W3F1-2008-0057, Startup Power Escalation Report for Cycle 16

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Startup Power Escalation Report for Cycle 16
ML082410188
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/25/2008
From: Murillo R
Entergy Nuclear Operations, Entergy Nuclear South
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2008-0057
Download: ML082410188 (19)
v • d • e


Text

Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504 739 6715 Fax 504 739 6698

~Entergy rmurill@entergy.com Robert J. Murillo Licensing Manager Waterford 3 W3F1-2008-0057 August 25, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Startup and Power Escalation Report for Cycle 16 Waterford Steam Electric Station, Unit 3 (Waterford 3)

Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

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 16 operation. Waterford 3 resumed commercial power operation on June 1, 2008, following the completion of refueling outage 15. This report summarizes the results of the WSES-3 Cycle 16 startup physics test program, which includes the impact of the introduction of Next Generation Fuel (NGF).

There are no new commitments contained in this submittal.

Please contact Mr. Robert J. Murillo, Manager, Licensing at (504) 739-6715 if there are any questions concerning this matter.

  • 1 RJM/GCS/ssf

Attachment:

Waterford's Startup and Power Escalation Report for Cycle 16.

W3F1-2008-0057 Page 2 cc: Mr. Elmo E. Collins, Jr.

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004' P

Attachment to W3F1-2008-0057 WATERFORD 3's STARTUP AND POWER ESCALATION REPORT FOR CYCLE 16

TABLE OF CONTENTS Page 1 .0 Intro d u ctio n .......................................................................................... 2 2.0 Reactor Core Description ................................................................... 2 3.0 Low Power Physics Testing ................................................................. 4 3 .1 Initia l C ritica lity ........................................................................ . . 4 3.2 Critical Boron Concentration Measurement .................................... 4 3.3 Isothermal Temperature Coefficient Measurement ........................... 4 4.0 Power Ascension Testing ..................................................................... 5 4.1 Fuel Symmetry Verification .......................................................... 5 4.2 Core Power Distribution Measurement ........................ 5 5.0 Operational Testing ......................................................................... .6 5.1 Isothermal Temperature Coefficient Measurement ................ 6 6 .0 C o n c lu s io n ......................................... ................................................. 7 7 .0 R eferences .................................................................................. . . . .8 8.0 Tables 8.1 Table 1 Waterford-3 Cycle 16 Design Core Loading Description ...... 9 8.2 Table 2 CECOR Results for Fuel Symmetry Verification ............ 11 8.3 Table 3 GETTARP Results at 68% Power with Westinghouse P red ictions ................................................................... . . 13 8.4 Table 4 GETTARP Results at 100% Power with Westinghouse P red ictions ................................................................... . . 15 I

1.0 Introduction This report summarizes the results of the WSES-3 Cycle 16 startup physics test program, as it pertains to the introduction of Next Generation Fuel (NGF). 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 these tests performed as part of this program were completed satisfactorily, not all test results are included in this summary. Only those tests deemed necessary to demonstrate acceptance of the measured core physics parameters are included.

The objective of these tests was to demonstrate that, during reactor operation, the measured core physics parameters would be within the assumptions of the Final Safety Analysis Report (FSAR) accident analysis 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 16 core performance with respect to the WSES-3 FSAR, Technical Specifications, Cycle 16 Core Operating Limits Report (COLR),

and Cycle 16 Reload Analysis Report.

2.0 Reactor Core Description WSES-3 Cycle 16 core includes using Next Generation Fuel (NGF) assemblies.

The introduction of 100 NGF (Region Z) to theMWSES-3 core entails the following changes:

  • A reduced pellet diameter of 0.3225 inches (vs. 0.325 inches for Region Y).

" A reduced cutback (i.e., non-poison) region of 6 inches at both the top and bottom of the ZRB 2 rods (vsI 7 inches for Region Y).

The use of Optimized ZIRLO TM fuel rod cladding material (vs.

ZIRLO TM for Region Y).

The fuel rod cladding diameters (in inches) for Region Z are reduced to 0.374 OD x 0.329 ID from 0.382 OD x 0.332 ID to accommodate the higher pressure drop of the mid and intermediate flow mixing (IFM) grids.

The overall fuel rod length has been increased from Region Z to 162.568 inches from 161.868 inches.

  • The fuel rod initial fill gas pressure has been reduced for Region Z to 275 psig at 75 0 F from 380 psig at 68 0 F.

" The IFBA rod initial fill gas pressure has been reduced for Region Z to 150 psig at 75°F from 150 psig at 68 0 F.

  • A new lower end fitting assembly, new outer and center guide tube assemblies, a new upper end fitting flow plate with longer hold-down springs, all new mid grid assemblies with I-springs, 2

intermediate flow mixing (IFM) grids, a new Inconel top grid, a modified Guardian TM grid, and new thimble crimp screws that replace the old bold/locking discs.

  • Top, mid, and IFM grid assemblies featuring sleeves that bulged to the guide tubes instead of welded and smaller cell sizes to accommodate the smaller diameter fuel rods.

" A guide tube flange that is bulged to the outer guide tube rather than welded.

" A Guardian TM grid that is attached to the lower end fitting via inserts instead of welding the grid skirt to the lower end fitting.

  • Stress-Relief Annealed (SRA) ZIRLO TM materials for guide tubes and Optimized ZIRLO TM materials for grid straps rather than the Zircaloy-4 materials used in previous fuel regions.
  • An anti-rotational joint between guide tubes and the upper nozzle to prevent damage to spacer grids and grid-to-guide tube joints during guide post installation and removal.

An initial shoulder gap of 0.502 inches less than the standard fuel assemblies.

