +......+-......+-......+ -...... +......+...... - -+ ..--- +-. .+ . .+

.193; .661; 1.253; 1.149; 1.390; 1.223; 1.404; 1.154; 1.404; 1.224; 1.388; 1.149; 1.255; .663; .201;

.213; .667; 1.247; 1.143; 1.381; 1.219; 1.405; 1.157; 1.403; 1.220; 1.378; 1.141; 1.249; .670; .221; 10.48; .87; -. 46; -. 54; -. 61; -. 31; .04; .26; -. 06; -. 35; -. 69; -. 73; -. 49; 1.07; 9.88;

+-......+.-....+.....-.+......+......+......+-----.... +-- ----......... +......-+..--

+.... ..----. + .+----

.243; .635; 1.255; 1.183; 1.393; 1.144; 1.374; 1.145; 1.395; 1.183; 1.253; .635; .244;

.242; .643; 1.249; 1.170; 1.384; 1.148; 1.384; 1.154; 1.406; 1.177; 1.255; .644; .242;

-. 37; 1.27; -. 47; -1.10; -. 63; .35; .73; .83; .79; -. 52; .13; 1.49; -. 77;

+--.. + .... +-

+.......-- +- .+.....+.....+...................+...------.+- - + -----.... +-....+

.244; .663; 1.149; 1.239; 1.325; 1.119; 1.328; 1.244; 1.154; .661; .243;

.264; .669; 1.144; 1.228; 1.321; 1.130; 1.331; 1.247; 1.159; .671; .266; 8.39; .83; -. 41; -. 89; -. 28; .99; .19; .21; .44; 1.58; 9.33;

+-...... + ... .. +... .. +......+

+... .. +... .. ....-- . .... . .... -.-- . .... .+-- - -. +

.201; .350; .543; 1.106; 1.238; 1.109; .549; .367; .193;

.205; .367; .555; 1.117; 1.265; 1.126; .571; .389; .197; 1.83; 4.78; 2.25; 1.00; 2.16; 1.52; 4.05; 6.10; 2.09;

+-......+..-...+.....-.+.....-.+....-.+..-.+- -. .----. +-......+

.209; .334; .335; .210;

.231; .365; .366; .234; 10.57; 9.24; 9.32; 11.53;

+-------.+-------.+-----+-. .+

15

Figure 5 GETARP Results at 68% Power with Westinghouse Predictions (Continued)

RELATIVE AXIAL POWER DISTRIBUTION COMPARISON NODE PREDICTED MEAS.  % DIFFERENCE 1 .3490 .4248 21.7196 2 .4770 .5147 7.8967 3 .5930 .5976 .7732 4 .6660 .6729 1.0341 5 .7290 .7402 1.5363 6 .7830 .7994 2.0998 7 .8270 .8508 2.8787 8 .8660 .8947 3.3175 9 .9000 .9318 3.5384 10 .9300 .9629 3.5414 11 .9580 .9889 3.2220 12 .9820 1.0105 2.9060 13 1.0040 1.0288 2.4724 14 1.0250 1.0445 1.9045 15 1.0440 1.0583 1.3722 16 1.0620 1.0708 .8272 17 1.0780 1.0823 .3990 18 1.0930 1.0931 .0110 19 1.1070 1.1034 -. 3296 20 1.1200 1.1130 -. 6265 21 1.1310 1.1219 -. 8029 22 1.1410 1.1300 -. 9635 23 1.1510 1.1371 -1.2093 24 1.1590 1.1430 -1.3812 25 1.1670 1.1476 -1.6589 26 1.1730 1.1510 -1.8761 27 1.1780 1.1531 -2.1142 28 1.1820 1.1541 -2.3628 29 1.1850 1.1541 -2.6064 30 1.1870 1.1535 -2.8262 31 1.1870 1.1523 -2.9201 32 1.1870 1.1510 -3.0341 33 1.1840 1.1495 -2.9100 34 1.1810 1.1481 -2.7888 35 1.1760 1.1464 -2.5139 36 1.1690 1.1444 -2.1051 37 1.1600 1.1415 -1.5982 38 1.1500 1.1370 -1.1317 39 1.1370 1.1301 -. 6049 40 1.1210 1.1199 -. 1011 41 1.1030 1.1051 .1902 42 1.0800 1.0846 .4283 43 1.0520 1.0573 .5000 44 1.0190 1.0219 .2821 45 .9780 .9775 -. 0532 46 .9280 .9233 -. 5074 47 .8660 .8588 -. 8322 48 .7880 .7838 -. 5352 49 .6980 .6984 .0592 50 .5600 .6032 7.7154 51 .4080 .4991 22.3171 PEAKING PARAMETER COMPARISON PARAMETER MEAS. PREDICTED % DIFFERENCE FXY 1.5921 1.5500 2.7143 %

FR 1.5143 1.5300 -1.0255 %

FZ 1.1541 1.1900 -3.0157 %

FQ 1.7684 1.8200 -2.8330 %

CALCULATED RMS VALUES RADIAL = 1.4191 AXIAL - 2.6702 MEASURED ASI = -. 0390 PREDICTED ASI = -. 0501 ACCEPTANCE CRITERIA REPORT MEASURED FXY WAS WITHIN PLUS OR MINUS 1.000 5 OP MEASURED FR WAS WITHIN PLUS OR MINUS 5.000 % OF* THE PREDICTED VALUE.