The reload region will consist of:

0 8 type Z1 assemblies, each with 48 integral burnable absorber rods a 16 type Z2 assemblies, each with 80 integral burnable absorber rods

  • 8 type Z3 assemblies, each with 88 integral burnable absorber rods
  • 24 type Z4 assemblies, each with 100 integral burnable absorber rods
  • 28 type Z5 assemblies, each with 112 integral burnable absorber rods
  • 16 type Z6 assemblies, each with 124 integral burnable absorber rods In addition twenty-one (21) Region X and ninety-six (96) Region Y assemblies in the core during Cycle 15 will be retained for Cycle 16. See Table 1 for additional enrichment information.

The Cycle 16 core makes use of a low-leakage fuel management scheme in which previously burned Region Y and Region X assemblies are placed on the core periphery. The 100 fresh Region Z assemblies are located throughout the interior of the core where they are arranged with the previously burned fuel in a pattern that minimizes power peaking. This type of fuel management is economically beneficial because it reduces core leakage and, therefore, uranium requirements for a specified total energy output. This low-leakage design also reduces the total neutron fluence that the reactor vessel is exposed to during the cycle.

WSES-3 Cycle 16 continues the use of a burnable absorber using zirconium diboride (ZrB 2 ) coating in the Next Generation Fuel. By design, ZrB 2 is coated 3

onto the outer surface of the uranium dioxide (U0 2 ) fuel pellets prior to loading into the fuel rod cladding tubes rather than being mixed with the U02 directly, as is done with other integral fuel burnable absorber (IFBA) materials. The ZrB 2 IFBA coated pellets are identical to the enriched uranium dioxide pellets except for the addition of a thin boride coating on the pellet cylindrical surface. Coated pellets occupy the central portion of the fuel stack.

3.0 Low Power Physics Testing 3.1 Initial Criticality Following each refuel, initial criticality is 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 of 1.5% Ap. An estimated CBC is calculated for ARO, Regulating CEA Group P at 75 inches withdrawn. All shutdown and regulating CEA groups are withdrawn to their upper electrical limits, with the exception of Group P at 75 inches, and dilution is commenced. For Cycle 16, the estimated ARO CBC was calculated to be 1194 ppm. Criticality was achieved with a CBC of 1166 ppm and Group P at 75 inches withdrawn.

3.2 Critical Boron Concentration Measurement The purpose of this test is to verity the critical boron concentration for the ARO CEA configuration of the startup test predictions. Initially, CEA's are ARO except for Regulating 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 measured ARO CBC for Cycle 16 was 1206 ppm. The predicted ARO CBC for Cycle 16 was 1194 ppm.

3.3 Isothermal Temperature Coefficient Measurement Isothermal Temperature Coefficient (ITC) at Hot Zero Power (HZP) measurement was not performed due to the implementation of the Startup Activity Test Reduction (STAR) program approved by the NRC.

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 than this 4

difference must be less than or equal to 10%. The largest percent difference from average observed was approximately 2.88%. See Table 2 for CECOR output.

4.2 Core Power Distribution Measurement The purpose of this test is to verity 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 (Fxy), integrated radial peaking factor (Fr), core averaged axial peaking factor (Fz), 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 Tables 3 and 4, and summarized in Tables 4.2-1 and 4.2-2.

Table 4.2-1 WSES-3 Cycle 16 68% Core Power Distribution Results Westinghouse Measured* % Difference Acceptance Predicted Criteria Radial RMS N/A 1.2748 N/A < 5.0%

Axial RMS N/A 4.7253 N/A < 5.0%

Fxy 1.490 1.4839 -0.4088 +/- 10.0 %

Fr 1.436 1.4296 -0.4428 +/- 10.0 %

F, 1.102 1.1164 1.3028 +/- 10.0 %

Fq 1.581 1.6100 1.8348 +/- 10.0 %

  • RMS values in %.

5

Table 4.2-2 WSES-3 Cycle 16 100% Core Power Distribution Results Westinghouse Measured* % Difference Acceptance Predicted Criteria Radial RMS N/A 1.0889 N/A < 5.0%

Axial RMS N/A 3.6358 N/A 5 5.0%

Fxv 1.4700 1.4669 -0.2111 +/- 10.0 %

Fr 1.4170 1.4163 -0.0522 +/- 10.0 %

F, 1.0880 1.1385 4.6455 +/- 10.0 %

Fq 1.5980 1.6743 4.7761 +/- 10.0 %

  • RMS values in %.

The acceptance criteria states that for the measured radial power distribution, the total RMS error between measured and predicted relative power densities for all assemblies must be less than 5.0%. Also, for each assembly with a predicted relative power density less than 0.9, the percent difference between measured and predicted must be less that 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.

5.0 Operational Testing 5.1 Isothermal Temperature Coefficient (ITC) Measurement Prior to reaching 40 Effective Full Power Days (EFPD) core burnup,, an Isothermal Temperature Coefficient/Moderator Temperature Coefficient (ITC/MTC) test must be conducted to verify compliance with Technical Specification and COLR requirements. Initially, power is reduced to approximately 99.5% to allow temperature fluctuations necessary for the test. The RCS average temperature is increased and decreased by approximately 5 OF and the power change is measured. This process is repeated two (2) 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 Fuel Temperature Coefficient (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).

6

Table 5.1-21 Echelon* Measured* Acceptance*

Prediction Criteria ITC -1.1593 -1.3705 +/- 0.5 MTC (70%)** N/A -0.8888 -3.9 < MTC < 0.0 MTC (100%)** N/A -1.2739 -3.9 < MTC < -0.2 EOC MTC (100%)** N/A -2.2764 -3.9 < MTC < -0.2

  • All values are xl 0-4
    • MTC values at 70%, 100% and EOC 100% are extrapolated.

The acceptance criteria demands that, for any core burnup; the MTC be less positive than 0.0 x 1 0 -4 Ap / OF at 70% power, more negative than -0.2 x 10. Ap / OF at 100% power, and less negative than -3.9 x 10-4 Ap / °F at any power. Also, the measured average ITC must agree with predictions to within +/- 0.5 x 10-4 Ap / OF. All acceptance criteria were met and are summarized in Table 5.1-1.