MEASURED FR WAS WITHIN PLUS OR MINUS 5.000 % OF*THE PREDICTED VALUE.

THE PREDICTED VALUE.

MEASURED FQ WAS WITHIN PLUS OR MINUS 5.000 % OF THE PREDICTED VALUE.

RMS ERROR ON WAXIL DISTRINUIPON MAS LESS THAN OR EQ RMS ERROR ON RADIAL DISTRIBUTION WAS LESS THAN OR E'UAL TO 5.000 6.

QUAL TO 5.000 %.

ALL PREDICTED RADIAL POWERS LESS THAN 0.9 WERE WITHIN PLUS OR MINUS 15.000 % OF MEASURED.

ALL PREDICTED RADIAL POWERS GREATER THAN OR EQUAL TO 0.9 WERE WITHIN PLUS OR MINUS 10.000 % OF MEASURED.

.*. ALL ACCEPTANCE CRITERIA WEREMET ***

16

Figure 6 GETARP Results at 100% Power with Westinghouse Predictions W1069CD on April 22, 2002 RELATIVE RADIAL POWERDISTRIBUTION COMPARISON

+ ----------- - ------

PREDICTED ;  ;'.213; .337; .336; .212; (MEAS.-PREDICTED)

MEASURED  ;;.232; .361; .361; .232; 5DIFFERENCE-- --------------------N 100.0

% DIFFER ;  ; 6.72; 7.24; 7.+44; 9.36; PREDICTED

+--------+ ----------------- +- -- - +----------------+------

.198; .372; .551; 1.096; 1.220; 1.093; .545; .355; .206;

.209; .389; .565; 1.114; 1.249; 1.115; .569; .369; .218; 5.34; 4.44; 2.63; 1.62; 2.,40; 1.*99; 4.21; 4.*04; 5.*79;

.249; .669; 1.__ 149; 1*_230;1.__310; 1,°110;1. _2308; 1.*

1. __225; 144; .671 .250;

.262; .668; 1.148; 1.234; 1.319; 1.117; 1.319; 1.233; 1.148; .672; .263;

5.27; -. 05; .01; .33; .72; .66; .86; .68; .31; .14; 5.27;

+----+ - + - - +-+------------------+ --

.250; .644; 1.250; 1.179; 1.392; 1.141; 1.364; 1.141; 1.390; 1.180; 1.252; .644; .249;

.250; .641; 1.248; 1.161; 1.385; 1.145; 1.378; 1.143; 1.385; 1.168; 1.252; .643; .255;

.07; -.49; -.16; -1.49; .21; .37; 1.01; .18; .37; -.98; .03; -.08; 2.22;

.-. +-+---------.- +- --- -- +-+-------- +-- +-.°---.- +- .----- ---- + ---- + .. -

.206; .971; 1.252; 1.150; 1.382; 1.224; 1.400; 1.119; 1.400; 1.223; 1.383; 1.150; 1.250; .669; .199; S.216; .667; 1.241; 1.130; 1.372; 1.212; 1.404; 1.157; 1.408; 1.222; 1.382; 1.135; 1.242; .666; .210;

-4.97; -.66; -.96; -1.70; -.72; -.99; .29; -.07; .57; -.09; -.09; -1.26; -.65; -.26; 6.24;

.355; 1.144; 1.180; 1.383; 1.164; 1.387; 1.167; 1.378; 1.167; 1.3988; 1.164; 1.382; 1.179; 1.148; .372;

.372; 1.157; 1.163; 1.360; 1.151; 1.366; 1.155; 1.377; 1.159; 1.395; 1.156; 1.364; 1.161; 1.159; .390; 4.69; 1.19; 1.47; 1.64; -1.13; -1.49; -1.01; -. 09; -.70; .47; -.68; -1.29; -1.49; .89; 4.96;

; .545; 1.225; 1.390; 1.223; 1.389; 1.157; 1.356; 1.093; 1.361; 1.157; 1.397; 1.224; 1.392; 1.230; .551;

+---  ; .564; 1.229; 1.391; 1.222; 1.399; 1.157; 1.354; 1.074; 1.350; 1.143; 1.392; 1.206; 1.372; 1.230; .569;----