6.0 Conclusions Based upon the successful completion of all startup tests required, specifically those described above, and the proximity of core physics parameters to predicted values, it is concluded that the measured core parameters verify that Cycle 16 nuclear design calculations and demonstrate adequate conservatism with respect to the limits and requirements of the FSAR and technical specification, respectively.

7

r 7.0 References(

7.1 WSES-3 Technical Specifications 7.2 WSES-3 Cycle 16 Core Operating Limits Report (COLR) 7.3 WSES-3 Final Safety Analysis Report (FSAR) 7.4 NF-WTFD-08-10, "Waterford 3 Cycle 16 Final 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-002-050, Critical Boron Concentration Measurement 7.9 WSES-3 Procedure NE-002-110, Fuel Symmetry Verification 7.10 WSES-3 Procedure NE-002-140, Core Power Distribution Measurement 7.11 NF-WTFD-08-20, "Waterford 3 Cycle 16 Startup Test Predictions" 7.12 CE02008-00107, "Waterford 3 Cycle-16 Variable Tavg Test Predictions" 8

Westinghouse Proprietary Class 2 Enclosure I to CE-08-13 1, Rev. 0 Table 1 Waterford-3 Cycle 16 Design Core Loading Description Nominal Shim Sub- Number of U0 2 Rods per ENricnt ZrB2 Rods per Loading Number of Fuel Rods Number of Batch ID Assemblies Assembly (wt. %) Assembly (ZrB) (including ZrB 2 Rods) ZrB2 Rods 8 176 4.60 8 2.0 X 1472 64 Zi 12 4.00 40 2.0 X 416 320 144 4.60 40 2.0 X 2944 640 Z2 16 12 4.00 40 2.0 X 832 640 Z3 8 124 3.80 60 2.0 X 1472 480

_ _24 3.40 28 2.0 X 416 224 24 136 3.80 48 2.0 X 4416 1152 Z4 0 3.40 52 2.0 X 1248 1248 Z5 28 116 3.80 68 2.0 X 5152 1904 8 3.40 44 2.0 X 1456 1232 112 3.80 72 2.0 X 2944 1152 Z6 16 0 3.40 52 2.0 X 832 832 Total 100 23600 .9888 184 4.10 0 2.0 X 2208 0 Y1 12 28 3.80 24 2.0 X 624 .288

,Y2 16 176 4.10 8 2.0 X 2944 128

.12 3.80 40 2.0 X 832 640 4 164 4.10 20 2.0 X 736 80 12 3.80 40 2.0 X 208 160 160 4.10 24 2.0 X 1472 192 Y4 8 8 3.80 44 2.0 X 416 352 144 4.10 40 2.0 X 6624 1440 Y5 36 12 3.80 40 2.0 X 1872 1440 Y6 20 136 4.10 48 2.0 X 3680 960 0 3.80 52 2.0 X 1040 1040 Total 96 1 22656 6720 9

Westinghouse Proprietary Class 2 Enclosure I to CE-08-13 1, Rev. 0 Table 1 (cont.)

Waterford-3 Cycle 16 Design Core Loading Description Nominal Shim Sub- Number of U0 2 Rods per Enrichment Erbia Rods Loadi Number of Fuel Rods Number of Batch ID Assemblies Assembly (w t per Assembly ing (inci

_________ (wt. %) (Erbia) uigEbaRd)EbaRd 184 4.35 0 --- 736 0 XT 4 52 4.00 0 --- 208 0 0 --- 184 0 X0 1 184 4.48 52 4.13 0 --- 52 0 4.48. 0 -- 1152 0 X3 8 144 20 4.13 72 2.1 736 576 4.48 0 -- 1088 0 X4 8 136 12 4.13 88 2.1 800 704 Total 21 4956 1280 ZrB2 Grand 217 51212 16,608 Total Erbia 1280 10

Table 2 1CECRNP02 = W3 C16 CASE=W3301UM EXP=0.0O EDIT= 21 DATE= 6 1 TIME=2020 PAGE = 37 GLOBAL TILT FOR OCTANT SYMMETRIC GROUPS SUMMEDOVER ALL AXIAL DETECTOR LEVELS BOX INST AZIMUTHAL CYCLES POWER POWER/ PERCENT DIFFERENCE ANGLE(DEG) IN CORE SYMMETRIC AVERAGE FROM AVERAGE 84 21 10.62000 2 77186 1.02058 2.05777 83 20 169.38000 2 .74791 .98892 -1.10847 134 36 190.62000 2 .74911 .99051 -. 94932 205 52 240.25500 2 .86086 1.00000 .00000 11 4 74.05500 2 1.85281 .98060 -1.94026 7 2 105.94500 2 1.89463 1.00273 .27313 207 53 254.05500 2 1.89689 1.00393 .39279 211 55 285.94500 2 1.91355 1.01274 1.27431 9 3 90.00000 0 3.29821 1.00326 .32622 209 54 270.00000 0 3.27676 .99674 -. 32622 25 6 140.19400 2 1.49867 1.05787 5.78692 181 45 219.80600 2 1.21977 .86100 -13.90044 193 51 320.19400 2 1.53164 1.08114 8.11353 66 19 26.56500 0 2.96302 .97851 -2.14919 54 13 153.43500 0 3.09058 1.02064 2.06353 152 38 206.56500 0 2.94340 .97203 -2.79720 164 44 333.43500 0 3.11539 1.02883 2.88287 98 28 9.46200 0 3.38469 .99509 -. 49123 86 22 170.53800 0 3.42992 1.00839 .83852 120 29 189.46200 0 3.37432 .99204 -. 79612 132 35 350.53800 0 3.41666 1.00449 .44881 27 7 128.66000 0 3.39563 .99258 -. 74158 183 46 231.34000 0 3.38407 .98921 -1.07935 191 50 308.66000 0 3.48329 1.01821 1.82092 P02 1CIECRN w3 CU6 CASE=W3301UM EXP=O.00 EDIT= 21 DATE= 6 1 TIME=2020 PAGE = 38 BOX INST AZIMUTHAL CYCLES POWER POWER/ PERCENT DIFFERENCE ANGLE(DEG) IN CORE SYMMETRIC AVERAGE FROM AVERAGE 33 10 68.19900 0 3.71417 .99125 -. 87485 29 8 111.80100 0 3.74190 .99865 -. 13498 185 47 248.19900 0 3.71249 .99080 -. 91976 189 49 291.80100 0 3.81926 1.01930 1.92960 187 48 270.00000 0 3.46702 1.00000 .00000 64 18 36.87000 0 3.52815 .98070 -1.92959 56 14 143.13000 0 3.63290 1.00982 .98206 154 39 216.87000 0 3.54497 .98538 -1.46201 162 43 323.13000 0 3.68425 1.02410 2.40952 96 27 14.03600 0 3.32935 .98241 -1.75857 88 23 165.96400 0 3.40753 1.00548 .54846 130 34 345.96400 0 3.42995 1.01210 1.21011 62 17 56.31000 0 3.12623 .99721 -. 27905 156 40 236.31000 0 3.14373 1.00279 .27905 60 16 90.00000 0 3.10605 .99684 -. 31591 158 41 270.00000 0 3.12574 1.00316 .31591 94 26 26.56500 2.90268 .99057 -. 94263 90 24 153.43500 0 2.92627 .99862 -. 13768 124 31 206.56500 0 2.94242 1.00414 .41375 128 33 333.43500 0 2.94983 1.00667 .66657 92 25 90.00000 2.86552 1.00000 .00000 Page 11

Table 2 (cont.)

During the performance of NE-002-1 10, all octant symmetric groups passed the 10%

criteria except for the group containing instruments 6, 45, and 51 (instrument 12 would normally be within this group but was taken out of scan due to bad signals). The percent deviations for this group were (from CECOR edit 21):

BOX INST AZIMUTHAL CYCLES POWER POWER/ PERCENT DIFFERENCE ANGLE (DEG) IN CORE SYMMETRIC AVERAGE FROM AVERAGE 25 6 140.19400 2 1.49867 1.05787 5.78692 181 45 219.80600 2 1.21977 .86100 -13.90044 193 51 320.19400 2 1.53164 1.08114 8.11353 From the Startup test predictions (NF-WTFD-08-20), the powers in these locations are predicted to be:

BOX 15% Power 68% Power 25 0.52 0.52 181 0.40 0.41 193 0.52 0.52 Average 0.48 0.483 The large differences in powers are due to the non-symmetric loading of the assemblies in these locations. Box 25 and 193 contain assemblies from Batch Y5 while Box 181 has a Batch XT assembly. As can be seen, the power in Box 181 from the startupltest predictions is significantly different than those in the other two boxes.

Using the above information, the "expected" deviations for these locations would be:

BOX 15% Power 68% Power 25 8.33 7.66 181 -16.67 -15.11 193 8.33 7.66 Therefore, a difference for Box 181 on the order of - 17% can be expected based on predicted data. The measured difference was -13.90%.

The large differences using the predicted power distribution demonstrates that the group containing detectors 6, 12, 45, and 51 are not symmetric by design and need not be included in the symmetric group check for this procedure.

Page 12

Table 3 GGGGGGGGGG EEEEEEEEEE TTTTTTTTTTT AAAA RRRRRRRRR PPPPPPPPP GGGGGGGGGG EEEEEEEEEE TiTTTTTTTTl AAAAAA RRRRRRRRRR PPPPPPPPPP GGG EEE TTT AAA AAA RRR RRR PPP PPP GGG GGGGG EEEEEE TTT AAAAAAAAAA RRRRRRRRRR PPPPPPPPPP GGG GGGGG EEEEEE TTT AAAAAAAAAA RRRRRRRRR PPPPPPPPP GGG GGG EEE TTT AAA AAA RRR RRR PPP GGGGGGGGGG EEEEEEEEEE TTT AAA AAA RRR RRR PPP GGGGGGGGGG EEEEEEEEEE TTT AAA AAA RRR RRR PPP (FPA)

A PROGRAMTO EXTRACT DATA FROMCECOR

SUMMARY

FILES FOR COMPARISON OF AXIAL AND RADIAL POWER DISTRIBUTIONS.

GETRNP01 - GETARP FOR NT REVISION 1 MEASURED DATA EXTRACTED FROM: w3303tw.s01 PREDICTED DATA EXTRACTED FROM: c16p068 RELATIVE RADIAL POWERDISTRIBUTION COMPARISON

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

PREDICTED .280; .490; .480; .270; (MEAS.-PREDICTED)

MEASURED ;.287; .497; .493; .270;  % DIFFERENCE = ------- X 100.0

% DIFFER ; 2.59; 1.42; 2.80; .09; PREDICTED

+

o-+---- - - ------ ----

.310; .530; .690, 1.040; 1.150, 1.030; .680, .520; .300;

.315; .532; .672; 1.014 1.140; 1.003; .656; .519; .300; 1.63; .39; -2.66; -2.52; -. 86; -2.65; -3.56; -. 11; .13;

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

.520; 1.060; 1.060; 1.100; 1.180; 1.220; 1.180; 1.090; 1.050; 1.040; .500;

.517; 1.039; 1.046; 1.079; 1.163; 1.210; 1.157; 1.066; 1.029; 1.015; .500;

-. 55; -1.96; -1.30; -1.95; -1.40; -. 79; -1.97; -2.16; -2.01; -2.44; .00;

.520; 1.070; 1.200; 1.330; 1.290; 1.240; 1.220; 1.240; 1.280; 1.310; 1.170; 1.010; .410;