.212; 3.43; .22; .09; -.11; .60; .00; -.16; -1.77; -.78; -1.21; -.38; -1.49; -.70; .00; 3.16; .213;

- + -

.222+- -------------- - + ----- +---

--------------+ ------- -- ------- ------- ------- ------------- .223; 4.73; 1.093; 1.309; 1.141; 1.400; 1.167; 1.361; 1.154; .993; 1.154; 1.356; 1.167; 1.400; 1.141; 1.310; 1.096; 4.52;

+-------; 1.096; 1.298; 1.146; 1.440; 1.179; 1.389; 1.144; .939; 1.122; 1.333; 1.149; 1.393; 1.132; 1.304; 1.094; ------ +

.336; .30; -. 80; .47; 2.88; 1.03; 2.05; -. 91; -5.40; -2.76; -1.66; -1.53; -. 48; -. 80; -. 44; -. 18; .337;

.356+-...... +..--+......-+- .....- +... .. + .... +.. ... .... ----------

.+. .... ... .. + ..... +- .. ...- +....--------+ +-. + .353; 5.91; 1.220; 1.110; 1.364; 1.159; 1.379; 1.993; .993; .926; .993; 1.093; 1.378; 1.159; 1.364; 1.110; 1.220; 4.99;

.------- ; 1.229; 1.113; 1.379; 1.164; 1.397; 1.107; 1.000; .831; .980; 1.075; 1.367; 1.144; 1.359; 1.099; 1.213;,-----+

.337; .74; .31; 1.10; .53; 1.39; 1.25; .69; .58; -1.29; -1.66; -.83; -1.24; -.34; -1.03; -.58; .336;

.359+---------------------------------------------------+ -- +------------+ + -- + .352, 6.53; 1.096; 1.310; 1.141; 1.400; 1.167; 1.356; 1.154; .993; 1.154; 1.361; 1.167; 1.400; 1.141; 1.309; 1.093; 4.79;

+-------; 1.115; 1.341; 1.141; 1.369; 1.161; 1.383; 1.160; .9899; 1.137; 1.338; 1.143; 1.376; 1.126; 1.296; 1.089;----+-

.213; 1.77; 2.36; -.01; -2.21; -.47; 2.00; .52; -.41; -1.46; -1.69; -2.04; -1.73; -1.35; -.94; -.36; .212;

.227+--- +-

+ + - + ---------------- -- .222; 6.51; .551; 1.230; 1.392; 1.224; 1.397; 1.157; 1.361; 1.093; 1.356; 1.157; 1.399; 1.223; 1.390; 1.225; .545; 4.64;

+-;_-_- .577; 1.245; 1.381; 1.206; 1.387; 1.155; 1.366; 1.084; 1.345; 1.136; 1.374; 1.200; 1.367; 1.222; .561; ------

4.65; 1.22; -.09; -1.46; .03; -.21; .39; -.96; -.90; -1.92; -1.03; -1.90; -.94; -.21; 2.99;

+ + + +

- + - - + - -. 4- 4-- +

+ - - +-+----

.372; 1.149; 1.179; 1.392; 1.164; 1.399; 1.167; 1.379; 1.167; 1.397; 1.164; 1.393; 1.190; 1.144; .355;

.392; 1.158; 1.166; 1.370; 1.151; 1.375; 1.152; 1.353; 1.143; 1.362; 1.144; 1.368; 1.162; 1.157; .372; 5.49; .91; -1.07; -.86; -1.15; -.96; -1.31; -1.79; -2.09; -1.90; -1.71; -1.06; -1.51; 1.12; 4.76;

  • .198; .668; 1.250; 1.150; 1.383; 1.223; 1.400; 1.158; 1.400; 1.224; 1.382; 1.150; 1.252; .671; .206;

.213; .667; 1.244; 1.136; 1.373; 1.205; 1.394; 1.147; 1.394; 1.209; 1.370; 1.133; 1.243; .669; .219; 7.56; -.10; -.48; -1.25; -.74; -1.47; -.40; -.96; -.44; -1.33; -.84; -1.44; -.69; -.41; 6.55;

+-- +-+------- +-- + 4- +

- + - - +- -4 + --- -- -+- +-+---

.249; .644; 1.252; 1.190; 1.390; 1.141; 1.364; 1.141; 1.392; 1.179; 1.250; .644; .250;

.253; .643; 1.248; 1.159; 1.361; 1.132; 1.364; 1.138; 1.380; 1.163; 1.247; .642; .251; 1.47; -.11; .31; -1.77; -1.41; -.79; .02; -.27; -. 14; 1.33; -.27; -.29; .42;

+--------------------------------------+- + - + - + -------- ----------

.250; .671; 1.144; 1.225; 1.309; 1.119; 1.310; 1.230; 1.149; .669; .249;