.523; 1.038; 1.169; 1.311; 1.285; 1.245; 1.215; 1.240; 1.278; 1.295; 1.145; .980; .412;

.51; -3.02; -2.60; -1.43; -. 41; .39; -. 43; .02; -. 17; -1.17; -2.17; -3.01; .43;

+- - - +

.310; 1.070; 1.210; 1.250; 1.260; 1.220; 1.200; 1.230; 1.200; 1.210; 1.240; 1.220; 1.150; 1.000; .290;

.323; 1.058; 1.187; 1.248; 1.247; 1.224; 1.195; 1.234; 1.192; 1.216; 1.229; 1.216; 1.131; .984; .300; 4.06; -1.11; -1.92; -. 15; -1.05; .34; -. 45; .36; -. 64; .48; -. 85; -. 31; -1.64; -1.60; 3.39;

.530; 1.070; 1.330; 1.260; 1.270; 1.130; 1.120; 1.120; 1.120; 1.130; 1.250; 1.240; 1.290; 1.030; .510;

.547; 1.071; 1.335; 1.261; 1.267; 1.122; 1.120; 1.112; 1.116; 1.110; 1.245;.1.228; 1.293; 1.031; .528; 3.30; .08; .38; .08; -. 28; -. 71; -. 04; -. 74; -. 32; -1.78; -. 37; -. 93; .20; .13; 3.49;

.680; 1.100; 1.290; 1.220; 1.140; 1.140; 1.060; 1.050; 1.050; 1.130; 1.130; 1.210; 1.270; 1.080; .680;

+------  ; .699; 1.105; 1.312; 1.241; 1.139; 1.142; 1.055; 1,058; 1.050; 1.130; 1.120; 1.213; 1.284; 1.081; .690; ------ +

.270; 2.72; .43; 1.71; 1.70; -. 07; .18; -. 46; .79; .01; .03; -. 89; .26; 1.10; .11; 1.40; .280;

.266+---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 279;

-1.49; 1.030; 1.180; 1.240; 1.200; 1.120; 1.060; 1.060; 1.040; 1.050; 1.050; 1.110; 1.190; 1.230; 1.170; 1.030; -. 35;

-- -----  ; 1.017; 1.187; 1.261; 1.198; 1.129; 1.056; 1.065; 1.039; 1.059; 1.045; 1.113; 1.173; 1.243; 1.170; 1.015; -------

.480; -1.24; .61; 1.73; -. 20; .80; -. 35; .51; -. 05; .90; -. 45; .24; -1.43; 1.04; .01; -1.49; .480;

.491+-+ 494; 2.39; 1.150; 1.220; 1.220; 1.230; 1.120; 1.050; 1.040; 1.010; 1.030; 1.050; 1.120; 1.230; 1.220; 1.220; 1.140; 2.93;

-- -----  ; 1.126; 1.221; 1.228; 1.245; 1.125; 1.064; 1.044; 1.018; 1.038; 1.059; 1.118; 1.235; 1.222; 1.219; 1.129; -------

.480; -2.12; .10; .66; 1.21; .44; 1.31; .34; .83; .73; .85; -. 18; .37; .16; -. 07; -. 96; .480;

.491+- -+--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - 495; 2.23; 1.030; 1.170; 1.240; 1.190; 1.110; 1.050; 1.050; 1.030; 1.050; 1.050; 1.120; 1.200; 1.240; 1.180; 1.030; 3,09;

-- -----  ; 1.011; 1.175; 1.255; 1.202; 1.127; 1.055; 1.064; 1.038; 1.064; 1.058; 1.130; 1.200; 1.262; 1.186; 1.022; -------

.280; -1.84; .43; 1.24; 1.03; 1.54; .50; 1.30; , .74; 1.30; .79; .92; .01; 1.75; .49; -. 75; .270;

.270+- -+--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - 274;

-3.54; .680; 1.080; 1.270; 1.210; 1.130; 1.130; 1.050; 1.050; 1.050; 1.140; 1.140; 1.220; 1.290; 1.100; .680; 1.59;

+ . 687; 1.083; 1.293; 1.226; 1.129; 1.137; 1.054; 1 061, 1.058; 1.148; 1.146; 1.248; 1.318; 1.108; .703; ------+

.97; .32; 1.80; 1.31; -. 06; .61; -36; 1 04; .81; .71; .51; 2.30; 2.16; .77; 3.44;

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

.510; 1.030; 1.290; 1.240; 1.250; 1.130; 1.110; 1.120; 1.110; 1.130; 1.260; 1.260; 1.330; 1.060; .530;

.527; 1.029; 1.299; 1.231; 1.251; 1.112; 1.119; 1.116; 1.126; 1.133; 1.279; 1.275; 1.346; 1.076; .551; 3.27; -. 13; .70; -. 73; .11; -1.60; .77; -. 36; 1.43; .27; 1.52; 1.16; 1.17; 1.48; 3.88;

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

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

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

.290; 1.000; 1.150; 1.220; 1.240; 1.210; 1.200; 1.230; 1.200; 1.220; 1.260; 1.250; 1.200; 1.070; .310;

.302; .996; 1.145; 1.230; 1.238; 1.218; 1.193; 1.235; 1.201; 1.238; 1.263; 1.266; 1.200; 1.067; .325; 4.11; -. 37; -. 41; .78; -. 15; .69; -. 56; .41; .10; 1.49; .24; 1.25; .01; -. 28; 4.87;

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

- + -+- +-+---

.410; 1.010; 1.170; 1.310; 1.280; 1.240; 1.220; 1.240; 1.290; 1.320; 1.200; 1.060; .520;

.434; 1.002; 1.172; 1.307; 1.277; 1.238; 1.206; 1.250; 1.307; 1.332; 1.193; 1.052; .528; 5.91; -. 75; .15; -. 20; -. 24; -. 18; -1.17; .83; 1.29; .92; -. 55; -. 76; 1.60;

.500; 1.040; 1.050; 1.090; 1.180; 1.220; 1.180; 1.100; 1.060; 1.060; .510;

.510; 1.033; 1.040; 1.071; 1.156; 1.205; 1.165; 1.088; 1.060; 1.053; .519; 1.99; -. 71; -. 92; -1.71; -2.06; -1.24; -1.28; -1.07; -. 02; -. 65; 1.79;

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

.300; .520; .680; 1.030; 1.150; 1.030; .690; .530; .310;

.305; .526; .666; 1.001; 1.127; 1.010; .672; .536; .319; 1.61; 1.14; -2.08; -2.80; -1.96; -1.98; -2.61; 1.18; 2.80;

................. -----+ -----+ ----- +-----+;- .......... + .......