.264; .667; 1.137; 1.218; 1.308; 1.113; 1.316; 1.234; 1.149; .667; .264; 5.54; -. 54; -. 59; -. 56; -. 02; .27; .43; .31; .06; -. 08; 6.02;

+- + - + - +------+----+ - ---- +-

.206; .355; .545; 1.093; 1.220; 1.096; .551; .372; .199;

.212; .367; .560; 1.105; 1.242; 1.112; .572; .388; .203; 2.79; 3.42; 2.72; 1.09; 1.77; 1.45; 3.99; 4.40; 2.63;

+-----------+- + - - +-+- - +--------------+-+--

.212; .336; .337; .213;

.229; .359; .360; .232; 9.05; 6.82; 6.92; 9.71;

+-+--------+- +--- +---

17

Figure 6 GETARP Results at 100% Power with Westinghouse Predictions (Continued)

RELATIVE AXIAL POWERDISTRIBUTION COMPARISON NODE PREDICTED MEAS.  % DIFFERENCE 1 .3840 .4663 21.4329 2 .5220 .5643 8.1001 3 .6460 .6541 1.2547 4 .7250 .7350 1.3761 5 .7920 .8064 1.8237 6 .8490 .8684 2.2851 7 .8950 .9211 2.9122 8 .9350 .9649 3.2020 9 .9680 1.0008 3.3853 10 .9980 1.0295 3.1542 11 1.0240 1.0521 2.7445 12 1.0460 1.0697 2.2680 13 1.0660 1.0834 1.6322 14 1.0840 1.0941 .9334 15 1.1000 1.1027 .2493 16 1.1150 1.1100 -. 4509 17 1.1280 1.1163 -1.0338 18 1.1390 1.1222 -1.4765 19 1.1490 1.1277 -1.8556 20 1.1570 1.1329 -2.0873 21 1.1640 1.1376 -2.2680 22 1.1700 1.1418 -2.4141 23 1.1740 1.1451 -2.4614 24 1.1770 1.1474 -2.5119 25 1.1790 1.1486 -2.5804 26 1.1800 1.1484 -2.6759 27 1.1800 1.1470 -2.8008 28 1.1780 1.1442 -2.8673 29 1.1760 1.1404 -3.0284 30 1.1720 1.1356 -3.1017 31 1.1660 1.1302 -3.0660 32 1.1600 1.1244 -3.0662 33 1.1520 1.1184 -2.9174 34 1.1430 1.1122 -2.6917 35 1.1320 1.1059 -2.3017 36 1.1200 1.0994 -1.8436 37 1.1060 1.0921 -1.2565 38 1.0910 1.0837 -. 6729 39 1.0730 1.0733 .0276 40 1.0530 1.0601 .6772 41 1.0310 1.0432 1.1785 42 1.0050 1.0213 1.6183 43 .9750 .9934 1.8831 44 .9390 .9584 2.0633 45 .8970 .9154 2.0463 46 .8480 .8635 1.8320 47 .7880 .8024 1.8258 48 .7160 .7317 2.1897 49 .6330 .6515 2.9234 50 .5090 .5623 10.4739 51 .3730 .4649 24.6364 PEAKING PARAMETER COMPARISON PARAMETER MEAS. PREDICTED % DIFFERENCE FXY 1.5785 1.5400 2.5032 %

FR 1.5424 1.5300 .8125 %

FZ 1.1486 1.1800 -2.6629 %

FQ 1.7710 1.8000 -1.6116 %

CALCULATED RMS VALUES RADIAL = 1.4456 AXIAL = 3.0018 MEASURED ASI = .0033 PREDICTED ASI = -. 0006 ACCEPTANCE CRITERIA REPORT MEASURED PFXY WAS WITHIN PLUS OR MINUS 5.000 OF THE PREDICTED VALUE.

MEASURED FR WAS WITHIN PLUS OR MINUS 5.000 % OF THE PREDICTED VALUE.

MEASURED FR WAS WITHIN PLUS OR MINUS 5.000 % OF THE PREDICTED VALUE.

MEASURED FQ WAS WITHIN PLUS OR MINUS 5.000 % OF THE PREDICTED VALUE.

PMS ERROR ON AXIAL DISTRIBUTION HAS LESS THAN OR EQUAL TO 5.000 0.

RMS ERROR ON RADIAL DISTRIBUTION WAS LESS THAN OR EQUAL TO 5.000 %.

ALL PREDICTED RADIAL POWERS LESS THAN 0.9 WERE WITHIN PLUS OR MINUS 15.000 % OF MEASURED.

ALL PREDICTED RADIAL POWERS GREATER THAN OR EQUAL TO 0.9 WERE WITHIN PLUS OR MINUS 10.000 % OF MEASURED.

      • ALL ACCEPTANCE CRITERIA WERE MET 18
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