.270* 480 .o490, .280;

.271; .490; .493; .286;

.26; 2.13; .65; 1.97;

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

Page 13

Table 3 (cont.)

RELATIVE AXIAL POWERDISTRIBUTION COMPARISON NODE PREDICTED MEAS.  % DIFFERENCE 1 ,6030 .6205 2.9010 2 .7140 .6982 -2.2114 3 .8040 .7723 -3.9380 4 .8470 .8333 -1.6181 5 -'.8850 .8757 -1.0496 6 .9130 .9086 -. 4768 7 .9330 .9355 .2721 8 .9480 .9585 1.1126 9 .9590 .9786 2.0417 10 .9680 .9960 2.8975 11 .9770 1.0116 3.5421 12 .9840 1.0254 4.2058 13 .9900 1.0379 4.8397 14 .9960 1.0491 5.3289 15 1.0020 1.0589 5.6771 16 1.0070 1.0674 5.9999 17 1.0130 1.0746 6.0793 18 1.0190 1.0805 6.0307 19 1.0240 1.0851 5.9699 20 1.0300 1.0888 5.7070 21 1.0360 1.0916 5.3683 22 1.0420 1.0939 4.9833 23 1.0480 1.0958 4.5590 24 1.0540 1.0979 4.1664 25 1.0620 1.1017 3.7405 26 1.0720 1.1080 3.3586 27 1.0810 1.1139 3.0398 28 1.0880 1.1164 2.6063 29 1.0920 1.1162 2.2117 30 1.0950 1.1145 1.7782 31 1.0980 1.1118 1.2613 32 1.1010 1.1081 .6447 33 1.1020 1.1033 .1192 34 1.1020 1.0974 -. 4147 35 1.1020 1.0904 -1.0499 36 1.1010 1.0823 -1.6974 37 1.1000 1.0729 -2.4612 38 1.0970 1.0624 -3.1583 39 1.0940 1.0504 -3.9838 40 1.0890 1.0370 -4.7746 41 1.0830 1.0222 -5.6181 42 1.0750 1.0052 -6.4925 43 1.0630 .9859 -7.2485 44 1.0460 .9636 -7.8737 45 1.0250 .9377 -8.5132 46 .9960 .9073 -8.9042 47 .9550 .8704 -8.8637 48 .9010 .8241 -8.5336 49 .8400 .7613 -9.3658 50 .7390 .6948 -5.9846 51 .6220 .6302 1.3162 PEAKING PARAMETER COMPARISON PARAMETER MEAS. PREDICTED % DIFFERENCE FXY 1.4839 1.4900 -. 4088 %

FR 1.4296 1.4360 -. 4428 %

FZ 1.1164 1.1020 1.3028 %

FQ 1.6100 1.5810 1.8348 %

CALCULATED RMS VALUES RADIAL = 1.2748 AXIAL = 4.7253 MEASURED ASI = -. 0047 PREDICTED ASI = -. 0361 ACCEPTANCE CRITERIA REPORT MEASURED FXY WAS WITHIN PLUS OR MINUS 10.000 % OP THE PREDICTED VALUE.

MEASURED FR WAS WITHIN PLUS OR MINUS 10.000 % OF THE PREDICTED VALUE.

MEASURED FZ WAS WITHIN PLUS OR MINUS 10.000 % OF THE PREDICTED VALUE.

MEASURED FQ WAS WITHIN PLUS OR MINUS 10.000 % OF THE PREDICTED VALUE.

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

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
  • Page 14

Table 4 GGGGGGGGGG EEEEEEEEEE TTTTTTTTTTT AAAA RRRRRRRRR PPPPPPPP GGGGGGGGGG EEEEEEEEEE TTTTTTIIITI AAAAAA RRRRRRRRRR PPPPPPPPPP GGG EEE TTT AAA AAA RRR RRR PPP PPP GGG GGGGG EEEEEE TTT AAAAAAAAAARRRRRRRRRR PPPPPPPPPP GGG GGGGG EEEEEE TTT AAAAAAAAAARRRRRRRRR PPPPPPPP GGG GGG EEE TIT AAA AAA RRR RRR PPP GGGGGGGGGG EEEEEEEEEE TTT AAA AAA RRR RRR PPP GGGGGGGGGG EEEEEEEEEE TTT AAA AAA RRR RRR PPP (FPA)

A PROGRAMTO EXTRACT DATA FROMCECOR

SUMMARY

FILES FOR COMPARISON OF AXIAL AND RADIAL POWER DISTRIBUTIONS.

GETRNPO1 - GETARP FOR NT REVISION 1 MEASURED DATA EXTRACTED FROM: w3305nj.s02 PREDICTED DATA EXTRACTED FROM: C16P100 RELATIVE RADIAL POWERDISTRIBUTION COMPARISON

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

. . .. +

PREDICTED .290; .490; .490; .270; (MEAS.-PREDICTED)

MEASURED .285; .491; .487; .268;  % DIFFERENCE = ------ X 100.0

% DIFFER -1.76; .11; -. 59; -. 72; PREDICTED

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

+

.320; .530; .690; 1.030; 1.140; 1.020; .680; .530; .310;

.310; .528; .675; 1.011; 1.130; 1.001; .660; .520; .304;

-3.10; -. 42; -2.12; -1.81; -. 86; -1.89; -3.01; -1.92; -1.94;

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

.520; 1.060; 1.060; 1.100; 1.180; 1.210; 1.170; 1.090; 1.050; 1.040; .500;

.509; 1.028; 1.040; 1.077; 1.162; 1.203; 1.157; 1.068; 1.031; 1.018; .499;

-2.02; -3.07; -1.91; -2.12; -1.49; -. 56; -1.08; -1.99; -1.77; -2.14; -. 16;

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

+- +

.530; 1.060; 1.190; 1.310; 1.280; 1.240; 1.220; 1.230; 1.270; 1.300; 1.160; 1.000; .420;

.521; 1.030; 1.155; 1.296; 1.270; 1.237; 1.217; 1.235; 1.268; 1.291; 1.150; .984; .415;

-1.78; -2.84; -2.97; -1.05; -. 75; -. 21; -. 24; .39; -. 19; -. 70; -. 90; -1.59; -1.16; 320; 1060; 1190; 1240, 1.250; 1210, 1.200; 1230, 1.200 1.210; 1.240; 1.220; 1.140; .990; .300;

.318; 1.050; 1.181; 1.237; 1.244; 1.217; 1.199; 1.237; 1.199; 1.214; 1.234; 1.214; 1.135; .985; .298;

-. 73; -. 92; -. 72; -. 26; -. 46; .59; -. 08; .60; -. 07; .31; -. 47; -. 45; -. 41; -. 46; -. 69;

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

.530; 1.060; 1.310; 1.250; 1.260; 1.140; 1.120; 1.130; 1.120; 1.140; 1.250; 1.230; 1.280; 1.030; .520;

.540; 1.061; 1.323; 1.260; 1.265; 1.130; 1.126; 1.129; 1.125; 1.122; 1.248; 1.229; 1.288; 1.032; .525; 1.87; .12; .97; .80; .36; -. 88; .54; -. 06; .45; -1.57; -. 18; -. 10; .62; .17; .96;

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

.690; 1.100; 1.280; 1.220; 1.140; 1.150; 1.070; 1.060; 1.070; 1.140; 1.130; 1.200; 1.270; 1.080; .680;

+  ; .693; 1.099; 1.300; 1.236; 1.147; 1.151; 1.071; 1.072; 1.068; 1.142; 1.131; 1.210; 1.278; 1.083; .689; ---- +

.270; .44; -. 09; 1.58; 1.28; .62; .05; .07; 1.11; -. 23; .19; .05; .87; .63; .27; 1.29; .280;

.269+-------+.. . .- ...-- - -. ..-..--

- --- - ----------------------------------------------- ------------------------- .285;

-. 28; 1.020; 1.170; 1.240; 1.200; 1.120; 1.070; 1.070; 1.060; 1.070; 1.070; 1.120; 1.190; 1.230; 1.170; 1.020; 1.68;

-- -----  ; 1.016; 1.181; 1.254; 1.205; 1.135; 1.075; 1.080; 1.064; 1.076; 1.068; 1.121; 1.180; 1.239; 1.172; 1.018;---- +

.490; -. 44; .95; 1.09; .40; 1.38; .48; .95; .33; .56; -. 18; .11; -. 82; .75; .21; -. 18; .490;

.488+- -------- + ------- ------- -- ------------ ------- ------- ------- ------- ------- + ------- ------- ------- ------- --- .492;

.34; 1.130; 1.210; 1.220; 1.230; 1.130; 1.060; 1.060; 1.030; 1.050; 1.060; 1.130; 1.230; 1.220; 1.200; 1.130; .49;

-- -----  ; 1.125; 1.213; 1.229; 1.246; 1.137; 1.076; 1.063; 1.034; 1.057; 1.073; 1.131; 1.237; 1.225; 1.214; 1.130;---- +

.490; -. 49; .28; .75; 1.31; .59; 1.49; .24; .43; .70; 1.24; .11; .58; .42; 1.17; -. 01; .490;

.488+-...... +. . .. +.. - ..-- - - -------- +-.....-+..------ ... +. .. .--... ..--. ...- +-... .--.. ... +-. .. +...

.- ..--. ...---- .492;

-41; 1.020; 1.170; 1.230; 1.190; 1.120; 1.070; 1.070; 1.050; 1.070; 1.070; 1.120; 1.200; 1.230; 1.170; 1.020; .33;

-- -----  ; 1.011; 1.170; 1.248; 1.207; 1.133; 1.075; 1.078; 1.058; 1.079; 1.080; 1.137; 1.206; 1.254; 1.180; 1.020;---- +

.290; -. 88; .01; 1.4S; 1.42; 1.19; .42; .73; .79; .80; .90; 1.55; .51; 1.94; .82; .02; .270;

.275+ -...... +- .. ... +-. ...- +- ....- +... ..-.. +- ..- +-....- +... .. - ..- -... ---- +. ... + .. .. .. ... +-. ...- +-....-+... ..-- .275;

-5.22; .680; 1.080; 1.270; 1.200; 1.130; 1.140; 1.070; 1.060; 1.070; 1.150; 1.140; 1.220; 1.280; 1.090; .690; 1.74;

+ .684; 1.081; 1.284; 1.221; 1.138; 1.147; 1.070; 1.073; 1.074; 1.158; 1.154; 1.241; 1.306; 1.103; .697; ---- +

.53; .13; 1.07; 1.76; .74; .65; -. 02; 1.23; .40; .70; 1.19; 1.74; 2.00; 1.23; 1.09;

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

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

.520; 1.030; 1.280; 1.230; 1.250; 1.140; 1.120; 1.130; 1.120; 1.140; 1.260; 1.250; 1.310; 1.060; .530;

.523; 1.027; 1.292; 1.231; 1.253; 1.126; 1.126; 1.132; 1.133; 1.144; 1.276; 1.269; 1.332; 1.070; .544;

.50; -. 28; .91; .09; .20; -1.26; .58; .21; 1.12; .37; 1.30; 1.49; 1.72; .90; 2.61;

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

.300; .990; 1.140; 1 220;, 1.240; 1.210; 1.200; 1.230; 1.200; 1.210; 1.250; 1.240; 1.190; 1.060; .320;

.299; .995; 1.145; 1.222; 1.239; 1.214; 1.198; 1.236; 1.204; 1.230; 1.259; 1.253; 1.194; 1.060; .320;

-. 22; .53; .45; .19; -. 10; .33; -. 16; .51; .37; 1.67; .73; 1.01; .34; -. 04; .13;

.. +. ...... +. . . .. . .... . .+....

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

.420; 1.000; 1.160; 1.300; 1.270; 1.230; 1.220; 1.240; 1.280; 1.310; 1.190; 1.050; .530;

.437; 1.001; 1.164; 1.296; 1.262; 1.229; 1.206; 1.240; 1.288; 1.315; 1.180; 1.043; .524; 4.14; .06; .36; -. 29; -. 62; -. 05; -1.17; .00; .60; .41; -. 84; -. 62; -1.05;

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

.500; 1.040; 1.050; 1.090; 1.170; 1.210; 1.170; 1.100; 1.060; 1.050; .510;

.506; 1.028; 1.037; 1.069; 1.153; 1.196; 1.162; 1.084; 1.052; 1.041; .511; 1.13; -1.13; -1.21; -1.90; -1.41; -1.18; -. 72; -1.49; -. 79; -. 87; .25;

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

.310; .530; .680; 1.020; 1.130; 1.030; .690; .530; .310;

.308; .524; .667; .997; 1.117; 1.005; .673; .531; .313;

-. 59; -1.10; -1.88; -2.23; -1.16; -2.39; -2.40; .16; 1.09;

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

.270; .490; .490; .290;

.268; .483; .486; .283;

-. 77; -1.34; -. 76; -2.54;

+ ------ +

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

Page 15

Table 4 (cont.)

RELATIVE AXIAL POWER DISTRIBUTION COMPARISON NODE PREDICTED MEAS.  % DIFFERENCE 1 .7080 .7180 1.4058 2 .8360 .8076 -3.4014 3 .9360 .8920 -4.7020 4 .9800 .9601 -2.0312 5 1.0180 1.0058 -1.1948 6 1.0450 1.0396 -. 5134 7 1.0620 1.0655 .3280 8 1.0730 1.0859 1.2034 9 1.0800 1.1020 2.0380 10 1.0840 1.1143 2.7975 11 1.0870 1.1237 3.3746 12 1.0880 1.1303 3.8913 13 1.0880 1.1350 4.3197 14 1.0880 1.1377 4.5662 15 1.0870 1.1385 4.7418 16 1.0860 1.1378 4.7725 17 1.0840 1.1356 4.7589 18 1.0820 1.1320 4.6246 19 1.0800 1.1274 4.3897 20 1.0780 1.1220 4.0780 21 1.0760 1.1160 3.7149 22 1.0740 1.1098 3.3309 23 1.0720 1.1034 2.9321 24 1.0700 1.0977 2.5862 25 1.0690 1.0938 2.3225 26 1.0700 1.0926 2.1120 27 1.0700 1.0911 1.9684 28 1.0680 1.0863 1.7157 29 1.0640 1.0790 1.4143 30 1.0600 1.0704 .9846 31 1.0540 1.0610 .6661 32 1.0480 1.0506 .2522 33 1.0410 1.0394 -. 1502 34 1.0340 1.0274 -. 6391 35 1.0260 1.0146 -1.1156 36 1.0180 1.0010 -1.6709 37 1.0100 .9866 -2.3141 38 1.0000 .9716 -2.8398 39 .9900 .9558 -3.4548 40 .9800 .9391 -4.1686 41 .9680 .9217 -4.7824 42 .9540 .9029 -5.3593 43 .9380 .8824 -5.9227 44 .9190 .8597 -6.4491 45 .8950 .8342 -6.7916 46 .8650 .8050 -6.9343 47 .8270 .7703 -6.8544 48 .7780 .7276 -6.4729 49 .7240 .6706 -7.3824 50 .6430 .6103 -5.0830 51 .5500 .5519 .3486 PEAKING PARAMETER COMPARISON PARAMETER MEAS. PREDICTED % DIFFERENCE FXY 1.4669 1.4700 -. 2111 %

FR 1.4163 1.4170 -. 0522 %

FZ 1.1385 1.0880 4.6455 %

FQ 1.6743 1.5980, 4.7761 %

CALCULATED RMS VALUES RADIAL = 1.0889 AXIAL = 3.6358 MEASURED ASI = .0728 PREDICTED ASI = .0495 ACCEPTANCE CRITERIA REPORT MEASURED FXY WAS WITHIN PLUS OR MINUS 10,000 % OF THE PREDICTED VALUE.

MEASURED FR WAS WITHIN PLUS OR MINUS 10.000 % OF THE PREDICTED VALUE.

MEASURED FR WAS WITHIN PLUS OR MINUS 10.000 % OF THE PREDICTED VALUE.

MEASURED FQ WAS WITHIN PLUS OR MINUS 10.000 % OF THE PREDICTED VALUE.

RMS ERROR ON AXIAL DISTRIBUTION WAS LESS THAN DR EQUAL TO 5.000 %.

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%1POWERS GREATER THAN OR EQUAL TO 0.9 WERE WITHIN PLUS OR MINUS 10.000 % OF MEASURED.

- ALL ACCEPTANCE CRITERIA WERE MET ***

Page 16

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